L-93-216, Combined Semiannual Radioactive Release Rept for Jan-June 1993 for St Lucie Plant,Units 1 & 2
| ML17309A708 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/30/1993 |
| From: | Sager D FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-93-216, NUDOCS 9308310229 | |
| Download: ML17309A708 (157) | |
Text
ACCEI ERAT REGULAT DOCVMENT DIST VTION SYSTEM INFORMATION DISTRIBUTION
.STEM (RIDS)
ACCESSION NBR:9308310229 DOC.DATE: 9L@A)~)
NOTARIZED:
NO FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power
& Light Co.
50-389 St. Lucie Plant, Unit 2, Florida Power
& Light Co.
AUTH.NAME AUTHOR AFFILIATION SAGER,D.A.
Florida Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION DOCKET N
05000335 05000389
SUBJECT:
"Combined Semiannual Radioactive Release Re t for Jan-June 1993 for St Lucie Plant, Units 1
& 2." W/930826 ltr.
DISTRIBUTION CODE:
IE48lFj COPIES RECEIVED:LTR f
ENCL +
SIZE:
TITLE: 50.36a(a)(2)
Semiannual Effluent Release Reports NOTES:
RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J COPIES LTTR ENCL 3
3 1
1 RECIPIENT ID CODE/NAME PD2-2 PD COPIES LTTR ENCL 1
1 INTERNAL:
REG F
01 FILE 02 1
1 1
1 1
1 NRR/DRSS/PRPB11 RGN2 DRSS/RPB 2
2 2
2
'" EXTERNALS BNL TICHLERij03 NRC PDR EG&G SIMPSON,F 2
2 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'7 NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL 16
'I P
t 0
C
P.O. Box 128, Ft. Pierce, FL 34954-0128 August 26, 1993 L-93-216 10 CFR 50.36 U.'. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 Re:
St. Lucie Units 1 and 2
Docket Nos.
50-335 and 50-389 1993 Semi-Annual Radioactive Effluent Release Re ort Attached is the 1993 Semi-Annual Radioactive Effluent Release Report for the St. Lucie Units 1 and 2.
This report is being sent pursuant to section 6.9.1.7 of the St. Lucie Unit 1 and 2 Technical Specifications.
Should there be any questions on this information, please contact us
~
Very truly yours, D. A.
Vice P St.
Lu er sident e Plant DAS/CDW/kw cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant Attachment DAS/PSL 8974-93 93083i0229 930630 PDR ADQCK 05000335 R
1
'E d
0 l(
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE PLANT UNITS NO.
1 2
LICENSE NUMBERS DPR-67
& NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1 g 1 993.
THROUGH JUNE. 30 ~., 1 993
TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION............
1 OFFSITE DOSE CALCULATION MANUAL REVISIONS.......................
7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.......................
PROCESS CONTROL PROGRAM REVISIONS...............................
7 LIQUID EFFLUENTS:
Summation of all Releases Unit g
1 Summation of all Releases Unit g
2
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9 Nuclide Summation by Quarter Unit 5
1......................
10 Nuclide Summation by Quarter Unit g
2.....................
12 GASEOUS EFFLUENT:
Summation of all Releases Unit 5
1 Summation of all Releases Unit 0
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15 Nuclide Summation by Quarter Unit 4
1......................
16 Nuclide Summation by Quarter Unit g
2...........-..........
18 SOLID WASTE
SHIPMENT SUMMATION.............................
20 ATTACHMENT A UNPLANNED GAS RELEASE ATTACHMENT B UNPLANNED LIQUID RELEASE ATTACHMENT C OFFSITE DOSE CALCULATION MANUAL Revision 11
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION
- 1. Regulatory Limits 1.1 For Liquid Waste Effluents A. The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20 Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 micro-Curies/ml total activity.
B. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive material in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:
During any calendar quarter to <= 1.5 mrems to the Total Body and to <= 5 mrems to any organ, and During any calendar year to <=
3 mrems to the Total Body and to <= 10 mrems to any organ.
1.2 For Gaseous Waste Effluents:
A. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to:
For Noble Gases:
<= 500 mrems/yr to the total body and
<= 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
<= 1500 mrems/yr to any organ.
- B. The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
During any calendar quarter, to <= 5 mrads for gamma radiation,and
<= 10 mrads for beta radiation and, during any calendar year to
<= 10 mrads for gamma radiation. and
<.=
- 20. mrads for beta radiation.
- C. The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives 8 Days in gaseous effluents released, from each reactor unit to areas at and beyond the site boundary, shall be limited to the following:
During any calendar quarter to <= 7.5 mrem to any organ, and During any calendar year to <= 15 mrem to any. organ.
The calculated doses contained in a semi-annual report shall not apply to any STS LCO.
The reported values are based on actual release conditions instead of historical conditions that the STS LCO dose calculations are based on.
The STS LCO dose limits are therefore included in Item 1 of the report, for information only
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.
1.1.A of this report.
Air:
Release concentrations are limited to dose rate limits described in 1.2.A. of this report.
- 3. Average Energy of fission and activation gases in gaseous effluents is not applicable.
- 4. Measurements a'nd approximations of total radioactivity Where alpha, tritium, and listed nuclides are shown as zero Curies
- released, this should be interpreted as "no activity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Limit of Detection (LLD) sensitivity for radioactive effluents".
A summary of liquid effluent accounting methods is described in Table 3.1.
A summary of gaseous effluent accounting methods is described in Table 3.2.
4.1 Estimate of Errors LIQUID GASEOUS Error Topic Avg.%
Max.%
Avg.%
Max.%
Release Point Mixing Sampling Sample Preparation Sample Analysis Release Volume 2
1 1
3 2
Total 0
9 5
5 5
10 5
30 NA 2
1 3
4 10 NA 5
5 10 15 35 The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.
Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 4. Measurements and Approximations of Total Radioactivity (Cont.)
4.1 (Continued)
B.
(Continued)
RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS Liquid Source Sampling Frequency Type of Analysis Method of Analysis Each Batch Principal Gamma Emitters p.h.a.
Monitor Tank 1
Releases Continuous Releases Monthly Composite Quarterly Composite Daily Grab Samples Tritium Gross Alpha Sr-89, Sr-90,
& Fe-55 Principal Gamma Emitters
& I-131 for 4/M Composite Analysis Dissolved
& Entrained Gases One Batch/ Month Tritium Composite Monthly Alpha Composite Monthly Sr 89'r 90' Fe 55 Composite..Quarterly L.S.
G.F.P.
p.h.a.
p.h.a.
L.S.
G.F.P.
C.S.
1-Boric Acid Evaporator Condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Waste 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.F.P.-Gas Flow Proportional Counting 4/M-Four per Month
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 4. Measurements and Approximations of Total Radioactivity (Continued) 4.1 (Continued)
B.
(Continued)
TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Source Sampling Frequency Type of Analysis Method of Analysis Waste Gas Decay Tank Releases Containment Purge Releases Each Batch Principal Gamma Emitters Principal Gamma Emitters Each Purge Tritium p.h.a.
p.h.a.
L.S.
4/M Principal Gamma Emitters Tritium p.h.a.
L.S.
Plant Vent Monthly Composite Quarterly Composite Particulate Gross Alpha Particulate Sr-89
& Sr-90 G.F.P.
C.S.
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.F.P.-Gas Flow Proportional Counting 4/M-Four per Month
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 8
1 SEMIANNUAL REPORT JANUARY 1g 1993 THROUGH JUNE 30'993 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
Batch Releases A. Liquid
- 1. Number of batch releases:
- 2. Total time period for batch releases:,
- 3. Maximum time period for a batch release:
- 4. Average time period for a batch release:
- 5. Minimum time period for a batch release:
- 6. Average dilution stream flow during the period:
All liquid releases are summarized in tables.
B. Gaseous 28 11563 602 413 265 minutes minutes minutes minutes 748002 gpm
- 1. Number of batch releases:
- 2. Total time period for batch releases:
- 3. Maximum time period for a batch release:
- 4. Average time period for a batch release:
- 5. Minimum time period for a batch release:
33 15061 842 456 90 minutes minutes minutes minutes All gaseous waste releases are summarized in tables.
Unplanned Releases A. Liquid 1.
Number of releases:
- 2. Total activity of releases:
B. Gaseous 1
(See Attachment-B) Curies
- 1. Number of releases;
- 2. Total activity of releases:
C.
See attachment (if applicable) for:
1 8.25E-02 Curies 1.
A description of the event and equipment 2.
Cause(s) for the unplanned release.
3.
Actions taken to prevent a recurrence.
4.
Consequences of the unplanned release.
involved.
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 0 2
SEMIANNUAL REPORT JANUARY 1~
1993 THROUGH JUNE 30~
1993 EFFLUENT
& WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.
Batch Releases A.
Liquid 1.
Number of batch releases:
2.
Total time period for batch releases:
3.
Maximum time period for a batch release:
4.
Average time period for a batch release:
5.
Minimum time period for a batch release:
6.
Average dilution stream flow during the period:
All liquid releases are summarized in tables.
B.
Gaseous 28 11563 602 413 265 minutes minutes minutes minutes 748002 gpm l.
2 ~
3 ~
4 ~5.
Number of batch releases:
Total time period for batch releases:
Maximum time period for a batch release:
Average time period for a batch release:
Minimum time period for a batch release:
57 18469 893 324 15 minutes minutes minutes minutes 6.
All gaseous waste releases are summarized in tables.
Unplanned Releases A.
Liquid 1.
Number of releases:
2.
Total activity of releases:
B.
Gaseous 0
O.OOE+00 Curies 1.
Number of releases:
2.
Total activity of releases:
C.
See attachments (if applicable) for:
0 O.OOE+00 Curies 1.
A description of the event and equipment involved.
2.
Cause(s) for the unplanned release.
3.
Actions taken to prevent a recurrence.
4.
Consequences of the unplanned release.
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 7.
Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC is provided on the end of year report.
8.
Offsite Dose Calculation Manual Revisions (ODCM):
The ODCM was revised during the reporting interval.
A complete copy of the revised ODCM is provided as Attachment C to this report.
The revision affected Step 1.3 "Determining Setpoints for Radioactive Liquid Effluent Monito'rs" as per Page 13 of ODCM Revision 11.
This change added instuction for setpoints of a liquid effluent monitor channel that was modified from counts per minute to micro-Curies per milli-literengineering units.
This was the only change to the ODCM.
No dose methodology was affected.
9.
Solid Waste and Irradiated Fuel Shipments:
No irradiated fuel shipments were made for the site.
Common Solid waste from St. Lucie Units 1 and 2 were shipped jointly.
A summation of these shipments is given in Table 3.9 of this report.
- 10. Process Control Program (PCP)
Revisions:
The PCP was not revised during the reporting interval.
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT ¹ 1
SEMIANNUAL REPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹1 QTR¹2 A.
Fission and Activation Products 1.
Total Release (Not including Tritium, Gases, and Alpha)
.2.
Average Diluted Concentration During Period B.
Tritium 1.
Total Release 2.
Average Diluted Concentration During Period C.
Dissolved and Entrained Gases 1.
Total Release 2.
Average Diluted Concentration During Period D.
Gross Alpha Radioactivity 1.
Total Release E.
Volume of Waste Released (Prior to Dilution)
F.
Volume of Dilution Water Used During Period Ci 1.47E-Ol 3.45E-01 uci/ml 3.74E-10 1.00E-09 Ci 5.80E+01 3.10E+01 uci/ml 1.47E-07 9.01E-08 Ci 4.15E-Ol 1.43E-02 uci/ml 1.05E-09 4.16E-11 Ci
'.OOE+00 2-34E-05 Liters 1.69E+06 1.50E+06 Liters 3.93E+ll 3.44E+ll
'8'
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 5 2
SEMIANNUAL REPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRSl A.
Fission and Activation Products QTRN2 1.
Total Release (Not including Tritium, Gases, and Alpha) 2.
Average Diluted Concentration During Period B.
Tritium 1.
Total Release 2.
Average Diluted Concentration During Period C.
Dissolved and Entrained Gases 1.
Total Release
.2.
Average Diluted Concentration During Period Ci 1.47E-01 3.45E-01 uci/ml 3.74E-10 1.00E-09 Ci 5.80E+01 3.10E+01 uci/ml 1.47E-07 9.01E-08 Ci 4.15E-Ol 1.43E-02 1.05E-09 4.16E-.11 uci/ml D.
Gross Alpha Radioactivity 1.
Total Release E.
Volume of Waste Released (Prior to Dilution)
Ci Liters O.OOE+00 2.34E-05 1.69E+06 1.50E+06 F.
Volume of Dilution Water Used During Period Liters 3.93E+11 3.44E+ll
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 5 1
SEMIANNUAL REPORT JANUARY lg 1993 THROUGH JUNE 30, 1993 NUCLIDES RELEASED TABLE UNIT 3.4-1 LIQUID EFFLUENTS Continuous Mode QTRgl QTRg2 Batch Mode QTR51 QTR52 NA-24 CR-51 MN-54 FE-55 MN-56 CO-57 CO-58 FE-59 CO-60 ZN-65 NI-65 BR-82 RB-88 SR-89 SR-90 Y-90 SR-91 SR-92 Y-92 ZR-95 NB-95 ZR-97 NB-97 TC-99M MO-99 RU-103 AG-110 SN-113 SB-122 SB-124 SB-125 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
- 0. O.OE+0,0.,
O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.94E-05 4.27E-03 1.08E-03 3.04E-02 O.OOE+00 5.75E-05 2.23E-02 5.74E-05 1.45E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-04 2.40E-04 1.86E-04 1.86E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.74E-03 2.84E-03 0 ~ OOE+00 5.16E-04 O.OOE+00 O.OOE+00 O.OOE+00 3.67E-04 3.83E-05 1.56E-03 5.20E-03 2.29E-02 3.47E-04 5.39E-02 3.01E-03 1.38E-01 O.OOE+00 5.66E-05 4.10E-02 2.61E-03 1.98E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.34E-04 2.45E-04 2.45E-04 7.27E-05 O.OOE+00 O.OOE+00 1.15E-02 1.94E-02 O.OOE+00 4.42E-03 1.93E-05 O.OOE+00 3.17E-04 4.05E-03 1.19E-03 8.40E-05 1.86E-02 1.58E-02 10
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FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 0 1
SEMIANNUAL REPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 TABLE 3 4-1 LIQUID EFFLUENTS (CONTINUED)
NUCLIDES RELEASED UNIT Continuous Mode QTRgl QTRN2 Batch QTRSl Mode QTR52 TE-129 TE-129M I-131 TE-132 I-132 I-133 I-134 CS-134 I-135 CS-136 CS-137 CS-138 BA-140 LA-140 CE-141 CE-144 PR-144 W-187 NP-239 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.68E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-02 O.OOE+00 O.OOE+00 2.35E-02 4.53E-05 O.OOE+00 1.47E-04 O.OOE+00 O.OOE+00 O.OOE+00 0
OOE+00 0 ~ OOE+00 1.44E-03 3.07E-04 6.17E-04 9.07E-05 1.28E-04 3.33E-04 O.OOE+00 2.28E-03 1.02E-04 O.OOE+00 3.51E-03 1.72E-04 3.68E-05 6.79E-04 O.OOE+00 4.78E-04 O.OOE+00 1.36E-04 2.37E-05 TOTAL FOR PERIOD CI O.OOE+00 O.OOE+00 1.47E-01 3.45E-01 AR-4 1 KR-85M KR-85 KR-87 KR-88 XE-131M XE-133M XE-133 XE-135M XE-135 CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.46E-05 2.72E-05 4.04E-03 O.OOE+00 O.OOE+00 1.86E-03 5.21E-03 4.00E-01 O.OOE+00 3.77E-03 3.39E-05 O.OOE+00 3.28E-03 O.OOE+00 O.OOE+00 O.OOE+00 7.06E-05 1.03E-02 5.63E-05 6.13E-04
P e
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FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT ¹ 2
SEMIANNUAL REPORT JANUARY lg 1993 THROUGH JUNE 30'993 NUCLIDES RELEASED TABLE UNIT 3.4-2 LIQUID EFFLUENTS Continuous Mode QTR¹1 QTR¹2 Batch QTR¹l Mode QTR¹2 NA-24 CR-51 MN-54 FE-55 MN-56 CO-57 CO-58 FE-59 CO-60 ZN-65 NI-65 BR-82 RB-88 SR-89 SR-90 Y-90 SR-91 SR-92 Y-92 ZR-95 NB-95 ZR-97 NB-97 TC-99M MO-99 RU-103 AG-110 SN-113 SB-122 SB-124 SB-125 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.94E-05 4.27E-03 1.08E-03 3.04E-02 O.OOE+00 5.75E-05 2.23E-02 5.74E-05 1.45E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-04 2.40E-04 1.86E-04 1.86E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.74E-03 2.84E-03 O.OOE+00 5.16E-04 O.OOE+00 O.OOE+00 O.OOE+00 3.67E-04 3.83E-05 1.56E-03 5.20E-03 2.29E-02 3.47E-04 5.39E-02 3.01E-03 1.38E-01 O.OOE+00 5.66E-05 4.10E-02 2.61E-03 1.98E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.34E-04 2 '5E-04 2.45E-04 7.27E-05 O.OOE+00 O.OOE+00 1.15E-02 1.94E-02 O.OOE+00 4.42E-03 1.93E-05 O.OOE+00 3.17E-04 4.05E-03 1.19E-03 8.40E-05 1.86E-02 1.58E-02 12
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FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 8
2 SEMIANNUAL REPORT JANUARY lg 1993 THROUGH JUNE 30~
1993 TABLE 3.4-2 LIQUID EFFLUENTS (CONTINUED)
NUCLIDES RELEASED UNIT Continuous Mode QTRNl QTR52 Batch Mode QTR51 QTR52 TE-129 TE-129M I-131 TE-132 I-132 I-133 I-134 CS-134 I-135 CS-136 CS-137 CS-138 BA-140 LA-140 CE-141 CE-144 PR-144 W-187 NP-239 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.44E-03 O.OOE+00 3.07E-04 2.68E-05 6.17E-04 O.OOE+00 9.07E-05 O.OOE+00 1.28E-04 O.OOE+00 3.33E-04 O.OOE+00 O.OOE+00 1.48E-02 2.28E-03 O.OOE+00 1.02E-04 O.OOE+00 O.OOE+00 2.35E-02 3.51E-03 4.53E-05 1.72E-04 O.OOE+00 3.68E-05 1.47E-04 6.79E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.78E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.36E-04 O.OOE+00 2.37E-05 TOTAL FOR PERIOD CI O.OOE+00 O.OOE+00 1.47E-01 3.45E-01 AR-41 KR-85M KR-85 KR-87 KR-88 XE-131M XE-133M XE-133 XE-135M XE-135 CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.46E-05 3.39E-05 2.72E-05 O.OOE+00 4.04E-03 3.28E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.86E-03 O.OOE+00 5.21E-03 7.06E-05 4.00E-01 1.03E-02 O.OOE+00 5.63E-05 3.77E-03 6.13E-04 1 3
+ i" I
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 5 1
SEMIANNUAL REPORT JANUARY lg 1993 THROUGH JUNE 30i 1993 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRgl QTR52 A.
Fission and Activation Gases 1.
Total Release 2.
Average Release Rate For Period B.
Iodines 1.
Total Iodine-131 2.
Average Release Rate For Period C.
Particulates 1.
Particulates (Half Life 8 days) 2.
Average Release Rate For Period I
Ci uCi/sec Ci uCi/sec Ci uCi/sec 2.18E+02 2.62E+01 2.77E+Ol 3.33E+00 1.89E-04 1.34E-03 2.40E-05 1.70E-04 3.29E-05 9.04E-06 4.18E-06 1.15E-06 3.
Gross Alpha Radioactivity D.
Tritium 1.
Total Release 2.
Average Release Rate For Period Ci Ci uCi/sec 1.00E-07 1.41E-07 2.02E+00 2.96E-02 2.57E-01 3.76E-03
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT ¹ 2
SEMIANNUAL REPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 TABLE 3.6-2
, GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹1 QTR¹2 A.
Fission and Activation Gases 1.
Total Release 2.
Average Release Rate For Period B.
Iodines 1.
Total Iodine-131 2.
Average Release Rate For Period C.
Particulates 1.
Particulates (Half Life )
8 days) 2.
Average Release Rate For Period Ci uCi/sec Ci uCi/sec Ci
'uCi/sec 9.47E+00 1.87E+01 1.21E+00 2.37E+00 7.22E-05 2.08E-04 9.18E-06 2.64E-05 7.63E-06 2.23E-05 9.71E-07 2.84E-06 3.
Gross Alpha Radioactivity D.
Tritium 1.
Total Release 2.
Average Release Rate For Period Ci Ci uCi/sec 1.03E-07 3.66E-08 3.53E+00 5.30E-01 4.49E-01 6.75E-02 15
FLORIDA POWER S( LIGHT COMPANY ST.
LUCIE UNIT 8
1 SEMIANNUAL REPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES.
Nuclides Released 1.
Fission Gases Unit Continuous Mode QTRgl QTR82 Batch Mode QTR81 QTR$ 2 AR-41 KR-85M KR-85 KR-87 KR-88 KR-89 KR-90 XE-127 XE-131M XE-133M XE-133
.XE-135M XE-135 XE-137 XE-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 2.37E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.02E+00 9.80E+01 O.OOE+00 1.10E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.75E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.63E+Ol O.OOE+00 7.10E-01 O.OOE+00 O.OOE+00 3 '5E-01 3.01E-01 1.06E+Ol 8.26E-03 2.28E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.50E-01 1.41E+00 8.60E+Ol 1.50E-03 6.98E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.42E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.21E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 2.
Iodines Ci 1.11E+02 2.47E+Ol 1.06E+02 1.46E+00 I-131 I-132 I-133 I-134 I-135 Ci Ci Ci Ci Ci 1.89E-04 O.OOE+00 1.24E-03 O.OOE+00 O.OOE+00 1.34E-03 1.33E-02 4.72E-04 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 3.
Particulates
(
8 Ci Days) 1.42E-03 1.51E-02 Cr-51 Mn-54
.Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.45E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.15E-06 O.OOE+00 O.OOE+00 O.OOE+00 16
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 5 1
SEMIANNUAL REPORT JANUARY lg 1993 THROUGH JUNE 30, 1993 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)
Nuclides Released Unit Continuous Mode QTRgl QTR52 3.
Particulates
(
8 Days)
(continued)
Sr-89 Sr-90 Y-90 Ru-103 Ag-110 Sn-113 Sb-124 Sb-125 Te-129m Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0-OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.44E-06 O.OOE+00 4.96E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.09E-06 1.09E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5 '1E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 4.
Particulates
(
8 Ci Days) 3.29E-05 9.04E-06 Mn-56 Ni-65 Br-82 Rb-88 Rb-89 Sr-91 Sr-92 Y-92 Zr-97 Nb-97 Tc-99m Mo-99 Sb-122 Te-129 Te-132 Cs-138 La-140 Pr-144 W-187 Np-239 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0
OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O..OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00
1
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT g
2 SEMIANNUAL REPORT JANUARY lg 1993 THROUGH JUNE 30, 1993 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Released 1.
Fission Gases Unit Continuous Mode QTRgl QTRg2 Batch Mode QTRgl QTRg2 AR-4 1 KR-85M KR-85 KR-87 KR-88 KR-89 KR-90 XE-127 XE-131M XE-133M XE-133 XE-135M XE-135 XE-137 XE-138 TOTAL FOR PERIOD 2.
Iodines Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.68E+00 O.OOE+00 3.84E-01 O.OOE+00 O.OOE+00 2.07E+00 7.93E-01 1.39E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.91E+00 O.OOE+00 4.42E+00 O.OOE+00 O.OOE+00 1.33E+01 1.89E-01 2.22E-01 8.09E-02 4.14E-03 O.OOE+00 O.OOE+00 8.66E-03 O.OOE+00 8.68E-02 5.43E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.51E-03 1.28E-02 1.32E-01 8.77E-02 5.08E+00 4.94E+00 O.OOE+00 O.OOE+00 1.82E+00 1.26E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.41E+00 5.40E+00 I-131 I-132 I-133 I-134 I-135 Ci Ci Ci Ci Ci 7.22E-05 2'.08E-04 O.OOE+00 6.34E-04 2.02E-04 2.08E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.40E-03 TOTAL FOR PERIOD 3.
Particulates
(
Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 8,
Ci Days)
Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci
- 2. 74E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.32E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.19E-05 O.OOE+00 O.OOE+00 O.OOE+00 18
Z
~ A P
I Pt I
0
\\
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 5
2 SEMIANNUAL REPORT JANUARY 1g 1993 THROUGH JUNE 30, 1993 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)
Nuclides Released 3.
Particulates Unit Continuous Mode QTRSl QTRg2
(
8 Days)
(continued)
Sr-89 Sr-90 Y-90 Ru-103 Ag-110 Sn-113 Sb-124 Sb-125 Te-129m Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-14,4 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.63E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.63E-07 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 4.
Particulates Mn-56 Ni-65 Br-82 Rb-88 Rb-89 Sr-91 Sr-92 Y-92 Zr-97 Nb-97 Tc-99m Mo-99 Sb-122
-Te-129 Te-132 Cs-138 La-140 Pr-144 W-187 Np-239
(
8 Ci Days)
Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.63E-06 2.23E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O,.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00 19
l
FL DA POWER AND LIGHT COMP Y
ST. LUCIE PLANT SEMI-ANNUALREPORT, JANUARY 1, 1993 THROUGH JUNE 30, 1993 UNITS 1 AND 2, TABLE3.9 A.
Solid Waste Shipped Off-Site for Burial or Disposal 1.
Type of Waste Unit 6 Mo. Period Error %
a.
C.
d.
1.
Spent Resin, Process Filters Dry Compressible Waste (Note 5)
Irradiated Components Other Non-Compressible Metal (DAW) (Note 6)
M3 Ci M3 Ci M3 Ci M3 CI 1.334E+1 2.980E+2 4.950E+0 1.353E-1 1.640E+0 1.190E+4 1.870E+0 2.356E-1 2.0 E+1 2.0 E+1 2.0 E+1 2.0 E+1 2.
Estimate of Major Nuclide Composition (By Type of Waste)
Category aO b.
Nuclides Co 58 Cs 137 Fe 55 CS 134 Ni'63
'o 60 Mn 54 I 131 Co 60 Fe 55 Co 58 Cs 137 Ni 63 Cs 134 Nb 95 Zr 95 Sb 125 MN 54 Cr 51 4.48E+1 1.76E+1 1.42E+1
'.43E+0 5;08E+0"
'.85E+0 2.58E+0 1.18E+0 2.52E+1 2.40E+1 1.52E+1 1.20E+1 1.03E+1 3.10E+0 2.47E+0 2.05E+0 1.94E+0 1.20E+0 8.10E-1 20
~l I
vt"fl:gjj
-t t
t
\\ g I
Category Nuclides C.
d.1.
Fe 55 Co 60 Mn 54 Ni 63 Co 58 Co 60 Fe 55 Co 58 Ni 63 Ce 144 Mn 54 Cs 137 5.52E+1 3.53E+1 5.72E+0 2.50E+0 1.18E+0 6.57E+1 2.21E+1 4.85E+0 2.81E+0 9.70E-1 8.70E-1 7.50E-1 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Sole Use Truck Sole Use Truck Sole Use Truck Destination Barnwell, S.C.
S.E.G. Oak Ridge, TN Quadrex, Oak Ridge, TN B.
Irradiated Fuel Shipments Number of Mode of Transportation Shipments N/A
- Destination N/A 8
~ N/A = Not Applicable
/dac
SEMI-ANNUALREPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 UNITS 1 AND 2, TABLE3.9 (CONTINUED)
Waste Class Class A Class A Class A Class B Total Volume Cubic Ft.
174.9 66.09 4.11 202.1 Total Curies (Note 1) 1.353E-1 2.356E-1 1.000E-3 1.008E+1 Principal Radionuclides (Notes 1&2)
N/A N/A N/A Ni 63, Sr 90, Cs 137 Type of Waste (Note 3)
PWR Compactible Trash (Note 5)
PWR Non-Compactible Trash (Note 6)
PWR Ion-Exchange Resin PWR Ion-Exchange Resin Category Reg-Guide 1.21 1.b 1.d.1 1.a 1.a Type of Container (Note 4)
Non-Specification Strong Tight Package Non-Specification Strong Tight Package Non-Specification Strong Tight Package NRC Certified LSA Type A Solidification Agent None None None None Class B Class C 264.8 57.8 2.879E+2 1.19E+4 C14, Ni63, Sr90, Cs137, Sum of Nuclides with 7 1/2
< 5 years C14, Ni59, Nb94, Tc99, Co60, Ni63, Sum of Nuclides with T 1/2 < 5 years PWR Ion-Exchange Resin PWR Irradiated Reactor Components l.a 1.c NRC Certified Type B None NRC Certified Type B None
FLORIDAPOWER AND LIGHT COMPANY ST. LVCIE PLANT SEMI-ANNUALREPORT JANUARY 1, 1993 THROUGH JUNE 30, 1993 UNITS 1 AND 2, TABLE3.9 (CONTINUED)
SOLID WASTE SUPPLEMENT NOTE 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Plant, Units 1 and 2 are determined using a combination of qualitative and quantitative techniques.
In general, the St. Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.
The most frequently used techniques for determining the total curie-quantity-in-a package are the dose to curie methods and the (concentration) x (volume or mass) calculations.
Where appropriate, engineering type activation analyses may be applied.
Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.
The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides.
The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type.
Off-site analyses ar used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99TC, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.
NOTE 2:
"Principal Radionuclides" refer to those radionuclides contained in the. waste in concentrations greater than.01 times the concentration of the nuclides listed in Table 1 or.01 times the smallest concentration of the nuclides listed in Table"2 of-10 CFR 61.-
NOTE 3:
"Type of Waste" is generally specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste".
NOTE 4:
"Type of Container" refers to the transport package.
NOTE 5: The volume and activity listed for Dry Compressible Waste represent the quantity of material that during the reporting period was sent to the Barnwell, South Carolina burial facility. This material was shipped to a contracted vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility. During the reporting period, four shipments of Dry Compressible Waste (4,140 cubic feet, 1.814 E+0 curies) were made from the St. Lucie Plant to the volume reduction facility. This material was shipped via "Sole Use Truck in non-specification strong tight packages.
23
NOTE 6: The volume and activity listed for non-compressible metal represent the quantity of material that during the reporting period could not be recycled by the contracted vendor and required disposal at the Barnwell, South Carolina burial facility. During the reporting period, two shipments of non-compressible metal waste (1,280 cubic feet, 2.097 E-3 curies), and secondary bead resin (519 cubic feet, 1.608 E-5 curies) were made from the St. Lucie Plant to the volume reduction facility. This material was shipped via "Sole Use Truck" in non-specification strong tight packages.
24
ATTACHMENT A UNPLANNED GASEOUS EFFLUENT RELEASE of January 29, 1993-
- 1) Description and analysis of event
- 2) Hourly average site meteorological for January 29, 1993
4 I
I
Attachment A
- 1) Description and analysis of event On January 28, 1993 the nitrogen system was in normal alignment, and the Air Ejector I 1 Exhaust was realigned directly to the Atmosphere instead of its normal alignment to the Plant Vent.
This realignment was performed to prevent steam from flowing into a static Plant Vent during Ventilation Flow Testing being performed in the Reactor Auxiliary Building(RAB).
On January 29, 1993 at 0445, with the Reactor operating at full power, the Air Ejector Il (SJAE)
Rad Monitor alarmed and Control Room personnel alerted Chemistry personnel.
The SJAE exhaust was then aligned to the Plant Vent Exhaust, a Technical Specification Continuous Release Monitored Pathway.
Chemistry sampled the Steam Generator blowdown for.radioactivity, detecting a trace of Xe-133.
A qualitative gas grab sample on the SJAE exhaust gases indicated:
- 1) noble gas radioactivity was present,
- 2) the gas isotopic mix indicated that the source was not from the Reactor Coolant System, but was typical of decayed gas from a
gas decay tank.
A quantitative gas sample was obtained on the Air Ejector Monitor.
Operations personnel immediately checked current plant conditions and confirmed the suspected pathway could have occurred when the nitrogen system supply pressure dropped when the Condensate Storage Tank(CST) Atmospheric Water Seal lost integrity.
This put a large demand on the nitrogen cover gas supply to this tank and Decay Tank 1B had back flowed a small amount (5 psig total loss based on observation of previous pressure in the tank) through V6596 and into the nitrogen supply.
The radioactive gas was detected by the SJAE Monitor since nitrogen gas is injected into the condenser for dissolved oxygen removal'".
The: nitrogen-supply valve V-6596 to GDT 1B was then checked closed and the nitrogen supply root valve V-6788 was closed for double valve isolation to insure the release path was terminated.
Gas Decay Tank 1B was sampled as the source of the Unplanned Release as per procedure C-72.
The analyses included Gas, Iodine, Particulate, and Tritium to account for all activity that could have been present in the source.
Noble gas activity was the only type of activity present in the tank.
Plant Work Order (PWO I 93002828) was issued to repair V-6596.
1 I
t g+ "M%
Review of Technical Specification Limits:
The Air Effector Exhaust Monitor is only a noble gas activity monitor and Technical Specifications do not require continuous sample collection for Iodine and Particulates.
It is the policy of the plant to align the SJAE Exhaust to the continuous Iodine and Particulate sampler in the Plant Vent when th'er'e is a primary to secondary leak.
The SJAE Exhaust was aligned to the Plant Vent upon receipt of the SJAE alarm until the source of the radioactivity could be identified.
The identified source, Gas Decay Tank 1B, was analyzed for Iodine Particulates, and Tritium to ensure that all activity was accounted for in this event.
This event was an unplanned batch release.
The calculated release rate for the event was 5.1E-04 Ci/sec which is approximately a factor of 690 lower than the Site Limit of 0.35 Ci/sec.
No Technical Specification Release Rate Limits were exceeded.
All required sample surveillances were performed during this event.
FLORIDA POWER
& LIGHT CO.
ST.
LUCIE PLANT CHEMISTRY DEPARTMENT Radioactive Assay Results of an UNPLANNED RELEASE REACTOR UNITS:
1 SAMPLE I.D.
1B GDT SAMPLE TIME 1-29-1993 8
8:30 NUCLIDE SYMBOL KR-85 XE-131M XE-133 XE-133M XE-135 SAMPLE uCi/cc 3.443E-03 5.625E-04 5.478E-02 5.686E-04 9.809E-05 milli-Ci RELEASED 4.776E+00 7.802E-01 7.598E+01 7.887E-01 1.360E-01 KEYLINE KEV.
513.99 163. 93 81.00 233.18 249.79 NET PEAK AREA 31.
76.
134714.
288.
396.
PEAK EFF 1.83E-01 6.21E-01 5.86E-01 4.41E-01 4.10E-01 PEAK ABUND 0.43 1.96 37.60 10.30 89.90
FLOR-I DA POMER-0 LIGHT CON ANY HOUR ENDING E.S.T.
ST.
LUCIE HETEOROLOGICAL DATA JAN 29, 1993 MIND DRCTN.
h SPEED TEMPERATURE DELTA"T SIGNA THETA RAIN 60"HETER 10-HETER'YS TEMP SYS CAT CAT DEG HPH DEG NPH DEG.
F DEG.
C/100K DEG IN.
1 340 5.5 310 3.4 A
60.3 A
2.1 "F tlISG
- 0. 00 342
- 6. 6 311
- 3. 4 33&
9.6 308 4.1 342 8.&
314 4.2 330 10.4 312 4.4 328 12.0 314 4.8 A
59.9 A
59.9 A
593 A
59,2 A
59.3 A
2 6
F A
2 9
F A
3 8
F A
2.1 F
A 1
3 E
NISG 9.0 D
9 ~ 1 D
10.7 D
13.8 C
0.00
- 0. 00
- 0. 00
- 0. 00
- 0. 00 8
328 9.4 9
344 7.6 319
- 3. 6 338 4.0 A
- 61. 9 334
- 10. 9 318
- 4. 4 A
- 59. 9 A
1.5 E
14.3 C
A 10 E
138 C
A 00 E
179 B
0.00
- 0. 00
- 0. 00 12 15 16 17 18 19 20 21 22 345 10.6 348 7.7 351 10.1 356 8.0 5 11.0 4
7.1 352
- 10. 8 354
- 8. 0 350 11.2 352 8.0 347 11.4 349
- 7. 2 349 11 '
349 6.'9 351 10.7 350 6.5 352 9.8 349 5.7 354 8.3 349 4.7 351 9.0 347 5.2 352 9.6 348 5.4 346 10.8 342 5.8 A
67.0 A
67.4 A
66.6 A
67.7 A
67.3 A
66.0 A
65.3 A
64.9 A
65.0 A
64.9 A
&5.2 A
65.3 A
&5.&
10-
- 343 8.6 342 5.4 A
&4.1 li 345 9.4 346 6.6 A
65.4 A -0 9
D -
19 3
B 0.00" A -0.5 E
18.0 B
0.00 A -0.1 E
17.8 B -
0.00 A "01 E
180 B
000 A
0.2 E
17.4 C
0.00 A
0 1
E A
0 1
E 17.2 C
0.00 18.2 B
0.00 A
0.0 E
18.8 B
0.00 A -1.5 C
19.1 B
0.00 A -1.9 A
20.1 B
0.00 A -2.0 A
18.0 B
0.00 A "1.8 B
1/.2 C
0.00 A -2.1 A
17.5 8
0.00 A "1.8 B
17.4 C
0 F 00 A "1.0 D
18.4 B
0.00 HAXINUN:
NEAN NININUN:
- 12. 0 9.7 5.5 8.0 5.6 3.4 SUNNARY OF DAY-67.7 63.6 59.2 TOTAL:
0.00
Page 12: of'12.
ST: LUCIE UNIT1 OPERATING PROCEDURE. NO. 1'-0530021,. REVISION 36 CONTROLLED GASEOUS BATCH RELEASE TO ATMOSPHERE GASEOUS RELEASE PERMIT GASEOUS PERMIT NUMBER SAMPLE DATE AND TIME GDT NAME OR PURGE LIMITS g3 cf3c ACTUALCONCENTRATION
'(erat On IGAh REMARKS GDT 20.0 uCVcc
~~> ~"+
uCVcc Containment Purge 4.76 X 10 uCVcc uCVcc Maximum Discharge Flow Rate for Gas DecaY Tanks GDT
¹/hr.
GDT Decrease or C.F.M. Flow Setting Waste Gas Monitor Setpoints Alert:
GPM High:
Waste Gas Monitor Source Check Performed bY (initials):
Nh' tc in.
(
0 Review - Approval (Prior to Release)
Containment Purge Chemistry Supervisor g+
Signature GDT o or 25% of Section II GDT c25% of Section II GhemistrYSupervisor ~,~
~<<~ ~
I
)
Permit Preparer Assistant Nuclear Plant Supervisor IV.
Start Date I-Z, g
Time o~
V Stop Date i-zg-g$
Start GDT Pressure Stop GDT Pressure Time CP' W
V.
Review - Approval (Post - After Release)
Assistant Nuclear Plant Supervisor Chemistry Supervisor Signature I'a'.
lIcable.
S~OPS DATE 7 W I SYS COMP C.c w4'.F.M.
PGL Cl! iViIGTPY DEPT.
counts per minut'e greater than or equal to percent
> or=
+ -8&n<+S t aiI-NOTATION OF PERMlT SYMBOLS eg'ei:Qt-a,la~ +im~
GDT Gas Decay Tank
- 4. MQeg ICSt P L
W~
A=ir specs~
uCi/cc micro-Curies per cubic centimeter
~~l'<~~<
¹/hr.
pounds per hour cubic feet per minute CPM
ATTACHMENT B UNPLANNED LIQUID EFFLUENT RELEASE of June/July 1993
ATTACHMENT B Description and analysis of event On 6/15/93 Operations noted a decreasing trend in Refueling'Water Tank (RWT) level and began a search of interconnecting systems for the leakage source.
The leakage was approximately 1.5 gpm.
On 6/29/93, after extensive interconnecting system alignment and leakage checks, Operations reported that the volume loss could not be located.
A systematic search was initiated which involved independent alignment checks, isolation of individual sections of piping and a line by line walkdown of interconnecting systems.
Again, no cause of the RWT volume loss could be found and the focus of the investigation shifted to the possibility of a leak in the RWT shell.
On 7/6/93 Monitoring Wells in the vicinity of the RWT were sampled specifically for Boron and Tritium.
Test results were positive which indicated that the leakage was from the RWT shell.
Voluntary notification to the State of Florida Department of Environmental Regulation of the Tritium release was made by Juno Environmental on 7/7/93.
The NRC was notified in accordance with 10CFR50.72B.VI where an inadvertent release of radioactively contaminated materials occured and another government agency was notified.
A remote controlled submersible was placed in the RWT to perform a visual survey on'/10/93.
Some minor debris was found, but no leakage site was identified.
On 7/12/93 a contractor with Acoustic Leak Detection experience arrived on site.
External acoustic data collection was performed.
Analysis of the data was completed on 7/13/93.
The data indicated several"possible" leakage'sites.'-
Divers entered the RWT on 7/15/93 to locate the leakage sites.
The remote controlled submersible was put into the RWT to perform internal acoustic monitoring.
Divers located a single leak at a
pit location in the RWT on 7/16/93.
Divers repaired the leakage site utilizing an epoxy repair with an Aluminum backing plate approved by Engineering.
The repair method is a
recommended practice per EPRX Underwater Maintenance Guide NP-7088.
Permanent, repair of tank bottom is planned for the 1994 Unit 1 outage.
On 7/17/93 cleanup of debris was completed.
A random sample Ultrasonic Test (UT) of the RWT bottom was also performed.
Results of the UT indicated that there were no areas of general thinning in the bottom aluminum liner.
Operations personnel and additional acoustic testing verified that RWT level stabilized upon completion of the repair.
The liquid release was accounted for in accordance with Technical Specifications Table 4.11-1b, Continuous
- Releases, and will be reported in the July-December 1993 SemiAnnual Release Report once Sr89/90 and Fe55 composite analysis is done.
Analysis shows 55,000 gallons with approximately 6.5 curies of Tritium and 0.037 curies of gamma emitting solids were released to the groundwater table which is 14 feet below ground surface.
There are no drinking water wells on site or on the Island.
The magnitude of the release was equivalent to a normal batch liquid release.
The groundwater movement is towards our circulating water system canals and then to the Atlantic Ocean.
Therefore there will be no adverse impact on the health and safety of the public as a
result of the release.
Records of this event will become part of the site decommissioning files.
Y
ATTACHMENT C CHEMISTRY OPERATING PROCEDURE C
200 OFFSITE DOSE CALCULATION MANUAL REVISION 11 As requested, a complete copy is provided with the revisions denoted by "/R11."-in the right margin of page 13, the only page affected by this revision.
Page 1 of 88 FZORIDA, POMME & ZZGRZ CCNPANY Sr.
ZUCIE PIANr CHEMISZRY OPEPATING HKCEIXZK NO. C-200 REVISION 11 Tl'KP Offsite Dose Calculation Manual (ODCM)
REVI157 AND APICAL:
Reviewed by Facility Review Group Approved by C. M. Weth Revision 11 Reviewed hy F R G Approved by G. Z. Boi Plant General Manager Plant General Manager ril 22 1982 ril 27 1982 0+
7 19+3 0
t 1973 S
FOR INFORMATION ONLY This document is not controlled. Before use, verify information with a controlled document.
DATE DXT PROCEUJRE DOCN C-200 SYS CGHP CXMPIZIED HM 11 t
..9308310229
K%f 4 I.
WlkllI '
'4 <<& M74&
Lg h
Il
%C &
O'Q e, ~
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~
.Jfl,jr',<li'g>> ',';"3
<, "g. i. 3 i~" i'.V ~ ~)'"y <<t cl>i'i/ y4'$,pV
>>~m~w e<<
- 4gw.<< ~ we~ eraes~mow ~~~owl
Page 2 of 88 ST.
IIJCZE EKANT CSEKESZRY OPKRATjING PBOCEIXRE NO. C-200, REVISION 11 OFFSITE DOSE CMXUIATIONMANUAL OIXH TMKZ OF CONTEPIS PAGE NO.
Title:
St. Zucie Plant Offsite Dose Calculation Manual.......................l In~ c-~
~uc uonr ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 lOSSaryr
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ r5 G
1.0 Radioactive Releases of Liquid Effluents.................................7 1.1 Llquld Effluent Model Assumptions...................................8 1.2 Determining the Fraction'F) of 10CFR20 MEC-Limits for Radioactive Liquid Releases..............................8 1.3 DeterInining Setpoints for Radioactive Liquid Effluent Monitors..................................................
11
- 1. 4 DeterInining the Dose fram Radioactive Liquid Effluents.............
13 1.5 Projecting Dose for Radioactive Liquid Effluents...................17 2.0 Radioactive Releases of Gaseous Effluents...............................18 2.1 Gaseous Effluent: Model Assumptions.................................19 2.2 DeteIxun~ the Total Body and Skin Dose Rates for Noble Gas Releases and Establishing Setgoints f
~ r or Effluent Y~nltors..............................................20 2.3 Determining the Radioiodine and Particulate Dose Rate to Any Organ Fram Instantaneous-Gaseous Releases...................25 DISCXJSSION 2.3.1, XrM.ation..................................................27
.3.2 Ground Plane................................................28 2
2
%ri %1
~
3 YLL~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~
~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~
2
~ r
~
r 3 ~ 4 Tl'ltlum~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 30 2.3.5 Total Dose Rate by Release Source...........................32 2.4 Determining the Gamtt~ Air Dose for Radioactive Noble Gas Releases.................................................32 2.5 Determining the Beta Air Dose for Radioactive Noble Gas Releases
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 35
Page 3 of 88 ST. WCIE PIANT CHEKESTRY OP1&ATING PHQCEDUEK NO C 200'EVISION 11 OFFSITE DOSE CAHXJIATIONMANUAL'IXK TABLE OF CONTIMIS (continued)
PAGE NO.
2.0 (continued) 2.6 Determining the Radioiodine and Particulate Dose to Any Organ From CmaQative Releases..............................37 DISCXJSSION 2 ~ 6 1 Illlldlatlon<<~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 40
.6.2 Ground Plane..............................................;
..40 2
2
<<'t
~ 6 o 3 Mllk<< ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 2.6.4 Tritium Dose (All Pathways).................................42
~ 6 ~ 5 Total Organ Dose o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 43 2
2.7 Projecting Dose for Radioactive Gaseous Effluents..................43 3.0 40 CFR 190 Dose Evaluation..............................................44 4 ~ 0 SK Annual Report Format o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 45 Appendix A MPC, Dose Factor and Historical Meteomlogical Tables...........56 Q~enclix B Limited Analysis Dose Assessment for Liquid Rachoactzve Effluents...........................................
76 Appendix C Technical Bases for Effective Dose Factors......................78 Appenciix D Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Storage Tanks.................................81 Appendix E Current R.E.M. Sample Point Zacation Map for SXS-A 3/4<<12.......83 F Description of Meteorological Dispersion Formulas Utilized for Historical Data and Methodology for De&GIllng Actual MET Data<<
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 88
0
Page 4 of 88 ST. WCIE PrANT CHIMIPZRY OPERATING XSOCEIX3EK NO C 200 g REVISION 11 OFFSITE DOSE CADXJLATIONMANUAL ODCÃ
'his manual provides the methodology to calculate radiation dose, to individuals in the vicinity of the St. Zucie site, fram radioactive gaseous and liquid effluents. It also provides methodology for calculating effluent monitor setpoints and allowable release rates to ensure-campliance with the STS and 10CFB20 release criteria.
The in-plant procedures specify what sections of the,OIXK should be completed-to calculate the dose to an individual.
The ODCM follaws the methodology and models= suggested by NUREG-0133 (November, 1978) and Rectulatory Guide 1.109..
Simplifying assumptions have been applied where applicable to provide a more workable document for Rd St f
calculation methods may be used fram those presented as long as the overall methodology does nat change or as long as the alternative methods provide results that are more limiting. Also, as available, the most up-
'Iate revisions of the Regulatory Guide 1.109 dose conversion factors and enviroranental transfer factors may be substituted for those currently included and used in this docunent.
Page 5 of 88 ST. WCIE PUTZ CKMESZRY OPERATjXG PfKCEIXJRE NO. C-200, RIWXSION 11 OFFSITE DOSE ('AZCXJIATIONMANUAL OIXX GIDSSARY OF COMMONLY USED TERMS Ci Ci
- Dose fram Beta Radiation Cubic centimeter Curies a unit of radioactivity see uCi Activityor concentration of a nuclide in the release scmxe.
Units of uCi, uCi/cc, or uCi/ml Code of Federal Regulations Ghe exposure, in mrem or mrad, the organ or the individual receives fram radioactive effluents (D/Q)
Ground Plane H-3 I&8DP m
Normally, a factor that converts the effect of ingesting radioactive material into the body, to dose to a specific organ.
Body elimination, radioactive decay, and organ uptaIce are same of the factors that deternune a dose factor for a given nuclide A specific path that radioactive material physically travels through prior to exposing an individual to radiation.
'lhe Grass-Caw-Milk-Infant is a dose pathway
%he dose received per unit time A long term D aver Q a factor with units of 1/M which describes the deposition of particulate matter fram a plume at a point downrange fram the source. It can be thought of as what part of the cloud is going to fallout and deposit aver one scgx~ meter of ground.
(See Apperxlbc F).
,I i
tl 1 I 4,
~
.I
~
I A garrtma photon - The dose fram Gantmas in air, etc.
Radioactive material deposited uniformly over the ground emits radiation that produces an exposure pathway when an irdividual is standing, sitting, etc., in the area. It is assumed that an adult receives the same ~cposure as an infant, regardless of the physical height differences.
Only the total body is considered for the OIXK.
Hydrogen-3, or Tritium, a weak Beta emitter
- Radioiodines and particulates with half-lives greater than 8 days Limiting condition for operation in STS Cubic Meters
& padre Meters
Page 6 of 88 ST.
ZIJCIE PZANT CHIKZiFIRY OPERATj2Kr PROCIKUBE NO C 200'EVISION 11 OFFSITE DOSE CAICGZATION MANUAL OIXK GZOSSARY OF COMMONLY USED TERMS (continued)
Maxim'm+~sible Concentration nuclide Ch~n (Q Dat)i Qi
- For the purgoses of this manual, a radioactive isotope.
Nuclide (i) signifies a specific. nuclide, the 1st, 2nd, 3rd one under consideration.
If nuclide (i) is I-131, then the Mi (dose factor) under consideration should be MI 131 for 63GKple For the OIXK either the bone, liver, thyroid, kidney,,
lung, GI-LLI, or the T. Body.
Total Body is considered an organ for ease of writing the methodology in the ODCM.
- (Q Dat)i Denotes a release rate in uCi/sec for nuclide (i).
Denotes uCi of nuclide (i) released over a specified time interval.
Radioiodines Receptor Iodine-131 and Iodine I-133 for gaseous release pathways.
%he individual receiving the exposure in a given location or who ingests food products fram an animal for example.
A receptor can receive dose fram one or more pathways.
Release Source(s)
A subsystem, tank, or vent where radioactive material can be released independently of other radioactive release points.
The St. Zucie Plant Standard Technical Specifications uCi micro Curies.
1 uCi,=. 10,:
Curies... The.uCi is the standard unit of radioactivity for all dose calculations in the ODCM.
(VQ)
(VQ)D A long term Chi aver Q. It describes the physical
~ion characteristics of a semi-infinite cloud of
=
noble gases as the cloud traverses dawnrange fram the release point.
Since Noble Gases are inert, they do nat tend to settle out on the ground.
(See Appendix F).
A long term Depleted Chi aver Q. It describes the physical dispersion characteristics of a semi-infinite cloud of radioactive iodines and particulates as the cloud travels dawnrange.
Since Iodines and particulates tend to settle out (fallout of the cloud) on the ground, the (QQ) q repre ~ts what physically remains of the cloud and its aspersion qualities at a given location dawnrange fram the release point.
(See Appendix F).
- A sgecific delta time interval that, corresImnds with the release interval data etc.
ST. IIJCIE PZtÃI'SEKZSTRY OPlPATING PROCEDURE NO C 200 g RLVISION 11 OFFSITE DOSE KQXXJZATION MAM.M OIXM Page 7 of 88
- 1. 0 LI D 'R1K1RSES MEIHODOZDGY
Page 8 of 88 ST. IIJCIE PI2ÃZ CKMESTEE OPERATING PROCEXXJRE NO C 200 g REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCN 1.1 Radioactive Li
'd Effluent Model As ions Ghe HJSAR contains the official description of the si.'te ch-mcteristics.
The description that follows is a brief surmaary for dose calculation purposes:
The St. Zucie Plant is located on an island surrounded on two sides'by the Atlantic Ocean and the Indian River, an estu-ey of the Atlantic Ocean.
Normally, all radioactive liquid releases enter the Atlantic Ocean where the CirnQating Water Discharge Pipe terminates on the ocean floor at a point approximately 1200 feet offshore.
No credit is taken for subsequent muring of the discharge flume with the ocean.
The diffusion of radioactive material into the ocean is dependent on the corditions of tide, wind, and same eddy currents caused by the Gulf S~mn.
'Ihe conditions are sufficiently rardam enough to distribute the discharges over a wide area and no concentrating effects are assuHled o
%here are no direct disch;mme paths for liquid effluents to either of the north or south private property bound-~ lines.
The Big Mud Cret& (part of the Indian River) does connect to a normally loci<ed shut dam, that is intended to provide an emergency supply of circulating water to the Intake Cooling Water Canal in the event a Hurricane causes blockage of the Intake Canal.
No radioactive water could be disch-~ed directly into the Intake Cooling Water Canal because all plant piping is routed to the discharge canal and no back flow can occur.
Consult the HJSAR for a detailed description of characteristics of the water hd ~
p Only those nuclides that appear in the Liquid Dose Factor Tables will be considered for dose calculation.
I 5-: I'
\\ ~ K I 1.2 Detain'he Fraction F of 10CFR20 MPC Limits for A Li id Release Source Discussion Technical specification 3.11.1.1 recpures that the sanpling and analysis reeQts of liquid waste (prior to discharge) be used with calculation methods in the in-plant procedures to assure that the concentration of liquid radioactive material in the uruwstricted areas will not exceed the concentrations specified in 10CFR20, Appendix B, Table II. This section presents the calculation method to be used for this determination.
This method only addresses the calculation for a specific release source.
The in-plant procedures will provide instructions for deteratuning that the summation of each release source's F values do not exceed the site's 10CFR20 MPC limit.
The values for release rate, dilution rate, etc.,
willalso have to be obtained from in-plant procechues.
The basic equation is:
FL R
n D
Z i=1 Ci (MPC)i
ST. IIJCIE PlUÃZ CK~8GK OPERATING PROCEIXJRE NO. C-200, REVISION 11 OFFSITE DOSE CALCULATIONMANUAL ODCÃ Page 9 of 88 1.2 (continued)
Where:
FL D
Ci (MPC)i the fraction of 10CFR20 MPC that would result if the release source was discharged under the conditions specified.
%he undiluted release rate in gpm of the release source.
Liquid Rad Waste = 170 gran Steam Generator = 125 ggq/Steam Generator The dilution flaw in ggm of Intake Cooling Water or Circulating Water Pumps Intake Cooling flaw is 14,500 gpm/pump Circulating Water flaw is 121,000 gpay'pump The undiluted concentration of nuclide (i) in uCi/ml fram sBIlple assay
%he maximum permissible concentration of nuclide (i) in uCi/ml fram Table L-1.
For dissolved or entrained noble gases the MPC value is 2 X 10 4 uCi/ml for the sum of all gases o
We fraction of the 10CFR20 MPC limit may be deteonined by a nuclide-by-nuclide evaluation or for purposes of simplifying the calculation by a cumulative activity evaluation. Ifthe simplified method is usedg the value of 3 X 10 uCi/ml (unidentified MPC value) shauld be substituted for (MPC)i and the cumulative concentration (sum of all identified radionuclide concentrations) or the gross concentration should be a2mtituted for Ci.
As long as the diluted concentration (Ctc~ QD) is less than 3 X 10 uCi/ml, the nuclide-by-nuclide calculation is nat required to.,demonstrate.compliance. with the, 10CFR20 MPC limit.
'Ihe follawing section pravides a step-by-step procedure for determining the MPC fraction.
1.
Calculation Process for Solids A.
Obtain fram the in-plant procechues, the release rate value (R) in ggm for the release source.
B.
Obtain fram the in-plant procedures, the dilution rate (D) in gpm.
No credit is taken for any dilution beyond the disch-ape canal flaw.
C.
Obtain (Ci), the undiluted assay value of nuclide (i), in uCi/ml. Ifthe simplified method is used, the cumulat:ive concentration (C~~) is used.
D.
Fram Table L-1, obtain the correspondinc~
(MPC) for nuclide (i) in uCi/ml.
The value of 3 X 10 uCi/ml should be used for the simplified method.
Page 10 of 88 ST.
IIJCZE PIANT CKMISTRY OPERATING PRDCEXURE NO. C-200, REVISION 11 OFFSITE DOSE CADXKATIONMANUAL OIXM 1.2 (continued) 1.
(continued)
E.
Divide Ci by (MPC)i and write dawn the quotient F. If the simplified method is used, proceed to the next step.
If"determining the MPC fraction by the nuclide-by-nuclide evaluation, repeat steps 1.2.1.C thrush 1.2.1.E for each nuclide reported in the assay, for H3 fram previous month omagosite, and for SR89/90 and,Fe55 fram previous quarter ax@osite.
G.
Add each Ci/(MPC) quotient fram step 1.2.1.E and solve for FL as follows:
R n
i FZ,
=
D Z
(MPC)i i=1 FL = a unit-less value where:
the value of FL could be < or >1.
%he purpose of the calculation is to determune what the initial value of FL is for a given set of release conditions. If FL is >1, administrative steps are taImn to ensure that the actxml release conditions for dilution will ensure that F~ is <1 during the actual release.
FL is called the fractz.on of 10CFR20 MPC because it should never be allured to be >1.
2.
Calculation Process for Gases in Liquid A.
Sum the uCi/ml of each noble gas activity reported in the release.
B.
'Ihe values of R and D fram 1.2.1 above shall be used in the calculations belch:
Fg =
sum of 1.2.2.A uCi ml X R 1
D C.
'Fg shall be less than 2 X 10 4 uCi/ml for the site for all releases in progress.
Each release point will be administratively controlled.
Consult in-plant procedures for instxuctions
Page ll of 88 ST. IIJCIE PUÃZ CSEKLSZRY OPZRATjIZG PROCEiXRE, NO. C-200, REVISION 11 OFFSITE DOSE CALCULATION.MANUM ODCX 1.3 Determin'e ints for Radioactive Li
'd Effluent Monitors Discussion Technical Specification 3.3.3. 9 requires that the liquid effluent monitoring instmnentation alarms'trip setpoints be set to initiate an alarm or trip so that the radioactivity concentration in water in the unrestricted area does not exceed the concentration of
- 10CFR20, Appenciix B, Table II as a result of radioactivity in liquid effluents.
(Technical Specification 3.11.1.1). ~ section presents the method to be used for determining the instnmmntation setpoints.
Gross cpm vs. total liquid activity curves are available for Liquid Effluent Monitors based on a canyosite of real release data.
A dQ~t correlation between gross cpm and the concentrations that would achieve 10CFH20 MPC levels in the discharge catml can be estimated.
%he 1978 liquid release data fram semi-annual reports was used to determine the average undiluted release concentration.
'Ihese concentrations were then projected to a diluted concentration in the discharge canal assundng a 1 gpm release rate and a constant dilution flmr of 121,000 gpm from 1 circ. water pump.
This diluted activity was divided by the nuclide's respective 10CFR20 MPC value (Table L-1) to obtain the Mi column on the table that follows:
ST.
ZIJCIE PLANT CHEMISTRY OP1XATING PfKCEXURE NO C 200 g REVISION 11 OFFSITE DOSE 'AIlXJLATION'MANUALOIXK Page 12 of 88 1.3 (continued)
TABLE 1.3 NUCLIDE SYMBOL I-131 I-132 I-133 I-135 Na-24 Cr 51 Mn-54 Mn-56 Co-57 Co-58 Fe-59 Co-60 Zn-65 Ni-65
-110 Sn-113 Sb-122 Sb-124 W-187 239 Br-82 Zr-95 Zr-97 Mo-99 Ru-103 Sb-125 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 t=
1978 UNDIII3TED uCi/ml1 4.43 E-5 2.23 E-7 3.17 E-6 1.31 E-6 1.72 E-7 2.51 E-5 5.64 E-6 1.11 E-9 3.69 E-7 1.51 E-4 2.92 E-6 3.66 E-5 4.55 E-7 8.23 E-7 1.96 E-6 5.75 E-7 2.15 E-6 8.40 E-6 3.51 E-6 1.57 E-7 3.64 E-7 2.82 E-5 4.05 E-6 3.24 E-6 3.84 E-8 2.26 E-6 2.14 E-5 '"
7.82 E-7 4.85 E-5 6.44 E-7 3.04 E-8 2.37 E-6 4.01 E-4 M,2 3.
(no units) 1.22 E-3 2.30 E-7 2.62 E-5 2.71 E-6 4.74 E-8 1.04 E-7 4.66 E-7 9.17 E-11 7.62 E-9 1.39 E-5 4.83 E-7 1.00 E-5 3.76 E-8 6.80 E-8 5.40 E-7 5.94 E-8 5.95 E-7 3.47 E-6 4.83 E-7 1.30 E-8 7.52 E-8 3.88 E-6 1.67 E-6 6.70 E-7 4.00 E-9 1.87 E-7
'.96'E-5" 1.08 E-7 2.00 E-5 2.66 E-8 2.80 E-9 1.96 E-6
////////////////
1.33 E-3 (1) 1978 Undiluted Release Volume = 7 E 9 mls.
(2) Mi = 1978 Undil. Act Nuclide i MPCi (frcan Table L-1)
X 1
release rate 121000 ggm (dil rate)
A I
vhv v'wv
~
r o r,
r
. w-n
. w...~ w r...
~ ~ tw, s r.
~ r.,ar:
.n vr r rr,vvr~w vvV vw
Page 13 of 88 ST. IUCIE PZtÃZ CHEKZSZfK OPERATING PROCEIX3RE NO C 200'1RISION 11 OFFSITE DOSE
. CAICIUZATIONKQKAL OIXH 1.3 (continued)
~ is the talM average uCi/ml concentration of the reference uuxture and~ is the fraction of the MPC of all nuclides for the release conditions specified.
Dividing~ by ~t yields AMax which is the maxi@am total activity concentration equivalent to the MPC limit for the nuclide distribution typical of radwaste discharges.
4.01 E-4
=
0.302 uCi/ml 1.33 E-3 The assumption that the mixture does nat change is only used for calculational purposes.
- 1. If the effluent monitor requir~ counts per minute units, a
(~) value in cgm should be obtained for the~ (0.302 uCx/ml) fram the release sources radioactive liqtu.d effluent monitor curve of cgm vs. uCi/ml.
NOZE
'this setpoint is for a specified release of 1 ggm into 121000 dilution flaw.
2.
For establishing the setpoint prior to liquid radwaste disch-capes, the~ or~ will be adjusted as needed to account for actual release conditions (i.e., actual design maximUm liquid discharge flow rate, dilution flaw rate, and the contribution of dissolved and entrained Nobles Gas Activityto the Monitor ActivityZevel).
1.4 De the Dose for Radioactive Li id Releases
/R11 Discussion Technical Specification
- 3. 11.1. 2 rec~res calculations be performed at least once per 31 days to verify that cumulative radioactive liquid effluents do not cause a dose in excess of 1.5 mrem to the tatal body and 5 mrem to any organ during any calendar quarter and nat in excess of 3 mrem to the total body and 10 mrem to any organ during any calendar year. ~s section presents calculational method to be used for this. verification.
'Ibis method is based on the methodology suggested by sections 4.3 and 4.3.1 of NUR1M-0133 Revision 1, November, 1978.
Lhe dose factors are a ccaqxmite of bath the fish and shellfish pathways so that the fish-shellfish pathway is the only pathway for which dose will be calculated.
For St. tucie Plant, the adult is the most limiting age group, but the dose for child, and teenager can also be calculated by this method provided that their appropriate dose factors are available for the organ of intev~wt.
Only those nuclides that appear in the Tables of this marnal will be considered.
Page 14 of 88 ST. IIJCIE PI2&Z CKM[8ZRY OPZRRHXG PfKCEIXJRE NO. C-200, REVISION ll OFFSITE DOSE CAICXKATIONMAMJAL ODCÃ 1.4 (continued) 1.
'Ihis method provides for a dose calculation to the total body or any organ for a given age group based on real release conditions during a specified time interval for radioactive liquid release sources.
The equation is:
AiT dt1 Qil (DF) 1 mere:
AiT dose azmnitment in mrem received by organ T of age group (to be specified) during the release time interval dt1.
the camposite dose factor for the. fish-shellfish pathway for nuclide (i) for organ T of age gnxp (to be specified)..'Ihe Ai~ values listed in the Tables in this manual are independent of any site specific information and have. the units mrem-ml uCi-hr
= the number of hours that the release occurs.
= 'Ihe total quantity of nuclide (i) release during dt1 (uCi)
(DF)1
= %he total volume of dilution that acmic~
during the release time period dt1 (i.e., the cirnQating water flow times time)
Qil
%he doses associated with each release may then be sunmed to provide the cumulative dose over a desired time period (e.g.,
sum all doses for release during a 31 day period, calendar gum~ or a year).
tot-~
= Z" D1'
%here: ~
= the total dose caamitznent to organ T due to all releases during the desired time integral(mrem)
Based on the radionuclide distribution typical in radioactive effluents, the calculated doses to individuals are damiLnated by the radionuclides Fe-59, Co-58, Co-60, Zn-65, Nb-95, Cs-134 and Cs-137.
'these nuclides typically contribute over 95< of the total body dose and over 90% of the GI-LLX dose, which is the critical organ.
'Iherefore, the dose canunitment due to radioactivity in liquid effluents may be reasonably evaluated by limiting the dose calculation process to these radionuclides for the adult total body and adult GI-IZZ.
To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.6 is intnxtuced into the equation.
After calculatirg the dose based on these 7 nuclides, the cumulative dose should be divided by 0.6, the conservatism factor.
(i.e., DI = Dl/0.6).
Refer to Appendix B for a detailed evaluation and explanation of this limited analysis approach.
ST. IIJCIE ERAL CSEKIBTRY OPERATING E%KC5KURE NO. C-200, RIVISION 11 OFFSITE DOSE CAICUIATIONMANUAL 0 Page 15 of 88 1.4 (continued) 1.
(continued)
'Ihe methodology that follows is a step-by-step breakdown to calculate doses based on the abave equation.
Refer to the in-plant procedures to determine the applicable organs, age groups, and pathway factors. Ifthe limited analysis, approach is used, the calculation should be limited to the Adult total body dose and Adult GI-LZZ dose fram the fish and shellfish pathways.
Only the 7 previously specified radionuclides should be evaluated.
For the dose calculations to be included in semi-annual reports, the doses to the adult groups and all organs should be evaluated for all radionuclides identified in the liquid effluents.
NOPE Table 1.4 pravides a convenient form for campiling the dose accent';
Deh~e the time inteL~l dtl that the release took place.
%he in-plant proces~ shall describe the procedure for calculating dtl for official release purposes.
B.
Obtain (DF)l for the time period dtl fram Liquid Waste Management Records for the release scam'(s) of interest.
C.
Obtain Qi for nuclide (i) for the time period dt1 fram the Liquid Wakte Management Records D.
Obtain AiT fram the appropriate Liquid Dose Factor-Table
Page 16 of 88 Sr.
ZVCIZ Prmr CKMISZRY OPERAT32IG FRQCEIXRE NO. C-200, R1WISION 11 OFFSITE DOSE CAICUIATIONMAKJAL ODCN TABLE 1.4 FISH AND SHELLFISH PAGANRY TIME/DATE START:
TIME/DATE STOP:
HOURS TOTAL DILUTION VOLUME:
mls AGE GROUP:
ORGAN:
DOSE FACTOR TABLE NUCLIDE ( I )
Ci (uCi)
A)T DOSE (i) mrem Fe-59 Co-58 Co-60 Zn-65 Nb-95 Cs-134 Cs-137 OTHERS TOTAL DOSE If based on limited.anat.ysis,.di.v.ide..by...0.,6.i....
I I
I I
I I
I I
I I
I I
I I
I I
mrem mrem E.
SoLve for Dose (i)
Dose (i)
=
i1 1
iT G
Page 17 of 88 ST. WCIE PZtÃZ CHEMISTRY OPERATING PROCEDURE NO C 200 I REVISION 11
'FFSITE DOSE CAICUZATIONMANUAL OIXR 1.4 (continued) 1.
(continued)
F.
Repeat steps 1.4.1.C through 1.4.1.E for each nuclide reported and each organ required. Ifthe limited analysis method is used, limit, the radionuclides to Fe-59, Co-58, Co-60, Zn-65, Nb-95, Cs-134, and Cs-137 and deteraune the adult tot~ body dose and the adult GI-LLZ dose.
G.
Sum the Dose (i) values to obtain the total dose to organ T fram the fish-shellfish pathway. If the limited analysis method is being used, divide the cuaaiLative dose by a conservatism factor of 0.6 to account for any unexpected variability in radionuclide distribution 1.5 Pro'ect'ose for Radioactive Li id Effluents Discussion Technical Specification 3. 11.1. 3 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce radioactive material in liquid effluents when the projected monthly dose due to liquid releases to unrestricted areas when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
Doses are to'e projected at least once per 31 days.
The following calculation method is provided for perfomniag this dose projection.
The method is based on dose as calculated in section 1.4 with the adult as the bases for projecting i 1.
Obtain the latest result of the monthly calculation of the adult total body dose and the adult's highest organ dose.
'Ihese doses can be obtained from the in-plant records.
2.
Divide each dose by the" number of days"the reactor plant was
'perational during the month.
3.
Multiplythe quotient of each dose by the nurser of days the.
reactor plant is projected to be operational during the next month.
The products are the projected dose for the next month.
lhese values should be adjusted as needed to account for any changes in failed fuel or other identifiable operating conditions that could significantly alter the actual releases.
- 4. If the projected dose is greater than 0.06 mrem to the totM body or greater than 0.2 mrem to the adults highest exposed organ, the liquid radwaste system shall be used to reduce the radioactivity levels prior to release.
Page 18 of 88 ST. IIJCIE PLtÃZ CHEKISBK OPERATlIZG PROCEDURE NO C 200 g REVISION 11 OFFSITE DOSE CAICUZATION MANUM 0
I 2.0 GMKGUS REXZRSES METHODOIDGY
Page 19 of 88 ST. WCIE EKANT CHIMESZRY OPERATING X%KCEIXJRE NO C 200 g REVISION 11 OFFSITE DOSE CADXJIATIONMNUAL OIXN Gaseaus Effluent Model ions Descri ion of Site ('Ihe HJSAR contains the official description of the site characteristics.
Lhe description that follaws is a brief summary for dose calculation purposes only).
The St. tucie Plant is located on an island surtzazded on two sides by the Atlantic Ocean and the Indian River, an estuary of the Atlantic Ocean.
Private pszperty adjoins the plant site in the north and south directions.
A meteorological tawer is located north of the plant near the site property line.
'Jhere are 16 sectors, for dose calculation purposesg divided into 22.5'ach.
'Ihe met tower is calibrated such that a zero degree bearing coincides with TRUE NOKK.
A bearing of zero degrees dissects the north sector such that bearings of 348.75'nd 11.25'efine the boundaries of the north sector.
%he nearest distance to private property occurs in the north sector at approximately 0.97 miles.
For ease of calculation, this 0.97 mile radius is assumed in all dit~ions, although the real Unrestricted Area Boundary is defined in Figure 5.1-1 of the STS.
Doses calculated aver water are-m do not apply to the STS ZCO's or the annual report and may be listed as O.W. (aver water) in lieu of perforating calculations.
%he 0.97 mile range in the NW sector is O.W., but it was chosen as the worst secor for conservative dose calculations using the historical MET data.
Historical MET Data MET data, between September 1,. 1976 and August 31, 1978, fram the St. tucie MET Tower was analyzed by Dames
& Moore of Washington, D.C.
%he methodology used by Dames
& Moore was consistent with methods suggested by Regulatory Guide 1.111, Revision 1.
Recirculation correction factors were also calculated for the St.
tucie Site and are incorporated into the historical MET tables (Tables M5, M6, and M7) in Appendix A of this manual. It was deterauned that these two years are representative data for this locale.
Dose Calculations Dose calculations for Technical Specification dose limits are normally calculated using historical MET data and receptor location(s) which yield calculated doses no lower than the real location(s) experiencing the most exposure.
Actual MET data factors are calculated and used in dose calculations for the Semi-annual reports.
Live MET data and hour-by-hour dose calculations are beyond the scope of this manual.
Historical information and conservative receptor locations, etc., are only used for ease of STS ZCQ dose limit calculations.
Dose calculations for PIS dose limits may be performed using actual MET data, real receptor locations, and sector wind frecpency distribution if desired.
Any dose calculations performed with actual data should note the source of the data in the annual report.
Actual MET data reduction should be performed in accordance with Regulatory Guide 1.111, Revision 1 and should incorporate Reaction Correction Factors fram Table M-4 of this manual.
Page 20 of 88 ST. ZVCIE ver CHEKCSTRY OPERAT3XG PROCEDJRE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCH 2.1 (continued)
Dose Calculations (continued)
The St. tucie site uses the long term ground release model for all gaseous effluents.
Only those radionuclides that appear in the gaseous effluent dose factor tables will be considered in any dose calculations.
Radioiodines are defined as Iodine-131 and I-133 for application to S.T.S.
?CO's.
Other nuclides of Iodine may be included in dose calculations for ease of perfomnirg calculations, but their dose contribution does not have to be included in the STS pply year following the year that the census was ta3o n in to avoid splitting quarters, etc.
2.2 De the Total and Skin Dose Rates for Noble Gas Releases And Establish'e ints for Effluent Monitors Discussion Technical Specification 3.11.2.1 limits the dose rate fram nable gases in airborne releases to <500 mr~yr total body and <3000 mremgyr skin.
Technical Specification 3.3.3.10 requires that the gaseous radioactive effluent monitoring instmnentation be ogmable with alan'/trip setpoints set to ensure that these dose rate limits are nat exceeded.
The results of the sampling and analysis
.prcx~m of Technical Specification Table 4.11-2 are used to demonstrate campliance with these limits.
The follmring calculation method is pravided for detexnuning the dose rates to the total body and skin fram noble gases in airborne releases.
The alarm/trip setpoints are based on the dose rate calculations.
The Technical Specification ZCO s apply to all airborne releases on the site but all releases may be treated as if discharged fram a single release point.
Only those noble gases appearing in Table G-2 will be considered;- 'he calculation methods are based on Sections 5.1 and 5.2 of NUREG-0133, Navember 1978.
The equations are; For 'IGTAL BODY Dose Rate:
n Ki (X/Q)
(Q IX')i 3.
For TOZAL SKIN Dose Rate:
n DRskin
=
[Li + 1.1 Mi] (X/Q)
(Q Inr)i 3.
Page 21 of 88 ST. IIJCIE PZANZ CHEKESTRY OP1XATllZG PROCEEXJEK "NO C 200'EVlSION 11 OFFSITE DOSE CMXUIATIONMAWJAL OIXN 2.2 (continued) where:
n
= total body dose rate fram noble gases in airborne releases (mrem/yr)
= skin dose rate fram noble gases in airborne releases (mrs'yr)
= a mathematical symbol to signify the operations to the right of the symbol are to be performed for each noble gas nuclide (i) through (n), and the irdividual nuclide doses are summed to arrive at the total dose rate for the release source.
Ki
= the total body dose factor due to.gamma emissions for each noble gas nuclide reported in the release source.
(mam-m /uCi-yr)
Mi
= the skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the assay of the release source.
(mrem-m3/uCi-yr)
= the air dose factor due to gamma emissions. for each noble gas nuclide (i) reported in the assay of the release source.
'Ihe constant 1.1 converts mrad to
'rem since the units of Mi are in (mrad-m /uCi-yr)
(X/Q)
= for ground level, the highest calculated annual long term historic relative concentration for any of the 16 sectors, at or beyond the exclusion area boundary (sec/m3)
~ P
~ \\V M ~ Vtl~ '
4s W
'as y=
V /\\
~
~ i 1
(Q DOZ)i= The release rate of noble gas nuclide (i) in uCi/sec fram the release source of interest 1.
Simplified Total Body Dose Rate Calculation Fram an evaluation of past releases, an effective total body dose factor (I( ff) can be derived.
This dose factor is in effect a weighted average total body dose factor, i.e., weighted by the radionuclide distribution typical of past operation.
(Refer to Appendix C for a detailed explanation and evaluation of reff).
The value of Keff has been derived fram the radioactive nable gas effluents for the years
- 1978, 1979, and 1980.
Ihe value is:
I( ff =
6.8 X 10 mren~m uCi-yr
Page 22 of 88 ST. IIJCIE PIAÃZ CKMESTRY OPERATING PROCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAlXXJIATIONMANUAL ODCK 2.2 (continued) 1.
(continued)
'Ihis value may be used in conjunction with the total noble gas release rate (Q DOZ)i to verify that the dose rate is within the allowable limits.
To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is into:xhxced into the calculation.
The simplified equation is:
DRTB
= @ff (Q DOZ)
'.8 To further simplify the determination, the historical annual average meteorological X/Q of 1. 6 X 10 sec/m (Fram Table M-1) may be. substituted into the equation.
Al'so, the dose limit of 500 mxeq/yr may be substituted for~.
MaJcing these substitutions yields a sir@le cumulative (or gross) noble gas release rate limit. This value is:
Noble gas release rate limit = 3.5 X 10 uCi/sec As long as the noble gas release rates do not exceed this value (3.5 X 10 uCi/sec),
no additional dose rate calculations are needed to verify catopliance with Technical Specification 3.11.2.1.
2.
Setpoint Determination To comply with Tech.
Spec.
3.3.3.10, the alarm/trip setpoints are established to ensure that the noble gas releases do not exceed the value of 3.5 X 105 uCi/sec, which corresponds'o a total body dose rate of 500 mrem/yr'." Qie'method" that'follows'is'a step-by-step procedure for establishing the setpoints.
To allow for multiple sources of releases fram diffexmt or caatmon release points, the allowable operating setpoints will be controlled administratively by allocating a percentage of the total allowable release to each of the release sources.
A.
Determine (V) the maxinMm volume release rate potential fram the in-plant procedures for the release sou~ under consideration.
'lhe units of (V) are ft /min.
B.
Solve for A, the activity concentration in uCi/cc that would produce the Y dose rate LCD A =, 3.5 X 10 uCi X min X
ft X
60 sec E
~(V) ft 2.8317 X 10 cc min A = uCi/CC
Page 23 of 88 ST. IIJCIE PUTZ CHIKISTRY OPEZATjlÃG PROQKURE NO. C-200, REVISION 11 OFFSITE DOSE CAIQUIATIONMANUAL ODCÃ 2.2 (continued) 2.
(continued)
C.
Refer to the uCi/cc vs.
cpm curve for the Release Source's Gaseous Effluent Monitor cpm value (C), corresponding to the value of A above.
D.
C is the 100% setpoint, assunung that there are no other release sources on the site.
E.
Obtain the current 4 allocated to this release source from the gaseous wa.~ management logs.
F.
lhe Operating setpoint SP SP = (C) cpm X allott~
in-lant-rocedures 100%
'Ihe total body dose is more limiting than the calculated skin dose.
(Refer to Appendix C for a detailed evaluation.)
Therefore, the skin dose rate calculations are not required ifthe simplified dose rate calculation is used (i.e., use of
+ffto deternune release rate limits).
'Ihe calculation process of the following Section (2.2.3) is to be used ifa~ releases of noble gases exceed the above limit of 3.5 X 10 uCi/sec.
Under these corditions, a nuclide-by-nuclide evaluation is required to evaluate compliance with the dose rate limits of Technical Specification 3.11.2.1.
3.
Total Body and Skin Nuclide"Specific"Dose"Rate Calculations The following outline provides a step-by-step explanation of how the total body dose rate is calculated on a nuclide-by-nuclide basis to evaluate compliance with Tech.
Spec.
3.11.2.1.
Ihis method is only used if the actual releases exceed the value of 3.5 X 105 uCi/sec.
A.
Lhe (X/Q) value =
sec/m3 and is the most limiting sector at the exclusion area.
(See Table M-1 for value and sector.)
B.
Enter the release rate in ft3/min of the release source and convert it to:
60 sec cc/sec volume release rate
page 24 of 88 ST. IUCIE PDKZ CKMISTRY OPERATING PROCEZURE NO. C-200, REVISION 11 OFFSITE DOSE CAIXUZATIONMANUAL ODCN 2.2 (continued) 3.
(continued)
C.
Solve for(Q DOT)i for nuclide (i) by obtaining the uCi/cc assay value of the release source and multiplying it by the product of 2.2.3. B above.
(Q DOT)i = (nuclide [i])
CC sec uCi/sec for nuclide (i)
D.
To evaluate the total body dose rate cbtain the Ki value for nuclide (i) fram Table G-2.
E.
Solve for DRTBi DRTBi Ki(X/Q) (Q DOT)i nu~-m X sec X uCi uCi-yr m
sec mrem total body dose fram nuclide (i) for.
yr the specified release source F.
To evaluate the skin dose rate, obtain the L and Mi values fram Table G-2 for nuclide (i).
G.
Solve for DR k DRsI~ i =
[Li + 1.1 Mi] (X/Q) (Q DCT)i DR~ i
=
mrem skin dose fram nuclide (i) for the
- -. ---yr---specified-release source H.
Repeat steps 2.2.3.D through 2.2.3.G for each noble gas nuclide (i) reported in the assay of the release source.
Z.
The Dose Rate to the Total Body fram radioactive noble gas ganja radiation fram the specified release source is:
DRTBi 3.
J.
The Dose Rate to the skin fram ncble gas radiation fram the specified release source is:
n i
The dose rate contribution of this release source shall be added to all other gaseous release sources that are in progress at the time of intere..C.
Refer to in-plant procedures and logs to determine the Tel~ Dose Rate to the Total Body and Skin fram ncble gas effluents.
ST. IIJCIE PUÃZ CHENIS'I%K OPERATING PBOCEIXJEK NO. C-200, REVISION 11 OFFSITE DOSE C2CJ33IATION MANUAL ODCM Page 25 of 88 2.3 De the Radioicdine
& Particulate Dose Rate to Gaseous Releases Discussion Tech. Spec. 3.11.2.1 limits the dose rate from I-131, I-133, tritium and all radionuclides in particulate form with half lives >eight days to <1500 mreay'yr to any organ.
The following calculation method is provided for de~mining the dose rate from radioiodines (see 2.1) ard particulates and is based on Section 5.2.1 and 5.2.1.1 through 5.2.1.3 in NUKG-0133, November 1978.
%he Infant is the controlling age group in the inhalation, ground plane, and cow/goat milk pathways, which are the only pathways considered for releases.
%he long term (X/Q)D (depleted) and (D/Q) values are based on historical MET data prior to implementing Appendix I.
Only those nuclides that appear on their respective table will be. considered.
'Ihe ecpations are:
For Inhalation Pathwa exclud'-3:
n DRI&SDEtp 4
Q (VQ)D (Q DOT)i For Ground Plane:
n DRI&SDP
=
Pi (D/Q) (Q Inr)i
~ 1.
For %ass-Gm Goat Milk:
n DRZ&SD9Z,
= 5 R5j.
(D/Q) (Q DOT)i 3.
For Tritium Releases Inhalation
& Grass-Qm Goat-Milk:
R-3T (VQ)D (Q ~)H-3 For Total Dose Rate from I & SDP ard H-3 To An Infant T.
~
L~I&SD~ +
H-3T~
Z Normally should be PiT, but RiT values are the sanie, thus use RiT tables in Appendix A.
Page 26 of 88 ST. IDCIE ERAL CKMISTEK OPERATING PROCEDURE NO C 200'EVISION 11 OFFSITE DOSE CAUXKATIONMANUAL ODCÃ
- 2. 3 (continued)
%here IG8DBp m-3T n
The organ of interest for the infant age group The applicable pathways Dose Rate in r~yr to the organ T fram iodines and 8 day particulates Dose Rate in deny'yr to organ T fram Tritium Total Dose Rate in mrem/yr to organ T fram all pathways under consideration A mathematical symbol to signify the operations to the right of the symbol are to be performed for each nuclide (i) through (n), and the individual nuclide dose rates are mmmm'o arrive at the total dose rate from the pathway.
A mathematical ~abol to indicate that the total dose rate Q to organ T is the sum of each of the pathways dose rates Pi lhe dose factor for nuclide (i) for organ T for the pathway specified (units vary by pathway)
'Ihe dose factor for instantaneous ground plane pathway in units of mrem-m sec uCi-yr yf 7,'g 4 'I ~
8 Jf
~ 'I' p
~
Fram an evaluation of the radioactive releases and environmental pathways, the grass-ccar/goat-milk pathway has been identified as the most limiting pathway with the infant's thyroid being the critical organ. ~ pathway typically contributes
>90% of the total dose received by the infant's thyroid and the radioiodine contribute essentially all of this dose.
'Iherefore, it is possible to demonstrate compliance with the release rate limit of'Tech.
Spec.
3.11.2.1 for radioiodines and particulates by only evaluating the infant's thyroid dose for the release of radioiodines via the grass-cxm/goat-milk pathway.
The calculation method of Section 2.3.3 is used for this detexmination. If this limited analysis approach is used, the dose calculations for other radioactive particulate matter and other pathways need not be performed.
Only the calculations of Section 2.3.3 for the radioiodines need be performed to demonstrate compliance with the Technical Specification dose rate limit.
Page 27 of 88 ST. IIJCIE PIANT CKMESZRY OPERATING PfKC1KURE NO. C-200, REVISION ll OFPSITE DOSE CAICUD~ON MANUAL ODCN 2.3 (continued)
The calculations of Sections 2.3.1, 2.3.2, 2.3.4, and 2.3.5 may be omitted.
'Ihe dose rate calculations as specified in these sections are included for completeness and are to be used only for evaluating than radioiodines in airborne releases are abnormally high.
'Ihe calculations of Sections 2.3.1, 2.3.2, 2.3.4, and 2.3.5 will typically be used to demonstrate compliance with the dose rate limit of Tech.
Spec. 3.11.2.1 for radioiodines and particulates when the measured releases of particulate material (other than radioiodines arxl with half lives >8 days) are >10 times the measured releases of raQ3.oiocl3Jles e
1.
The Inhalation Dose Rate Method:
NOPE
'Ihe H-3 dose is calculated as 2.3.4 A.
the controlling location is assuaged to be an Infant located in the sector at the mile range.
Ghe (X/Q)D for this location is sec/m3.
%his value is common to all nuclides.
(See Table M-2 for value, sector and range.)
B.
Enter the release rate in ft3/min of the release source and convert to cc/sec.
ft X
2.8317 X 10 CC X
min
= CC/sec ft 60 sec.
C.
Solve for (Q DOZ)i for nuclide (i) by obtaining the uCi/cc assay value of the release source activity and:multiplying it by the product of 2.3.1.B above.
(Q DOT)i =
nuclide i assa uCi X
Value 2.3.1.B cc CC sec (Q DOZ) '
uCi/sec for nuclide (i)
D.
Obtain the Ri value from Table G-5 for the organ T.
E.
Solve for DRi DRiT = RiT (X/Q)D (Q IX')i=
mrem-m X
sec X uci uci-yr m
sec DRiT = mrem
'Ihe Dose Rate to organ T from nuclide (i)
F.
Repeat steps 2.3.1.C through 2.3.1.E for each nuclide (i) reported in the assay of the release source.
Page 28 of 88 ST. WCIE PIANT CKMESTRY OPERATING"PROCEDURE'NO.-- C-'200, REVISION 11'FFSITE DOSE CAICUZATIONMANUAL-ODCÃ 2.3 (continued) 1.
(continued)
G.
The Dose Rate to the Infarrts organ T fram the Inhalation Pathway is:
DRInhalationT
=
DR1
+
DR2
+
for all nuclides except H-3.
%his dose rate shall be added to the other pathways as per 2.345 Total Organ Dose.
NOPE Steps 2.3.1. C thme3h 2.3.1.G need to be campleted for each o T of the Infant.
2.
'Ihe Ground Plane Dose Rate Method:
N7ZE Tritium dose via the urd lane is zero.
A.
Lhe controlling location is assumed to be an Infant located in the sector at the mile range.
%he (D/Q) for this location is 1/m.
Lhis value is ccaamon to all nuclides.
(See Table M-2 for sector, range and value. )
B.
Enter the release rate in ft3/min of the release source and convert to cc/sec.
ft X
2.8317 X 10 cc X
min
= cc/sec IlGn ft 60 sec.
4t.
'0 844 ~ -4'4'7 y \\
~IP
~
C.
Solve for (Q DOT)i for nuclide (i) by obtaining the uCi/cc assay value fram the release source activity and multiplying it by the product of 2.3.2. B above.
(Q DOT)i nuclide i assa uCi X
Value 2.3.2.B cc (Q DOT)i uCi/sec for nuclide (i)
D.
Obtain the Pi value fram Table G-3 E.
Solve for DRi DRi iT (D/Q)
(Q ~)i mrem-m sec X
1 X uCi uCi-yr le sec DRi =
mrem Lhe Dose Rate to organ T fram yr nuclide (i)
Page 29 of 88 ST. IIJCIE PI2ÃZ CHEKESTRY OFERATING PROCEDURE NO. C-200, REVISION ll',
OFFSITE DOSE CAICUIATIONMANUAL ODCN 2.3 (continued) 2.
(continued)
F.
Repeat steps 2.3.2.C through 2.3.2.E for each nuclide (i) reported in the assay of the release source.
G.
The Dose Rate to the Infant's Total body fram the Ground Plane Pathway is:
~ py
=
GRy
+
QR2
+
+
for all nuclides.
This dose rate shall be added to the other pathways as per 2.3.5.
3.
'Ihe Grass-Caw Goat-Milk Dose Rate Method:
NOFE H-3 dose is calculated as 2.3.4.
A.
The controlling animal was established as a located in the sector at miles.
Ihe (D/Q) for this location is 1/
%his value is ex@amon to all nuclides.
(See Table M-3 for sector,
- range, and value. )
B.
Enter the anticipated release rate in ft3/min of the release source and convert to cc/sec.
ft X
2-8317 X 10 CC X
min
= cc/sec 60 sec.
C.
Solve for (Q DOZ)i for nuclide (i) by obtainizg the uCi/cc assay value of the release'source activity< and multiplying it hy the product of 2.3.3.B above.
(Q DOI')i =
nuclide i assa uCi CC X
value 2.3.3.B cc (Q DOI')i uCi/sec for nuclide (i)
D.
Obtain the Ri value from Table G-6(7)
(whichever is the controlling animal, ccar/goat, for infant).
Ifthe limited analysis approach is being used, limit the calculation to the infant thyroid.
ST.
IIJCZE PI2ÃZ CKMLSZRY OPERATING ER3CEIXRE NO. C-200, REVISION 11 OFFSITE DOSE CADXKATIONMANUAL ODCN Page 30 of 88 2.3 (continued) 3.
(continued)
E.
Solve for DR.T iT DRiT = RiT (D/Q)
(Q DVI')i
~~ m sec X
1 X
uCi..
uCi-yr sec DRiT =
mr~yr the Dose Rate to organ T fram nuclide (i)
F.
Repeat steps 2.3.3.C through 2.3.3.E for each nuclide- (i),
reported in the assay of the release source.
Only the radioiodines need to be included ifthe limited analysis approach is being used.
G.
The Dose Rate to the Infant's organ T from Grass-
-Milkpathway is:
D~s-
-MilkT =
DR1 + DR2 +
+ DR for all nuclides.
'Ibis dose rate shall be added to the other pathways as per 2.3.5 - Total Organ Dose.
NOTE Steps 2.3.3.C through 2.3.3.G need to be campleted for each organ of the Infant.
Limit the calculation to the infant th id if the limital anal sis a roach is be'sed.
4.
%he H-3 Dose Rate Method:
A.
Me controlling'ocations" and their-'(X/Q) D values-for each pathway are:
Inhalation Infant at range in the sm~r.
(X/Q)D =
sec/m (See Table M-2 for range, secor and value)
Ground Plane Does not apply to H-3 Grass-Caw Goat-Milk-located in the sector at miles with an Infant at the exclusion area in the sector drinking the milk.
Ihe (X/Q)D for the location is (X/Q)D =
sec/m3.
(Fram Table M-6 at the range and sector cor2nsponding to the location of the MilkAnginal above.)
\\
ST. WCIE PLANT CKMESTRY OPERATING PBOCEXURE NO. C-200, REVISION 11 OFFSITE DOSE CAHXJZATION MANUAL OIXK Page 31 of 88 2.3 (continued) 4.
(continued)
B.
Enter the anticipated release rate in ft /min of the release source and convert it to cc/sec.
ft X
2.8317 X 10 CC" X
min ft 60 sec.
cc/sec volume release rate.
C.
Solve for (Q DOT)H 3 for Tritium, by obtainizg the uCi/cc assay value of the release
- source, and multiplying it by the product of 2.3.4.B above.'Q CC sec (Q DOT)H 3 uCi/sec activity release rate D.
Obtain the, Tritium dose factor (Ri) for Infant organ T fram:
Inhalation Grass-Cmr Goat -Milk G-6 7 E.
Solve for DH 3 (Inhalation) using the (X/Q)D for inhalation from 2.3.4.A and RH 3 (Inhalation) from 2.3.4.D.
H-3Inh H-3
( VQ) D (Q ~)H-3 I
3
= Ill&~~from"H 3" Infant -Inhalation for organ T F.
Solve for DH 3 (Grass-
-Milk) using the (QQ)D for Grass-Milk fram 2.3.4.A and (Grass-
-Milk) from 2.3.4.D 3G ~
RH 3G ~
(X/Q) D (Q DOT)H 3 mrean/yr from H-3 Infant G-G.
Repeat steps 2.3.4.D through 2.3.4.F for each Infant organ T of interest.
H.
The individual organ dose rates from H-3 shall be added to the other organ pathway dose rates as per 2.3.5.
Page 32 of 88 ST.
IIJCZE PI2QG'KMESTRY
-OPIZQTING PROCEDURE 'NO. C-200, REVISION 11 OFFSITE DOSE'CAIlXJIATION MANUAL. ODCÃ 2.3 (continued) 5.
De the Total Dose Rate from Iodines SD-Particulates and H-3 fmm Release Source s A.
The following table describes all the pathways that must be sunned to arrive at the total dose rate to an organ T:
I PATHWAY Inhalation I&8DP I
Ground Pl.
I&SDP Gr-
~1k I&SDP Inhalation H-3 Gr-sum of above STEP REF.
2.3.1.G 2.3.2.G 2.3.3.G 2.3.4.E 2.3.4.F B.
Repeat the above smanation for each Infant organ T.
C.
%he KRT above shall be added to all other release sources on the site that will be in progress at any instant.
Refer to in-plant procedure and logs to determine the Total DRT to each organ.
2.4 De the Geant Air Dose for Radioactive Noble Gas Release Source s Discussion Tech.
Spec.
3.11.2.2 limits the air dose due to noble gases in gaseous effluents for ganana radiation to <5 mrads for the quarter and to <10 mrads in any calendar year.
'The follmring calculation method is provided--for-deterauning"the noble gas ghana air dose and is based on section 5.3.1 of NUREG-0133, November 1978.
'Jhe dose calculation is independent of any age group.
'lhe ecgmtion may be used for STS dose calculation, the dose calculation for the annual report or for projecting dose, provided that the appropriate value of (X/Q) is used as outlined in the detailed explanation that follows.. %he equation for gamaa air dose is:
n air 3 17 X 10-8 Mi QJQ) Qi 3.
Page 33 of 88 ST. IIJCIE PZt&1 CHEMISTRY'PERATING PHQC1KlURE NO C 200I REVISION 11 OFFSITE DOSE CAICUZATION MANUAL ODCÃ 2.4 (continued)
Where DY-air
= gamma air dose in mrad fmm radioactive noble gases.
= A mathematical symbol to signify the operations to the right side of the symbol are to be performed for each nuclide (i) through (n), and sunset to arrive at the total dose, from all nuclides reported during the inM~l.
No units apply.
3.17 X 10
= the inverse of the neer of seconds per year with units of year/sec.
Mi
= the gamma air dose factor for radioactive noble gas nuclide (i) in units of mrad-m uCi-yr (X/Q)
Qi
= the long term atmospheric dispersion factor for ground level releases in units of sec/m The value of (X/Q) is the same for all nuclides (i) in the dose calculation, but the value of (X/Q) does vary depending on the Limiting Sector the L.C.O. is based on, etc.
= the number of micro-curies of nuclide(i) released (or proj~~) during the dose calculation ensure period.
(e.g., month, quarter, or year)
Fram an evaluation of past releases, a single effective gastlla air dose factor (M ff) has been derived, which is representative of the radionuclide abundances and conwsponcUing dose contributions typical of past operation.
(Refer"to-Appendix-C.-for-a. detailed. explanation and evaluation of M ff).
The value of +ff has been derived fram the radioactive noble gas effluents for the years
- 1978, 1979, and 1980.
'Ihe value is M
= 7.4 X 102 mrad uCi/m this value may be used in conjunction with the total noble gas releases
(
-Qi) to simplify the dose evaluation and to verify that the cumulative gamma air dose is within the limits of Specification 3.11.2.2.
To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is intzoctuced into the calculation.
The simplified equation is 3.17 X 10 Meff X/Q Qi 0.8 3.
Page 34 of 88 ST. WCIE PUKE CHEMISTRY OPERATING PRO CIKORE NO 200 I RLVISION 11
'FFSITE DOSE CATXUIATIONMANUAL OIXX 2.4 (continued)
For purposes of calculations, the appropriate meteorological dispersion (X/Q)fram Table M-1 should be used.
Tech. Spec. 3.11.2.2 vapxires that the doses be evaluated once per 31 days, (i.e.,
monthly).
She quarterly dose limit is 5 mrads, which corresponds to a monthly allotnent of 1.7 mrads. If the 1.7 mrads is substituted, for D~, a cunaQative noble gas monthly release cbjective can be cal ated.
This value is 36,000 Ci/month, noble gases.
As long as this value is not exceeded in any month, no additional calculations are needed to verify compliance with the qu;overly ncble gas release limits of Specification 3.11.2.2.
Also, the gartttna air dose is more limiting than the beta air dose.
Therefore, the beta air dose does not need to be calculated per Section 2.5 if the M ff dose factor is used to detm+Lne the garttma air dose.
Refer to Appendix C for a detailed evaluation and explanation.
The calculations of Section 2.5 may be omitted when this limited analysis approach is used, but should be performed ifthe radionuclide specific dose analysis is performed.
Also, the radionuclide specific calculations willbe performed for inclusion in Semi;annual reports m
The following steps provide a detailed explanation of how the radionuclide specific dose is calculated.
'ibis method is used to evaluate cgm~ly doses in accordance with Tech.
Spec.
3.11.2.2 if the releases of noble gases during any month of the qu eer exceed 36,000 Ci.
1.
To determine the applicable (X/Q) refer to Table M-1 to obtain the value for the type of dose calculation being performed.
(i.e., Quarterly L.C.O. or.Dose'.Projection for:examples).
%his value of (X/Q) applies to each nuclide(i).
2.
Detmxdne (Mi) the gamma air dose factor for nuclide (i) fram Table G-2.
3.
Obtain the micro-~ies of nuclide (i) from the in-plant.
radioactive gaseous waste management logs for the sources under consideration during the time interval.
4.
Solve for Di as follows:
Dz
=
3.17 X 10-8 X M mrad mX ~X-mmu X Q~uCi sec UCi-tu.
m i
Di
=
mrad
=
the dose from nuclide (i) 5.
Perform steps 2.4.2 through 2.4.4 for each nuclide (i) reported during the time inter~i in the source.
page 35 of 88 ST. IIJCIE PIC%2, CHEMISTRY OHXAT32V PROCEIXRE NO. C-200; R1WlSION 11-OFFSITE DOSE CAIXGZATIONMANUAL ODCN 2.4 (continued) 6.
The total gamma air dose for the pathway is determined by summing the Di dose of each nuclide (i) to obtain DY-air dose.
DzZ air = D1 + D2 +
+ Dn
=
mrad NOPE Ccarpliance with a 1/31 day QX), Quarterly ZCO, yearly or 12 consecutive months ZCG can be demonstrated by the limited analysis approach using +ff.
Using this method only requires that steps 2.4.2 through 2.4.5 be performed one time, remembering that the dose must be divided b
- 0. 8 the conservatism factor.
7.
Refer to in-plant. procedures for ccaaparing the calculated dose to any applicable limits that might apply.
2.5 Determin'he Beta Air Dose for Radioactive Noble Gas Releases Discussion Tech.
Spec. 3.11.2.2 limits the quarterly air dose due to beta radiation from noble gases in gaseous effluents to <10 mrads in any calendar qu-~ and <20 mrads in any calendar year.
'Ihe following calculation method is provided for deteanining the beta air dose and is based on Sections 5.3.1 of NURZG-0133, November 1978.
'Ihe dose calculation is independent of any age group.
'Ihe equation may be used for STS dose calculation, dose calculation for annual reports, or for projecting dose, provided that the appropriate value of (+Q) is used as outlined in the detailed explanation that follows.
~
=
~
W S
~ ~,
~ ~ ar ew (~(re
~
S.-
r~,a ir
Page 36 of 88 ST. IIJCIE,E~
CKRCSTRY'. OHXAT3IZG PfKCEGURE NO. C-200, BEVISION:11 OFFSITE IXSE CAICUIATIONMANUM OIXK 2.5 (continued)
'Ibe equation for beta air dose is:
n DB air 3 17 X 10-8Ni(X/Q) Q 3.
Where:
B-air
= beta air dose in mrad fr@an radioactive noble gases.
n
= a mathematical ~nbol to signify the operations to the right side of the sya6ml are to be performed for each nuclide (i) through (n), and sunned to arrive at the total dose, frcan all nuclides reported during the interval.
No units apply.
3.17 X 10
= the inverse of the number of seconds per year-with units of year/sec.
Ni (X/Q)
= the beta air dose factor for radioactive noble gas nuclide (i) in units of mrad-m uCi-yr the long tenn atmospheric dispersion factor fear ground level rele-mes in units of sec/m3.
The value of (X/Q) is the same for all nuclides (i) in the dose calculation, but the value of (X/Q) does vary depending on the Limiting Sector the DX) is based on, etc.
Qi
= the raanber-of=microWries of-nuclide (i) released (or projected) during the dose calculation exposure period Xhe beta air dose does not have to be evaluated if the noble gas gamna air dose is evaluated by the use of the effective gamma air dose factor (N ff).
However, if the nuclide specific dose calculation is used to evaluate compliance with the quarterly gamma air dose limits (Section 2.4), the beta air dose should also be evaluated as outlined belch for the purpose of evaluating campliance with the cpm<erly beta air dose limits of Tech.
Spec. 3.11.2.2.
9he follmring steps pmvide a detailed explanation of how the dose is calculated.
1.
To detexmine the applicable (X/Q) refer to Table M-1 to obtain the value for the type of dose calculation being performed (i.e.,
quarterly ZCG or Dose projection for examples).
This value of (X/Q) applies to each nuclide (i).
2.
Determine (Ni) the beta air dose factor for nuclide (i) from Table G-2.
Page 37 of 88 ST. WCIE PIXY CSHESZRY OPERATING PBOCEIXJEK NO.'-200, REVlSION 11 OFFSITE DOSE CADXJIATIONMANUAL ODCN 2.5 (continued) 3.
Obtain the micrc~uries of nuclide (i) fram the in-plant radioactive gaseous waste management logs for the source under consideration during the time interval.
4.
Solve for Di as follows:
Di =
3.17 X 10 8 sec X
N mrad-m X
X sec X ~uCi uCi-yr m
1 Di = mrad = the dose fram nuclide (i) 5.
Perform steps 2.5.2 through 2.5.4 for each nuclide (i) reported during the time interval in the release source.
6.
The total beta air dose for the pathway is deternuned by summing the Di dose of each nuclide (i) to obtain DB air dose.
Q+ D2
+ Da
=
mrad 2.6 De the Radioiodine and Particulate Dose To An Cumulative Releases 7'.
Refer to in-plant procedures for catttparing the calculated dose to any applicable limits that might apply.
Discussion Technical Specification 3.11.2.3 limits the dose to the total body or any organ resulting fram the release of I-131, I-133, tritium, and particulates with half-lives >8 days to <7.5 mrem during any calendar quarter and <15 mrem during any calendar year.
Ihe following calculation method is provided for detexmining the critical organ dose due to releases of radioiodines and particulates and is based on Section 5.3.1 of. NUR1~0133-,<<Navaober-1978.
Ihe equation can be used for any age coup provided that the appropriate dose factors are used and the total dose reflects only those pathways that are applicable to the age group.
'Ihe (+Q) D synbol represents a
DEXLlETED-(QQ) which is different fram the Noble Gas (X/Q) in that (X/Q)D takes into account the loss of I&SDP and H-3 fram the plume as the semi-infinite cloud travels aver a given distance.
'Ihe (D/Q) dispersion factor represents the rate of fallout from the cloud that affects a square meter of ground at various distances fram the site.
'Ihe I&SDP and H-3 notations refer to I-131, I-133 Particulates having half-lives >8 days, and Tritium.
For ease of calculations, dose fram other Iodine nuclides may be included (see 2.1).
Tritium calculations are always based on (QQ)D.
'Ihe first step is to calculate the I&8DP and H-3 dose for each pathway that applies to a given age group.
The total dose to an organ can then be determined by summing the pathways that apply to the receptor in the sector.
Page 38 of 88 ST. IIJCIE PLANT CHEMISTRY OPERATING PROCEDURE-NO.
C-:200, REVISION 11 OFFSITE DOSE CAlXGZATIONMANUAL'IXK
- 2. 6 (continued)
'Ihe equations are:
For Inhalation Pathway (exclucUing H-3):
n DI&SD~ =
3.17 X 10 Ri (X/Q)DQi 3.
For Ground Plane, or Grass~/Goat~1k n
DI&SD~ =
3.17 X Ri (D/Q)Qi 3.
For each pathway above (excluLimp Ground Plane)
For Tritium:
3 17 X 10-8R 3T(X/Q)DQ For Total Dose fram Particulate Gaseous effluent to organ T of a specified age group:
~DI&SDP
+
DH-31 2
Where:
I&8DP n
the organ of interest of a specified age group the applicable pathways for the age group of interest Dose in mrem to 'the organ T 'of a specified age group fram radioiodines and SD Particulates Dose in mrem to the organ T of a specified age group fram Tritium Total Dose in mrem to the organ T of a specified age group from Gaseous particulate Effluents A mathematical symbol to signify the operations to the right of the ~nbol are to be performed for each nuclide (i) through (n), and the individual nuclide doses are sunmed to arrive at the total dose fram the pathway of interest to organ T.
A mathematical syahol to indicate that the tot-Q.
dose Dl to organ T is the sum,of each of the pathway doses of I&SDP and H-3 fram gaseous particulate effluents.
Page 39 of 88 ST. WCIE PUNT CK!MISTILYOPERATING PROCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCÃ
- 2. 6 (continued) 3.17 X 10
= The inverse of the number of seconds per year with units of year/sec.
Ri (VQ)D (D/Q)
Qi QH-3
= The dose factor for nuclide (i) (or H-3) for pathway Z to organ T of the specified age group.
The units are either ItKEIMIP fGL pi~~
IIEIKt%P SEC fOL pKtltABpS yr OCi usinp g/Q)D (R
yr uzi usitrf (D/g)
=-The depleted-(X/Q) value for a specific location.
where the receptor is located (see discussion).
The units are sec/m3
= the deposition value for a specific location where the receptor is located (see discussion).
'Ihe units are 1/m2 where m=meters
= The rnanber of micnr-Curies of nuclide (i) released (or projected) during the dose calculation exposure period+
= the number of mien>-Curies of H-3 released (or projected) during the dose calculation measure period.
As discussed in Section 2.3, the grass-caw/goat-milk pathway has been identified as the most limiting pathway with the infant's thyroid being the critical organ.
This pathway typically contributes
>90< of the total dose received by the infant's thyroid and the radioiodine contributes essentially all of this dose.
Therefore, it is possible to demonstrate campliance with the dose li'm'it of Tech.
Spec.
3.11.2.3 for radioiodines and particulates by only evaluating the infant's thyroid dose due to the release of radioiodines via the grass~/goat-milk pathway.
'Ihe calculation method of Section 2.6.3 is used for this deterndnation.
'Ihe dose determined by Section 2.6.3 'should be divided by a conservatism factor of 0.8.
This added conservatism provides assurance that the dose determined by this limited analysis approach willbe < the dose that would be determined by evaluating all radionuclides and all pathways. Ifthis limited analysis approach is used, the dose calculations for other radioactive particulate matter and other pathways need not be performed.
Only the calculations of Section 2.6.3 for the radioiodines are required to demonstrate compliance with the Tech.
Spec.
dose limit.
Hcarever, for the dose assessment included in Semi-Annual Reports, doses will be evaluated for the infant age groups and all organs via all designated pathways fram radioiodines and particulates measured in the gaseous effluents acconUing to the sampling and analyses recpired in Tech.
Spec.
Table 4.11-2.
The following steps provide a detailed explanation of how the dose is calculated for the given pathways:
Page 40 of 88 ST. IIJCIE E~
CHEKISTRY OPERATING PROCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAIXUIATIONMANUAL ODCM
- 2. 6 (continued) 1.
'Ihe Inhalation Dose Pathwa Method:
NOPE Lhe H-3 dose should be calculated as 2.6.4.
A.
Detexnune the applicable (X/Q)D from Table M-2 for the location where the receptor is located.
%his value is common to each nuclide (i)
B.
C.
Deternune the Ri factor of nuclide (i) for the organ T and age group fram Table G-5.
Obtain the minn-Curies (Qi) of nuclide (i) fram the radioactive gas waste management logs for the release source(s) under consideration during the time interval.
D.
Solve for Di Di
=
3.17 X 10 Ri(QQ) DQi Di mrem fram nuclide (i)
E.
F.
Perform steps 2.6.1.B through 2.6.1.D for each nuclide (i) reported during the time interval for each organ.
'Ihe Inhalation dose to organ T of the specified age group is debmuned by summing the Di Dose of each nuclide (i)
DInhalation
=
D1 + D2 +
(Age Group)
Refer to 2.6.5 to determine the total dose to organ T fram radioiodines
& 8D ~iculates 2.
The Ground Plane Dose Pathwa Method:
NOZE Tritium dose via the ground plane is zero.
'Ihe total Body is the only organ considered for the Ground Plant thwa dose.
A.
B.
C.
Determine the applicable (D/Q) fram Table M-2 for the location where the receptor is located.
This (D/Q) value is carmnon to each nuclide (i)
Determine the Ri factor of nuclide (i) for the total body fram Table G-4.
The ground plane pathway dose is the same for all age groups.
Obtain the micro-Curies (Qi) of nuclide (i) fram the radioactive gas waste management logs for the source under consideration.
page 41 of 88 ST. WCIE PIANT CEMESTRY OPERATING PROCEDURE NO C 200 g R1VXSION 11 OFFSITE DOSE CAIXUIATIONMANUAL ODCN
- 2. 6 (continued) 2.
(continued)
D.
Solve for Di Di 3.17 X 10 Ri (D/Q)Qi Di mrem for nuclide (i)
E.
Perform steps 2.6.2.B through 2.6.2.D for each nuclide (i) reported during the time =int~.
F.
%he Amund Plane dose to the tni~ body is detexmined by su@mung the Di Dose of each nuclide (i)
DGr pl ~~ Dl+ D2 +
mrem Refer to step 2.6.5 to calculate total dose to the Total Body.
3.
'Ihe Grass-Ccar Goat-Milk Dose Pathwa Method:
NOTE Tritium'dose is calculated as 2.6.4 A.
A cd, or a goat, will be the controlling anhal; (i.e., dose willnot be the sum of each animal), as the human receptor is assuned to drink milk from only the most restrictive animal.
Refer to Table M-3 to determine which anginal is controlling based on its (D/Q).
B.
Deteraune the dose factor Ri for nuclide (i), for organ T, from 1.
Fram Table G-6 for a cow, or; 2.
Fram Table G-7 for a goat.
If the limited analysis approach is being used, limit the calculation to the infant thyroid.
C.
Obtain the micrcMuries (Qi) of nuclide (i) from the
.radioactive gas wa.M management logs for the release source under consideration during the time inta~i.
I D.
Solve for Di Di
=
3.17 X 10 Ri(D/Q)Qi Di mrem from nuclide (i)
Page 42 of 88 ST. WCIE PIANT CKMEPZRY,OPiPATING PBOCEXX3RE NO. C-200, REVISION 11 OFFSITE DOSE CAICIUIATIONMANUAL OIXN
- 2. 6 (cont,inued) 3.
(continued)
E.
Perform steps 2.6.3.B through 2.6.3.D for each nuclide (i) reported during the time int~wal.
Only the radioiodines need to be included if the limited analysis approach is used.
F.
%he Grass-Ccar-Milk (or Grass-Goat-Milk) pathway dose to organ T is determined by sumndng the Di dose of each nuclide(i).
G-C-M (
G-G-M)
Ihe dose to each organ should be calculated in the same manner with steps 2.6.3.B through 2.6.3.F.
Refer to step 2.6.5 to detexn6ne the total dose to organ T fram radioiodines
&8D Particulates.
Ifthe limited analysis approach is being used the infant thyroid dose via the grass-caw(goat)-milk pathway is the only dose that needs to be deterauned.
Section 2.6.5 can be amitted.
4.
'Ihe Gaseous Tritium Dose Each Pathwa Method:
A.
B.
%he controlling locations for the pathway(s) has already been determined by:
Inhalation as per 2.6.1.A Ground Plane not applicable for H-3 Grass-Cmr/Goat-Milk as per 2.6.3.A Tritium dose calculations use the depleted (X/Q)D in Lead of (D/Q).
Table M-2 describes where the (X/Q) D value should be obtained from.
C.
Determine the Pathway.,Tritium. dose factor (RH 3) for the organ T of interest from the Table specified belcar:
Infant INHAIATION COW GOAT G-6 G-7 D.
Obtain the micro~ries (Q) of Tritium fram the radioactive gas waste management logs (for projected doses the micro-Curies of nuclide(i) to be projected) for the release source(s) under consideration during the time ind~l.
%he dose can be calculated from a single release source, but the total dose for S.T.S. limits or.quarterly reports shall be from all gaseous release sources.
E.
Solve for D 3
3 ~ 17 X 10 R
3 (QQ) DQ mrem fram Tritium in the specified pathway for organ T of the specified age group
Page 43 of 88 ST. IIJCIE PIt&Z CHEKKSTRY OPEBATING PBOCEIXJEK NO C 200 g REVISION 11 OFFSITE DOSE CAD~TION MEAL ODCH
- 2. 6 (continued) 5.
De the Total Dose Fram Iodines SD-Particulates and H-3 Fram Cumulative Gaseous Releases NCfZE SIS ?CO dose limits for I&SDP shall consider dose fram all release smuts fram the reactor unit of interest.
A.
'Ihe following pathways shall be suntmed to arrive at the total dose to organ T fram a release source, or if applicable to STS, fram all release sources:
Grass-
-Milk H-3 I
PATHNAY Inhalation I&SDP Ground Plane I&SDP Grass-
~1k I&SDP Inhalation H-3 STEP 2.6. 1.F I
262F I
2.6.3.F 2.6.4.E 2.6.4.E I
DoseT =
(
S of Ab e
B.
The dose to each of the INF2ÃZ'S ORGANS shall be calculated:
BONE g IZVERg IRQRIDg KIDNEYg ZI3NGg
'XOZAL BODYg
& GI ILI The INFANT organ receiving the highest exposure relative to its STS Limit is the most critical organ for the radioiodine SD Particulates gaseous effluents.
2.7 Pro'ect'ose for Radioactive Gaseous Effluents Discussion Tech.
Spec.
3.11.2.4 requires that the gaseous radwaste treatment system be used to reduce radioactive materials in waste prior to discharge when the'projected-dose-due to gaseous effluents would exceed 0.2 mrad for gamtta radiation and 0.4 mrad for beta radiation.
The following calculation method is provided for determining the projected doses.
'Ibis method is based on using the results of the calculations performed in Sections 2.4 and 2.5.
1.
Obtain the latest results of the monthly calculations of the ganma air dose (Section 2.4) and the beta air dose if performed (Section 2.5).
'Ihese doses can be obtained fram the in-plant'. records.
2.
Divide these doses by the nunber of days the plant was operational during the month.
3.
Multiplythe quotient by the number of days the plant is projects to be operational during the next month.
The product is the projected dose for the next month.
The value should be adjusted as needed to account for any ch;ages in failed-fuel or other identifiable operating conditions that could significantly alter the a~ releases.
- 4. Ifthe projected doses are >0.2 mrads gamtna air dose or 0.4 mrads beta air dose, the appropriate subsystems of the gaseous radwaste system shall be used to reduce the radioactivity levels prior to release.
Page 44 of 88 ST. WCIE PIANOS CKMESTRY OPERATING HKCEDURE NO C 200 g REVISION 11 OFFSITE DOSE CAZCULATIONKQKAL ODCÃ 3.0 40 CFR 190 Dose Evaluation Discussion Dose or dose ccmnu.tment to a real irdividual fram all uranium fuel cycle sources be limited to <25 mrem to the total body or any organ (excx~ thyroid, which is limited to <75 mrem) over a period of 12 consecutive months.
The following approach should be used to demonstrate campliance with these dose limits.
This approach is based on NUR1.'G-0133, Section 3.8.
3.1 Evaluation Bases Dose evaluations to demonstrate compliance with the abave dose limits need only be performed ifthe quarterly doses calculated in Sections 1.4, 2.4 and 2.6 exceed twice the dose limits of Tech. Specs.
3.11.1.2.a, 3.11.1.2.b, 3.11.2.2a, 3.1.2.2b, 3.11.2.3a, and 3.11.2.3b respectively; i.e., cgm~ly doses exceeding 3 mrem to the total body (liquid releases),
10 mrem to any organ (liquid releases),
10 mrads gamma air dose, 20 mrads beta air dose, or 15 mrem to the thyroid or any organ fram radioiodines and particulates (atmospheric releases).
Otherwise, no evaluations are required and the remainder of this section can be canitted.
3.2 Doses From Li id Releases For the evaluation of doses to real individuals fram liquid releases, the same calculation method as employed in Section 1.4 will be used.
However, more realistic assumptions will be made concernizg the dilution and ingestion of fish 'and shellfish by individuals who live and fish in the area.
Also, the results of the Radiological Environmental Monitoring program will be included in determining more realistic dose to these real people by praviding data on actual measured levels of plant related radionuclides in the environment.
3.3 Doses From A heric Releases""
For the evaluation of doses to real individuals fram the atmospheric
- releases, the same calculation methods as employed in Section 2.4 and 2.6 will be used.
In Section 2.4, the total body dose factor (Ki) should be substituted for the ~zaa air dose factor (Mi) to determine the total body dose.
Othexwise the same calculation sequence applies.
However, more realistic assumptions will be made concerning the actual location of real individuals, the meteorological conditions, and the consumption of food (e.g., milk).
Data obtained fram the latest land use census (Tech.
Spec.
3.12.2) should be used to determine locations for evaluating doses.
- Also, the results of the Radiological Environmental Monitoring program will be included in determining more realistic doses to these real people by providing data on actual me-mured levels of radioactivity and radiation at locations of interest.
Page 45 of 88 ST. IIJCIE PIXY CH1MESTRY ORATING PBOCEDURE NO. C-200, REVISION 11 OFFSITE DCSE CAQ"UIATIONMANUAL ODCM
- 4. 0 Semi-Annual Radioactive Effluent Re rt Discussion The information contained in a semi-annual report shall not apply to any SIS ZOO.
The reported values are based on actual release conditions instead of historical conditions that the STS IXD dose calculations are based on.
The STS ?CO dose limits are therefore included in item 1 of the report, for information only.
The MPC's in item 2 of the report shall be those listed in Tables L-1 and G-1 of this manual.
The average energy in item 3 of the report is not applicable to the St. Lucie Plant.
%he format, order of nuclides, and any values shown as an example in Tables 3.3 through 3.8 are samples only.
Other formats are acceptable ifthey contain equivalent information.
A table of contents should also accampany the report.
The follmring format should be used:
RADIOACTIVE EFFIDEN'IS SUPPU~RIVK INK)HMATION 1.
RxyQ.atory Limits:
- 1. 1 For Radioactive liquid wa.~ effluents:
a.
The concentration of radioactive material released fram the site (see Figure 5.1-1 in STS-A) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10 4 uCi/ml total activity.
b.
The dose or dose cxzmnitment to a M1MKR OF 'IHE PUBLIC fram radioactive materials in liquid effluents released fram each reactor unit to unre.evicted areas (See Fig. 5.1-1 in STS-A) shall be limited during any calendar qum~ to <1.5 mrem to the total body and to <5 mrem to any organ and <3 mrem to the total body and <10-mrem'to'any organ during any calendar year.
1.2 For Radioactive Gaseous Waste Effluents:
a.
The dose rate in unrestricted areas (see Fig. 5.1-1 in the STS-A) due to radioactive materials released in gaseous effluents fram the site shall be limited to the following values:
The dose rate limit for noble gases shall be <500 mreay'yr to the tot~ body and <3000 mreay'yr to the skin, and The dose rate limit from I-131, I-133, Tritium, and particulates with half-lives >8 days shall be <1500 mvzgyr to any organ.
Page 46 of 88 ST. IIJCIE PIANT CSEKZSTRY OPERATING PROCEDURE NO. C-200, REVISION. 11 OFFSITE DOSE CAICULATIONMANU'IXM I
- 4. 0 (continued) 1.
(corrtinued) 1.2 (continued) b.
%he air dose (see Figure 5.1-1 in the STS-A) due to noble gases released in gaseous effluents, fram each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
During any calendar qum~, to <5 mrad for ganma radiation and <10 mrad for beta radiation and during any calendar year to <10 mrad for ganma radiation and <20 mrad for beta radiation c.
The dose to a MM3ER OF THE HJBIZC fram I-131, I-133, Tritium, and all radionuclide in particulate form, with half-lives >8 days in gaseous effluents released fram each reactor unit to arms at and beyond the S1TE BOUNDARY (see Figure 5.1-1 in the STS-A) shall be limited to the following:
During any calerx3ar quarter to <7.5 mrem to any organ, and during any calendar year to <15 mrem to any organ.
2.
Kocintum Pernussible Concentrations:
Air as per attached Table G-1 Water as per attached Table L-1 3.
Average energy of fission ard activation gases in gaseous effluents is nat applicable to the St. Iucie Plant.
4.
M'easurements and Approximations of Total Radioactivity:
A summary of liquid effluent accounting methods is described in Table 3.1.
A summary of gaseous effluent accounting methods is described in Table 3.2.
Estiznate of Errors IZ D
GASEOUS Error To ic Release Point Mixing Sampling Sample Preparation Sample Analysis Release Volume Am~>
A~1.%
Avc1.%
~Max.
2 5
NA NA 1
5 2
5 1
5 1
5 3
10 3
10 2
5 4
15
'B>aal 0 9
30 10 35 (above values are mcamples only)
The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.
Nuclides that are near bad<ground'relative to the predaminant nuclides in a given sample could easily have errors greater than the above 13.sted maxhtums
Page 47 of 88 ST. ZUCIE PIANr CHEMISTRY OPERATjIZG PROCEEURE NO. C-200, REVISION ll OFFSITE DOSE CAlXXJZATIONMANUAL OIXM
- 4. 0 (continued) 4.
(continued)
TAl3IZ 3. 1 Radioactive Liquid Effluent Sampling and Analysis LIQUID I
SOURCE I
HONITOR I
TANK I
RELEASES I
I STEAH I
GENERATOR BLOIJDOMN I
RELEASES I
SAHPL ING FREQUENCY EACH BATCH I
MONTHLY COMPOSITE QUARTERLY COMPOSITE I
FOUR PER HONTN I
HONTNLY COHPOSITE QUARTERLY COMPOSITE TYPE OF ANALYSIS PRINCIPAL GAHHA EH ITTERS TRITIUM GROSS ALPHA Sr-89 Sr-9D Fe-55 PR INCIPAL GAHHA EHI TTERS AND DISSOLVED GASES I
TR IT IUH GROSS ALPHA Sr-89 Sr-9D Fe-55 I
HETHOD OF I
ANALYSIS
.h.a.
L.S.
G.F.P.
I C.S.
a L.S.i I
.h.a.
L.S.
G.F.P C.S.
a L.S
(
TABLE NOIATION:
Boric Acid Evaporator condensate is normally recovered.to the Primary Water Storage Tank for recycling into the reactor coolant system arxl normally does not contribute to liquid waste effluent totals.
p.h.a.
gamma sp~m pulse height analysis using Lithium Germanium detectors.
All peale@ are identified and quantified.
L.S.
C.S.
G.F.P.'iquid Scintillation counting Chemical Separation Gas Flow Proportional Counting
Page 48 of 88 ST. IIJCIE PUTZ CH1MZSTRY OPl&ATjlZG HKCECURE NO.'-200, REVISION 11 OFFSITE DOSE CAIIOUIATIONKQKAL ODCN
- 4. 0 (continued) 4.
(continued)
TABLE 3.2 Radioactive Gaseous Waste Sampling and Analysis GASEOUS I
METHOD OF I
SOURCE SAMPLIHG FREQUENCY TYPE OF ANALYSIS ANALYSIS (llaste Gas Decayj Tank Releases Each Tank Princi al Gamm'a Emitters G
.h.a.
Containment Pur e Releases Each Pur e
Princi al Gamma Emitters G
.h.a.
H-3 I..S.
I j
I Plant Vent I
I Four er Month Monthly Composite I
Particulates Quarterly Composite Particulates Princi al Gamma Emi tters H-3 Gross Al ha Sr-90 S r-89 G
C P
-.h.a.
L.S.
I P
G F
P ~
I I
C.S.
8, L.S.
L.S.
C.S.
Gaseous Grab Sample Charcoal Filter Sample Particulate Filter Sample Liquid Scintillation Counting Chemical Separation p.h.a.
Gamma spectrum pulse'height analysis using Lithium Germanium detectors.
All peaks are identified and quantified.
G.F.P.
Gas Fleer Proportional Counting
Page 49 of 88 ST. WCIE PIAHZ CKMZSTRY OPERATING'PROCEDURE NO. C-200, REVISION 11 OFFSITE DOSE'AD;GEON MANUAL ODCH
- 4. 0 (continued) 5.
Batch Releases A.
Liquid 1.
Number of batch releases:
2.
Total time period of batch releases:
3.
Maximum time period for a batch release:
4.
Average time period for a batch release:
5.
Minilttum time period for a batch release:
6.
Average dilution stream fleer during the period (see Note 1 on Table 3.3):
All liquid releases are maamarized in tables B.
Gaseous 1.
Huniber of batch releases:
2.
Total time period for batch releases:
3.
Maxilttum time period for a batch release:
4.
Average time period for batch releases:
5.
Mizdmum time period for a batch release:
ltunutes ImILi1nnutes Itunutes minutes minutes llQnutes R1Ilutes minutes All gaseous waste releases are summarized in tables J
6.
Unplanned Releases A.
Liquid 1.
Humt~ of releases:
2.
'Ibtal activity releases:
B.
Gaseous 1.
Humber of releases:
2.
TOM activity released:
C.
See attachltents (if applicable) for:
1.
A description of the event and equipment involved.
2.
Cause(s) for the unplanned release.
3.
Actions taken to prevent a recun~ce 4.
Consequences of the unplanned release Curies Curies 7.
Description of dose assessment of radiation dose fram radioactive effluents to the general public due to their activities inside the site are reported on the January semiannual report.
8.
Offsite dose calculation manual revisions initiated during this reporting period.
See STS-A 6.14 for rapxired attachments to the Semiannual Report.
ST. WCIE PZtÃZ CHEMISTRY OPEZATjING -PROCEDURE NO'-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCN page 50 of 88 FIDRIDA POWER 6 LIGHZ CGNPANY ST. WCIE UNIT g TABLE 3.3:
LIQUID EFFIOENIS SUMMATION OF ALL REXZ%SES A.
Fission and Activation Products 1.
Tat~ Release (Not including Tritium, Gases, Alpha) 2.
Average Diluted Concentration During Period B.
Tritium 1.
Total Release 2.
Average Diluted Concentration During Period C.
Dissolved and Entrained Gases 1.
Tot~ Release 2.
Average Diluted Concentration During Period D.
Grooms Alpha Radioactivity 1.
Tot~ Release E
E E
E.
Volume of Waste Released (Prior to Dilution)
F.
Volume of Dilution Water Used During Period1 LITlXS 1 %be volume reported should be for the entire interval of the reporting period, not just during release intervals.
'Ibis volume should also be used to calculate average dilution stxeam flmr during the period.
Page 51 of 88 ST. WCIE PIANT CHEKLSTRY OPERATING. HRCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCM FIORIDA PIMPS
& IZGHZ CXMPANY ST. WCIE UNIT 5 TABLE 3.4:
IZQUID 1~WEtGS (EXAMPLE PDRMAT)
NUCLIDES RELEASED>>
UNIT CONTINUOUS HODE QUARTER ¹ QUARTER ¹ BATCH HODE QUARTER ¹ QUARTER ¹ 1-131 1.133 1-135 NA-24 CR-51 HN-54 C0.57 C0.58 FE-59 C0-60 ZN-65 N I -65 AG-110 SN-113 SB-122 SB-124 II-187 NP-239 ZR-95 HO-99 RU-103 CS-134 CS-136 CS-137 BA-140 CE-141 BR-B2 ZR-97 SB-125 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI E
E E
E E..
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
E E
Page 52 of 88 ST.
ZIJCIE PLASS CH1MESTRY'OPlXATjlZG PROCEZURE NO".C-200, REVXSION 11 OFFSITE DOSE CAICUIATIONMAKJAL OIXX FIDRIDA HER & LIGHT COMPANY ST.
ZIJCIE UNIT 4 TABLE 3. 4:
LIQUID EFFIHEN'IS (continued)
NUCLIDES RELEASED CE-144 SR.89 SR-90 UNIDENTIF I ED TOTAL FOR PERIOD (ABOVE)
UNIT CI CI CI CI CI CONTINUOUS HODE OUARTER ¹ QUARTER E
E E
E E
E BATCH HODE OUARTER ¹ OUARTER ¹ E
,E E
AR-41 KR 85 CI E
CI E
E XE-131M XE-133 XE-133H XE-135 CI CI CI CI E
E E
E E
<<All nuclides that were detected should be added to the partial list of the example format.
FIORIDA KNUR & Li:GEZ COMPANY ST. WCIE UNIT 5 TABLE 3.5 LIQUID 1~IDEN'IS DOSE SUMMATION Age Group:
Adult Location:
Any Adult Exposure Interval:
From Through Fish 8 Shellfish Pathway to Or an BONE L IVER TNYRO ID KIDNEY LUNG GI-LLI T.
BODY I
CALENDER YEAR I
I DOSE I
I I
mrem
Page 53 of 88 ST. IIJCIE Pl2lNT CKMISTfK OPERATING PROCEDURE NO, C 200 i REVISION 11 OFFSITE DOSE CADXKATIONMANUAL OIXK FIOBIDA POWER & IZGHT CXMPMY ST. IIJCIE UNIT g TMKE 3.6:
GASEOUS EPTIIJEÃIS SUMMATION OF ALL RJK2RSES A.
Fission and Activation Gases 1.
Total Release 2.
Average Release Rate For Period B.
Iodines 1.
Total Iodine-131 2.
Average Release Rate for Period C.
Particulates UN I T, CI UCI/SEC CI UCI/SEC OUARTER ¹ QUARTER ¹ E
E 1.
Particulates T-1/2 8 Days 2.
Average Release Rate for Period 3.
Gross Alpha Radioactivity D.
Tritium 1.
Total Release 2.
Average Release Rate for Period CI UCI/SEC CI CI UCI/SEC E
E E
Page 54 of 88 ST. IIJCIE PZANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL OIXR FIDRIDA. PCNER
& IZGHZ COMPANY ST. WCIE UNIT 5 TM3IZ 3.7 GASEOUS EFEII3EtGS CKKUND G'"VEL RELEASES (EDQHIPIZ FORMAT)
NUCL IDES RELEASED*
UNIT CONTINUOUS HODE QUARTER ¹ QUARTER ¹ BATCH HODE QUARTER ¹ QUARTER ¹ 1.
Fission Gases AR-41 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M XE-138 UNIDENTIFIED CI CI CI CI CI CI CI CI CI CI CI CI E
E E
E E
E E
E E
E E
TOTAL FOR PERIOD (ABOVE)
CI 2.
Iodines I-131 1-133 I -135 TOTAL FOR PERIOD (ABOVE)
CI CI CI CI E
E E
E 3.
Particulates C0-58 SR-89 SR-90 CI CI CI
<<AII nuclides that were detected should be added to the partial list of the example format.
SZ. WCZE PI2ÃZ.
CHEHISTRY OPERATING PROCEIXJEK NO. C-200, REVISION 11 OFFSITE DOSE CADXJIATIONMAKJAL OIXX Page 55 of 88 AGE GRNJP'I'ORIDA HNER & IZGHZ CXMPANY ST. WCrZ UNIT 4 TABIZ 3.8 GASEOUS J~IHEÃIS DOSE SUMKKION CAIENQAR YEAR INFRA EXPOSURE% INTERVAL:
FBQM KHBOUGH I
PATHWAY Ground Plane A
]Grass-
-Milk B
Inhalation A
I TOTAL BONE I
mrem LIVER mrem I
THYROID I
KIDNEY I
mrem mrem LUNG mrem I
GI-LII mrem I
T.
BODY I
mrem I
A SECTOR:
RANGE!
'mi les J
I B
COW GOAT SECTOR:
RANGE:
mites(
I NOBLE GASES Gamma Air Dose Beta Air Dose
[Sector:
I CALENDAR YEA(
I (mrad)
I I
I Ran e:
0.97 miles)
I NOTE I
The dose values above Mere calculated using actual meteorological data during the specified time interval with MET data reduced as Re
. Guide 1.111 March
'1976.
I
ST.
ZVCIE Veer CHEMISTRY OPERATING-PBQGKORE NO.;C-.200, REVISION 11 OFFSITE IXSE CAIlXJIATIONMANUAL ODCÃ Page 56 of 88 APHRlDIX A
- MPC, DOSE FACIOR HISTORICAL M'TEOROZQGICAL TABAC
Page 57 of 88 ST. WCZE PZAÃI.'HEMISTRY,-,OPERATING PEXZDURE NO.,C-200, REVISION 11 OFFSITE DOSE CAIXGIATIONMANUAL ODCM TMKE L-1 MUHAM PEiKISSIBXE CONCEFXBATIONS IN NMt&IN UNRESXRICZED AREAS Hucl fde1 MPC uCi ml Nuclide MPC uCi ml H-3 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co.58 Co-60 Ni-65 Cu-64 Zn-65 Zn.69 Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 3 E-3 3 E-5 2 E-5 2 E-3 1
E-4 1
E-4 8 E-4 5
E-'5 4 E-4 9 E-5 3 E-5 1 E-4 2 E-4 1 E-4 2 E-3 4 E-5 3 E-6 None2 None 2 E-5 None Hone 3 E-6 3 E-7 5 E-5 6 E-5 Y-90 Y.91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Hb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110 Sn-113 2 E-5 3 E-3 3 E-5 6 E-5 3 E-5 6 E-5 2 E.5 1
E-4 9 E-4 4 E-5 3 E-3 None 8 E-5 E-4 1
E-5 3 E-5 8 E-5 Sb-122 Sb-124 Sb-125 Te-125m Te-127m TQ-127 Te-129m 3 E.5 2 E.5 1
E-4 1 E-4 5 E-5 2 E-4 2 E-5 In-113m 1 E-3 Te-129 Te-131m Te-131 Te-132 I -130 I -131 1-132 1-133 I
134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-144 H-187 Hp-239 8 E-4 4 E-5 None 2 E-5 3 E-6 3 E-7 8 E-6 1 E-6 2 E-5 4 E-6 9 E-6 6 E-5 2 E-5 None None 2 E-5 Hone None 2 E-5 None 9 E-5 4 E-5 1
E-5 None 6 E-5 1 E-4 1 If a nuclide is not listed, refer to
- 10CFR20, Appendix 8, and use the most conservative insoluble/soluble MPC where they are given in Table I I, Column 2.
None
- (As per
- 10CFR20, Appendix 8)
"No MPC limit for any single radionuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radioactive half-life less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.>>
ST. IlJCIE PGKZ CHERKSZRY OPERATING E%KCElXJRE NO. C-200, REVISION 11 OFFSITE DOSE CAIlXKATIONMANUAL OIXK Page 58 of 88 TABZE L-2 PATHRAY SALT HATl&FISH AND SHELLFISH AGE GROUP AIX3LT NUCLIDE ORGAN DOSE FACIOR KHYIRID PER uCi GI-LLI
%OTAL BODY H
3 NA 24 P
32 CR 51 MN 54 MN56 FE55 FE 59 CD57 CD58 CD60 NI65 CU64 ZN65 ZN69 HR 82 HR 83 HR 84 HR85 RB86 RB88 RB89 SR 89 SR90 SR91 SR 92 0.
6.08E-01 1.67E+07 0.
0.
0.l.15E+05 8.08E+04 0.
0.
0.
2.02E+02 0.
- 1. 62E+05 3.43E+02 0.
0.
0.
0.
0.
0.
0.
- 5. 01E+03 1.23E+05 9.43E+01 3.50E+Ol 3.60E-01 6.08E-01 1.05E+06 0.
7.07E+03 1.78E+02 5.19E+05 1.92E+05 1.42E+02 6.05E+02
'.74E+03-2.63E+01
- 2. 15E+02 5.13E+05 c
6.60E+02
'=
0.
0.
0.
0.
6.25E+02 1.79E+00 1.19E+00 0.
0.
0.
0.
3.60E-01 6.08E-01 0.
3.34E+00 0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
3.60E-01 6.08E-01 0.
1.23E+00 2.10E+03 2.26E+02 0.
0.
0.
0.
0.
0.'.41E+02 3.43E+05 4.27E+02 0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
3.60E-01 6.08E-01 0.
7.42E+00 0.
0.
6.01E+05 5.32E+04 0.
0.
0.
0.
0.
0.
0.
0.
0.0."
0.
0.
0.
0..
0.
0.
0.
0.
3.60E-01 6.08E-01 1.88E+06 1.41E+03 2.17E+04 5.68E+03 2.03E+05 6.33E+05 3.60E+03 1.22E+04 3.26E+04 6.65E+02 1.83E+04 3.23E+05 9.87E+Ol 4.68E+00 1.05E-01 7.38E-07 0.
1.23E+02 0.
0.
8.01E+02 1.65E+03 4.75E+02 6.91E+02 3.60E-01 6.08E-01 6.47E+05 5.59E+00 1.35E+03 3.17E+01 1.36E+05 7.29E+04 2.36E+02 1.35E+03 3.83E+03 1.20E+01
- 1. 01E+02 2.32E+05 4.57E+01 4.08E+00 7.26E-02 9.42E-02 3.86E-03 2.91E+02 9.50E-01 8.38E-01 1.44E+02 3.02E+04 4.15E+00 1.51E+00
~ on 1 uCi/sec release rate of-each isotope in discharge flcar of 1 cc/sec with no additional dilution
ST. IIJCIE PUTZ CKKZSTRY OPERATING PMKZIX3RE NO. C-200, REVISION ll OFFSITE DOSE CAHXJIATIONMANUAL ODCM Page 59 of 88 TABLE L-2 PAIHWAY-DOSE CDNVZRSION FACIORS FOR IZQJID DISCHARGES PAIHWAY SALT WATER FISH AND SHELLFISH AGE GROUP AIX3LT (continued)
NUCLIDE Y
90 Y
91M Y
91 6.07E+00 5.74E-02 8.89E+Ol 0.
0.
0.
ORGAN DOSE FACIOR THYROID 0.
0.
0.
0.
0.
0.
PER uCi 0.
0.
0.
GI-LLI 6.43E+04 1.68E-01 4.89E+04 TXM BODY 1.63E-01 2.23E-03 2.38E+00 Y
92 Y
93 ZR 95 ZR 97 NB95 NB 97 MO 99 TC-99M
'IC-101 RU-103 RU-105 RU-106 AG-110 SB-124 SB-125 TE125M TE127M TE-127 TE129M TE-129 TE131M TE-131 TE-132 5.34E-01 1.69E+00 1.60E+01 8.82E-01 4.48E+02 3.76E+00 0.
1.30E-02 1.33E-02
- 1. 07E+02 8.90E+00 1.59E+03 1.57E+03 2.78E+02
- 2. 20E+02
- 2. 17E+02 5.50E+02 8.92E+00 9.32E+02 2.55E+00 1.41E+02 1.60E+00 2.05E+03 0.
0.
5.13E+00'.78E 2.49E+02'.50E-01 1.28E+02 3.67E-02'.93E-02'.
0.
0.
1.45E+03'.23E+00 2.37E+00 7.89E+01 1.92E+02 3.20E+00 3.49E+02 9.65E-01 6.87E+01 6.68E-01 1.33E+02 0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
6.71E-01
- 1. 96E-01
- 6. 54E+Ol 1.40E+02 6.61E+00 3.20E+02 1.95E+00 1.09E+02 1.31E+00
- 1. 46E+02 0.
0.
8.09E+00 2.69E-01 2.47E+02 1.13E+00 2.90E+02 5.57E-01 3.47E-01 4.09E+02 1.15E+02 3.08E+03 2.85E+03 0.
0.
8.83E+02 2.23E+03 3.63E+01 3.89E+03
- 1. 07E+01 6.95E+02 7.00E+00 1.28E+03 0.
0.
0.
0.
0.
0.
0.
1.80E-02 9.82E-03 0.
0.
0.
0.
2.15E+02 2.30E+04 0.
0.
0.
0.
0; 0.
0.
0.
9.33E+03 5.36E+04 1.59E+04 5.51E+04 1.51E+06 3.51E+03
- 2. 97E+02 2.17E+01 0.
1.25E+04 5.44E+03 1.03E+05 5.92E+05 7.85E+03 1.95E+03 8.67E+02 1.84E+03 7.04E+02 4.69E+03 1.92E+00 6.81E+03 2.39E-01 6.25E+03 1.56E-02 4.67E-02 3.47E+00 8.19E-02 9.79E+01 3.47E-01 2.43E+Ol 4.67E-01 1.89E-01 4.61E+01 3.51E+00 2.01E+02 8.62E+02 1.10E+02 4.42E+Ol 2.91E+Ol 6.70E+01 1.93E+00 1.48E+02 6.21E-01 5.72E+01 5.04E-01 1.24E+02 Based on 1 uCi/sec release rate of each isotope in discharge flmr of 1 cc/sec with no additional dilution
/
ST. IIJCIE PUTZ CKKZSZRY OPERATING HKCEIXJRE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL O Page 60 of 88 TABID L-2 PAIHWAY-DOSE CONVIBSION FACIORS FOR LIQUID DISCKBGES PAIHNAY SALT WPZIK FISH AND SHELL'FISH AGE CKKUP AIXJLT (continued)
ORGAN DOSE FACIOR PER uCi NUCLIDE I
130 I
131 I
132 I
133 I
134 I
135 CS-134 CS-136 CS-137 CS-138 BA-139 BA-140 BA-141 BA-142 IA-140 IA-142 CE-141 CE-143 CE-144 PR-144 W
187 NP-239 3.98E+01 2.18E+02 1.07E+01 7.51E+01 5.57E+00 2.33E+01 6.85E+03 7.17E+02 8.79E+03 6.08E+00 7.87E+00 1.65E+03 0.
1.73E+00 1.58E+00 8.07E-02 3.43E+00 6.05E-01 1.79E+02 1.91E-02 9.17E+00 3.56E-02 1.18E+02 3.13E+02 2.85E+01 1.30E+02
- 1. 51E+Ol 6.14E+01 1.63E+04 2.83E+03 1.20E+04 1.20E+01 5.61E-03'.07E+00'.89E-03".
1.78E-03 7.95E-01 3.67E-02 2.32E+00 4.47E+02 7.48E+Ol 7.88E-03 7.68E+00 3.50E-03
'IHYIK)ID 1.50E+04 1.02E+05 3.76E+03 2.51E+04 1.96E+03 8.03E+03 0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
1.83E+02 5.36E+02 4.55E+01 2.27E+02 2.41E+01 9.77E+01 5.29E+03 1.58E+03 4.09E+03 8.84E+00 5.24E-03 7.04E-01 2.68E-03 1.50E-03 0.
0.
1.08E+00 1.97E-01 4.43E+01 4.45E-03 0.
1.08E-02 0.
0.
0.
0.
0.
0.
1.75E+03 2.16E+02 1.36E+03 8.73E-01 3.18E-03 1.18E+00 1.64E-03 1.01E-03 0.
0.
0.
0.
0.
0.
0.
0.
GI-IZZ l.01E+02 8.24E+Ol 5.36E+00 1.15E+02 1.32E-02 6.88E+01 2.85E+02 3.22E+02 2.31E+02 5.12E-05 1.39E+Ol 3.39E+03 1.80E-09 0.
5.83E+04 2.68E+02 8.87E+03 1.67E 04 6.05E+04 2.73E-09 2.51E+03 7.12E+02 TCG%L BODY 4.63E+01 1.79E+02
- 1. 01E+Ol 3.98E+01 5.41E+00 2.25E+01 1.33E+04 2.04E 03 7.88E+03 5.96E+00 2.30E-01 1.09E+02 1.29E-01 1.09E-01 2.11E-Ol 9.15E-03 2.63E-01 4.95E-02 9.60E+00 9.65E-04 2.69E+00 1.92E-03 Based on 1 uCi/sec release rate of each isotope in disch-use flow of 1 cc/sec with no additional dilution
Page 61 of 88 ST. WCIE PIANT CHEMISTRY"OPERATING PROCEDURE NO C 200'EVISION 11 OFFSITE DOSE CAICUZATION MANUAL ODCN TABLE G-1 MMGMUM PERMISSIBIZ CONCEhGKKIONS IN AIR IN UNKWZRICXKDARFAS Nuclidel Ar 41 Kr 83m Kz 85m Kr 85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 H-3 P-32 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zn-65 Rb-86 Sr-89 Sr-90 Rb-88 uCi cc E-8 E-8 1 E-7 E-7 E-8 E-8 E-8 E-8 E-7 E-7 E-7 3 E-8 1 E-7 E-8 E-8 E-7 E-9 E-8 1 E-9 E-9 6 E-9 E-9 E-10 E-9 E-9 E-10 E-11 E-8 Nuclidel Y-91 Zr-95 Nb-95 Rx-103 Ru-106 Ag-110 Sn-113.
In-113m Sn-123 Sn-126 Sb-124 Sb-125 Te-125m Te-127m Te-129m I-130 I-131.
I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Za-140 Ce-'141 Ce-144 uCi cc 1 E-9 1 E-9 E-9 E-9 E-10 E-10 E-9 E-7 1 E-10 E-10 7 E-10 9 E-10 E-9 1 E-9 1 E-9 1 E-10 1 E-10 E-9 E-10 6 E-9 1 E-9 E-10 6 E-9 5 E-10 E-9 E-9 E-9 E-10 If a nuclide is not listed, refer to 10CFR20, Appendhc B, and use the most conservative insoluble/soluble MPC where they are given in Table II, Column 1
ST. IIJCIE PZtÃZ CHEMISTRY OHKATj2IG PBOCEEGRE NO. C-200, REVISION 11 OFFSITE DOSE CATlXJIATIONKQRAL 0 Page 62 of 88 Tt63LE G-2 DOSE FACIORS POR NOBIZ GASES*
RADIONUCLIDE Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 TOZAL BODY DOSE FACIQR Ki uci m3 7.56E-02**
- 1. 17E+03
- 1. 61E+01 5.92E+03
- 1. 47E+04 1.66E+04 1.56E+04 9.15E+01
- 2. 51E+02 2.94E+02 3.12E+03 1.81E+03 1.42E+03 8.83E+03 8.84E+03 SKIN DOSE FACIOR uci m3 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11E+02 1.86E+03 1.22E+04
- 4. 13E+03 2.69E+03 GAMMAAIR DOSE FACIOR Mi uCi m3 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04
- 1. 56E+02
- 3. 27E+02 3.53E+02 3.36E+03 1.92E+03
- 1. 51E+03 9.21E+03 9.30E+03 BEZL AIR DOSE FACIOR Ni uci m3 2.88E+02 1.97E+03 1.95E+03 l.03E+04 2.93E+03 1.06E+04 7.83E+03
- 1. 11E+03 1.48E+03
- 1. 05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03
%he listed dose factors are for radionuclides that may be detected in gaseous effluents.
- 7.56E-02 = 7.56 X 10 2
ST. IOCIE PItKZ CfiEMISBK OPERATING PRQCEIXJRH NO. C-200, REVISION 11 OFFSITE DOSE CAICGIATIONMANUAL OIXR TAKZ G-3 ENVIRONHENTAL PATHWAY-DOSE CONVERSION FACTORS P (I)
FOR GASEOUS DISCHARGES PATHWAY -
GROUND PLANE DEPOSITION AGE GROUP INFANT ORGAN DOSE FACTOR SO.
HETER HREH YR PER uCi Sec Page of 88 NUCLIDE H----3 TOTAL BODY 0.
CR--51 6.68E+06 HN--54 1.10E+09 FE--59 3.92E+08 CO.-57 1.64E+08 C0--58 5.27E+08 C0--60 4.40E+09 ZN--65 6.87E+08 RB--86 1.29E+07 SR--89 3.07E+04 SR--90 5.94E+05 Y---91 1.53E+06 ZR--95 6.94E+08 NB--95 1.95E+08 RU-103 1.57E+08 RU-106 AG-'110 SN-126 2.99E+08 3.18E+09 4.80E+09 SB-124 8.42E+08 SB-125 7.56E+08 TE125H 2.19E+06 TE'127H
- 1. 15E+06 TE129H 5.49E+07 1--130 7.90E+06 I --131 I --132 2.46E+07 1.78E+06 I--133 3.54E+06 I --134 6.43E+05 1--135 3.66E+06 CS-134 CS-136 2.82E+09 2.13E+08 CS-137
- 1. 15E+09 BA-140 2.39E+08 CE-141 1.95E+07 CE-144 9.52E+07 Based on 1 uCi/sec Release Rate of Each Isotope in and a Value of 1. for X/0, depleted X/0 and Relative Deposition
ST. IIJCIE PUTZ CSEKIPZRY OPERATING PMCEIXHK NO. C-200, REVISION 11 OFFSITE DOSE CAIlX3IATIONMANUAL OIXR Page of 88 TABIZ G-4 ENVIRONHENTAL PATH'NAY-DOSE CONVERSION FACTORS R
( I )
FOR GASEOUS DISCHARGES PATH'NAY -
GROUND PLANE DEPOSITION AGE GROUP -
CKILD -
TEEN-ADULT 4 INFANT ORGAN DOSE FACTOR SO.
HETER HREH YR PER uCi Sec I
I I
I'I I
I I
I I
I I
I I
I I
J I
I I
I I
I I
I I
I I
I I
I I
I I
I I
NUCLIDE TOTAL BODY N----3 0.
CR--51 4.68E+06 HN 54 1.38E+09 FE--59 2.75E+08 C0--57 1.89E+08 C0--58 3.80E+08 CO--60
- 2. 15E+10 ZN--65 7.43E+08 RB--86 9.01E+06 SR--89 2.17E+04 SR--90 5.35E+06 Y---91 1.08E+06 ZR--95 5.01E+08 NB--95 1.36E+08 RU-103 1.10E+08 RU-106 4.19E+08 3.58E+09 5.16E+10 5.98E+08 AG-110 SN-126 SB-124 SB-125 2.30E+09 TE125H 1.55E+06 TE127H 8.79E+05 TE129H 3.85E+07 1--130 5.53E+06 I --131 1.72E+07 I--132 1.25E+06 I--133 2.48E+06 1--134 4.50E+05 1--135 2.56E+06 CS-134 6.99E+09 CS-136 1.49E+08 CS-137
- 1. 03E+10 BA-140 CE-141 CE-144 1.68E+08 1.37E+07 1
13E+08 I
Based on 1 uCi/sec Release Rate of Each Isotope in and a Value of 1. for X/0, depleted X/0 and Relative Deposition
ST. IIJCIE PIAÃ2 CKHISTRY OPEBATINQ HKCEEXHK NO. C-200, REVISION 11 OFFSITE DOSE CAUXJIATIONMANO'DCH TABLE G-5 EHVIRONHENTAL PATH'WAY-DOSE CONVERSIOH FACTORS R( I)/P( I)
FOR GASEOUS DISCHARGES PATHWAY -
INHALATIOH AGE GROUP INFANT ORGAN DOSE FACTOR HREH YR PER uCi Cu Heter Page 6 of 88 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI LLI TOTAL BODY H----3 P---32 0.
2.31E+05 4.30E+02 1.35E+OC 4.30E+02 1.88E+02 0.
0.
4.30E+02 0.
4.30E+02 1.51E+04 4.30E+02 8.78E+03 CR--51 NN--54 0.
0.
0.
6.93E+03 1.40E+01 0.
3.99E+00 1.72E+03 2.52E+03 2.45E+05 5.81E+02
- 1. 35E+04 1.75E+01
- 1. 10E+03 FE--59 2.06E+03 4.86E+06 0.
0.
1.78E+05 3.29E+04 1.85E+03 CO--57 CO--58 0.
0.
1.21E+02
- 1. 18E+02 0.
0.
0.
0.
6.47E+04 8.79E+05 5.50E+03 1.21E+04 1.18E+02 1.68E+02 Co--60 0.
8.40E+02 0.
0.
5.57E+06 3.28E+04 1.17E+03 ZN--65 5.67E+03 1.81E+OC 0.
1.21E+04 1.53E+05 9.35E+03 8.15E+03 RB--86 SR--89 0.
4.31E+OC 2.37E+04 0.
0.
0.
0.
0.
0.
2.31E+06 2.91E+03 6.80E+04 1.03E+04 1.24E+03 SR--90 1.32E+07 0.
0.
0.
1.53E+07 1.39E+05 8.06E+05 Y---91 ZR--95 NB--95 RU-103 RU-106 AG110 SN-123 SN-126 SB-124 SB-125 TE125H TE127H TE129N 5.98E+04 1.08E+04 1.28E+03 1.69E+02 9.31E+03 1.89E+03 3.11E+OC 2.21E+05 5.46E+03
- 1. 16E+04 4.54E+02
- 2. 21E+03 1.32E+03 0.
2.73E+03 5.75E+02 0.
0.
- 1. 75E+03 6.CSE+02 5.85E+03
- 1. 03E+02
- 1. 25E+02 1.95E+02 9.83E+02 5.80E+02 0.
0.
0.
9.48E+03 0.
0.
1.35E+03
- 1. 02E+03 0.
6.45E+02 3.4CE+03 0.
1.72E+03 0.
1.32E+01 0.
1.03E+01 0.
1.53E+02
- 2. 17E+03 5.75E+02 8.01E+03 5.08E+02 6.40E+03 0.
2.34E+04 2.63E+06 1. 81E+06 4.77E+05 5.66E+05 1.50E+07 8.12E+05
- 3. 61E+06 1.6CE+06 4.34E+05 3.85E+05 4.96E+05 1.68E+05
- 1. 83E+06 7.17E+OC
- 1. C1E+04 1.21E+OC 1.58E+OC 1.76E+05 5.29E+OC 5.99E+04 2.23E+04 7.11E+04 1.76E+04 1.36E+04 2.62E+04
- 7. 32E+04 1.60E+03 1.95E+03 3.37E+02 5.85E+01 1.14E+03 1.04E+03 1.02E+03 8.COE+03 2.17E+03 2.32E+03
- 6. 16E+01 2.74E+02 2.06E+02 I--130 8.02E+02 2.35E+03 3.05E+05 3.65E+03 0.
1.35E+03 9.25E+02 I--131 I --132 1--133 I --134 I --135 CS-134 3.63E+04 2.03E+02 1.34E+04 1.13E+02 4.70E+02 4.80E+05 4.27E+04 5.70E+02 1.93E+OC 3.02E+02 1.22E+03 8.25E+05 1.41E+07
- 1. 07E+OC 7.67E+04 9.09E+02 4.66E+06 4.55E+03 4.02E+04 4.82E+02 1.64E+05 1.95E+03 0.
5.0CE+04 0.
0.
0.
0.
0.
- 1. 01E+05 1.07E+03
- 7. 11E+01 2.28E+03 1.76E-01
- 9. 18E+02
- 1. 37E+03 2.51E+OC 2.03E+02 5.87E+03 1.08E+02
- 4. 51E+02 7.32E+04 CS-136 6.85E+03 2.56E+04 0.
- 1. 50E+04 2.10E+03 1.95E+04 2.04E+03 CS-137 6.86E+05 5.70E+03 0.
7.31E+05 3.89E+04 9.C5E+OC 1.32E+03 4.41E+04 BA-140 4.27E+00 0.
2.93E+00 1.64E+06 3.88E+03 2.95E+02 CE-141 2.52E+03 1.55E+03 0.
- 1. 10E+03 5.2CE+05 2.06E+OC
- 1. 81E+02 CE-144 4.68E+05
- 1. 82E+05 0.
1.CBE+05
- 1. 27E+07
- 1. 61E+05 2.49E+04 Release Rate of Each Isotope in and a Value of 1. for X/0, Based on 1 uCI/sec depleted X/G and Relative Deposition
ST. IIJCIE PRATE CHEMISTRY OPERATING HKCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCN TABLE G-6 ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS R(1)/P( I)
FOR GASEOUS DISCHARGES PATHMAY -
CONS HILK (CONTAHIHATED FORAGE)
AGE GROUP INFAHT ORGAN DOSE FACTOR SQ.
HETER HREH YR PER uCi Sec Page of 88 NUCLIDE BONE L IVER THYROID KIDNEY LUNG GI-LLI TOTAL BODY H----3 P---32 CR--51 0.
1.82E+10 0.
2.37E+03
- 1. 14E+09 0.
2.37E+03 0.
1.82E+OC 1.0CE+03 0.
6.72E+03 2.37E+03 0.
4.0CE+04 2.37E+03 2.05E+09 7.66E+06 2.3?E+03 7.05E+08 3.05E+04 MN--54 FE--59 0.
- 3. 1?E+07 8.96E+06 0.
2.67E+06 7.52E+07 0.
0.
0.
2.09E+07
- 2. 74E+07 2.48E+08 1.71E+06 2.86E+07 CO--57 CO--58 C0--60 0.
0.
0.
- 1. 36E+06 2.55E+07 8.73E+07 0.
0.
0.
0.
0.
0.
0.
0.
0.
3.46E+07 6.60E+07
- 2. 16E+08 2.27E+06 6.24E+07 2.09E+08 ZN--65 1.46E+09 4.65E+09 0.
- 3. 11E+09 0.
2.93E+09 2.10E+09 RB--86 0.
2.77E+09 0.
0.
0.
5.45E+08 1.29E+09 SR--89 1.47E+10 0.
0.
0.
0.
2.75E+08 4.22E+08 SR--90 1.65E+11 0.
0.
0.
0.
1.61E+09 C. 21E+10 Y---91 ZR--95 NB--95 8.12E+04 2.12E+05 5.49E+05 0.
0.
0.
- 9. C1E+04 0.
1.86E+04 2.47E+05 0.
C.8CE+OC 0.
0.
0.
5.37E+06 7.47E+07 1.98E+08 2.16E+03 5.56E+04 1.C5E+05 RU-103 8.30E+03 0.
0.
- 4. 16E+03 0.
1.0CE+05 2.86E+03 RU-106 AG110 SN-126 SB-124
- 2. 01E+05
- 6. 21E+07 1.75E+09 2.75E+07 0.
0.
4.20E+04 5.75E+07 0.
- 1. 13E+08 3.48E+07
- 1. 01E+07 0.
5.19E+05 6.64E+04 0.
0.
0.
C.97E+06 2.13E+07 1.56E+06 2.35E+10
- 1. 16E+09 7.78E+08 2.46E+04 3.42E+07 5.25E+07 1.09E+07 SB-125 3.59E+07 3.27E+06 2.93E+06 3.96E+06 2.83E+09 2.43E+08 6.62E+06 TE125M TE127H TE129H I--130 I--131 I - -132 I - -133 I--134 I --135 CS-134
- 1. 57E+08 5.54E+07 5.87E+08 4.54E+05 2.59E+09
- 1. 78E-01 3.75E+07 0.
1.49E+04 4.43E+10 5.48E+07 1.30E+10 1.29E+07 0.
1.06E-09 0.
3.94E+04 5.15E+06
- 6. 26E+04
- 7. 97E+10 4.65E+09 0.
5.30E+07 5.18E+07 7.05E+07
- 1. 93E+07 1.79E+07 2.DOE+08
- 2. 02E+08 2.21E+08 2.70E+08 1.35E+06
- 1. 71E+08 2.09E+06 3.09E+09 9.94E+11 7.74E+08
- 4. 76E-01 6.26E+01 7.58E-01 0.
0.
0.
0.
0.
0.
0.
8.07E-02 9.12E+09 7.57E+07 3.24E+08 3.54E+08
- 1. 15E+06
- 1. 16E+08 8.93E-02 9.74E+06 0.
C.41E+DC 2.10E+07 7.38E+06 8.95E+07 5.29E+05 1. 81E+09 1.69E-01 1.66E+07 0.
1.C4E+04 CS-136 CS-13?
BA-140 2.78E+08 6.4CE+10 2.45E+08
- 1. 10E+09
- 7. 21E+10 2.47E+05 0.
0.
0.
- 6. 11E+08" 3.66E+09 1.22E+04 8.37E+07 8.69E+09
- 1. 51E+05 1.90E+08 1.25E+08
'1.86E+08
- 8. 13E+06 6.75E+09 7.90E+08 4.14E+09 1.27E+07 CE-141 CE-1CC 2.65E+05 2.10E+07 1.62E+05 8.29E+06 0.
0.
9.72E+03 5.67E+05 Based on 1 uCi/sec Release Rate of Each Isotope in and a Value of 1. for X/O, Note:
The units for C--- 14 and H----3 are (HREM/YR Per uCi/Cu. Heter) 7.8?E+07 0.
1.90E+04 0.
8.66E+08 1. 13E+06 depleted X/O and Relative Deposition
t
~
ST. IIJCIE PIANT CKMESTRY OPERATING PROQKURE NO. C-200, REVISION 11 OFFSITE DOSE CAHHIATIONMANUAL 0 TABLE G-7 ENVIROHHENTAL PATHIJAY-DOSE CONVERSION FACTORS R( I)/P( I)
FOR GASEOUS DISCHARGES PATHMAY -
GOATS HILK (COHTAHINATED FORAGE)
AGE GROUP INFANT ORGAN DOSE FACTOR SO.
HETER HREH YR PER uCi Sec Page of 88 NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-LLI TOTAL BODY I
t H----3 P---32 CR--51 HN--54 0.
2.19E+10 0.
0.
4.8CE+03
- 1. 37E+09 0.
1.08E+06 C.84E+03 0.
2.19E+03 0.
- 2. 11E+03 0.
8.07E+02 3.20E+05 4.8CE+03 0.
C.85E+03 0.
4.84E+03 2.C6E+09
- 9. 19E+05 3.29E+06 4.8CE+03 B.C6E+08 3.66E+03 2.05E+05 FE--59 C.12E+05 9.78E+05 0.
0.
2.72E+05 3.23E+06 3.72E+05 C0--57 0.
1.6CE+05 0.
0.
0.
- 4. 15E+06 2.72E+05 C0--58 CO--60 0.
0.
3.06E+06 0.
0.
1.05E+07 0.
0.
0.
0.
7.92E+06 2.59E+07 7.49E+06 2.51E+07 ZN--65 1.76E+08 5.57E+08 0.
3.73E+08 0.
3.51E+08 2.52E+08 RB--86 0.
3.32E+08 0.
0.
0.
6.54E+07 1.55E+08 SR--89 SR--90
'Y---91 3.09E+10 3.46E+11 9.74E+03 0.
0.
0.
0.
.0.
0.
0.
0.
0.
0.
0.
0.
5.77E+08 3.35E+09 6.45E+05 8.87E+08 8.83E+10 2.60E+02 ZR--95 NB--95 RU-103 RU-106 AG110 SN-126 SB-124 SB-125 TE125H TE127H TE129H 2.54E+04 6.59E+04 9.96E+02 2.41E+04 7.45E+06 2.10E+08 3.30E+06 4.31E+06 1.89E+07 6.64E+06 7.05E+07
- 4. 17E+06 1.22E+06 0.
6.22E+OC 7.97E+03 0.
3.92E+05 3.52E+05 4.76E+05 6.36E+06 6.21E+06 8.46E+06 2.31E+06 2.15E+06 2.40E+07 2.42E+07 2.66E+07 3.23E+07
- 1. 13E+04 0.
2.23E+03 2.97E+04 0.
5.81E+03 0.
0.
4.99E+02 0.
0.
5.04E+03 6.90E+06 0.
1.36E+07 0.
0.
0.
0.
5.97E+05 2.56E+06 3.40E+08 0.
0.
0.
8.95E+06 2.37E+07 1.2CE+04 1.87E+05 2.81E+09 1.40E+08 9.33E+07 2.92E+07 9.09E+06 3.88E+07 4.25E+07 6.67E+03 1.75E+04 3.43E+02 2.96E+03
- 4. 10E+06 6.30E+06 1.30E+06 7.9CE+05 2.52E+06 8.85E+05 1.07E+07 I --130 5.45E+05
- 1. 61E+06 2.05E+08
- 2. 51E+06 0.
1.38E+06 6.35E+05 1--131 I --132 I --133 I --134 3.11E+09 2.13E-01 4.50E+07 0.
3.70E+09 1.19E+12 9.28E+08 5.71E-01
- 7. 51E+01
- 9. 10E-01 6.57E+07 1.55E+10
- 1. 55E+07 0.
1.27E-09 0.
0.
0.
0.
0.
1.39E+08 1.07E-01
- 1. 17E+07 0.
- 2. 17E+09 2.03E-01 1.99E+07 0.
I --135 1.79E+04 4.72E+OC 6.18E+06 7.51E+04 2.42E-01 5.29E+04 1.73E+04 CS-134 1.33E+11
- 2. 39E+11 0.
- 1. 39E+10 2.74E+10 5.69E+08 2.02E+10 CS-136 8.3CE+08 3.29E+09 0.
- 1. 83E+09 2.51E+08 3.7CE+08 2.37E+09 t
P t
"r
~
t
(
CS-137 BA-1CO CE-141 1.93E+11 2.95E+07 3.17E+04 0.
- 2. 16E+11
- 1. 10E+10 2.96E+DC 0.
1.47E+03 1.95E+04 0.
- 1. 17E+03 CE-1C4 2.52E+06 9.95E+05 0.
6.80E+04 Based on 1 uCi/sec Note:
The units Release Rote of Each Isotope in and a Value of 1. for X/0, for C---14 and H----3 are 1HREH/Yr per uCI/Cu meter.
2.61E+10 1.81E+04 0.
0.
5.59E+08
- 9. 76E+05 9.4CE+06 1.04E+08 1.24E+10 1. 52E+06 2.28E+03 1.36E+05 depleted X/0 and Relative Deposition
Page 68 of 88 ST. IIJCIE PIANI'HEMISTRY%
OPlPATING PK)CEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCN
%ABER M-1 Select'he Gases foz".
riate Ia Term X
for Dose Calculations Involv'oble (1) Total Body dose fram instantaneous releases (2) Skin dose fram instantaneous releases (3)
Gamma air dose (cumulative)
(4) Beta air dose (cumulative)
TYPE OF DOSE CALCULATION Instantaneous-LCO
(
1 31 da s -
LCO LIHITING RANGE (miles) 0.97 0.97 LIHIT ING Sector NW (X/Q) VALUE sec/m
.6 1.6 X 10 Quarterly -
LCO Yearl 12 Consecutive months LCO 0.97 0.97 1.
Normally (X/Q) ~ 1.6 X 10 sec/m
[
2 ~
Hay use option of actual meteorological data for time of concern Semi-Annual Re ort 0.97 I
N/A I
Note-1 Note 1 0.97 miles The (X/Q) has to be calculated based on actual meteorological data that occurred during the period of interest.
'Ihe sector of interest is N/A because the limiting (X/Q) will be determined fzam the actual meteorological data and may occur in any sector.
Corresponds to the minimum site boundazy distance in the north direction and 0.97 miles was chosen for all other sectors for ease of calculations when the averaging is done for cpmrterly reports.
Page 69 of 88 ST. IlJCIE PIANT CHEMISTRY OPERATING HKCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAIlXJIATIONMAÃ%L OIXN
~ M-2 Selecting the Appropriate Long Term (X/Q)D or (D/Q) for Dose Calculations Involving Radioiodines
& 8 D Particulates for:
(1)
Inhalation (2)
Tritium (All gas pathways)
(3)
Ground Plane TYPE OF DOSE CALCULATION I LIMITING RANGE I LIMITING SECTOR I
(mi les)
(OL)
(X/Q)o sec/m (O/Q) 1/m )
Instantaneous LCO 0'7 NW e
) / / / / / /
1.3 X 10
/ / / / / /
Quarterly for Semiannual Re orts 1/31 days
- LCO, Qtr. yearly LCO, 12 consecutive month LCO 0.97 0.97 0.97 0.97 WNW NW
'WNW
///////
A B
B 6
1.3 X 10
///////
0.2 X 109 A
//////
0.2 X 10 9 (OL)
Over land areas only (A)
To be determined by reduction of actual met data occurring during each quarter For Tritium in the MilkAnimal Pathway, the (X/Q)D value should be that of the respective controlling sector and range where the MilkAnimal is located as per Table M-3.
Example: If a ccar was located at 4.25 miles in NW sector, use the (X/Q)D for 4.25 miles NN.
ST. IIJCIE PIANOS CHEMISTRY OPlPATING HKCEDURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL OIXR Page 70 of 88 TABLE M-3 Selecting the Appropriate Zang Term (D/Q) for Dose Calculations Involving Radioiodines and 8D Particulates for Grass-Cmr-Milk or Grassy~
TYPE OF DOSE CAZCUIATION I
1 31 Da s ICO I
l -Yearl ICO 12 Consecutive Months IlD I
Semi-Annual Re rt LIMITING L'IMZZING RANK SECIOR A
A B
B (D/Q) Value 1/m2 A.
The worst cd or goat as per locations from land census.
If no milk animal in any sector, assume a ccar at 4.25 miles in the highest (D/Q) sector over land.
B.
'The historical (D/Q) of all land sectors with the worst cow or goat fram each sector as reported in the Land Census.
A 4.25 mile cow should be assuaged in the worst sectar when no milk animal is reported.
C.
'Ihe highest (D/Q) at a milk animal location of all milk animals reported in the land Census Report.
(If no milk animals within 5 miles a 4.25 mile cow should be assumed in the sector having the highest (D/Q) at 4.25 miles).
Actual Met Data should be used for the selection of the worst case milk anginal and for the dose calculations. If both goat and milk annals are reported inside 5 miles, dose calculations should be performed on each animal and the higher dose animal contribution should be used.
Ghe historical wind frequency fractions for each sector are listed in Table M-8.
ST. WCIE PTAS CKMEPZBY OPERATING PROQKGRE NO. C-200, REVISION 11 OFFSITE DOSE CAUXKATIONMANUAL OIXR Page 7
f 88 TABLE H-4 TERRAIN CORRECTION FACTORS Florida Power 8 Light Company St
~ Lucie Unit 1
Hutchinson Island, Florida Dames and Hoore Job No:
4598 -
'112 Terrain Correction Factors (PUFF / STRAIGHT LINE)
Period of Record:
8/29/77 to 8/31/78 BASE DISTANCE IN HILES KILOHETERS I
DESIGN IAFFECTED DISTANCE I
SECTOR HI LES
.25
.40
.75 1.25 1.75 2.25 2.75 3'5 3.75 4.25 4.75 I
1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 I
NNE 0.
I NE 0.
E 0 ~
ESE 0.
SE 0.
I SSE 0.
s 0.
ssu 0.
su 0.
usu 0.
u 0.
uNu 0 ~
Nu NNu N
0.
0.
0.
I ENE 0.
1.906 1.887 1.452 1.662 1.690 1.818 1.812 1.398 1.534 1.685 1 ~ 620 1.651
- 1. 720 1.681
- 1. 739 1.816 1.576
'I ~ 581 1.23D 1.425 1.483 1.691 1.586 1.321 1.411 1.492 1.333 1.415 1.430 1.407 1.488 1.524 1.465 1.461 1.122 1 ~ 277 1 ~ 404 1.391 1.081
- 1. 193 1.470 1.370 1.125 1.296 1 ~ 294 1.210 1.290 1.267 1.257 1.316 1.389 1.427 1.302
- 1. 083 1 ~ 192 1.233
- 1. 173 1.218 1 ~ 185 1 ~ 173 1.212 1.285 1.328 1.260 1.338 1.310 1.047 1.151 1.246 1.435 1 ~ 270 1.108 1.205 1.200 1.082 1 ~ 154 1.150 1.119
- 1. 172 1.257 1.318 1.259
- 1. 033 1 ~ 123 1.190 1.361 1.263 1.127 1.132 1.222 1.091 1.099 1.133 1 ~ 078 1.122
- 1. 263 1.334 1.164
.941 1.097 1 ~ 134 1.366 1.229 1.073 1.135 1.160 1.099 1.081 1.125 1 '63 1.135 1.285 1.386 1.128
.941
'I. 121
- 1. 094 1.331
- 1. 193 1 '63 1.116 1.160 1.056 1.067 1.085
.995 1.080 1.267 1.346 1.101
.906 1.'123
- 1. 032 1.279 1.171 1 ~ 047 1 ~ 077 1.198 1.034 1.093
- 1. 033
.998 1.099 1.231 1.338 I
1.>>6
[
.902 I
1.122 f
.968 I
1.239 I
1 ~ 151 I
1 ~ 024 1.060 I
1.196 1 '04
[
1.083 I
1.045 I
.978 I
1.091 I
1 213 I
Note 1:
Any interpolations between stated mileages will be done by log-log
ST.
IIJCZE PZtÃZ CHEMISTRY OE%2QZING PROCEIX3RE NO. C-200, REVISION 11 OFFSITE DOSE CADXJIATIONMANUAL OIXM Page of 88 TABLE H-5 HISTORICAL LONG TERH - (X/G) (Frequency corrected)
,3 "s- '
hr r ~
NHE 0.
I HE 0.
I ENE 0.
I E
0.
I ESE 0.
SE 0.
I SSE 0 ~
s o.
ssu o.
su o.
usu o.
u o.
uNu o.
Hu o.
NHu o.
H O.
1.1E-05 1.3E-05 9.3E-06 9.8E-06 1.2E-05 1 'E-05 1.1E-05 6.2E-06 5.7E-06 6r 1E-06 7.3E-06 7.6E-06 1.4E-05 1.6E-05 1.5E-05 9.1E-06 1.7E-06 2.1E-06 1.4E-06 1.6E-06 1.9E-06 2.4E-06 1.7E-06 1.0E-06 9.0E-07 9.4E-07 1.1E-06 1.2E-06 2.1E-06 2.4E-06 2.2E-06 1.4E-06 T.8E-07 8.9E-07 6.2E-07 6'E-07 8 'E-OT 9.7E-07 7.3E-07 4.2E-07 4.0E-07 3.9E-OT 4.6E-OT 5.2E-OT 9.1E-07 1 'E-06 9.6E-07 6.3E-07 4.5E-07 5 'E-07 3.?E-07 3 'E-07 USE-07 5.7E-07 4.3E-07 2.5E-07 2.3E-07 2.2E-07 2.7E-07 2.9E-OT 5.2E-07 5 'E-07 5.5E-07 3.6E-OT 3.1E-07 3.4E-07 2.5E-07 2.5E-07 3 'E-07 4.0E-07 2.9E-07 1.8E-07 1.6E-07 1.6E-07 1.7E-07 2.0E-07 3.4E-07 3.9E-07 3.6E-07 2.4E-07 2'E-07 2 'E-07 1.9E-07 1.8E-07 2.4E-07 2.9E-07 2.1E-07 1.4E-OT 1.1E-07 1.'IE-07 1.3E-07 1.3E-07 2.6E-07 USE-07 2.6E-07 1.8E-07 1.7E-OT 1.7E-07 1.3E-07 1.4E-07 1.8E-07 2.3E-07 1.6E-07 1.0E-07 8.9E-08 8.6E-08 1.0E-07
'I.OE-07 2.0E-OT 2.1E-OT 2.0E-07 1.4E-07 1.5E-07 1 ~ 4E-07
- 1. 'IE-07 1.2E-07 1.4E-07 1.9E-07 1.3E-07 8'E-08 7.0E-08 7'E-08 8.0E-08 8.4E-08 1.5E-07 1.7E-OT 1.6E-07 1.2E-07 1.2E-07 1.1E-07 8.8E-08 9'E-08 1 ~ 1E-07 1.4E-OT
- 1. 1E-07 6.6E-OB 5 'E-08 6.0E-OB 6'E-08 7.2E-08 1.2E-07 1.4E-OT 1.3E-OT 9.4E-OB 1 'E 07 I
9.8E-OS
/
7.5E-08 I
8.4E-08 I
9.0E-OB I
1.2E-OT I
9.1E-OS I
5 SE 08 I
4 SE 08 I
5 ~ 1E-08 I
5'4E 08 I
6.1E-08 I
1.0E-07 I
~ 2E-07 I
1.2E-or
[
7.9E-OB I
Terrain / Recirculation Adjusted Program ANNXOQ9 Version - 11/18/76 Florida Power 8 Light Company St. Lucie Unit 1
Hutchinson Island, Florida Dames and Hoore Job Ho:
1.4598 112 Average Annual Relative Concentration (sec/cubic meter)
Period of Record:
9/1/76 to 8/31/78 BASE DISTANCE IN HILES KILOMETERS I
DESIGN I
iAFFECTED DISTANCE
.25
~ 75 1 '5 1'5 2'5 2.75 3'5 F 75 4'5 4'5 I
I SECTOR HILES 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 r.64
[
Number of Valid Observations
= 17135 Number of Invalid Observations
= 385 Number of Calms Lower Level
= 95 Number of Calms Upper Level
=
0 Note 1
Any interpolations between stated mi leages will be done by log-log
ST.
IIJCZE PIANOS GiEHISTRY OPERATING PBOCEIXJRH NO. C-200, REVISION 11 OFFSITE DOSE CADXJIATION %ANNUAL01'age 7
of 88 TABLE H-6 HISTORICAL LONG TERH DEPLETED
- (X/O)D (Frequency corrected)
TERRAIN / RECIRCULATION ADJUSTED PROGRAH ANHXOQ9 VERSION - 11/18/76 Florida Power
& Light Company St. Lucie Unit 1
Hutchinson Island, Florida Dames and Hoore Job No:
4598 112 AVERAGE ANNUAL RELATIVE CONCENTRATION DEPLETED Period of Record:
9/1/76 to 8/31/78 (sec/cubic meter)
BASE DISTANCE IN NILES KILONETERS I
NHE 0.
I NE 0.
I EHE 0.
I E
0 ~
I ESE 0.
SE 0.
I SSE 0 ~
S O.
ssu OS su o.
usu o.
u O.
I uNu 0.
Hu o.
I NHu 0.
0.
1.1E-05 1.2E-05 8.9E-06
- 9. 1E-06 1 'E-05 1.3E-05 1.1E-05 5.9E-06 5.4E-06 5.7E-06 T.OE-06 7.3E-06 1.3E-OS 1.5E-05 1.4E-05 8.7E-06 I
DESIGN IAFFECTED DISTANCE I
SECTOR NII.ES
.40
.75
'1.21 1.6E-06 1.7E-06 1.2E-06 1.3E-06 1.6E-06 2.0E-06 1.6E-06 9.1E-07 B.OE-07 8.4E-07 9.6E-07 1 ~ 1E-06 1.9E-06 2.1E-06 2.1E-06 1.3E-06 7.6E-OB I
7.4E-OB I
5.6E-OB I
6.3E-OB I
6.7E-OB I
9.0E-OB I
6.8E-OB I
4.1E-OB I
3.6E-OB I
3.8E-OS I
4.OE-OB I
4.4E-OB I
7.8E-OB I
8 SE 08 I
8.6E-OB I
5.8E-OB I
9.2E-OB 8.6E-OS 6.6E-OB 7.5E-OS 8.5E-OB 1.1E-07 8.2E-OB 5.0E-OS 4.3E-OB 4.6E-OB 5.0E-OB 5.5E-OS 9.3E-OB 1.0E-OT 1.0E-07 7.0E-OB 1.1E-07 1.1E-07 8.4E-OB 9.1E-OB 1 ~ 1E-07 1.3E-07 1.0E-07 6'E-08 5 'E-08 5 'E-08 6.1E-OB 6.4E-OB 1.2E-07 1.3E-07 1.2E-07 8.9E-OB 1.3E-07 1.4E-07 1.0E-07 1.1E-07 1.4E-07 1.8E-07 1 'E-07 7.7E-OB 6.9E-OS 6'E-08 B.OE-OB 8.2E-OS 1.6E-07 1 'E-07 1.6E-07 1.1E-07 1.7E-07
'l.9E-07 1.4E-07 1.5E-07 1.9E-07 2.3E-07 1.8E-07
'I. 1E-07 8.9E-OB 9.2E-OB 1.0E-07 1.1E-07 2.0E-07 2.3E-07 2.0E-07 1.4E-07 3.8E-07 4.3E-07 3.0E-07
- 3. 1E-07 3 'E-07 4.7E-07 3.5E-07 2.1E-07 1 'E-07 1.8E-07 2.2E-OT 2.4E-07 4.4E-07 4.9E 07 4.5E-07 3.0E-OT 2.4E-07 2.8E-07 2.0E-07
- 2. 1E-07 2.6E-07 3 'E-07 2.4E-07 1 'E-07 1.3E-OT 1.2E-07 1 'E-07 1.6E-07 2.9E-07 3.1E-07 2.9E-07 2.0E-07 6-6E-07 7.6E-OT 5.3E-07 5.6E-07 6.9E-07 8.2E-07 6.3E-07 3.6E-07 3.4E-OT 3.4E-07 4.0E-OT 4.4E-DT 7.9E-07 8.9E-07 8.3E-07 5.4E-07 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 2 01 2 82 3 62 4 42 5 23 6.03 6.84 7 64 I
Number of Valid Observations
= 17135 Number of Invalid Observations
= 385 Number of Calms Lower Level
= 95 Number of Calms Upper Level
"- 0 Note 1
Any interpolations between stated mileages will be done by log-log
PZ. WCIE PTAS CSHCSTRY OPEZVZISx HKCEXURE NO C 200~ REVISION 11 OFFSITE DOSE CAIQUIATIONMANUAL ODCH Page of 88 TABLE M-7 HISTORICAL LONG TERM - (0/O) (Frequency corrected)
TERRAIN / RECIRCULATION ADJUSTED PROGRAM AHNXOQ9 VERSION - 11/18/76 Florida Power 8 Light Company St.
Lucie Unit 1
Hutchinson Island, Florida Dames and Moore Job No:
4598 112 AVERAGE ANNUAL RELATIVE DEPOSITION RATE Period of Record:
9/1/76 to 8/31/78 (square meter 1)
BASE DISTANCE IN MILES KILOMETERS I
DESIGN UNAFFECTED DISTANCE
.25
~ 75 1.25 1.75 2.25 2'5 3.25 3'5 4.25 4'5 I
SECTOR MILES
.40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE I
HE I
ENE E
ESE SE I
SSE I
ssu su usu u
uNu Nu NNu I
N 0.
0.
0.
0 ~
0.
0.
0.
0.
0.
0.
0.
0.
0.
0.
0 ~
0.
6'E-08 6.0E-OB 3.2E-OS 3.0E-OS 3 'E-08 6.4E-OS 6.2E-OS 4.2E-OS 3.4E-08 4.5E-OB 5 'E-08 5.0E-OB 8.8E-OS 8.2E-08 8.2E-OS
- 5. 1E-08 9.3E-09 8.9E-09 4.8E-09 4.6E-09 5.8E-09 1.0E-OB 9.5E-09 7.0E-09 5.4E-09 7.0E-09 7.7E-09 7.5E-09 1.3E-OB 1.2E-OS 1 'E-08 7.3E-09 3.7E-09 3.5E-09 1.9E-09
. 1.8E-09 2.3E-09 4.0E-09 3.6E-09 2.6E-09 2.2E-09 2.6E-09 3.0E-09 3.0E-09 4.9E-09 4.7E-09 4.6E-09 2.9E-09 2.1E-09 1.9E-09 1.0E-09 9.5E-10 1.2E-09 2.1E-09 2.0E-09 1.4E-09 1.1E-09 1.5E-09 1.6E-09 1.6E-09 2.6E-09 2 'E-09 2.4E-09 1.5E-09 1.3E-09 1.2E-09 6.6E-10 6.0E-10 8.0E-10 1.4E-09 1 'E-09 9.5E-10 7.5E-10 9.0E-10 1.0E-09 9.8E-10 1.7E-09 1.6E-09 1.5E-09 9.8E-10 9.0E-10 8.1E-10 4.6E-10 4.2E-10 5 'E-10 9.7E-10 8.7E-10 6.9E-10 5.0E-10 6.6E-10 7.3E-10 6.7E-10 1.1E-09 1 ~ 1E-09 1 ~ 1E-09
- 7. 1E-10 6.8E-10 5.6E-10 3.2E-10 3.1E-10 3.9E-10
- 7. 2E-10 6.4E-10 4.9E-10 3.7E-10 4.6E-10 5.5E-10
- 5. OE-.10 8.7E-10 7.9E-10
- 8. 1E-10 5.4E-10 5.5E-10 4.3E-10 2.4E-10 2.5E-10 3.0E-10
" 5.6E-10 4.9E-10 3.8E-10 2 ~ 9E-10 3.6E-10 4.1E-10 3.8E-10 6.6E-10 5.8E-10 5.9E-10 4.2E-10 4.3E-10 3.3E-10 1.9E-10 2.0E-10 2.2E-10 4 'E-10 3 'E-10 3.0E-10 2 'E-10 3 ~ OE-10 3.3E-10 3.2E-10 5.1E-10 4.7E-10 4 ~ SE-10 3.2E-10 3.5E-10 2.8E-10 1.5E-10 1.6E-10 1.7E-10
- 3. SE-10 3.1E-10 2.5E-10 1.8E-10 2.5E-10 2.6E-10 2.6E-10 4.2E-10 3.8E-10 4.0E-10 2.7E-10 Number of Valid Observations
= 17135 Number of Invalid Observations
= 385 Number of Calms Lower Level
= 95 Number of Calms Upper Level
= 0 Note 1 -
Any interpolations between stated mi leages will be done by log-log
Page 75 of 88 ST.
IIJCCE PZAÃZ CSEHISTRY OPERATING HKCEIXRE NO. C-200, REVISION 11 OFFSITE DOSE CAIIQKATIONMANX%
ODCM TABLE N-8 Joint Mind Frequency Distribution Data Period:
September 1,
1976
- August 31, 1978 All Minds Data Source:
Mind Sensor Height Table Generated:
On-Site St. Lucie Unit 2 10.00 Haters Hutchinson Island, Florid~
12/05/78. 07.42.18.'lorida Power 8 Light Co.
Dames and Noore Job Ho:
4598 -
1'12 - 27 MIHD SPEED CATEGORIES METERS PER SECOND
'MIND SECTOR HNE NE ENE ESE SE SSE SSM MSM MHM N'M HNM CALM 0.0-1 '
71
- 43 62
.38 60
.36 69
.42 115
.70 183 1.11 129
.78 72
.44 84
.51
'129
.78 155'94
'1 74 1.05 203 1.23 143
.87'5
.51 91
.55 95
.57 1.5-3.0 206 1.25 292 1.77 334 2.02 355 2.15 684
- 4. 14 660 3.99 579 3.50 310 1.88 372 2.25 440 2.66 320 1.94 267 1.62 304 1.84 518 3.14 379 2.29 194 1.17 3.0-5.0 318 1.92 385 2.33 505 3.06 510 3.09 744 4.50 749 4.53 656 3.97 407 2.46 446 2.70 336 2.03 186 1.13 119
.72 172 1.04 424 2.57 535 3.24 531 3.21 5.0-7.5 71
.43 128
.77 158
.96 76
.46 72
.44 28
.17 93 56 99
.60 105
.64 106
.64 29
.18 37
.22 17
.10 50
.30 70
.42 148
.90 7.5-10.0 3
.02 0
0.00 0
0.00 0
0.00 1
.01 0
0.00 1
.01 8-
.05 33
.20 14
.08 5
.03
.01 0
0.00 0
0.00 1
.01 5
.03
>10.0 0
0.00 0
0.00 0
0.00 0
0.00 0
0.00 0
0.00 0
0.00 1
.01 4
.02 0
0.00 0
0.00
'0 0.00 0
0.00 0
0.00 0
0.00 0
0.00 TOTAL 669 4.05 867
'.25 1057 6.40 1010 6.11 1616 9.78 1620 9.81 1458 8.82 897 5.43 1044 6.32 1025 6.20 695 4.21 599 3.63 696 4.21 1135 6.87 1070 6.46 969 5.86 95
.57 MEAN SPEED 3.32 3.43 3.51 3.25 3.04 2.88 3.10 3.36 3.48 3.10 2.59 2.43 2.34 2'5 3.22 3.69 CALN TOTAL 7023 6214 1920 11.62 37.61 42.51 1287 7.79 73
,44 5
.03 16.522 100.00 3.10 NUNBER OF VALID OBSERVATIONS 16522 94.30 PCT.
HUHBER OF INVALID OBSERVATIONS 988 5.70 PCT.
TOTAL HUNGER OF OBSERVATIONS 17520 100.00 PCT ~
Key XXX Number of Occurrences XXX Percent Occurrences
- Totals below are given in hours 8, percent for wind frequency by sectors
Page 76 of 88 ST. IIJCIE 'PZRK CH1MESTRY OPERATING PEKCEDKK NO C 200 g REVZSION 11 OFFSITE DOSE CAICUIATIONMANUAL OIXK APPENDIX B Limited Analysis Dose Assessment for Liquid Radioactive Effluents
'Ihe radioactive liquid effluents for the years
- 1978, 1979, and 1980 were evaluated to determine the dose contribution of the radionuclide distribution.
Ibis analysis was performed to evaluate the use of a limited dose analysis for determining environmental doses.
Limiting the dose calculation to a few selected radionuclides that contribute the majority of the dose provides a simplified method of determining 'compliance with the dose limits of Technical Specification 3. 11.1.2.
Tables B-1 and B-2 present the results of this evaluation.
Table B-1 presents the fraction of the adult total body dose contributed by the major radionuclides.
Table B-2 pcs the same data for the adult. GI-LLE dose.
'Ihe adult total body and adult GI-LLIwere detezzdned to be the limiting doses based on an evaluation of all age groups (adult, teenager, child, and infant) and all organs (bone, liver, kidney, lung, and GI-LIZ).
As the data in the tables st, the radionuclides Fe-59, Co-58, Co-60, Zn-65, Cs-134, and Cs-137 dominate the total body dose; the radionuclides, Fe-59, Co-58, Co-60, Zn-65, and Nb-95 dominate the GI-LLE dose.
In all but one case (1979-fish, GI-IZZ dose) these radionuclides contribute 90% or more of the total dose. If for 1979 the fish and shellfish pathways are combined as is done to determine the total dose, the contribution fmm these nuclides is 84%
of the total GI-LLK dose o
'Iherefore, the dose cammitrMnt due to radioactive material in liquid effluents can be reasonably estimated by limiting the dose calculation to the radionuclides, Fe-59, Co-58, Co-60, Zn-65, Nb-95, Cs-134, and Cs-137, which cumulatively contribute the majority of the total dose calculated by using all radionuclides detect.
This limited analysis dose assessment method is a simplified calculation that provides a-reasonable evaluation of. doses due to liquid radioactive effluents and allows for an estimate of Fe-55 contribution to dose.
Tritium is not included in the limited analysis dose assessment for liquid releases because the potential dose resulting from normal reactor releases is negligible and is essentially independent of radwaste system operation.
'Ihe amount of tritium release annually is about 300 curies.
At St. Zucie, 300 Ci/yr releam6 to the Atlantic Ocean produces a calculated whole body dose of 5 X 10 mrem/yr via the fish and shellfish pathways.
'Ihis amounts to less than 0.001% of the design objective dose of 3 mrem/yr.
Furthermore, the release of tritium is a function of operating time and paver level and is essentially unrelated to radwaste system operation.
A- 'Ihe dose due to Iron -55 made it necessary to change the conservatism factor from 0.8 to 0.6, which was done on Revision 7 to the ODCM, based on early 1986 data.
Page 77 of 88 ST. IIJCIE PZt&Z CSEKISTRY OPERATING PROCEIXJRE NO C 200 r REVISION 11 OFFSITE DOSE CAICXJIATION MANUAL ODCN Adult Total Body Dose Contributions Fraction of Total I
I 1978 I
1979 I
1980 I
I RAOIOHUCLIDE FISH SHELLFISH FISH SHELLFISH FISH SHELLFISH I
Co-58 f
0 ~ 08
(
0.27
/
0 F 06 f
0.28 Co-60
/
0.05 i
0.19
)
0.03 t
0.15 Fe-59
/
0.10
)
0.25
/
0.04 f
0.13 Zn-65 I
0.01 I
0.10 I
0'2 I
0'9 Cs.134 i
0.31 i
0.07
/
0.46
/
0.14 Cs-137 0.42
- 0. 10 0.38 0.11 O.OZ O.ZO 0 ~ 15 I
0.04 I
o.27 0.30 o.os o.44 O.22 O.ZO o.o4 o.or, I
TOTAL 0.97 0.98 0.99 1.00 0.98 0.99 Table B-2 AchIlt GI-LLI Dose Contribution Fraction of Total'" "
I I
1978 I
1979 I
1980 I
I RAOIOHUCLIOE FISH SHELLFISH FISH SHELLFISH FISH SHELLFISH I
Co-58 i
0.03
)
0.36 i
0.25 i
0.44 Co-60 i
0.02 i
0.23
(
- 0. 12 i
0.22 Fe-59
/
0.03 f
0.31
)
0 ~ 16
/
0.19 Zn-65
/
0.01
/
0.02
/
0.01 f
0.05 I
Hb-95 0.89 0.01 0.21 0.01 0.01 o.os o.o4 0.01 I
0.88 o.or o.sr 0.29 I
o.or, 0.01 I
TOTAL 0.98 0.92 0.75 0.90 0.97 0.97
Page 78 of 88 ST. WCIE PZANI'HEMISTRY OPERATING HKCEK1EK NO. C-200, REVISION 11 OFFSITE DOSE CAICUZATION MANUAL ODCH APHXDIX C Technical Bases for Effective Dose Factors Overview The evaluation of doses due to releases of radioactive material to the atmosl&exe can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific.
'Ihese effective factors, which are based on the typical radionuclide distribution in the
- releases, can be applied to the total radioactivity released to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (I( ffg Meffg or Neff) times the total quantity of radioactive material released would be needed.
This approach provides a reasonable estimate of the actual dose while elimbmting the need for a detailed calculational technique.
Determination of Effective Dose Factors
'Ihe effective dose transfer factors are based on past operating data.
'Lhe radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations:
Where:
ff Ki fi 3.
(C-1)
%ff the effective total body dose factor due to gamma emissions from all noble gases rel~
Ki the total body dose factor due to gamma emissions from each-noble gas radionuclide i released the fractional abundance of noble gas radionuclide i is of the total noble gas radionuclides Where:
(?st.1.1 M)eff =
(Li + 1.1 Mi). fi 1
(C-2)
(Zrl.1.1 M)eff the effective skin dose factor due to beta and gamma emissions from all noble gases released (L
+ 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released ff Z
Mi fi i
(C-3)
Page 79 of 88 ST. IIJCIE PItQK CHEMISTRY OPERATING PROCEIXRE NO C 200 g REVISION 11 OFFSITE DOSE CAD;UZATIONMANO'DCM APPENDIX C Technical Bases for Effective Dose Factors (continued)
Where:
eff
= the effective air dose factor due to gamma emissions from all noble gases released
= the air dose factor due to ganma emissions fram each noble gas radionuclide i rel~
Neff
=
5 Ni
. fi 3.
(C-4)
Where:
eff Ni
= the effective air dose factor due to beta emissions from all noble gases rel~
= the air dose factor due to beta emissions from each noble gas radionuclide i To deteraune the appropriate effective factors to be used and to evaluate the degree of variability, the atznospheric radioactive effluents for the past 3 years have been evaluated.
Tables C-1 and C-2 present the results of this evaluation.
As can be seen from Tables C-1 ard C-2, the effective dose transfer factors varies little from year to year.
The max&num o~ed variability fram the average value is 18..
This variability is minor considering other areas of uncertainty and conservatism inherent in the environmental dose calculation models o To provide an additional degree of conservatism, a factor of 0.8 is irrtroduced into the dose calculation process when the effective dose transfer factor is used.
'Ihis added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly und~imate any actual doses in the envirorment.
Page 80 of 88 ST. IIJCIE PIANOS CHIMfSIRY OPERATING PRCICEIURE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL OIXH Reevaluation Technical Bases for Effective Dose Factors (continued)
The doses due to the gaseous effluents are evaluated by the more detailed calculation methods (i.e., use of nuclide specific dose factors) on a yearly basis.
At this time a camparison can be made between the simplified method and the detailed methcd to assure the overall reasonableness of this limited analysis approach. Ifthis colttparison indicates that the radionuclide distribution has changed significantly causing the simplified method to und~imate the doses by more than 20%, the value of the effective factors will need to be reexamined to assure the overall acceptability of this approach.
However, this reelmnination will only be needed if the doses as calculated by the detailed analysis exceed 50~ of the design bases doses (i.e.,
greater than 5 mrads gamma air dose or 10 mrads beta air dose).
In any case, the appropriateness of the A ffvalue will be periodically evaluated to assume the applicability of a single effective dose factor for evaluating environmental doses.
Table C-1 Effective Dose Factors Noble Gases~tal Body and Skin Doses 1978 1979 I
1980 I
AVERAGE
'XOI'AL BODY EFFECTIVE DOSE FACIOR
%ff mrem-m uc1-7.3 X 102 7.4 X 10 5.6 X 102 6.S X 1O2 SKEN EFFECTIVE DOSE FACIOR
~
(Id.1. 1M)eff mrem-m uCi-1.4 X 103 1.4 X 10 1.2 X 103 1.3 X 103 Table C-2 Effective Dose Factors Noble~ - Air~
1978 1979 I
1980 I
AVIXAGE
~ AIR EFFECZIVE DOSE FACIOR Meff mrad-m3 uCi-lj S.O X 1O2 8.0 X 10 6.2 X 102 7.4 X 102 EEIA AIR EFFECTIVE DOSE FACIOR Neff lirad-m uCi-1.2 X 103 1.2 X 10 1.2 X 103 1.2 X 103
Page 81 of 88 ST. IIJCIE PIANT CKHISTRY OPERATING HKCEIXJRE NO. C-200, REVISION 11 OFFSITE DOSE CAICUZATION MANUAL OIXM Technical Bases for Eliminating Curie Inventory Limit For Gaseous Waste Storage ~
The NRC Standard Technical Specifications include a limit for the amount of radioactivity that can be stored in a single waste gas storage tank.
'Ibis curie inventory limit is established to assure that in the event of a tank failure releasing the radioactivity to the environment the resulting total body dose at the site bourdazy would not exceed 0.5 rem.
For St. tucie, the inventory limit in the waste gas storage tank has been determined to be approximately 285,000 curies (Xe-133, equivalent).
An allowable primary coolant radioactivity concentration is established by the Appemiix A Technical Specifications which limits the primary coolant radioactivity concentrations to 100/E with E being the average energy of the radioactivity in Mev.
This equation yields an upper primary coolant gross activity limit of about 160 uCi/ml.
By applying this activity concentration limitto the total liquid volume of the primary system, a total activity limit can be deterndned.
For St. tucie the primary system volume is about 70,000 gallons, which yields a limiting total inventory of approximately 43,000 Ci.
By assuming a typical radionuclide distribution an equivalent Xe-133 inventory can be determined.
Table D-1 provides the typical radionuclide (ncble gases) distribution and the Xe-133 equivalent con~tration.
The equivalent concentration is deteanined by multiplying the radionuclide concentration by the ratio of the nuclide total body dose factor to the Xe-133
~ body dose factor.
Sun>ning all the individual radionuclide equivalent concentrations provides the overall reactor coolant Xe-133 equivalent concentration.
The data shor that the equivalent concentration is a factor of 2 larger than the gross concentration (i.e.,
24 uCi/gm total versm 47 uCi/gm equivalent).
The resulting Xe-133 equivalent curie inventory of the reactor coolant system is approximately 86,000 Ci.
Therefore, even if the total primary system at the maximum Tech.
Spec.
allowable concentration was degassed to a single wa.~ gas decay tank, the tank curie inventory would be well below the 285,000 Ci limit.
Based on this evaluation, the curie inventory limit on a single waste gas storage tank cannot exceed the Technical Specification requ~~nent.
Page 82 of 88 ST. WCIE PZAÃZ CHEMISTRY OPERATING PBQCEIXRE NO. C-200, REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCÃ Table D-1 Reactor Coolant Xe-133 Effective Concentration I
I I
I REACTOR COOLANT>>
I I
CONCENTRATION I RADIONUCLIDE uCi m
I REG ~
GUIDE 1 ~ 109 I
TOTAL BODY DF
(~mrem r>
Ci ml I
Xe-133 RATIO
)
/ Concentration
/
Xe-133 OF uCi m
Xe-133 Xe-135m I
XQ-135 I
I Xe-137 I
Xe-138 12.
0.11 1.2 0.02 0.12 Kr-85m
/
0.19 Kr-85
[
0.83 I
Kr-87
[
0.16 Kr-88
[
0.31 Xe-131m f
8.8 I
Xe-133m i
0.20 1.2 X 10 1.6 X 10 5.9 X 10 1.5 X 10 9 '
X 10 2.5 X 10 2.9 X 10 3.1 X 10 1.8 X 10 1.4 X 10 8.8 X 10 o.o6 2O.
S2
~
o.32 I
0.86 I
1.O 6.2 4.8 30.
O.78 o.os 3.2 16.
I 2.8 0.17 I
12.
I 1.2 0.1 I
3.6 TOTALS 24.
47.
<<Data adapted from the NRC GALE Code
ST. IIJCIE PIZÃZ CKMESTRY OPERATING PBOCEXURE NO. C-200, REVISION 11 OFFSZIB DOSE CAICUIATIONMAKJtK ODCM Page 8 of 88 APPENDIX E RADIOIOGICAL SURVEZLULNCE ST. WCIE PIANOS Key to Sample Locations PATHIJAY LOCATION DESCRIPT ION I
I SAHPLE I APPROXIHATE I
I SAHPLES I
COLLECTION I
DISTANCE I
DIRECTION COLLECTED FREOUENCY miles SECTOR Direct Radiation N-1 North of Blind Creek TLD Ousrterl N
Direct Radiation HNIJ-5 South of Pete Stone Creek TLD Ouarterl Direct Radiation NNIJ-10 C.
G. Station Direct Radiation NIJ-5 Direct Radiation HW-10 Indian River Drive st Rio Vista Drive Intersection of SR 68 and SR 607 TLD TLD TLD Ousrterl Ouarterl Ousrterl 10 HNIJ NIJ NIJ Direct Radiation WNIJ-2 Cemeter South of 7107 Indian River Drive TLD auarterl MHIJ Direct Radiation MNM-5 US-1 st SR 712 Direct Radiation W-2 7609 Indian River Drive Direct Radiation MNM-10 SR 70
'West of Turn ike TLD TLO TLD Ousrterl auarterl Ouarterl 10
'MNIJ IJHIJ Direct Radiation W-5 Oleander and Ss er Streets TLD ausrterl Direct Radiation IJ-10 I-95 and SR 709 Direct Radiation Direct Radiation MSIJ-2 8503 Indian River Drive IJSM-5 Prima Vista Blvd. at Yacht Club Direct Radiation SM-2 Direct Radiation S'M. 5 9207 Indian River Drive US 1 snd Villa e Green Drive Direct Radiation SM-10 Port St. Lucie Blvd. and Cairo Road Direct Radiation IJSIJ-10 Del Rio snd Davis Streets TLD TLO TLD TLD TLD TLD TLO Ouarterl ausrterl ausrterl Ouarterl ausrterl Ouarterl Ousrterl 10 10 WSW
'MSW
'WSW SIJ S'W SIJ Direct Radiation SS'M-2 10307 indian River Drive TLD Ousrterl SSW Direct Radiation SSM-5 Port St. Lucie Blvd. snd US 1
Direct Radiation SSIJ-10 Pine Voile snd Mestmorelsnd Roads TLD TLD Ouarterl Ouarterl SSM SSM Direct Radiation S-5 13179 Indian River Drive TLD Ouarterl
ST. IIJCIE PLANT CSMESIIK OPERATING HKQM1RE NO. C-200, REVISION 11 OFFSITE DOSE CAIlXJIATIONMANUAL ODCH Page of 88 APPENDIX E (continued)
RADIOIDGICAL SUISZZLIANCE ST. WCIE PGKZ Key to Sample locations PATHMAY LOCATION DESCR IPT ION I
I SAMPLE I APPROXIHATE I
I SAKPLES I
COLLECTION I
DISTANCE I
DIRECTION COLLECTED FREQUENCY miles SECTOR Direct Radiation SSE-5 Entrance of Nettles Island Direct Radiation S-10 US 1 snd SR 714 Direct Radiation S SSE-10 Indian River Drive snd Quail Run Lane TLD TLD TLD Ousrterl Qusrterl Ousrterl 10 S
10 SSE 5
SSE Direct Radiation SSE-10 Elliot Huseum TI.D Ousrterl 10 SSE Direct Radiation SE-1 South of Coolin Canal Direct Radiation
SE 19 NNIl Airborne
[
HOS
[
FPL Substation
- Meatherby Road Radioiodine
(
Meekly
[
6 Particulates Airborne
)
<<HI2
(
FPL Substation SR 76, Stuart Radioiodine
)
Meekly
]
12 Particulates Airilorne
)
H14
( Onsite
- near south property line Radioiodine
)
Meekly
[
1 Particulates Airborne
[
H30
[ Po~er Line - 7609 Indian River Drive Radioiodine
[
Meekly
]
2 Part iculates MNM s
I SE M
Airborne
)
H34
[ Onsite - At Heteorological Tower Radioiodine
(
Meekly
[
0.5
(
N Particulates Materborne
)
H15
( Atlantic Ocean vicinity of public beaches I
) east side of Route A1A I
I Materborne
)
- H59
[ Near south end of Hutchinson Island I
I I
I Denotes Control Sample Surface Mater (ocean)
Sediment From shoreline Surface lister (ocean)
Sediment From shoreline Meekly
[
1 I
I Semi-Annually
(
Honthly
[
10-20 I
Semi-Annually
(
I EHE/E/ESE I
Ir S/SSE I
I
0
'k ~
k
- tt'
'k k'I ik
~
k
- kit, k ~
k ~
t Vk
< >'c pt t't J'
'".:a
'lg }
kkk P
'kt k
}
"k~fk p)"k 2F ~
t, Ltt".)
4
, '<vj ST. IOCZE PIANT QiEMISTRY OPEBRTING HK)CEXXJRE NO. C-200, REVISION 11 OFFSITE DOSE VKCUIATIONMANUAL 0 Page 8
of 88 APPENDIX E ST. IIJCZE PZtÃZ Key to Sample Zocations Food Products I
H15 I Ocean side vicinity of St. Lucie Plant I Crustacea I
Semi-Annually I
1 I
ENE/E/ESE I
NOTE 1
Fish Semi-Annuslt I
Food Products I
H51 I Offsite near north property line I Broad leaf)
Monthly I
1 I
N/HHW I
I I
I vegetationI(when available)/
I I
I msn rove I
H52 I Offsite near south property line I Broad leaf(
Monthly I
1 I
S/SSE I
I I vegetationI(when available)I I
I msn rove I
Food Products I crustacea I
Fish I Broad leaf I I vegetation/
I s/ssE I
I I
I I
I
=
I I
Semi-Annually I
Semi-Annually I
Monthly Food Products I
- H59 I Near south end of Hutchinson Island 10-20 msn rove Denotes controt sample It is the policy of Florida Power
& Light Company (FPL) that the St. Lucie 1
& 2 Radiological Environmental Monitoring Programs are conducted by the State of Florida Department of Health and Rehabilitative Services (DHRS), pursuant to an Agreement between FPL and DHRS and; that co-ordination of the Radiotogical Environmental Monitoring Programs with DHRS and compliance with the Radiologicat Environmental Monitoring Program Technical Specifications are the responsibility of the Nuclear Energy Services Department.
I HOTE 1
I I These samples may be collected from or supplemented by I
I samples collected from the ptant intake canal if the requiredI I analyses are unable to be performed due to unavailability or insde uste usntit of ssm le from the ocean side location.
I I
I I
I SAMPLE I
APPROXIMATE I
I I
I I
I SAMPLES I
COLLECTION I
DISTANCE I
DIRECTION I
I PATHWAY LOCATION DESCRIPTION COLLECTED FREQUENCY miles SECTOR I
ST. IIJCIE~
CKMESTRY OP1XATING PROCEIXJRE NO C 200 g REVISION 11 OFFSITE DOSE CAICUIATIONMANUAL ODCÃ Page 86 of 88 APPENDIX E (continued)
Figure 5.1.1 MZES:
(1) L-Liquid Radwaste Release Point (2) Due to the Scale of the Figure the Exclusion Area Radius (0.97 miles) and the Ixar Pop&ation Zone (1 mile)
Are Shown as being the same size.
(3) The following are unrestricted areas:
(a)
All waterways (Hennans Bay, Big Mud Creek, Indian River) with the exception of the intake and discharge canal (b)
Ocean front beaches (c)
State Road A1A
0-ST. IIJCIE PGKV QiEHISIBY OPERATING HQCE3XJRE NO. C-200, REVISION 11 OFFSPZE DOSE CAICUIATIONMANUAL 0 Page 87 of 88 IA rm O
'~r '
~
~l M
APPENDIX E (continued) c~ ~t~
E
~
~
~
~~".
'+o 4,
." ':~B L
-rc NO m Qa>
O ID I
prK~~~r~':~~
ty 1
M AO/A A e(vf k Plant Yenta 202.1 n ~ 1v O4 Fuel Bldg Vents 109.511
~ Iv A
m Rl n1 m
j'h rO Vl~ U 7rC 0
no mm
'0r P.xr H OX rio 0jX
>O mm~
1'ubllc Acceja lo n44ch ~
Y 3'3 0
c'
~ ~ <o 4cle C x IQ HJ Oj I
,'0 S gati
~ ~ ~ 4 0lfIpllAP Q)H, 4
ianna
.3 I i,]V Y
7
$g u< ~
Pubnc Accost lo 844ch
ST. IIJCIE PIANT CKMISTfK OPERATING PROCEIXJRE NO C 200'EVISION 11 OFFSITR DOSE CAMUZATIONMANUAL ODCÃ Page 88 of 88 APPlM3IX F MBZHOROZDGICAL DISPERSION PORMIJZAS*
For )~:
2.032 (u-Bar)D (Z
+ cV /pi) /
z 2.032 (3) 1/2 Z
z (u-Bar) D EQ (1)
EQ (2)
Where C =.5 V = 207.5 ft. (63.2 meters)
(u-Bar) = a name for one term 1 in EQ (1) and EQ(2) denotes take the scpmre root of the texm in 2
parentheses in EQ(1) arxl EQ(2) should be a lower case sigma ifthis is cxzapared Z
to references concmzdng Meteorological data X/Q was calculated using each of the above EQ's for each hour.
'Ihe highest X/Q fram EQ (1) or EQ (2) was selected.
%he total integrated relative concentration at each sector and distance was then divided by the total number of hours in the data base.
(QQ)D = (QQ) X (Depletion factor of figure 2 of R.G. 1.111-R1)
For De ition D
D/Q = RDep/(2 sin [11.25] X) X (Freq. distribution)
Where D/Q
= Ground deposition rate X
= Calculation distance RDep = Relative ground deposition rate fram Figure 6 of R.G. 1.111, Rl
~vain correction factors given by Table M-4 were also applied to Dispersion Formulas
i.