ML17308A457
| ML17308A457 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1988 |
| From: | Conway W FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-89-68, NUDOCS 8903070017 | |
| Download: ML17308A457 (69) | |
Text
~~WC'CELERATED DISTRIBU'EON DEMONSTRATION SYSTEM REGULATOO INFORMATION DISTRIBUTION%STEM (RIDE)
ACCESSION NBR:8903070017 DOC..DATE: 88/12/31 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 CONWAY,W.F.
Florida Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION DOCKET N
05000335 05000389 DISTRIBUTION CODE:
IE48D COPIES RECEIVED:LTR J ENCL J SIZE:
TITLE: 50.36a(a)(2)
Semiannual Effluent Release Reports NOTES: 5~~ R~W4
SUBJECT:
"Combined Semiannual Radioactive Effluent Release Rept,"
for Jul-Dec 1988.W/890228 ltr.
3 R
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RECIPIENT ID CODE/NAME PD2-2 LA NORRISF J INTERNAL: ACRS ARM TECH ADV NRR/DREP/RPB 10 RGN2 FILE 02 EXTERNAL: BNL TICHLER,J03 LPDR COPIES LTTR ENCL 1
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NOXE TO ALL "RIBS" RIXZPZERIS:
PIZASE HELP US To REZQCB HASTE!
COMI'ACT THE DOCUMERZ CONIBDL DESK, BOCH Pl-37 (EXT. 20079)
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P.O. Box14000, Juno Beach, FL 33408-0420 FSBRUSN 2 8 1989 L-89-68 10 CFR 50.36 U: S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
St. Lucie Units 1 and 2
Docket Nos.
50-335 and 50-389 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of July 1, 1988 through December 31, 1988 for St. Lucie Units 1 and 2.
This report is required by Technical Specification 6.9.1.7.
Should there be any questions on this information, please contact us
~
Very truly yours, W.
F Seni onway Vice President Nuclear WFC/GRM/cm Attachment cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRMSARER an FPL Group company
)r]-gK I
(
8903070017 881231 PDR ADQCl( 0500033'mu FLORIDA POHER
&, LIGHT COMPANY ST.
LUCIE PLANT UNITS NO.
1 8c 2 LICENSE NO.S DPR-67
& NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY 1, 1988 THROUGH DECEMBER 31, 1988-
Vq N
TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION............
1 SITE VISITOR DOSE FROM EFFLUENTS........
OFFSITE DOSE CALCULATION MANUAL REVISIONS.
SOLID HASTE AND IRRADIATIED FUEL SHIPMENTS...
PROCESS CONTROL PROGRAM REVISIONS.......
LIQUID EFFLUENT:
7
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8 8
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8 SUMMATION OF ALL RELEASES
& NUCLIDE SUMMATION BY QUARTER UNIT ¹ 1
UNIT ¹ 2
ORGAN DOSE FOR CALENDAR YEAR 1988 9
10 UNIT ¹ 1
UNIT ¹ 2
GASEOUS EFFLUENT:
13
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o 14 SUMMATION OF ALL RELEASES 8c NUCLIDE SUMMATION BY QUARTER UNIT ¹ 1
UNIT ¹ 2
ORGAN DOSE SUMMATION FOR CALENDAR YEAR 1988 UNIT ¹ 1
UNIT ¹ 2
15 16
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19 20 SOLID HASTE
SHIPMENT SUMMATION
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21 ATTACHMENT A ODCM revisions during the reporting period
I
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EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION
- 1. Regulatory Limits
- 1. 1 For Liquid Haste 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 Haste 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.
4B.
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.
4C.
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 calcuations are based on.
The STS LCO dose limits are therefore included in Item 1 of the report, for information only.
/
EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMAT10N (Continued) 2.
Maximum Permissible Concentrations Hater:
As per 10 CFR 20 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 do'se rate limits described in 1.2.A. of this report.
3.
Average Energy of fission and activation gases in gaseous effluents is not applicable.
4.
Measurements and approximations of total radioactivity Hhere alpha, tritium, and named nuclides are shown as zero Curies
- released, this should be interpreted as "no acitvity 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
'T Total 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.
0
EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 4.
Measurements and Approximations of Total Radioactivity (Cont.)
- 4. 1 (Continued)
B.
(Continued)
TABLE 3. 1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS Liquid Source Sampling Frequency Type of Analysis Method of Analysis Monitor Tank 1
Releases Monthly Composite Tritium Gross Alpha Quarterly Sr-89, Sr-90, Composite 8c Fe-55 Each Batch Principal Gamma Emitters
- p. h. a.
L. S.
G. F. P.
C. S.
Continuous Releases Daily Grab Samples Principal Gamma Emitters 8c I-131 for 4/M Compos ite Analys is Dissolved
& Entrained Gases One Batch/ Month Tritium Composite Monthly Alpha Composite Monthly Sr-89, Sr-90, 8c Fe-55 Composite Quarterly
- p. h. a.
- p. h. a.
L. S.
G. F. P.
C. S.
1-Boric Acid Evaporator Condensate is normally recovered to the Primary Hater Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Haste Effluent Totals.
All peaks are identified and quantified.
L.S.-Liquid Scintillation Counting C.S.-Chemical Separation G. F. P.-Gas Plow Proportional Counting 4/M-Four per Month
EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 4.
Measurements and Approximations of Total Radioactivity (Continued)
- 4. 1 (Continued)
B.
(Continued)
TABLE 3.2 RADIOACTIVE GASEOUS HASTE 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.
Plant Vent 4/M Monthly Composite Quarterly Composite Principal Gamma Emitters Tritium Particulate Gross Alpha Particulate Sr-89 5 Sr-90
- p. h. a.
L. S.
G. F. P.
C. S.
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
II II
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
1 SEMIANNUAL REPORT JULY 1,
1988 THROUGH DECEMBER 31, 1988 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.
BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR ST.
LUCIE PLANT UNIT NO.
1 A.
NUMBER OF BATCH RELEASES-'.
TOTAL TIME PERIOD OF BATCH RELEASES:
C.
MAXIMUM TIME PERIOD FOR A BATCH RELEASE:
D.
AVERAGE TIME PERIOD FOR A BATCH RELEASE:
E.
MINIMUM TIME PERIOD FOR A BATCH RELEASE:
F.
AVERAGE STREAM FLOW DURXNG REPORTING PERIOD INTO A FLOWING STREAM:
18865.
MINUTES 888.
MINUTES 563.
MINUTES 148.
MINUTES 889386.
G.P.M.
6.
GASEOUS FOR ST.
LUCXE PLANT UNIT NO.
1 A.
NUMBER OF BATCH RELEASES:
B.
TOTAL TIME PERIOD OF BATCH RELEASES:
C MAXIMUMTIME PERIOD FOR A BATCH RELEASE D.
AVERAGE TIME PERIOD FOR A BATCH RELEASE:
E.
MINIMUM TIME PERIOD FOR A BATCH RELEASE:
UNPLANNED RELEASES LIQUIDS FOR ST.
LUCIE PLANT UNIT NO.
1 A.
NUMBER OF RELEASES B.
TOTAL ACTXVITY RELEASED:
6.
GASEOUS FOR ST.
LUCIE PLANT UNIT NO.
1 A.
NUMBER OF RELEASES:
B.
TOTAL ACTIVITY RELEASED:
SEE ATTACHMENTS (IF APPLICABLE) FOR:
3883.
MINUTES 788.
MINUTES 388.
MINUTES 2.
MXNUTES 8.
8.
CURIES 8.
8.
CURIES A.
A DESCRIPTXON OF THE EVENT AND EQUIPMENT INVOLVED.
B.
CAUSE(S)
FOR THE UNPLANNED RELEASE.
C.
ACTIONS TAKEN TO PREVENT A RECURRENCE.
D.
CONSEQUENCES OF THE UNPLANNED RELEASE.
FLORIDA POWER 8c LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
2 SEMIANNUAL REPORT JULY 1,
1988 THROUGH DECEMBER 31, 1988 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.
BATCH RELEASES AND UNPLANNED RELEASES LIQUXDS FOR ST.
LUCIE PLANT UNIT NO.
2 A.
NUMBER OF BATCH RELEASES:
B.
TOTAL TIME PERIOD OF BATCH RELEASES:
C.
MAXIMUMTIME PERIOD FOR A BATCH RELEASE:
D.
AVERAGE TIME PERIOD FOR A BATCH RELEASE:
E.
MINIMUM TIME PERIOD FOR A BATCH RELEASE:
F.
AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM:
33',
18865.
MINUTES 888.
MINUTES 563.
MINUTES 148.
MINUTES 889386.
G.P.M.
6.
GASEOUS FOR ST
~
LUCIE PLANT UNIT NO ~
2 A.
NUMBER OF BATCH RELEASES:
B.
TOTAL TIME PERIOD OF BATCH RELEASES:
C.
MAXIMUM TIME PERIOD FOR A BATCH RELEASE:
D.
AVERAGE TIME PERIOD FOR A BATCH RELEASE:
E.
MXNIMUM TIME PERIOD FOR A BATCH RELEASE:
UNPLANNED RELEASES LIQUIDS FOR ST.
LUCIE PLANT UNIT NO.
2 A.
NUMBER OF RELEASES:
B.
TOTAL ACTIVITY RELEASED:
6.
GASEOUS FOR ST.
LUCIE PLANT UNIT NO.
2 A.
NUMBER OF RELEASES-B.
TOTAL ACTIVITY RELEASED:
SEE ATTACHMENTS (IF APPLICABLE) FOR:
17.8 5926.
MINUTES 1388.
MINUTES 349.
MINUTES 68.
MINUTES 8.
8
~
CURIES 8.
8.
CURIES A.
A DESCRIPTION OF THE EVENT AND EQUIPMENT INVOLVED.
B CAUSE(S)
FOR THE UNPLANNED RELEASE C.
ACTIONS TAKEN TO PREVENT A RECURRENCE.
D.
CONSEQUENCES OF THE>>
UNPLANNED RELEASE.
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE PLANTS UNITS 1
8c 2 SEMIANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 EFFLUENT AND HASTE DISPOSAL
SUPPLEMENTAL INFORMATION (Continued) 7.
Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY assumes the visitor onsite for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at an average distance of 0.3 kilometers in the worst dispersion direction, and received exposured from each of the two reactor units on the Site.
VISITOR DOSE RESULTS FOR CALENDAR YEAR 1988 HERE:
NOBLE GAS EXPOSURE DOSE (mrad)
Gamma Air Dose Beta Air Dose GASEOUS PARTICULATE 8c IODINE EXPOSURE
- 1. 60 E-02
- 3. 32 E-02 DOSE (mrad)
Bone Liver Thyroid Kidney Lung GI-LLI Total Body 5.87 E-06
- 2. 44 E-04
- 2. 38 E-03
- 1. 05 E-04
- 2. 37 E-04
- 2. 37 E-04
- 2. 54 E-04
1 h
r 4
1 I
FLORIDA POWER 5, LIGHT COMPANY ST.
LUCIE PLANT UNITS NO.
1 8c 2 SEMIANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 EFFLUENT AND HASTE DISPOSAL
SUPPLEMENTAL INFORMATION (Continued)
- 8. Offsite Dose Calculation Manual Revisions (ODCM):
Revision 10 to C-200 was implemented during the reporting period.
The eleven pages affected by this revision are included as Attachment A to this report.
Most of these changes were administrative'nd an explanation is noted on each page.
The ODCM contains an example format for submitting six month reports.
The correct sample frequency was inserted to the Tables and on page 4S of 88, a more specific breakdown of error estimates was inserted as per the request of an NRC audit item in the Effluent area.
The change on page 9 of 88, was the result of an internal Quality Assurance
- audit, where the source of the data reference for Liquid Radwaste Release (Design bases)
Rate Flow was changed from 150 to 170 gallons per minute.
This change ties the ODCM value to the value stated in the revision to the Final Safety Analysis Report for this system.
The previous value was based on data that was available at the time the ODCM was implemented.
The actual observed maximum value of release rate was 88 gpm from pre-operational testing.
This change is to make the F.S. A. R. the official reference source for release rate.
- 9. Solid Haste and Irradiated Fuel Shipments:
No irradiated fuel shipments were made from the site.
Common Solid waste from St.
Lucie Units 1 and 2 were shipped jointly.
A summation of these shipments is given in Table 3.9 of this report.
10'.
Revisions:
The PCP was not revised during the reporting interval.
JULY FLORIDA POWER
&, LIGHT COMPANY ST.
lUCIE PLANT UNIT NO.
1 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1988 TABLE 3.3-1 lIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹3 QUARTER ¹4 A. FISSION AND ACTIVATION PRODUCTS 1.
TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD B,
TRITIUM 1.
TOTAl REl EASE 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD C.
DISSOLVED AND ENTRAINED GASES 1.
TOTAL RELEASE 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD D.
GROSS ALPHA RADIOACTIVITY CI 1.21E-81 CI 6.28E 81 UCI/ML 1.64E-87 CI 3.92E-81 UCI/ML 1.82E-89 UCI/Ml 3.14E-18 8.16E-82 1.62E-18
- 8. 28E 81 1.63E-87 1.98E-82 3.94E-11 1.
TOTAL RELEASE CI 8.18E-86 5 '5K-86 E.
VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)
F.
VOLUME OF DILUTION WATER USED DURING REPORTING PERIOD lITERS 3.98E 87 lITERS 3.84E 11
- 1. 34E 87 5.83E 11
JULY FLORIDA POWER k LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
2 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1988 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL REiLEiASES NUCLIDES RELEASED UNIT QUARTER ¹3 QUARTER ¹4 A. FISSION AND ACTIVATION PRODUCTS 1.
TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)
CI 1.18E-81 8.16E-82 2.
AVERAGE DILUTED CONCENTRATION DURING PERIOD BE 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 CI 6
27Ei 81 UCI/ML 1.63E-87 CI 3.92E-81 UCI/ML 1.82E-89 UCI/ML
- 3. 87Ei-18 1.62E-18
- 8. 28E 81
- 1. 63Ei-87 1.91E-82 3.81E-11 1.
TOTAL RELEASE CI 8.18E-86 5.65E-86 E.
VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)
F.
VOLUME OF DILUTION WATER USED DURING REPORTING PEiRIOD LITERS 2.88E 86 LITERS 3.84E 11 1.45E 86 5.83E 11 10
JULY FLORIDA POWER
&, LIGHT COMPANY ST, LUCIE PLANT UNIT NO.
1 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1968 TABLE 3.4-1 LIQUID EFFLUENTS NUCLXDES RELEASED UNIT CONTINUOUS MODE QTR.¹3 QTR.¹4 BATCH MODE QTR.¹3 QTR.¹4 I-131 I-132 I-133 I-134 NA-24 CR-51 MN-54 FE-55 CO-57 CO-58 CO-68 AG-118 SN-113 SB-122 SB-124 W-187 ZR-95 NB-95 NB-97 TC-99M RU-183 SB-125 CS-134 CS-137 LA-148 CE-141 TE-132 CI CI CI CI CI CI CI CI CX CI CI CI CX CI CI CI CI CI CX CI CI CI CI CI CI CI CI 2.63E-84 8,88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-gi 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8 89Ei-84 1.42E-83 8.88Ei-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8 '8K-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E 81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 2.83E-83 6.88E-85 3.83E-84 8.88E-81 6 '5E-85 1.55E-82 4.18E-84 2.65E-83 4.88E-86 4.27E-82 1.81E-82 8.25E-84 2.34E-84 4.89E-84 7.73E-83 8.88E-81 2.66E-83 4.44E-83 1.33E-83 1.27E-85 5.87E-84 9.47E-83 2.73E-83 3.82E-83 8.15E-84 5.55E-85 1.13E-84 1.64E-83 8.88E-81 1.17E-84 4.36E-85 4.48E-85 1.72E-83 4.98E-84 1.11E-82 8.88E-81 8.87E-83 2.49E-82 2.76E-84 8.75E-85 4.44E-84 4.21E-83 5.45E-85 8.67E-84 2.15E-83 5.86Ei-84 8.88E-81 4.51E-85 9.31E-83 5.56E-83 9.87E-83 7.76E-85 8 '8E-81 8.88E-81 TOTAL FOR PERIOD CI 2.57E-83 8.88E-81 1.18E-81 8.16E-82 XE-131M XE-133 XE-133M XE-135 CI CI CI CI 8.88E 81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 g 88E-81 8.88E-81 6.91E-84 3.83E-83 8.88E-81 3.82E-81 1.86E-82 4.62E-83 5.85E-85 3.12E-83 5.33E-84 TOTAL FOR PERIOD CI 8.88E-81 6.91E-84 3.92E-81 1.91E-82 11
JULY FLORIDA POWER 8c LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
2 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1988 TABLE 3.4-2 LIQUID EFFLUENTS NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR.¹3 QTR.¹4 BATCH MODE QTR.¹3 QTR.¹4 I-131 I-132 I-133 I-134 NA-24 CR-51 MN-54 FE-55 CO-57 CO-58 CO-68 AG-118 SN-113 SB-122 SB-124 W-187 ZR-95 NB-95 NB-97 TC-99M RU-3.83 SB-125 CS-134 CS-137 LA-148 CE-141 TE-132 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 8,88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8 '8E-81 8.88E-81 8 '8K-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8 '8E-81 8 '8E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E 81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8 '8E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E<-81 8 '8K-81 8.88E<-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 8.88E<-81 8.88E-81 8.88E<-81 8.88E-81 8.88E-81 8.88E<'-81 8.88E-81 8.88E-81 8.88E-81 2.83E-83 6.88E-85 3.83E-84 8.88E-81 6.75E-85 1.55E-82 4.18E"84 2 '5K-83 4.88E-86 4.27E-82 1.81E-82 8.25E-84 2.34E-84 4.89E-84 7.73E-83 8.88E-81 2 '6K-83 4.44E-83 1.33E-83 1.27E-85 5.87E-84 9.47E-83 2.73E<-83 3.82E-83 8.15E-84 5.55E-85 1 '3K-84 1,64E-83 8.88E-81 1.17E-84 4.36E-85 4.48E-85 1.72E-83 4.98E-84 1.11E-82 8.88E-81 8.87E-83 2.49E-82 2.76E-84 8,75E<-85 4.44E-84 4.21E<-83 5.45E-85 8.67E-84 2.15E-83 5.86E-84 8.88E-81 4.51E-85 9.31E-83 5.56E-83 9.87E-83 7.76E-85 8.88E-81 8.88E-81 TOTAL FOR PERIOD CI 8.88E<-81 8.88E-81 1.18E-81 8.16E-82 XE-131M XE-133 XE-133M XE-135 CI CI CI CI 8.88E-81 8.88E-81 8 '8E-81 8 '8E-81 8.88E-81 8.88E-81 8.88E-81 8.88E-81 3.83E-83 3.82E-81 4.62E-83 3.12E-83 8.88E-81 1.86E-82 5.85E-85 5.33E<-84 TOTAL FOR PERIOD CI 8.88E-81 8.88E-81 3.92E-81 1.91E-82 12
FLORIDA PONER
& LIGHT COMPANY ST.
LUCIE UNIT NO.
1 SEMI-ANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 TABLE 3. 5-1 LIQUID EFFLUENTS
DOSE SUMMATION Age Group:
ADULT Location:
Any ADULT Exposure Interval:
January 1,
1988 through December 31, 1988 FISH & SHELLFISH ORGAN Bone Liver Thyroid Kidney Lung GI-LLI Total Body Calendar Year Dose (mrem)
- 1. 80 E-02
- 7. 71 E-02
- 3. 99 E-03
- 1. 05 E-03
- 8. 97 E-02
- 9. 44 E-02 2.25 E-02 1 3
I I
4 Ih
'I Il
FLORIDA POHER 8c LIGHT COMPANY ST.
LUCIE UNIT NO.
2 SEMI-ANNUAL REPORT t
JULY 1, 1988 THROUGH DECEMBER 31, 1988 TABLE 3.5-2 LIQUID EFFLUENTS
DOSE SUMMATION Age Group:
ADULT Location:
Any ADULT Exposure Interval:
January 1,
1988 through December 31, 1988 F ISH 8c SHELLF IS H ORGAN
- Bone, Liver Thyroid Kidney Lung GI-LLI Total Body Calendar Year Dose (mrem) 1.75 E-02 7.69 E-02 3.76 E-03
- 1. 00 E-03
- 8. 97 E-02
- 9. 42 E-02
- 2. 23 E-02 14
S g 1'
4
JULY FLORIDA POWER 5, LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
1 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1988 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED A. FISSION AND.ACTIVATIONGASES 1.
TOTAL RELEASE UNIT QUARTER ¹3 QUARTER ¹4 3.43E 82 CI 2.81E 82 2.52E 81 B.
IODINES 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 4.32E 81 1.
TOTAL IODINE-131 CI 2 11E-83 1 36E-83 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2.66E-84 1.71E-84 CD PARTICULATES 1.
PARTICULATES T-1/2 )
8 DAYS CI 8.88E-81 2,
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88E-81 3.
GROSS ALPHA RADIOACTIVITY DE TRITIUM 1.
TOTAL RELEASE CI CI 1.23E-87 2.87E 81 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.61E 88 8.88E-81 8,88E-81 1.38E-87 4.66E 81 5.87E 88 15
JULY FLORIDA POWER 8c LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
2 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1988 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED A
FISSION AND ACTIVATION GASES UNIT QUARTER ¹3 QUARTER ¹4 1.
TOTAL RELEASE CI 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC B.
IODINES 1.
TOTAL XODINE-131 CI 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC C.
PARTICULATES 2.87E 83 2.68E 82 1.28E-82 1.61E-83 2.95E 83 3.71E 82 1.88E-83 2.36E-84 1.
PARTICULATES T-1/2 8 DAYS CI 8.88E-81 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.88E-81 3.
GROSS ALPHA RADIOACTIVITY D.
TRITIUM 1.
TOTAL RELEASE CI CI 1.81E-88 1.83E 81 2.
AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 1.38E 88 8.88E-81 8.88E-81 2.78E-87 1.93E 81 2.43E 88 1 6
JULY FLORIDA POWER
&, LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
1 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBER 31, 1988 TABLE 3;7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES NUCLIDES RELEASED UNIT 1.
NOBLE GASES CONTINUOUS MODE QTR.¹3 QTR.¹4 BATCH MODE QTR.¹3 QTR.¹4 AR-41 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI 8 '8E-81 8.88E-81 8.88E-81 8 '8K-81 8.88E-81 2.17E 82 8 '8E-81 7.83E 88 8.88E-81 8 '8E-81 8.88E-81 8.88E-81 8.88E-81 1.88E 82 8.88E-81 1.29E 81 3.83E 88
- 1. 13E 88 1 '7E-81 1.22E 88 8 '8E-81 9,22E 81 1.87E 88 1.87E 81 1.27E-82 1 '6E-84 8.88E-81 8.88E-81 1.83E-82 3.94E-83 3.18E-83 1.99E-83 2.25E 82 2.81E 82 1.18E 82 3.23E-82 2.
IODINE I-131 I-132 I-133 TOTAL FOR PERIOD CI 2.11E-83 1.36E-83 CI 4.28E-82 8.88E-81 CI 1.18E-82 1.21E-82 CI 5.67E-82 1.35E-82 3.
PARTICULATE TOTAL FOR PERIOD CI 8.88E-81 8.88E-81 17
I
/
JULY FLORIDA POWER
% LIGHT COMPANY ST.
LUCIE PLANT UNIT NO ~
2 SEMIANNUAL REPORT 1,
1988 THROUGH DECEMBEiR 31, 1988 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEiL RELEASES NUCLIDES RELEASED UNIT 1.
NOBLE GASES CONTINUOUS MODE QTR.¹3 QTR.¹4 BATCH MODE QTR.¹3 QTR.¹4 AR-41 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 TOTAL FOR PERIOD 2.
IODINE I-131 I-133 TOTAL FOR PERIOD 3
~
PARTICULATE RB-88 TOTAL FOR PEiRIOD CI CI CI CI CI CI CI CI CI 8.88Ei-81 8.88E-81 1.17E 81 8.88E-81 6.39E 88 8.88E-81 1.71E 83 6.53E 81 2.89E 82 8.88E-81 8 '8E-81 2.56E 81 8 '8E-81 7.52E 88 8.88E-81 2.28E 83 1.46E 81 2.67E 82 1.15E-81 8.88E-81 5.19E-82 6.84E-83 4.35E-82 4.23E-81 6.12E 81 6.62E-81 9.81E-81 1.32E 88 9.68E-81 2.83Ei 88 3.64E-81 2.32E 88 2.68E 88 3.24E 82 5.89E 88 2.26E 81 CI
- 1. 28E-82
- 1. 88Ei-83 CI 1.63E-82 4.34E-83 CI 2.91E-82 6.22E-83 CI 1.27E 88 8.88E-81 CI 1.27E 88 8.88E-81 CI 2.88Ei 83 2.59E 83 6.35E 81 3.61Ei 82 18
I l t
FLORIDA PONER 8c LIGHT COMPANY ST.
LUCIE PLANT UNIT 0 1
TABLE 3.8-1 GASEOUS EFFLUENTS
DOSE SUMMATION Age Group:
INFANT Exposure Interval:
January 1,
1988 through December 31, 1988 NOTE:
The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg.
Guide
- 1. 111, March 1976 PATHNAY BONE mrem LIVER mrem THYROID mrem KIDNEY mrem Ground Plane (A)
- 0. 00 E-01 Grass-Cow-Milk(B)
- 3. 68 E-04 0
~ 00 E-01 1
~ 85 E-03
- 0. 00 E-01
- 1. 42 E-01
- 0. 00 E-01
- 7. 26 E-04 Inhalation (A) 1.52 E-05
- 1. 19 E-03
- 6. 64 E-03
- 5. 17 E-04 TOTAL
- 3. 83 E-04
- 3. 04 E-03
- 1. 48 E-01
- 1. 24 E-03 PATHWAY LUNG mrem GI-LLI mrem T.
BODY mrem Ground Plane (A)
- 0. 00 E 00 Grass-Cow-Milk(B) 1.40 E-03
- 0. 00 E 00 2.40 E-05 1.42 E-03 1.65 E-03 Inhalation (A)
- l. 17 E-03
- l. 17 E-03
- 1. 18 E-03 TOTAL
- 2. 57 E-03
- 2. 59 E-03
- 2. 85 E-03 (A)-Sector NEST (B)-Sector 'HSN Range:
Range:
- 1. 78 miles
- 3. 75 miles (Actual Cow)
NOBLE GASES Gamma Air Dose Beta Air Dose Sector NEST CALENDAR YEAR (mrad)
- 2. 12 E-02 4.03 E-02 Range:
1.78 miles 00 19
Di I
FLORIDA POWER 8r, LIGHT COMPANY ST.
LUCIE PLANT UNIT 0 2
TABLE 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION AGE GROUP INFANT Exposure Interval:
January 1,
1988 through December 31, 1988 NOTE:
The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg.
Guide
- 1. 111, March 1976 PATHWAY BONE mrem LIVER mrem THYROID KIDNEY mrem mrem Ground Plane (A) rass-Cow-Milk(B)
Inhalation (A)
TOTAL 0
~ 00 E-01 1 ~ 57 E-03
- 2. 95 E-05
- 1. 60 E-03
- 0. 00 E-01
- 0. 00 E-01 2.63 E-03 5.85 E-01
- 6. 69 E-04
- 1. 15 E-02
- 3. 30 E-03
- 5. 97 E-01
- 0. 00 E-01
- 7. 92 E-04
- 2. 85 E-04
- 1. 08 E-03 PATHWAY LUNG mrem GI-LLI T.
BODY mrem mrem Ground Plane (A) 0.00 E 00 0.00 E 00 8.02 E-05 rass-Cow-Milk(B) 7.62 E-04 8.31 E-04 1.82 E-03 Inhalation (A)
- 6. 32 E-04
- 6. 34 E-04
- 6. 49 E-04 TOTAL 1.39 E-03 1
~ 47 E-03 2.55 E-03 (A)-Sector WEST (B)-Sector:
WSW Range:
Range:
1
~ 78 miles
- 3. 75 miles (Actual Cow)
NOBLE GASES Gamma Air Dose Beta Air Dose Sector WEST CALENDAR YEAR (mrad)
- 1. 18 E-01 2.48 E-01 Range:
1.78 mile 20 l
II pi t'~
FLORIDA POWER AND LIGHT COtlPANY ST.
LUCIE PLANT SEMI-ANf)UAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 UNITS 1 AND 2, TABLE 3.9 A.
Solid Waste Shipped Off-Site for Burial or Disposal 1.
Type of Waste Unit 6 No. Period Error I a.
Spent resin, tt3 1.945 E+1 Process filters Ci 3.732 E+2 b.
Dry Compressible N3 2.190 E+2 Waste (Note 5)
Ci 2.531 E+1 c.
Irradiated ti3 1.625 E+0 Components Ci 1.730 E+3
- 2. OE+1 2.0E+1 2.0E+1 d.
Other
- 1. Non-Compressible Ci Metal (DAW)
(Note 6) 3.924 E+1 6 773 E-1
- 2. OE+1 2.
Estimate of flavor Nuclide Composition (By Type of 't4aste)
Category a ~
b.
Nuclides Cs 137 Co 58 Cs 134 Co 60 Ni 63 Fe 55, t<n 54 I 131 Cs 137 Co 60 Cs 134 Fe 55 Co 58 Nb 95 Zr 95 Ni 63 lln 54 Cr 51 H
3 Sb 125
- 3. 46E+1
- 2. 15E+1 1.93E+1 1.21E+1 7.70E+0 1.75E+0 1.59E+0 5.80E 1
- 3. 89E+1
- 1. 70E+1
- 1. 47E+1 9.65E+0 5.65E+0 4.06E+0 2.57E+0 1.88E+0 1.43E+0 1.40E+0 1.32E+0 8.20E 1
0 4
A.
2.
Estimate of Major Nuclide Composition (By Type of Waste)
(continued)
Category Nuclides C.
d.
Fe 55 Co 60 Co 58 Mn 54 Ni 63 Zr 95 H
3 Co 60 Fe 55 Cs 137 Mn 54 Ni 63 Cs 134 Co 58 Sb 125 5.00E+1 2.96E+1 8.38E+0 7.75E+0 2.24E+0 9 70E 1
5.50E-1 6 33E+1 1.99E+1 5.46E+0 3.27E+0 2.34E+0 2.07E+0 1.28E+0 7 30E 1
3.
Solid Haste Disposition Number of Shipments 59 B.
Irradiated Fuel Shipments Number of Shipments 0
Mode of Transportation Destination Sole Use Truck Barnwell, S.C.
Mode of, Transportation Destination N/A N/A N/A = Not Applicable
0
0 FLORIDA POME D LIGHT COHPAriY ST.
LUCIE PLAtlT SEMI-ANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 UNITS 1 AND 2, TABLE 3.9 (CONTINUED)
Total Total Principal Waste Volume Curies Radionucl ides Class Cubic Ft.
(Note 1)
(Notes 1 5 2)
Type of Waste (Note 3)
Category Reg-Guide 1.21 Type of Container (Note 4)
Solidification Agent Class A
7528.3 Class A
1385.7 Class B
205.8 Class 8
566.7
- 2. 52 6.77E-1 22.79 217.27 NA NA Cs 137, Ni 63, Sr 90 Cs 137, Sr 90, Hi 63,
- TRU, Sum of Huclides with T 1/2
< 5 Years
..PWR Compactible Trash Note 5)
PWR f/on-Compactible Trash Note 6
-Compactible Trash PWR Ion-Exchange
-Resin 1.b.
1.d.
1.b.
l.a.
Non-Specification Strong Tight Package Non-Specification Strong Tight Package NRC Certified LSA
> T e A HRC Certified LSA
> Type A Hone None tlone t/one Class B
57.4 1730.0 Co 60, Ni 63, H3, C 14, Sum PWR Irradiated of Nuclides w/
Reactor T 1/2
< 5 Years Com onents 1.c.
t)RC Certified Type B
Hone Class C
120.3 155.98 Cs 137, Co 60, Sr 90, Hi 63, Sum of Huclides with T 1/2
< 5 Years PWR Ion-Exchange Resin l.a.
t/RC Certified LSA >
Type A None
I
FLORIDA POWER AND LIGHT COlPANY ST.
LUCIE PLANT SEMI-ANNUAL REPORT JULY 1, 1988 THROUGH DECEMBER 31, 1988 UNITS 1 AND 2 TABLE 3.9 (CONTINUED)
SOLID WASTE SUPPLEMENT Note 1:
Note 2:
The total curie quantity and radionuclide composition of solid waste shipped from the St.
Lucie Plant, Units 1
8 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 llaste Classification (5/ll/83) for these determinations.
The most frequently used techniques for determining the total curie uantity 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 are used to establish scaling factors or other estimates for radionuclides such as 3H,
- 14C, 99Tc,
- 129I, 241Pu,
- 242Cm, 63Ni,
- 55Fe, and 90Sr.
"Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than
.Ol 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:
Note 6:
The volume and activity listed for Dry Compressible Waste represent the quantity of material that to date has been 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, seven shipments of Dry Compressible Waste (6716 cubic feet, 2.09 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.
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.
1
A~lac>ment A Rev 10 changes Page 1 of 88 p~". GIK Fui r 4r~kwi Qnly FIOIUM R%ER
& LXGHI'CHPANY ST.
IIJCEE PZANZ CSMfSZRY OPERATING PBOCEIXIRE NO. C-200 REVISXON 10 Offsite Dose Calculation Manual (ODCM)
Reich.ewed by Facility Review Group Approved by W
Revtsio~Q Reviewed F R G Approved by Plant Manager Plant Manager 19~
7 19~8 19
+ ~19 S
OPS I
I I cess I sos 10 I
I I
I I
I I
I
ST.
IIJCZE PDÃT CSEKL'STRY OPERATING HKCECURE NO. C-200, REVISION 10 Page 9 of 88 1.2 (cord~ed)
Where:
FL D
Ci ma4h rEQMhc&
F'la~%
F,
()e, d).s)p) ada) a,h.a&i'>+~
the fraction of 10CFR20 MPC t would result if the release source was disctmxged er the conditions specified.
'Ihe urdiluted rel in of the release source.
Liquid Rad Waste ~
70 Steam Generator 12 Steam Generator
/R10
%he dilution flow in gpn of Intake Caalhxg Water or Circulating Water Pumps Intake Cooling flow is 14,500 ~pump Circulating Water flow is 121,000 gpai/pump ihe undiluted concentzation of nuclide (i) in uCi/ml fram sample assay (MPC)i Ihe maximum permissible concentxation of nuclide (i) in uCi/ml fzaa Table L-1.
For dissolved or entrained ncble gases the MPC value is 2 X 10 4 uCi/ml for the sum,of all gases o
Ihe fraction of the 10CFR20 MPC limitmay be detezrrdned by a nuclide-by-nuclide evaluation or for purposes of simplifying the calculation by a cumulative activity evaluation. If the simplified method is used, 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 shauld be substituted for Ci.
As long as the diluted concentration (C~~ R/D) is less than 3 X 10 uCi/ml, the nuclide-by-nuclide calculation is not required to deaanstzate ccapliance with the.
The following section provides a step-bye procedure for detezmining the ME@ fraction.
1.
Calculation Process for Solids A.
Obtain fram the in-plant pxacedures, the release xate value (R) in gPm for the release sauzce.
B.
Obtain fram the in-plant pxaceduzes, the dilution rate (D) in gpm.
No credit is taken for any dilution beyond the dischaxge canal flaw.
C.
Obtain (Ci), the undiluted assay value of nuclide (i), in uCi/ml. If the simplified methad is used, the cumulative concentration (C~) is used.
D.
Fram Table L-l, obtain the corresponding (MPC) for nuclide (i) in uCi/ml.
'Ihe value of 3 X 10 8 uCi/ml should be used for the simplified method.
)
4 N ~)
Page 13 of 88 ST.
WCZE PXANT CHZMZSXXK OPERATZNG PBGCEXUBE NO. C-200~
REVLSZON 10 1.3 (continued) is the total average uCi/ml concentxation of the reference and ~t is the fraction of the MPC of all nuclides for the xelease cordi&ons specified.
Dividing ATot by MZOt yields AMa, which is the maxirmnn total activity concentxation equivalent to the MPC limit for the nuclide distribution typical of rachmste discharges.
~0~
~
- 0. 302 uCi/ml 1.33 E-3
'Jhe assumption that the rtdxtuxe does not change is only used for calculational purposes.
1.
The (Cmax) value in cpn should be obtained for the Amax (0.302 uCi/ml) fmm the release sources xadioactive liquid effluent monitor cuxve of cpm vs. uCi/ml.
ggg
'Ihis setpoint is for a specified xelease of 1 gpm into 000 d ut'o ow.
1.4 2.
For establis1dng the setpoint prior to liquid radwaste discharges, the (~) will be adjusted as needed to account for actual release corxh.tions i.e.,
a li 'd di te ution flow rate, and contr on of lved',and en ined es ity to the Monitor ActivityZavel).
/R10 e
or Qjscus~so
- Technical Specification 3.11.1.2 requires calculations be perfoxmed at least once per 31 days to vexify that cumulative radioactive liquid effluents do not cause a dose in ~mess of 1.5 mxem to the total body and 5 mzem to any oxgan during any calerdar quarter and not in excess of 3 mxem to the total body ard 10 mxem to any organ during any calendar year.
%his section pxesentw calculational method to be used for this verification.
'Xhis method is based on the methcdology suggested by sections 4.3 and 4.3.1 of NURHG-0133 Revision 1, November, 1978.
The dose factors aze a composite of both the fish arrl shellfish pathways so that the fish-shellfish pathway is the only pathway for which dose willbe calculated.
For St. Zucie Plant, the adult is the most limiting age gmup, but the dose for child, ard teenager can also be calculated by this method pmvided that their appxcpriate dose factors are available for the organ of interwst.
Only those nuclides that appear in the Tables of this manual will be considered.
l provlr4s worn spec<@c l~gor~4oA, about paralne4ers O~d <~9 S&POl+P +K~MLAdglb&
ST.
IIJCZE PGKZ CKKZSIRY OPERATXNG HKC2KURE NO. C-200, REVISION 10 Page 29 of 88 2.3 (cont~ed) 2.
(continued)
F.
Repeat steps 2.3.2.C thrcugh 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 fry the Ground Plane Pathway is:
Der Pl DR1
+
DR2
+
+
for all nuclides.
'Ihis dose rate shall be added to the other pathways as per 2o3e5o 3.
e ss-Cofr t
k A.
the conttol1ind animal was established as a lccatad in the sector at miles.
The (D/Q) for this location is 1/aP.
'Xhis value is, common to all nuclides.
(See Table M-3 for sector,
- range, and value. )
B.
Enter the anticipated release rate in ft3/min of the release sour'nd convert to cc/sec.
ss ft3 X 4oc X~~
cc/sec min ft3 60 sec.
C.
Solve for (Q DCT)i for nuclide (i) by obtaining the uCi/cc assay value of the release source activity and multiplying it by the product of 2.3.3.B above.
(Q DC')i ~
'de u
X vau (Q DOZ)i uCi/sec for nuclide (i)
D.
Obtain the Ri value fram Table G-6(7)
(whichever is the controlling animal, ca@/goat, for infant:).
Ifthe limited analysis approach is being used, limit the calculation to the infant thyroid.
a.v, ey tfaa.
(( CA DOT). eke cor see+
+'/P
/R10
ST. WCIE PIANOS CKKISTRY OPERATING EBDCEQJEK NO. C-200, REVISION 10 DOS 2.3 (continued) 4.
(continued)
Page 31 of 88 B.
Enter the anticipated release rate in ft3/min of the release source and convert it to cc/sec.
ft3 X
X 04 X m~
ft 60 sec.
cc/sec volume release rate C.
Solve for (Q IXT)H 3 for Tritium, by obtaining the uCi/cc assay value of the release
- source, and multiplying it by the product of 2.3.4.B above.
(Q DOZ)H 3
~~uC X
ue (Q DVI')H 3 uCi/sec activity release rate D.
Obtain the Tritium dose factor (Ri) for Infant organ T fran:
l to Grass-Caw t
I G-6 E.
Solve for DH 3 (Inhalation) using the (+Q) D for inhalation fran 2.3.4.A and RH 3 (Inhalation) fran 2.3.4.D.
H-3~
= nmaq/yr fran H-3 Infant Inhalation for organ T P.
Solve for DH 3 (Grass-
~) using the (~Q)D for Grass-
-KQk fran 2.3.4.A and (Grass-
~1k) fxan 2.3.4.D
@pecan
/
0~~'-3g
~
H-3G ~
W'Q)D (Q ~)H-3 mreny'yr fram H-3 Infant G-G.
Repeat steps 2.3.4.D through 2.3.4.F for each Infant organ T of interest.
H.
'Ihe individual organ dose rates fran H-3 shall be added to the other organ pathway dose rates as per 2.3.5.
l A
x)
~
wg w jw' Page 43 of 88 ST. IIJCIE PZANT CHEMISTRY OPERATING PRQCEIXJRE NO. C-200, REVISION 10
- 2. 6 (continued) 5.
tezmin'he Total Dose
-3 Cumulat've Gaseous SIS IDO dose limits for I&8 P shal der d f
e o
/R10 A.
'Ihe following pathways l be arrl.ve at the total dose to organ T fram a release source, or if applicable to'SIS, fmm all release sources:
PA Y
&8
~
I G
ss-e
'1
&8DP t'o
-3
'1k
-3
.6.4.
~
w'I 2.7 DoseT ~
t I
B.
Ihe dose to each of the INFANT'S ORGANS shall be calculated:
BONE ~
LIVERY KKROIDg KIWEYg IONG'OZAL BODY' GI IZZ
'Ihe INFANT organ receivtng the highest exposure relative to its STS Limit is the mast critical organ for the radioiodine 8D Particulates gaseous effluents.
Dose o
d ve u ts J}j,~~go - Tech.
Spec.
3.11.2.4 requires that the gaseous zadwaste treatment system be used to reduce zadioactive materials in waste prior to disuse when the pmjected dose due to gaseous effluents wcuM exceed 0.2 mzad for gamma radiation ard 0.4 mrad for beta radiation.
'Ihe follming calculation method is pmvided for detezrtdning the pm)ected 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 gamma air dose (Section 2.4) and the beta air dose i.f performed (Section 2.5).
Ihese doses can be obtained fmm the in-plant records.
2.
Divide these doses by the number of days the plant was operational during the month.
3.
Miltiplythe quotient by the number of days the plant is pm)ected to be operational during the next @anth.
'Ihe product is. the pm)ected dose for the next month.
'Ihe value should be adjusted as needed to accost for any changes in failed-fuel or other
'dentifiable operating corditions that could significantly alter the actual releases.
- 4. If the pm)ected doses aze >0.2 mzads gamma air dose or 0.4 mrads beta air dose, the appmpriate subsystems of the gaseous radwaste system shall be used to reduce the radioactivity levels prior to release.
~ ~
Page 46 of 88 ST. IlJCIE PIAFFE CHEPZSTRY OPERATING PROCEIXJRE NO. C-200, REVISION 10 OFFS DOSE 0
~ '
'<<I "4
j<<l 4.0 (continued) 1.
(cont~ed) 1.2 (continued) b.
'Ihe air dose (see Figure 5.1-1 in the SXS-A) due to noble gases released in gaseous effluents, fzcm each reactor unit, to axeas at and beyond the SITE BXNDARY shall be limited to the following:
During any calendar quarter., to <5 mead for gamma radiation and <10 mrad for beta radiation arxl during any calendar year to <10 mrad for gamma zadiation and <20 mrad for beta radiation c.
Lhe dose to a MEKKR OF 'IHE HJBLIC fzun I-131, I-133, Tritium, and all radionuclide in particulate form, with half-lives >8 days in gaseaus effluents released fzcrn each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1-1 in the SXS-A) shall be limited to the followingr During any calendar qua~ to <7.5 mxem to any organ,'nd during any calendar year to <15 mzem to any organ.
<<,t 2.
Maximum Permissible Concentrations:
Air-as per attached Table G-1 Water as per attached Table L-1 3.
Average energy of fission a<xi activation gases in gaseous effluents is nat applicable to the St. Iucie Plant.
4.
J4easuzements and Approximations of Total Radioactivity:
A summary of liquid effluent accounting methcds is described in Table 3.1.
A sunrnazy of gaseous effluent accunting methods is described in Table 3.2.
Est1mate of Errors g,~8 ggg+glC oe, brea,kkW~
LI D
GASECUS 0
jl 4
II il 1
ic 2
5 NA NA 1
5 2
5 1
5 1
5 3
10 3
10 2
5 4
15, Total 4 9
30 10 354 (abave values are examples only)
'lhe predictability. of error for radioactive releases can only he applied to nuclides that are pzedaminmt in sample spectnrms.
Nuclides that are near background relative to the predominant nuclides in a given sample could easily have exzozs greater than the abave listed maxirtanns.
/R10
Page 47 of 88 ST.
UJCZE PZANI'SEHZPQK OPERATING HACHURE NO. C-200, REVXSZON 10 0
- 4. 0 (continued) 4.
(continued)
~ABLF~
Radioactive Liquid Effluent Sampling and Analysis LT0010 u
N F
OU M
Y I
HETHOO OF T
P NA I
HON1TOR I
TANK I
RELEASES1 I
STEAN GENERA'TOR BLOQOOQK RELEASES N
CH P
N M
T S
h e
ONT Y
HPO T
P 0
T Y
HPOS Sr
~
0 I
PR lMC1PAL CAHHA EHTTTERS I
SS V
CA S
h 6
f /R10 I
T H
MONTH Y
H TABLE NOIKTZON:
HPOS 0
I 1 Boric Acid Evaporator condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and noxmally does not contribute to liquid waste effluent totals.
p.h.a.
gamma spectrum pulse height analysis using Lithi GexTIIanium detectors.
All peaks are identified quantified.
L.S.
C.S.
G.F.P.
Liquid Scintillation counting Chemical Separation Gas Flow Proportional Counting cgYI<C S+
~ q c<~'
5'
Page 48 of 88 ST.
IOCZE HANZ CHEHZSTfK OPERATXNG PBDCECUBE NO. C-200, REVISION 10 0
0 4.0 (continued) 4.
(continued)
Radioactive Gaseous Waste Sampling ard Analysis IMaste Gss OecsyI Tsn R
es Each Tsn n1 mm m
r Contafnment P
1 s
mms m
u Re es sch Pur I
I Plant Vent I
I I
F ur er Honth Honth y o p te sr tcu a
Guarter\\y Composite Psr
'louis 5
Pr 1nc1 s
smms m(
r N
Gross Sr-90 r
9 GASEOUS I
I A
P N
FR O
N Y
TYP NA Y
I HE'TKOO OF Y
I P
. G.F.P.
C.S.
S S
I I
I I
I I
s I
10 L.S.
C.S.
p.h.a.
G.F.P.
Gaseous Grab Sample Charxxel Filter Sample Particulate Filter Sample Liquid Scintillation Oounting Chemical Separation Gamma spectrum pulse height analysis using Lithium Gexmanium detectors.
All peaks are identified and quantified.
Gas Flaw Proportional Counting
w
'¹
¹
¹ ST.
IIJCZE PZANT CSEKESIBY OPERATING PROCEIXJRE NO. C-200, REVISION 10 0
ITE DOS CADXJIA Page 52 of 88 FIDRZQh, POWER & ZZGHI'CNPANY ST.
IIJCZE UNTT g TABIZ 3.4:
ZZQJZD EFFZIJENZS (continued)
¹ CONTINUOUS HODE
¹~Ul¹ ¹ R ¹
¹~AR l~¹ BATCH HODE oUAIQfII s ol~ll s k
I CE ~ 144 SR 89 SR 90 UN IDENT IF I ED TOTAL FOR PERIOD (ABOVE)
CI CI CI CI CI 8
E E
E E
E E
E E
E E
E E
E E
E E
E E
k¹t k
e AR.41 KR 85 XE-131H XE 133 XE 133H XE-135 CI CI CI E
E E
E
¹ E
CI E
E CI E
E E
E E
E
<<AII nucl Ides that were detected should be added to the partial list of the exskaple forakst.
FZORZDA POWER & IZGRZ CGHPANY ST.
ZIJCZE UNIT g TABZE 3.5 IZQ3ID EFFIIJJ&IS - DOSE SUNKQXON Age Group:
Adult Location:
Any Adult Exposure Interval:
Froka Throuyh C
UNG BODY Fish 4 Shellfish Pathway to 0
an ON V
R NY OID I
CALENDER YEAR I
I DOSE I
I I
ak
/R10 Femoke~
)-eRreTL< ~
+O (hunI 4 g mval'
ST. IIJCIE PZAHT CSEHZSIRY OPERATING PROCEEURH NO. C-200, REVISION 10 OFFSITE DOSE CAIlXJGVPION MANUAI Page 55 of 88 AGE GROUPS HQEKDA EOHER & IZGHT CCHPANY SZ. IDCIE UNXT g TABIE 3.8 GASECUS EFFIIJENIS DOSE SUHKKION-INFANT EGQSUEK IPIKUTALS FRCN PA'TMMAT i Cround Plane A
lcrass-
-Hirk B
Inhalation A
TOTAL SOME i
LTVER i
THYROrD J
NrDNEY
(
LUNG i
cr-Lrr t
T.
BODY orecl area cree oreo drels nrem sr col I
A SECTOR:
RANCE eirresi i
B COll COAT SECTOR-RANGE aries(
I I
CALENDAR YEAR I
I (urad)
I NOBLE CASES I
Camas Air Dose Beta Air Dose isectort Ran e
0.97 eries' NOTE I
The dose values above vere calculated using actual aeteororogicar data during the specified true interval urth NET data reduced as Re
. Guide 1.111 March 1976.
I IR10
e C
t
]'
Page 76 of 88 ST. WCIE PIANT CSEHISTRY OPERATING HKCECURE NO. C-200, REVISION 10 DOS CAICUKATI 0
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 distr~on.
'Ibis analysis was performed to evaluate the use of a limited dose analysis for detexmining environmental doses.
Limiting the dose calculation to a few selected xadionuclides that contribute the majority of the dose provides a simplified method of detexrnining campliance 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 presents the same data for the adult GI-LLI dose.
'Ihe adult total body and adult GI-LLIwere determined to be the limiting doses based on an evaluation of all age groups (adult, teenager, child, ard infant) and all organs (bone, liver, kidney, lung, arxl GI-LLI).
As the data in the tables shaw, the radionuclides Fe-59, Co-58, Co-60, Zn-65, Cs-134, arxl Cs-137 daminate the total body dose; the radionuclides, Fe-59, Oo-58, Co-60, Zn-65, and Nb-95 daminate the GI-LLI dose.
In all but one case (1979-fish, GI-LLI dose) these radionuclides contribute 904 or more of the total dose. If for 1979 the fish and shellfish pathways are combined as is done to detexndne the total dose, the contribution fram these nuclides is 84%
of the total GI-LLI dose o Therefore, 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, arxl Cs-137, which cumulative1y contribute the majority of the total dose calculated by using all radionuclides detected.
1%us 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.
/R10 CarteCY +pP0 Tritium is not included in the limited analysis dose assessnent for liquid releases because the potential dose resulting fran normal reactor releases is negligible arxl is essentially independent of xadwaste system operation.
The amount of tritium releases annually is about 300 curies.
At St. Iucie, 300 Ci/yr released to the Atlantic Ocean produces a calculated whole body dose of 5 X 10 7 mreny'yr via the fish ard shellfish pathways.
Ibis anxunts to less than 0.0014 of the design objective dose of 3 mreny'yr.
Furthernnre, the release of tritium is a function of opexatiny time and power leve1 and essentially unrelated to radwaste system operation.
A-Ihe dose e to Iron -55 made it necessary to change the conservatism factor f 0.8 to 0.6, which was done on Revision 7 to the ODCM, based on early 1986 data.
Atta hmen 1
90062600ii2 N
Errata Table mi-Anni 1Ra i I icalEffli n R 1
R ni 11 hr ih in 3
1 Location oferror:
page 5, item S.A Description oferror:
the number of batch releases was incorrectly reported as 22; the correct number is 21 mi-Anni 1R i
1 'lEffl n R 1
R 1
1 h
hD em eral 1
Location oferror:
page 5, item 6.A Description oferror:
the number of batch releases was incorrectly reported as 10; the correct number is 11 Location of error:
page 5, item 6.B Description of error:
the total time ofbatch releases was reported as 3003 minutes; the correct time is 2506 minutes Location oferror:
page 5, item 6.D Description oferror:
the average time period for a batch release was reported as 300 minutes; the correct average time period for a batch release is 228 minutes Location oferror:
page 5, item 6.E Description oferror:
the minimum time period for a batch release was reported as 2 minutes; the correct minimum time for a batch release is 1 minute Location oferror:
page 6, item 6.A Description oferror:
the number of batch releases was incorrectly reported as 17; the correct number is 21 Location of error:
page 6, item 6 B Description of error:
the total time of batch releases was reported as 5926 minutes; the correct time is 10,285 minutes
hm n 1
n'n>
Location oferror:
page 6, item 6.D Description oferror:
the average time period for a batch release was reported as 349 minutes; the correct average time period for a batch release is 490 minutes Location oferror:
page 6, item 6.E Description oferror:
the minimum time period for a batch release was reported as 60 minutes; the correct minimum time for a batch release is 12 minutes Location oferror:
page 16, Table 3.6-2, item D.1 Description oferror:
the summation ofall tritiumreleases for Quarter ¹3 was listed a 1.03E 01 Ci; the correct number is 1.72E 01 Ci Location oferror:
page 16, Table 3.6-2, item D.2 Description oferror:
the average tritium release rate for Quarter ¹3 was listed as 1.30 pCi/sec.; the correct rate is 2.16 p,Ci/sec REVISED SEMI-ANNUALEFFLUENT RELEASE REPORT JANUARY 1, 1988 THROUGH JUNE 30, 1988