ML17228A784
| ML17228A784 | |
| Person / Time | |
|---|---|
| Site: | 05000054, 07000687 |
| Issue date: | 02/18/1994 |
| From: | Mcdede D HOFFMAN-LA ROCHE, INC. |
| To: | Wood R NRC |
| Shared Package | |
| ML17228A785 | List: |
| References | |
| NUDOCS 9403070403 | |
| Download: ML17228A784 (42) | |
Text
2/28/94...
9$ P3Q7PPQ3 FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE PLANT UNITS NO.
1 6
2 LICENSE NUMBERS DPR-67 S( NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY 1, 1993 THROUGH DECEMBER 31, 1993
TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION............
1 OFFSITE DOSE CALCULATION MANUAL REVISIONS......................
7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS.......................
7 PROCESS CONTROL PROGRAM REVISIONS........
7 LIQUID EFFLUENTS:
Summation of all Releases Summation of all Releases Nuclide Summation by Quarter Nuclide Summation by Quarter Liquid Effluent Dose Liquid Effluent Dose GASEOUS EFFLUENT:
Summation of all Releases Summation of all Releases Nuclide Summation by Quarter Nuclide Summation by Quarter Gas Effluent Dose Gas Effluent Dose Unit, ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ Unit ¹ 1
2 1
2
~
1
~
2
~
1 2
1 2
1 2
8 9
10 12 14 15 16 17 18 20 22 23 SOLID WASTE
SHIPMENT SUMMATION.............................
24 Attachment A
Quantification of an Unplanned Liquid Release from Refueling Water Storage Tank 1A Attachment.
B ODCM Revisions 12 and 13
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION
- 1. Regulatory Limits F 1 A.
B.
For Liquid Waste Effluents 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.
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:
During any calendar quarter to
<= 1.5 mrems to the whole body and to
<= 5 mrems to any organ, and During any calendar year to
<=
3 mrems to the whole body and to
<= 10 mrems to any organ.
1 '
A.
- BE For Gaseous Waste Effluents:
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 whole 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.
The air dose due to noble gases released in gaseous effluents from each 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.
- CD 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 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 an annual report shall not apply to any ODCM Control.
The reported values are based on actual release conditions instead of historical conditions that the ODCM Control dose calculations are based on.
The ODCM Control 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 and 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 ODCM Control 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 5
5 5
10 5
NA 2
1 3
4 NA 5
5 10 15 Total 0
9 30 10 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.
2
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, Sr-90,
& Fe-55 Composite Quarterly L.ST G.F.PE p.h.a.
p.h.a.
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 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
I' 1
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 4. Measurements and Approximations of Total Radioactivity (Continued) 4.1 (Continued)
B. (Continued)
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.ST Plant Vent 4/M Monthly Composite Quarterly Composite Principal Gamma Emitters Tritium Particulate Gross Alpha Particulate Sr-89
& Sr-90 p.h.a.
L ~ S ~
G.F.P.
C ~ S-p.h.a.-Gamma Spectrum Pulse Height Analysis using 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 g 1
SEMIANNUAL REPORT JULY 1g 1993 THROUGH DECEMBER 31'993 EFFLUENT
& WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.
Batch Releases A.
Liquid 1.2.
3.
4 ~
5.
6.
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:
Average dilution stream flow during the period:
20 8614 615 431 243 minutes minutes minutes minutes 993910 gpm All liquid releases are summarized in tables.
B.
Gaseous 1.
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:
7 4648 minutes 1200 minutes 664 minutes 265 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 1
6.59E+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.
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 8
2 SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 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 20 8614 615 431 243 minutes minutes minutes minutes 993910 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:
64 13291 565 208 48 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 due to their activities inside the SITE BOUNDARY assumes the visitor onsite for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per day for 312 days per year at a distance of 1.6 kilometers in the South East Sector.
The VISITOR received exposure from each of the two reactors on the Site.
VISITOR DOSE RESULTS FOR CALENDAR YEAR 1993 were:
Gamma Air Dose Beta Air Dose 2.63E-03 5.56E-03 GASEOUS PARTICULATE S(
Bone Liver Thyroid Kidney Lung GI-LLI Whole Body 2.32E-06 1.17E-04 8.35E-04 5.50E-05 1.19E-04 1.14E-04 2.41E-04 8.
Offsite Dose Calculation Manual Revisions (ODCM):
ODCM revisions 12 and 13 were implemented during the reporting interval.
The revisions were made to support License Amendments for Rev.
- 12) Moving Radioactive Effluent LCO's from the Technical Specifications to the ODCM as ODCM Controls as per guidance of NRC Generic Letter 89-01, and for Rev.
- 13) Implementing the new 10 CFR Part 20 revision new Maximum Permissible Concentrations where compliance was required by January 1,
1994.
In each case, the changes were made to conform to standardized regulatory guidance, except where existing plant Technical Specifications were more stringent that NRC generic guidance.
ODCM Methodology for Dose Calculations was not changed.
Revision 13 to the ODCM did require recalculation of Site Limit Calculation Steps.
These changes are outlined in Attachment B to this report with a complete copy of each ODCM Revision.
9.
Solid Waste 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 tabulated summation of these shipments is provided in this report.
- 10. Process Control Program (PCP) Revisions:
The PCP was not revised during the reporting interval.
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 5 1
SEMIANNUAL REPORT JULY 1g 1993 THROUGH DECEMBER 31'993 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR$ 3 QTR54 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 Ci 2.15E-01 4.72E-02 uci/ml 4.29E-10 9.53E-ll Ci 6.99E+Ol 9.86E+Ol uci/ml 1.39E-07 1.99E-07 Ci 5.27E-03 9.09E-02 uci/ml 1.05E-11 1.84E-10 Ci 9.01E-06 O.OOE+00 E ~
F ~
Volume of Waste Released (Prior to Dilution)
Volume of Dilution Water Used During Period Liters 1.35E+06 1.17E+06 Liters 5.02E+11 4.95E+11
1>
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT ¹ 2
SEMIANNUAL REPORT JULY 1J 1993 THROUGH DECEMBER 31'993 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹3 QTR¹4 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 Ci 1.39E-01 4.72E-02 uci/ml 2.77E-10 9.53E-ll Ci 6.34E+01 9.86E+01 uci/ml 1.26E-07 1.99E-07 Ci 5.27E-03 9.09E-02 1.05E-11 1.84E-10 uci/ml Ci 4.18E-06 O.OOE+00
,E.
Volume of Waste Released (Prior to Dilution)
Liters 1.14E+06 1.17E+06 F.
Volume of Dilution Water Used During Period Liters 5.02E+ll 4.95E+11
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 8
1 SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 NUCLIDES RELEASED TABLE UNIT 3.4-1 LIQUID EFFLUENTS Continuous Mode QTRN3 QTR54 Batch Mode QTRN3 QTRN4 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 9.21E-03 O.OOE+00 3.50E-04 O.OOE+00 3.76E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.87E-03 O.OOE+00 5.14E-04 O.OOE+00 4.44E-03 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 5.87E-05 O.OOE+00 3.65E-06 O.OOE+00 3.65E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-03 O.OOE+00 3.85E-03 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 2.34E-05 O.OOE+00 1.07E-04 0.00E+00 2.23E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-03 O.OOE+00 2.37E-03 O.OOE+00 4.14E-05 5.03E-03 1.14E-03 6.17E-02 O.OOE+00 O.OOE+00 6.72E-03 1.50E-04 7.32E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.41E-06 1.25E-05 1.25E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.81E-03 3.23E-03 O.OOE+00 9.74E-04 O.OOE+00 O.OOE+00 O.OOE+00 7.28E-04 1.78E-04 2.84E-04 8.95E-03 3.12E-02
- 3. 71E-04 5.04E-04 4.77E-04 1-23E-02 O.OOE+00 1.03E-05 4.30E-03 O.OOE+00 8.24E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.69E-04 4.69E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.95E-04 1.09E-03 O.OOE+00 3.00E-04 1.85E-05 O.OOE+00 O.OOE+00 2.21E-04 6.10E-05 3.22E-04 3.03E-04 3.92E-03
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 5
1 SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 TABLE 3.4-1 LIQUID EFFLUENTS (CONTINUED)
NUCLIDES RELEASED UNIT Continuous Mode QTRg3 QTRg4 Batch Mode QTR53 QTR$ 4 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 3.32E-03 O.OOE+00 O.OOE+00 5.02E-03 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 2.16E-04 7.02E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.45E-05 2.70E-04 O.OOE+00 O.OOE+00 3.99E-03 4.53E-03 O.OOE+00 3.21E-05 O.OOE+00 1.02E-04 5.05E-03 6.80E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.34E-04 1.15E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.43E-04 7.51E-04 3.12E-05 O.OOE+00 TOTAL FOR PERIOD CI 7.63E-02 O.OOE+00 1.39E-01 4.72E-02 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 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 1.43E-04 5.66E-05 1.87E-03 5.15E-03 8.69E-02 O.OOE+00 O.OOE+00 6.37E-05 2.02E-03
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT ¹ 2
SEMIANNUAL REPORT JULY 1g 1993 THROUGH DECEMBER 31, 1993 NUCLIDES RELEASED TABLE UNIT 3.4-2 LIQUID EFFLUENTS Continuous Mode QTR¹3 QTR¹4 Batch QTR¹3 Mode QTR¹4 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 4.14E-05 5.03E-03 1.14E-03 6.17E-02 O.OOE+00 O.OOE+00 6.72E-03 1.50E-04 7.32E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.41E-06 1.25E-05 1.25E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.81E-03 3.23E-03 O.OOE+00 9.74E-04 O.OOE+00 O.OOE+00 O.OOE+00 7.28E-04 1.78E-04 2.84E-04 8.95E-03 3.12E-02 3.71E-04 5.04E-04 4.77E-04 1.23E-02 O.OOE+00 1.03E-05 4.30E-03 O.OOE+00 8.24E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.69E-04 4.69E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.95E-04 1.09E-03 O.OOE+00 3.00E-04 1.85E-05 O.OOE+00 O.OOE+00 2.21E-04 6.10E-05 3.22E-04 3.03E-04 3.92E-03 12
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT ¹ 2
SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 TABLE 3.4-2 LIQUID EFFLUENTS (CONTINUED)
NUCLIDES RELEASED UNIT Continuous Mode QTR¹3 QTR¹4 Batch QTR¹3 Mode QTR¹4 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 0
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 2.16E-04 O.OOE+00 O.OOE+00 2.45E-05 O.OOE+00 3.99E-03 O.OOE+00 O.OOE+00 5.05E-03 O.OOE+00 O.OOE+00 1.34E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.43E-04 3.12E-05 O.OOE+00 O.OOE+00 7.02E-04 O.OOE+00 O.OOE+00 2.70E-04 O.OOE+00 4.53E-03 3.21E-05 1.02E-04 6.80E-03 O.OOE+00 O.OOE+00 1.15E-04 O.OOE+00 O.OOE+00 O.OOE+00 7.51E-04 O.OOE+00 TOTAL FOR PERIOD CI O.OOE+00 O.OOE+00 1.39E-Ol 4.72E-02 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 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 5.66E-05 5.15E-03 O.OOE+00 6.37E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.43E-04 1.87E-03 8.69E-02 O.OOE+00 2.02E-03
FLORIDA POWER AND LIGHT COMPANY ST.
LUCIE UNIT NO.
1 SEMI-ANNUAL REPORT JULY 1g 1993 THROUGH DECEMBER 3lg 1993 TABLE 3.5-1 LIQUID EFFLUENTS
DOSE SUMMATION AGE GROUP:
ADULT LOCATION:
ANY ADULT EXPOSURE INTERVAL JANUARY 1 g 1 993 THROUGH DECEMBER 3 1 g 1 9 93 FISH AND SHELLFISH ORGAN BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY CALENDER YEAR DOSE (mrem) 1.68E-01 7.43E-01 1.36E-03 2.34E-03 8.60E-01 5.66E-01 1.99E-01 14
FLORIDA POWER AND LIGHT COMPANY ST.
LUCIE UNIT NO ~
2 SEMI-ANNUAL REPORT JULY 1g 1993 THROUGH DECEMBER 31i 1993 TABLE 3.5-2 LIQUID EFFLUENTS
DOSE SUMMATION AGE GROUP:
ADULT LOCATION:
ANY ADULT EXPOSURE INTERVAL JANUARY 1 i 1 993 THROUGH DECEMBER 3 1 i 1 9 93 FISH AND SHELLFISH CALENDER YEAR ORGAN BONE LIVER THYROID KIDNEY LUNG GI-LLI WHOLE BODY DOSE (mrem) 1.45E-01 6.43E-01 1.35E-03 2.13E-03 7.46E-01 4.95E-01 1.73E-01 15
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT ¹ 1
SEMIANNUAL REPORT JULY lg 1993 THROUGH DECEMBER 31'993 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES 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 UNIT Ci uCi/sec Ci uCi/sec Ci uCi/sec QTR¹3 gTR¹4 6.32E+00 1.09E+01 2.71E-04 1.90E-04
Gross Alpha Radioactivity D.
Tritium 1.
Total Release 2.
Average Release Rate For Period Ci Ci uCi/sec 1.29E-07 1.62E-07 1.30E+00 1.27E+01 1.64E-01 1.59E+00
FLORIDA POWER
& LIGHT COMPANY ST LUCIE UNIT ¹ 2
SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹3 gTR¹4 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 3.86E+01 1.94E+Ol 4.86E+00 2.44E+00 1.05E-04 8.62E-05 1.32E-05 1.08E-05 9.92E-08 4.67E-06 1.25E-08 5.87E-07 3.
Gross Alpha Radioactivity D.
Tritium 1.
Total Release 2.
Average Release Rate For Period Ci Ci uCi/sec 5.53E-08 9.03E-08 1.57E+00 3.33E+00 1.98E-01 4.19E-01
FLORIDA POWER 8( LIGHT COMPANY ST.
LUCIE UNIT 5
1 SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Released 1.
Fission Gases Unit Continuous Mode QTR53 QTRN4 Batch Mode QTR53 QTRN4 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 I-131 I-132 I-133 I-134 I-135 TOTAL FOR PERIOD Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3.81E-01 4.44E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.54E+00 O.OOE+00 3.57E+00 O.OOE+00 O.OOE+00 5.54E+00 2.71E-04 O.OOE+00 8.96E-04 O.OOE+00 O.OOE+00 1.17E-03 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 4.89E+00 O.OOE+00 5.92E+00 O.OOE+00 O.OOE+00 1.08E+Ol 1.90E-04 O.OOE+00 2.31E-04 O.OOE+00 O.OOE+00 4.22E-04 4.51E-02 O.OOE+00 8.86E-03 O.OOE+00 O.OOE+00 O.OOE+00 2.39E-03 O.OOE+00 1.25E-02 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 7.50E-03 O.OOE+00 5.36E-01 1.29E-01 O.OOE+00 O.OOE+00 1.68E-01 5.39E-04 O.OOE+00 O.OOE+00 O.OOE+00 0
OOE+00 7.80E-01 1 29E-01 3.
Particulates
(
8 Days)
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 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 3.77E-05 O.OOE+00 O.OOE+00 O.OOE+00
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 8
1 SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)
Nuclides Released Unit Continuous Mode QTRN3 QTR54 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 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 5.55E-06 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 4.
Particulates
(
8 Ci Days)
O.OOE+00 4.32E-05 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 Ng-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 O.OOE+00 5.18E-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 TOTAL FOR PERIOD Ci O.OOE+00 5.18E-05
FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE UNIT 5 2
SEMIANNUAL REPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Released 1.
Fission Gases Unit Continuous Mode QTR$ 3 QTR54 Batch Mode QTRg3 QTRN4 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 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 1.81E+01 O.OOE+00 9.00E+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 7.17E+00 O.OOE+00 3.30E+00 O.OOE+00 O.OOE+00 2.05E-01 1.53E-01 5.47E-03 1.13E-02 8.24E-02 5.92E-03 O.OOE+00 O.OOE+00 8.10E-04 4.17E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.57E-02 3.72E-02 1.48E-01 1.45E-01 1.08E+01 8.12E+00 O.OOE+00 O.OOE+00 2.38E-01 4.65E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 2.
Iodines Ci 2.71E+Ol 1.05E+Ol 1.15E+01 8.94E+00 I-131 I-132 I-133 I-134 I-135 Ci Ci Ci Ci Ci 1.05E-04 O.OOE+00 9.75E-04 O.OOE+00 O.OOE+00 8.62E-'05 O.OOE+00 8.22E-04 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 3.
Particulates
(
8 Days) 1.08E-03 9.08E-04 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 O.OOE+00 O.OOE+00 O.OOE+00 0.'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 20
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE UNIT 0 2
SEMIANNUAL REPORT JULY 1~
1993 THROUGH DECEMBER 31~
1993 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)
Nuclides Released Unit Continuous Mode QTR83 QTR54 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 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 Ng-239
(
8 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Days)
Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 4.96E-08 4.96E-08 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 9.92E-08 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 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 2.57E-06 2.09E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.67E-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 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 21
EXPOSURE INTERVAL:
FLORIDA POWER AND LIGHT COMPANY ST.
LUCIE PLANT UNIT 0
1 TABLE 3.8-1 GASEOUS EFFLUENTS
DOSE SUMMATION AGE GROUP:
INFANT JANUARY 1 g 1 993 THROUGH DECEMBER 3 1 g 1 993 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 GROUND PLANE (A)
BONE mrem LIVER mrem THYROID mrem KIDNEY mrem COW
-MILK (B)
INHALATION (A)
TOTAL 1.35E-04 2.78E-04 4.17E-02 8.58E-05 2.78E-06 1.41E-04 9.85E-04 6.14E-05 1.37E-04 4.20E-04 4.27E-02 1.47E-04 PATHWAY LUNG GI-LLI mrem mrem T.
BODY mrem GROUND PLANE (A)
COW
-MILK (B)
INHALATION (A)
TOTAL 1.63E-04 1.21E-04 1.23E-04 1.96E-04 1.46E-04 1.38E-04 1.40E-04 2.67E-04 2.62E-04 4.99E-04 (A)
(B)
SECTOR:
SE SECTOR:
SW NOBLE GASES GAMMA AIR DOSE BETA AIR DOSE RANGE:
RANGE-1.5 4.25 CALENDER YEAR (mrad) 3.34E-03 7.98E-03 SECTOR:
SE RANGE:
1.5 MILES 22
FLORIDA POWER AND LIGHT COMPANY ST.
LUCIE PLANT UNIT 8
2 TABLE 3.8-1 GASEOUS EFFLUENTS
DOSE SUMMATION AGE GROUP:
INFANT EXPOSURE INTERVAL JANUARY 1 /
1 9 9 3 THROUGH DECEMBER 3 1 g 1 9 93 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 GROUND PLANE (A)
BONE mrem LIVER mrem THYROID mrem KIDNEY mrem
-MILK (B)
ALATION (A)
TOTAL 4.20E-05 1.16E-04 1.09E-02 3.83E-05 1.61E-06 7.96E-05 5.97E-04 3.44E-05 4.36E-05 1.95E-04 1.15E-02 7.27E-05 PATHWAY GROUND PLANE (A)
LUNG GI-LLI mrem mrem T.
BODY mrem 6.14E-05 COW
-MILK (B)
INHALATION (A)
TOTAL 6.76E-05 6.79E-05 8.59E-05 7.99E-05 7.76E-05 7.81E-05 1.47E-04 1.45E-04 2.25E-04 (A)
(B)
SECTOR:
SE SECTOR-SW RANGE-RANGE:
1.5 4.25 NOBLE GASES GAMMA AIR DOSE BETA AIR DOSE CALENDER YEAR (mrad) 1.83E-03 2.91E-03 SECTOR:
SE RANGE:
1.5 MILES 23
FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUALREPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 UNITS 1 AND 2, TABLE 3.9 A.
Solid Waste Shipped Off-Site for Burial or Disposal 1.
Type of Waste Unit 6 Mo. Period Error %
b.
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 2.99E+1 1.79E+2 3.61E+1 1.80E+1 0.00E+0 0.00E+0 2.40E-1 8.72E-3 2.0 E+1 2.0 E+1 2.0 E+1 2.
Estimate of Major Nuclide Composition (By Type of Waste)
Category Nuclides Fe 55
'Co 60 Cs 137 Cs 134 Ni 63 Co 58 Mn 54 Be 7 I 131 Nb 95 Cr 51 Zr 95 Sb 125 3.49E+1 1.75E+1 1.31E+1 1
~ 19E+1 7.45E+0 4.89E+0 2.28E+0 1.81E+0 1.42E+0 1.08E+0 9.90E-1 7.70E-1 7.70E-1 24
Category d.1.
Nuclides Co 60 Fe 55 Cs 137 Ni 63 Cs 134 Co 58 Sb 125 MN 54 Ag 110m C 14 N/A Fe 55 Co 60 Ni 63 Co 58 Cs 137 Cs 134 Nb 95 C 14 2.93E+1 2.56E+1 1.58E+1 1.17E+1 5.74E+0 4.39E+0 2.14E+0 1.66E+0 1.66E+0 1.14E+0 N/A 4.16E+1 2.96E+1 1.18E+1 7.09E+0 6.72E+0 3.01E+0 1.84E+0 1.13E+0 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 Shipments Mode of Transportation N/A Destination N/A
- N/A = Not Applicable
/dac 25
SEMI-ANNUALREPORT JULY 1, 1993 THROUGH DECEMBER 31, 1993 UNITS 1 AND 2, TABLE3.9 (CONTINUED)
Waste Class Class A Class A Class A Class A Class B Total Volume Cubic Ft.
871.4 8.48 404.2 613.7 120.3 Total Curies (Note 1) 1.655 8.70E-3 16.360 12.765 72.230 Principal Radionuclides (Notes 1&2)
N/A N/A Ni 63, Sr 90, Cs 137 Ni 63, Sr 90, Cs 137 Ni63, Sr90, Cs137, Sum of Nuclides with T 1/2 < 5 years Type of Waste (Note 3)
PWR Compactible Trash (Note 5)
PWR Non-Compactible Trash (Note 6)
PWR Compactible Trash PWR Ion-Exchange Resin PWR Ion-Exchange Resin Category Reg-Guide 1.21 l.b 1.d.1 l.b l.a 1.a Type of Container (Note 4)
Non-Specification Strong Tight Package Non-Specification Strong Tight Package NRC Certified LSA Type A NRC Certified LSA Type A NRC Certified LSA Type A SolidiTication Agent None None None None None Class C 202.1 3.035 C14, Pu 241, TRU, Co 60, Ni63, Sr 90, I 129, Cs 137, Sum of Nuclides with T 1/2
< 5 years PWR Process Filters 1.a NRC Certified LSA Type A None Class C 120.3 90.575 C14, Pu 241, Tc 99,
- TRU, Co 60, Ni63, Sr 90, Cs 137, Sum of Nuclides with T I/2
< 5 years PWR Process Filters l.a NRC Certified Type B None
FLORIDAPOWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUALREPORT JULY 1, 1993 THROUGH DECEMBER 31, 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 are 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, two shipments of Dry Compressible Waste (1,840 cubic feet, 7.54E-1 curies) were made from the St. Lucie Plant to the volume reduction facility. This material was shipped via "Sole Use Trucks" in non-specification strong tight packages.
Also, during the reporting period, one shipment of grit blasting material in non-specifications strong tight packages (736 cubic feet, 9.413E-5 curies) and two shipments of dried tank and sump solids in NRC Certified LSA, Type A packages (404.2 cubic feet, 7.54E-1 curies) were shipped via "Sole Use Trucks" from the St. Lucie Plant to the contracted vendor for volume reduction processing and disposal.
27
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 disposal facility. During the reporting period, two shipments of non-compressible metal waste (2,620 cubic feet, 3.811E-2 curies) and one shipment of secondary bead resin (637 cubic feet, 4.286E-S curies) were made from the St. Lucie Plant to the volume reduction facility. This material was shipped via "Sole Use Trucks" in non-specification strong tight packages.
28
ATTACHMENT A UNPLANNED LIQUID EFFLUENT RELEASE of June/July 1993
Attachment A
The January 1,
1993 through June 30, 1993 Semiannual Report contained a Description and analysis of the Unplanned Release as per Attachment B to the Report.
That Report stated that the Curie quantification of the release would be submitted on the July-December 1993 Semiannual Release Report once Sr-89, Sr-90, and Fe-55 composite analyses were done.
This attachment fulfills the requirement to fully quantify the Radionuclide assessment of the unplanned release referenced in the January 1 through June 30, 1993 Report.
The Refueling Water Tank 5
1 release totals were as follows:
Nuclide Alpha Tritium Cr-51 Mn-54 Fe-55 Co-58 Fe-59 Co-60 Sr-89 Sr-90 Y -90 Zr-95 Nb-95 Ru-103 Ag-110 Sn-113 Sb-124 Sb-125 Cs-134 Cs-137 Curies 4.80E-6 6.51E 0
9.21E-3 3.50E-4 3.76E-2 5.87E-3 5.14E-4 4.44E-3 5.87E-5 3.65E-6 3.65E-6 1.94E-3 3.85E-3 2.34E-5 1.07E-4 2.23E-4 1.48E-3 2.37E-3 3 '2E-3 5.02E-3 Release Volume: 2.09 E+05 Liters Release Start
- June 15, 1993 Release End
- July 18, 1993 The above quantities are included in Unit 5
1 Releases in Tables 3.3-1 and 3.4-1 as a Continuous Mode Release during Quarter Number 3.
No recurrence of this release path have been observed.
Three Sets of Monitoring Wells Samples have been obtained around the affected area.
The results of these samples are being provided to the Region II NRC I
6 E Inspector during on-site audits.
0
(Required by Technical Specification 6.14)
Attachment B
There were two revisions to the Offsite Dose Calculation Manual during the reporting interval.
Revision 12 was issued to implement NRC Generic Letter 89-01 guidance where the Radioactive Effluent.Sections of the Technical Specifications were relocated to the ODCM.
The ODCM Dose Methodology was not changed.
This revision did replace "Total Body" with new "Whole Body" as per the 89-01 guidance.
Appropriate administrative references to the ODCM Controls and/or Technical Specification Administrative Sections were also changed accordingly.
Revision 13 was approved on December 22, 1993 and became affective in January 1994.
This revision implemented the new 10 CFR Part 20 revision for Radioactive Effluents.
ODCM Table L-1 "Maximum Permissible Concentrations in Water in UNRESTRICTED AREAS" and Table G-1 "Maximum Permissible Concentrations in Air in UNRESTRICTED AREAS" were revised as per the new Part 20 Limits.
One methodology step was recalculated for compliance with the new Part 20 Limits:
ODCM Step 1.3 "Determining Setpoint for Radioactive Liquid Effluent Monitors" was recalculated using the new Part 20 MPC's.
The setpoint was adjusted accordingly.
An ODCM referenced procedures C-70 "Processing Aerated Liquid Waste" was also modified for the new setpoints, and ODCM referenced procedure C-72 "Processing Gaseous Wastes" was revised where Equivalent Xe-133 factors for Noble Gas were recalculated as per the ODCM revised MPC values in ODCM Table G-l.
No Dose Methodology changes were made, only recalculation of steps for compliance with new regulatory limits.
Each ODCM Revision is attached as a complete copy.