L-91-228, Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1991
| ML20082L954 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/30/1991 |
| From: | Sager D FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-91-228, NUDOCS 9109040485 | |
| Download: ML20082L954 (26) | |
Text
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P O tros 13. It Pierc e, IL 34 6 4 0178 ppL A U G 2 6 199)
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 Gentlemen:
Re:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 D_CP11-ADIBlaLRad152nctiye Ef f1uent Rclp_ nag _lleport Attached is the Radioactive Effluent Release Report for the period of January 1, 1991, through June 30, 1991, for St. Lucie Units 1 and 2.
This report is required by Technical Specification 6.9.1.7.
Should there be any question on this information, please contact us.
Very truly yours, SW cf D. A.
ager Vice > esident St. L le Plant DAS:JJB:kw cc:
Stewart D.
Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant Attachment DAS/PSL #502-91 9109040485 910630
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FLORIDA POWER & LIGilT COMPA11Y ST. LUCIE l'!,A!1T UNITS 110, 1& 2 I
LICEllSE IJUMBERS DPR-67 & 11PF-16 2
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P COMB 1t1ED SEMI-Af1NUAL RADI0 ACTIVE EFFLUEr1T RELE1.bG REPORT FOR Ti!E PERIOD 1
1 JA!1UARY 1, 1991 TilROUGil jut 1E 30, 1991 l
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.,,,q TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFOR!uTION..._......._._.
1 OFFSITE DOSE CALCULATIO!J MANUAL REVISIONS.......................
7 SOL 7D WASTE AND IRRADIATIED FUEL SilIPMEliTS......................
7 a
v H<, lF '
CONTROL PROGRAM REVISIONS...............................
7
.J'+ E ! EFFLUENTS:
Summation
.f all Releases - Unit #1 8
Summation of all Releases - Unit # 2........................
9 Nuclide-Summation by Quarter - Unit i1 10 Nuclide Summation by Quarter - Unit i 2.....................
12 GASEOUS EFFLUENT:
Summation of all Releases - Unit #1 14 Summation of all Releases - Unit #2..-.......................
1S Nuclide Summation by Quarter - Unit # 1 16 Nuclide Summation-by Quarter
. Unit #-2
......................--18 SOLID WASTE SHIPMENT-SUMMATION.............................
20:
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FFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1.
Regulatory Limits 1.1 For Liquid Waste Effluents A.
The concent.t ation of radioactive material rcleased 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-Curles/ml total activity.
B. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive material in liquid ef fluent.s released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:
During any calendar quarter to <= 1.5 mroms 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 t..e 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 perticulate form with half-livea greater than 8 days:
<= 1500 mroms/yr to any organ.
^9 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 gar.na radiation,and
<= 10 mrads for beta radiation and, during any calendar year to
<a 10 mrads for camma radiation and <= 20 mrads for beta radiation.
- C, The dose to a MEMBER OF THE PUBLIC from Indine-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 <a T.5 mrem to any organ, and n
During any calendar yer.r 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.
1
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EFFLUE!1T A!!D WASTE DISPOSAL SUPPLEME!1TAL I!JFORMAT10!J (Continued)
- 2. Maximum Permissible Concentrations Water: As per 10 CFR Part 20, Appendix D, Table II, Column 2, except for entrained or dissolved noble gaces as desctibed 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 gasec,us of f luents 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 uring the Plant Technical Specification analyson 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 L10UID GASEOUS Error Topic Avg.% -
- Max. % -
-Avg.%
Max.t Release Point Mixing 2
5 t4A tJA -
Sampling 1__
5 2
=5 Sample Preparation 1
5 1
5 Sample Analysis 3
10 3
10 Release Volume
-2 5
4 15 Total %
9 30 10 35 The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample' spectrums.
14uclides that are near background. relative to the prederiinant nuclides in a-given-sample could easily--have' errors greater than the above listed maximums.
2
EFFLUEtJT AtJD WASTE DISPOSAL SUPPLEMEt/TAL ItJF0141ATIO!i (Continued)
- 4. Measurements and Approximations of Total Radioactivity (Cont.)
4.1 (Continued)
B.
(Continued)
TABLE 3.1 RADI0 ACTIVE LlOUID EFFLUEtaT SAMPLItJG AtJD AtJALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Datch Principal Gamma Emitters p.h.a.
Monitor Monthly Tritium L.S.
Tank Composite Gross Alpt G.F.P.
1
~~--------
Poleases Quarterly Sr-89, Sr-90, Composite
& Fe-55 C.S.
Continuous Daily Principal Gamma Emitters Releases Grab
& I-131 for p.h.a.
Samples 4/M Composite Analysis Dissolved & Entrained Gases One Pst: chi Month p.h.a.
Tritium Composite Monthly L.S.
Alpha Composite Monthly G.F.P.
Sr-89, Sr-90, & Fe-55 Composite QuarterJy C.S.
l-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 3
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EFFLUE!JT A!JD WASTE DISPOSAL SUPPLEME!JTAL f tJFORMATIO!1 (Continued) i
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- 4. Measurements and Approximations of Total Radioactivity (Continued) 4.1 (Continued)
B.
(Continued)
TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLIllG A!JD AtlALYSIG Gaseous Sampling Type of Method of Source Frequcncy Analysis Analysis Waste Gas Decay Tank Each Batch Principal Gamma Emitters p.h.a.
Releases Containment Principal Gamma Emitters p.h.a.
Purge Each Purge Tritium L.S.
"aleases 4/M Principal Gamma Emitters p.h.a.
Tritium L.S.
Plant Monthly Particulate Vent Composite Gross Alpha G.F.P.
Quarterly Particulate Composite Sr-89 & Sr-90 C.S.
i 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 4
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FLORIDA P("*ER & LIGitT COMPA!1Y ST. LUCIE UNIT # 1 SEMIANNUAL REPORT JANUARY 1, 1991 T!! ROUGH JUNE 30, 1991 EFFLUENT & WASTE DISPOSAL - SUPPLEMENTAL INFORMATION (CONTINUED) 5.
Batch Releases A.
Liquid 1.
Number of batch releases 20 2.
Total time period for batch releases:
9078 minutes 3.
Maximum time period for a batch release:
629 minutes 4.
Average time period for a batch release:
454 minutes i
5.
Minimum time period for a batch release:
295 minutes 6.
Average dilution stream flow during the period:
1007597 gpm All liquid releases are summarized in tables.
B.
Gaseous 1.
Number of batch releases:
19 2,
Total time period for batch releases:
4716 minutes 3.
Maximum time period for a batch release:
559=
minutes 4.
Average time period for a batch release:
248 minutes 5.
Minimum time period for a batch release:
2S minutes All gaseous waste releases are summarized in tables.
6.
-Unplanned-Releases A.
Liquid 1.
Number of releases:
0 2.
Total activity of releases:
0.00E+00 Curies B.
Gaseous 1.
Number of releases:
0 2.
Total activity of releases:
_0.00E+00 Curies C.
See attachments _(if applicable) for:
1.
4 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, s
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FLORIDA POWER & LIGitT COMPAtJY ST. LUCIE UNIT # 2 SEM1 ANNUAL REPORT JA!10ARY 1, 1991 TilROUGli JUNE 30, 1991 EFFLUENT & WASTE DISPOSAL - SUPPLEMENTAL INFORMATION (CON 41NUED) 5.
Batch Releases A.
Liquid 1.
Number of batcP releases:
19 2.
Total timt n**Aod for batch releases:
8624 minutes 3.
Maximum tin
,eriod for a batch releases 629 minutes 4.
Average time period for a batch release 454 minutes 5.
Minimum time period for a batch release:
295 minutes 6.
Average dilution stream flow during the period:
1007597 gpm All liquid releases are summarized in tables.
B.
Gaseous 1.
Number of batch releases:
76 2.
Total time period for batch releases:
17027 minutes 3.
Maximum time period for a batch release:
861 minutes 4.
Average time period for a batch release:
224 minutes 5.
Minimum time period for a batch release:
20 minutes All gaseous waste releases are summarized in tables.
6.
Unplanned-Releases A.
Liquid 1.
Number of releases:
0 2.
Total activity of releases:
0.00E+00 Curies B.
GaF9ous 1.
Number of releases:
0 2.
Total activity of releases:
0.00E+00 Curies O.
See attachments (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 recurrence.
4.
Consequences of the unplanned release..
1 6
_.____._____.._.--_._-._-_________.___._.m...-_
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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL IlJFORMATION (Continued) 4 7
Assessment of radiation dose from radioactive effluents to MEMBERS OF TliE PUBLIC d.s provided on the end of_ year report.
8.
Offsite Dose Calculation Manual Revisions (ODCM) :
The ODCM was not revised during the reporting interval, 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.
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3 FLORIDA POWER & LIGilT COMPANY ST. LUCIE UNIT # 1 SEMIANNUAL REPORT JANUARY 1, 1991 TimOUGli JUNE 30, 1991 TABLE 3.3-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTRf1 QTR#2 A.
Fission and Activation Products 1.
Total Release - (Not including Tritium, Gases, and Alpha)
C1 4.40E-02 3.06E-02 2.
7 erage Diluted Concentration During Perion ucl/ml 8.78E-11 6.21E-11 B.
Tritium 1.
Total Release Ci-6.60E+01 1.22E+02 2.
Average Diluted Concentration During Period uci/mi 1.32E-07 2.47E-07 C.
Dissolved and Entrained Gases 1.
Total Release C1 2.37E-03 2.76E-01 2.
Average Diluted Concentration During Period uci/ml 4.74E-12 5.60E-10 D.
Gross Alpha Radioactivity-t 1.
Total Release C1 1.55E-05 0.00E400 E.
Volume of Waste Released (Prior to Dilution)
Liters 1.62E+07 2.29E407 F.
Volume of Dilution Water Used During Period Liters 5.01E+11 4.93E+11 1
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FLORIDA POWER & LIGilT CO!4PAtJY ST. LUCIE Uti1T #2 SE!41 A?1tJUAL REPORT JA14UARY 1, 1991 THROUGli JUlJE 30, 1991 TABLE 3.3-2 LIQUID EFFLUE!JTS - SUt4!4ATIOt1 OF ALL RELEASES Ut41T QTR$1 QTR#2 A.
Fission and Activation Products 1.
Total Release - (! Jot including Tritium, Gases, and Alpha)
C1 3.16E-02 3.06E-02 2.
Average Diluted Concentration During Period uci/ml 6.32E-11 6.20E-11 B.
Tritium 1.
Total Release Ci 6.60E+01 1.22E+02 2.
Average Diluted Concentration During Period uci/ml 1.32E-07 2.46E-07 C.
Dissolved and Entrained Gases 1.
Total Release C1 2.37E-03 2.76E-01 2.
Average Diluted Concentration 4.74E-12 5.60E-10 During Period uci/ml
)
D.
Gross Alpha Radioactivity 1.
Total Release Ci 1.55E-05 0.00E400 E.
Volume of Waste Released (Prior to Dilution)
Liters 8.34E+05 1.44E406 F.
Volume of Dilution Water Used During Period Liters 5.01E+11 4.93E411 r
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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT # 1 SEMIANNUAL REPORT JANUARY 1, 1991 THROUGH JUNE 30, 1991 TABLE 3.4-1 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES OTRf1 QTR#2 OTR#1 QTRf2 RELEASED UNIT NA-24 C1 0.00E400 0.00E+00 0.00E+00 2.38E-05 CR-51 Ci 0.00E400 0.00E400 0.00E+00 2.58E-04 MN-54 Ci 0.00E+00 0.00E+00 4.34E-04 2.37E-04 FE-55 C1 1.23E-02 0.00E+00 2.67E-03 3.48E-03 MN-56 Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00 Co-57 C1 0.00E400 0.00E+00 2.48E-05 1.38E-05 CO-58 C1 0.00E400 0.00E400 7.47E-03 3.78E-03 FE-59 Ci 0.00E400 0.00E+00 0.00E+00 0.00E400 Co-60 Ci 0.00E+00 0.00E+00 1.46E-02 4.21E-03 ZN-65 C1 0.00E+00 0.00E+00 0.00E400 0.00E400 NI-65 Ci 0.00E+00 0.00E400 0.00E+00 0.00E400 BR-82 Ci 0.00E+00 0.00E+00 0.00E400 0.00E+00 RB-88 C1 0.00E400 0.00E+00 0.00E400 0.00E400 SR-89 C1 0.00E+00 0.00E400 0.00E+00 0.00E+00 SR-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y-90 Ci 0.00E400 0.00E400 0.00E400 0.00E+00
(
SR-91 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E400 SR-92 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E400 Y-92 Ci 0.00E+00 0.00E400 0.00E+00'0.00E400 ZR-95 Ci 0.00E+00 0.00E+00 3.40E-04 3.21E-04 NB-95 Ci 0.00E+00 0.00E+00 5.93E-04 8.08E-04 ZR-97 Ci 0.00E400 0.00E+00 0.00E400 0.00E+00 NB-97 Ci 0.00E+00 0.00E+00 3.65E-04 9.07E TC-99M Ci 0.00E+00 0.00E+00 3.41E-06 8.97E-06 MO-99 Ci 0.00E+00 0.00E400 0.00E+00 0.00E+00 RU-103 Ci 0.00E+00 0.00E+00 0.00E+00 0.00Et00 AG-110 C1 0.00E+00 0.00E+00 3.18E-04 6.83E-04 SN-113 Ci 0.00E+00 0.00E+00 4.61E-05 1.84E-04 SB-122 Ci 0.00E+00 0.00E+00 4.87E-05 3;87E-05 SB-124 Ci 0.00E+00 0.00E400 1.86E-04 6.88E-04 SB-125 Ci 0.00E+00 0.00E+00 2.00E-03'9.77E-03 l
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l' FLORIDA POWER & LIGilT COMPANY ST. LUCIE UNIT #1 SEMIANNUAL REIQRT JANUARY 1, 1991 THROUGli JUNE 30, 1991 TABLE 3.4-1 LIQUID EFFLUENTS (CONTINUED)
Continuous Mode Batch Mode RELEASED UNIT QTR#1 QTR#2 QTR#1 QTR#2 TE-129 Ci 0.00E400 0.00E400 0.00E400 0.00E400 TE-129M Ci 0.00E+00 0.00E400 0.00E+00 0.00b+00 1-131 Ci 0.00E+LO 4.69E-05 1.35E-04 4.74E-04 TE-132 Ci 0.00E400 0.00E400 0.00E400 0.00E400 I-132 Ci 0.00E400 0.00E+00 0.00E400 0.00E400 I-133 Ci 0.00E+00 0,00E+0C 4.82E-05 2.69E-04 I-134 CA 0.00E+00 0.00E400 0.00E+00 0.00E400 CS-134 Ci 0.00E+00 0.00E400 9.42E-04 1.62E-03 I-135 Ci
-0.00E+00 0.00E400 0.00E400-8.72E-05 I
CS-136 Ci 0.00E400 0.00E400 0.00E+00 0.00E+00 i
CS-137 Ci 0.00E400 0.00E+00 1.52E-03 2.66E-03 CS-138 Ci 0.00E400 0.00E+00 1.04E-05 3.52E-05 BA-140 C1 0.00E400 0.00E+00 0.00E+00 0.00E+00 LA-140 Ci 0.00E400 0.00E+00 6.39E-05 3.81E-05 a
CE-141 Ci 0.00E+00 0.00E400 0.00E400 0.00E+00 CE-144 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR-144 Ci 0.00E+00 0.00E400 0.00E+00 0.00E+00 W-187 Ci 0.00E+00 0.00E400 0.00E400 0.00E+00 NP-239 Ci 0.00E+00 0.00E400 0.00E400 0.00E400 TOTAL FOR PERIOD CI 1.23E-02 4.69E-05 3.16E-02 3.06E-02 AR-41 CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-85M CI 0.00E+00 0.00E+00 0.00E+00 1.42E-04 KR-85 CI 0.00E400 0.00E+00 0.00E+00 2.05E-02 KR-87 CI 0.00E+00 0.00E+00 0.00E+00 0.00E400 KR-88 CI 0.00E+00 0.00E+00
'0.00E+00 0.00E+00 XE-131M CI 0.00E+00 0.00E400 0.'00E+00 3.12E-03 XE-133M CI 0.00E400 0.00E+00 0.00E400 2.71E XE-133 CI 0.00E+00 0.00E+00 2.30E-03 2.48E-01 XE-135M CI 0.00E+00 0.00E+00 0.00E400 0.00E400 XE-135 CI 0.00E+00 0.00E+00 7.05E-05 1.38E-03 11-
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FLORIDA POWER & LIGilT COMPANY ST. LUCIE UllIT # 2 SEMIA!1NUAL REPORT JANUARY 1, 1991 THROUGH JUl1E 30, 1991 TABLE 3.4-2 I.IQUID EFFLUEllTS Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR#1 QTRf2 QTRf1 QTRf2 UA-24 CI 0.00E400 0.00E400 0.00E+00 2.38E-05 CR-51 CI 0.00E+00 0.00E400 0.00E+00 2.58E-04 MN-54 CI 0.00E400 0.00E400 4.34E-04 2.37E-04_
FE-55 CI 0.00E400 0.00E+00 2.67E-03 3.48E-03 MN-56 CI 0.00E400 0.00E400 0.00E400 0.00E400 l
CO-57 CI 0.00E+00 0.00E400 2.48E-05 1.38E-05 i
CO-58 CI 0.00E400 0.00E+00 7.47E-03 3.78E-03 i
FE-59 CI 0.00E400 0.00E+00 0.00E+00 0.00E400 i
CO-60 CI 0.00E+00 0.00E400 1.46E-02--4.21E ZN-65 CI 0.00E400 0.00E400 0.00E400 0.00E400 NI-65 CI 0.00E+00 0.00E400 0.00E+00 0.00E400 i
BR-82 CI 0.00E400 0.00E+00 0.00E400 0.00E400 i
RB-88 C1 0.00E400 0.00E400 0.00E400 0.00E+00 i
SR-89 CI 0.00E+00 0.00E+00 0.00E+00 0.00E400 SR-90 CI 0.00E400 0.00E400 0.00E+00 0.00E400 Y-90 CI 0.00E+00 0.00E+00 0.00E+00 0.00E400 SR-91 CI 0.00E400 0.00E+00 0.00E400 0.00E400 SR-92 CI 0.00E400 0.00E400 0.00E400 0.00E+00 Y-92 CI 0.00E400 0.00E400 0.00E+00 0.00E400 ZR-95 CI 0.00E400 0.00E400 1.40E-04 3.21E-04 NB-95 CI 0.00E+00 0.00E+00 5.93E-04 8.08E-04 ZR-97 CI-0.00E400 0.00E+00 0.00E400 0.00E+00 NB-97 CI-0.00E+00 0.00E400 3.65E-04 9.07E-04 TC-99M CI 0.00E+00 0.00E+00 3.418-06 8.97E-06 3
MD-99 CI 0.00E+00-0.00E+00 0.00E400 0.00E+00 l
RU-103 CI 0.00E400 0.00E400 0.00E400 0.00E400 1
4 AG-110 CI 0.00E400 0.00E+00 3.18E-04 6.83E-04 SN-113 C1 0.00E+00 0.00E+00 4.61E-05 1.84E-04 SB-122 CI 0.00E400 0.00E+00 4.87E-05 3.87E-05 SB-124 CI 0.00E400 0.00E400 1.86E-04 6.88E-04 SB-125 CI 0.00E4 00 0.00E+00 2.00E-03 9.77E-03 t
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ST. LUCIE UNIT #2 07f'
(
SEMIANNUAL REPORT JANUA'
', 1991 THROUGH JUNE 30, 1991 4;
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TABLE 3.5-2 LIQUID EFFLUENTS (CONTINUED) y JV
[
C01..inuous Mode Eatch Mode
't :
I P E..
5
/ 2hSED UNIT QTR#1 OTR#2 OTR#1 Q1R#2 3
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4
". +129 CI 0.00E+00 0.00E+00 0.00E400 0.00E+00
" 129M CI 0.00E+00 0.00E+00 0.00E4G3 0.00E400 J31 CI 0.00E+00 0.00E+00 1.35E-04 4.?tr "'
J-132 CI 0.00E400 0.00E+00 0. 0 0 E + 0 0 0. C t..E C
I-132 CI 0.00E400 0.00E+00 0.00E+00 0.0 e4 1-133 CI 0.00E+00 0.00E400 4. 8 2 E-0 5 2. f "i' 0 4, 1
I-?34 C1 0.00E+00 0.00E+00 0.00E+00 0.C-
'00 CS-13e CI 0.00E+00 0.00EF00 9.42E-04 1 52-03 I-135 C1 0.00E+00 0.00E+00 0.00E+00 8.72E-05 CS-136 CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-137 CI 0.00E+00 0.00E+00 1.52E-03 2.66E-03 CS-138 CI 0.00E+;0 0.00E+00 1.04E-05 3.52E-05 BA-140 CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 LA-140 CI 0.00E+00 0.00E+00 f.39E-05 3.81E-05 CE-141 CI 0.00E+00 0.00E*00 0.00E&00 0.00E+00 CE 1.44 CI 0.00E+00 0.00E+00 s.00E'00 ".0SE+00 PR-144 CI 0.00E+0C 0.00E+00
^ 00E+'0 0.00E+00 W-187 CI 0.00E+00 0.00E+00 0.30"+00 0.00E&00 NP-239 CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PFRIOD CI 0.00E+00 0.00E+00 3.16E-02 3.06E-02 AR-41 CI 0.00E+00 0.00E+00 0.00E<00 0.00E+00 KR-85M CI 0.00Z+00 0.00E+00
- 0. 0 0E+ 00 1. c n' -0 4 KR-85 CI 0.00E+00 0.00E+00 0.00E+00 2.05E-02 KR-87 CI 0.00E+00 0.00E+00 0,00E+00 U.00E+00 EB-88 CI 0.00EF00 0.00L+00 0.00E+00 0.00E+00 XE-131M CI 0.00E+00 0.00E+0L 0,00E+00 3.12E-03 XE-133M CI 0.00E+00 0.00E+00 0.00E+00 2.71E-03 U 133 CI 0.00E+00 0.00E+00 2.30b-03 2.48E-01 XE ;35M CI 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE'- ! 3 5 CI 0.00E+00 0.00E+00 7.05E-05 1.38E-03 s
13 I
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT #1 SEMIANNUAL REPORT JJANUARY 1, 1991 THROUGH JUNE 20, 1991 TABLE 3.6-1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT OTR#1 QTR#2 A.
Fission and Activation Gases 1.
Total Release C1 1.53E+02 4.89E+02 2.
Average Release Rate For Period uCi/see 1.97E+01.6.22E+01 a
B.
Iodines 1.
Toto Iodine-131 Ct 2.73E-04 3.12E-04 2.
Average Release Rate For Period uCi/sec 3.50E-05 3.96E-05 C.
Particulates
' articulates (Half Life > 8 days)
C1 7.14E-05 2.31E-05 2.
Average Release Rate For Period uCi/sec 9.18E-06 2.94E-06 3.
Gross Alpha Radioactivity Ci 1.39E-07 1.13E-07 D.
Tritium k
1.
Total Release C1 1.41E+01 5.32E+00 2.
Average Release Rate For Period uCi/sec
-1.81E+00 6.77E-01 t
14
FLGRIDA POWER & LIGHT COMPANY ST. LUCIE UNIT #2 SEMIANNUAL REPORT JANUARY 1, 1991 THROUGH JUNE 30, 1991 TABLE 3.6-2 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR#1 QTR#2 A.
Fission and Activation Gases 1.
Total Release Ci 9.92E+01 1.00E402 2.
Average Release Rate For Period uCi.'se c 1.2BE+01 1.2BE+01 B.
Iodines 1.
Total Iodine-131 Yi 1.12E-03 2.44E-03 2.
Average Release Rate For Period uCi/sec 1.44E-04 3.11E-04 C.
Particulates 1.
Particulates (Half Life > 8 days)
Ci 0.00E+00 0.00E+00 2.
Average Release Rate For Period uCi/sec 0.00E+00 0.00E+00 3.
Gross Alpha Radioactivity Ci 8.49E-08 3.59E-08 D.
Tritium 1.
Total Release Ci 7.47E+00 2.32E+01 2.
Average Relecise Rate For Period uCi/sec 9.61E-01 2.95E+00 15 d
d,.
- NA Q
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 4 1 SEMIANNUAL REPORT JANUARY 1, 1991 THROUGH JUNE 30, 1991 TABLE 3.7-1 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode i
Released Unit QTR#1 QTR$2 QTR#1 QTR#2 1.
Fission Gases AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 2.75E-03 KR-85M C1 2.13E-01 5.69E+00 0.00E+00-8.57E-02 KR-85 Ci 0.00E+00 0.00E+00 7.25E-02 3.70E+00 KR-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-88 Ci 0.00E+00 5.04E+00 0.00E+00 2.77E-02 KR-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-127 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-131M C1
.0.00E+00 0.00E+00 2.21E-03 7.14E-01 XE-133M Ci 0.00E+00:0,00E+00-2.25E-03'2.14E+00 XE-133 Ci 1.31E402 2.80E+02 2.63E-01 1.15E+02 XE-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00Et00 XE-135 C1 2.20E+01 7.36E+01 A.24E-05E3.01E+00 XE-137 Ci-0.00E+00 6.00E+00 0.00E+00 0.~00E+00 XE-3 38 -
Ci 0.00E+00 0.00EiOO 0.00E+00-0.00E+00 TOTAL FOR PERIOD C1 1.53E+02 3.65E+02 3.40E-01 1.25a+02 2.
Iodines I-131 Ci 2.73E-04 3.12E I-132 C1 0.00E+00 0.00E+00 I-133 C1 1.33E-03 1.38E-03 g
l I.134 Ci 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E200 TOTAL FOR PERIOD Ci 1.60E-03 1.69E-03 l
3.
Particulates
(> 8 Days) l Cr-51 Ci-0.00E+00 0.00E+00 Mn-54 C1 0.00E+00-0.00E+00-Fe-55 Ci 0.00E+00 0.00E+00 Co-57 C1 0.00E+00 2.77E-06 Co-58 Ci'
'O.00E400 0.00E+00 Fe-59
. C 1--
-0.00E+0010.00E+00 Co-60 Ci-7.14E-05 2.04E-05 j
Zn-65 Ci 0.00E+00 0.00E+00-Zr-95 Ci-0.00E+00 0.00E+00 l
Nb-95 C1 0.00E+00:0.00E+00 l
16
-l 4
4 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT #1 SEMIANNUAL REPORT JANUARY 1, 1991 THROUGH JUNE 30, 1991 TABLE 3.7-1 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CONTINUED)
Nuclides Continuous P)de Released Unit QTR#1 QTR#2 3.
Particulates ( > 8 Days) (continued)
Sr-89 Ci 0.00E+00-0.00E+00 Sr-90 C1 0.00E+00 0.00E+00 Y-90 Ci 0.00E+00 0.00E+00 Ru-103 Ci 0.00E+00 0.00E+00 Ag-110 Ci 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 Sb-124 Ci 0.00E+00 0.00E+00 7b-125 Ci 0.00E+00 0.00E+00 Te-129m Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00.0.00E400 Cs-136 Ci 0.00E+00 0.00E400 Cs-137 Ci 0.00E+00 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00.0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00.
TOTAL FOR PERIOD Ci 7.14E-05 2.31E-05 4.
Particulates
( < 8 Days)
Mn-56 Ci 0.00E+00 0.00E+00 Ni-65 Ci 0.00E+00 0.00E+00 Br-82 C1 0.00E+00 0.00E+00 Rb-88 Ci 0.008+00 0.00E+00 Rb-89 Ci 0.00E+00 0.00E+00 Sr-91 Ci 0.00E+00 0.00E+00 Sr-92 Ci 0.00E+00 0.00E+00_.
Y-92 C1 0.00E+00 0.00E+00 Zr-97 Ci 0 90E+30-0.00E+00 d
Nb-97 Ci 0.00E+00 0.00E+00 Tc-99m C1 0.00E+00 0.00E+00 Mo-99 Ci 0.00E+00 0.00E+0C s
Sb-122 Ci 0.00E+00 0.00E+00 Te-129 Ci
-0.00E+00 0.00E+00 Te-132 Ci 0.00E+00 0.00E+00-Cs-138 Ci 0.00E+00 0.00E+00 i
La-140 C1
-0.00E+00 0.00E+00-
-Pr-144 Ci U.00E+00 0.00E+00 W-187 Ci 0.00E+00 0'.00E+00 Np-239 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIO#
C1 0.00E+00 0.00E+00 s
17 a____________
FLORIL
'OWER & LIGHT COMPANY ST. LUCIE UNIT #2 SEMIANNUAL REPORT-4 JANUARY 1, 1991 THROUGH JUNE 30, 1991 TABLE 3.7-2 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released Unit QTR#1 QTR#2 QTRf1 QTRf2 1.
Fission Gases AR-41 C1 0.00E+00 0.00E+00 1.57E-01 1.94E-01 KR-85M C1 0.00E+00 3.48E-01 6.41E-03 1.19E-02 KR-85 Ci 0.00E+00 0.00E400 0.00E+00 0.00E+00 KR-87 Ci 0.00E+00 0.00E+00 0.00E+00 9.72E-04 3
KR-88 Ci 0.00E+00 0.00E+00 5.77E-03 5.56E-03 KR-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-90 C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00 d
XE-127 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-131M Ci 0.00E+00 0.00E+00 1.37E-01 S.06E-01 XE 133M Ci 0.00E+00 0.00E+00 3.75E-01-2.97E-01 XE-133 Ci 7.09E+01 6.52E+01 2.46E+01 2.57E+01 XE-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-135 C1 2.69E+00 7.98E+00 3.77E-01 3.07E-01 XE-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 y
XE-138 Ci 0.0GE+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 7.36E+01 7.35E+01 2.57E+01 2.68E+01 2.
Ic nas 3
I-131 Ci 1.12E-03 2.44E-03 I-132 Ci 0.00E+00 0.00E+00 I-133 Ci 5.94E-03 1.18E-02 1-134 Ci 0.00E+00 0.00E+00 I-135 C1 0.00E+00 2.19E-03 TOTAL FOR PERIOD Ci 7.06E-03 1.65E-02 3.
Particulates
( > 8 Days)
Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Fe-55 Ci 0.00E+00 0.00E+00-Co-57 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 1
Fe-59 Ci 0.00E+00 0.00E+00
.Co-60 Ci 0=.00E+00 0.00E+00
{.
Zn-65 Ci 0.00E+00-0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 18
f FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT #2 SEMIANNUAL REPORT JANUARY 1, 1991 THROUGH JUNE 30, 1991 TABLE 3.7-2 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CONTINUED)
Nuclides Continuous Mode Released Unit QTR#1 OTR#2 3.
Particulates ( > 8 Days) (continued)
Sr-89 Ci 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 Y-90 Ci 0.00E+00 0.00E+00 Ru-103 C1 0.00E+00.0.00E+00 Ag-110 Ci 0.00E+00 0.00E+00 Sn-113 Ci 0.00E+00 0.00E+00 Sb-124 Ci 0.00E+00 0.00E+00 Sb-125 Ci 0.00E+00 0.00E+00 Te-129m Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-136 C1 0.00E+00 0.00E+00 Cs-137 Ci 0.00E&00 0.00E+00 Ba-140 Ci 0.00E+00 0.00E400 Ce-141 Ci 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 0.00E+00 0.00E+00 4.
Particulates
( < 8 Days)
Mn-56 Ci 0.00E+00 0.00E+00 Ni-65 Ci 0.00E+00-0.00E+00 Br-82 Ci 0.00E+00 0.00E+00 Rb-88 C1 0.00E+00 0.00E+00 Rb-89 C1 0.00E+00 0 00E+0n Sr-91 Cl-0. 0 0 E + 0 0 = 0. !) 0 E + 0 0 Sr-92 Ci 0.00E+00 0.00E+00 Y-92 Ci 0.00E+00 0.00E+00
- Zr-97 Ci 0.00E+00 0. NE+00 Nb-97 Ci 0.00E+00 0.00E+00
-Tc-99m Ci 0.00E40n 0.u0E+00 Mo-99 Ci 0.00E+(0 0;00E+00
-Sb-122 C1 0.00E+00 0.00E+00 Te-129 Ci 0.00E+00 0.00E+00 Te-132 Ci 0.00E+00 0.00E+00 Cs-138 C1 0.00E+00 0.00E+00 La-140 C1 0.00E+00 0.00E+00 Pr-144 Ci 0.00E+00 0.00E+00-W-187-Ci 0.00E+00 0.00E+00 Np-239 Cl-0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 0.00E+00 0.00Ev00 19 i
1 I~
L 1
Fl.0RIDA IQWI31 AND 1.1 Gilt COMPANY ST. IMCIE Pl. ANT fil:MI-ANNUA! HEI' ORT JANUAHY 1, 1991 TilHOUGil JUNH 30,.1991 UNIT!! 1 AND 2, TAllI.E 3.9 A.
Solid Wento Shipped Off-Site for 1-urial or Disposal 1.
Type of Wanta Unit 6 Mo. Period Error %
- a. Spent (cuin, M3 b.086 E+1 Procesa filtet; C1 1.114 E+2 2.0 I:+1 b.
Dry Cornpressible M3 6.760 E+1 Wasto (Notn 5)
C1 6.812 E+0 2.0 E+1 c.
Irradiated M3 0
Components C1 0
2.0 H+1
- d. Other
- 1. Non-Compres-M3 4.600 E40 2.0 E+1 cible Meta; Ci 1.850 E-1 (DAW) (Note 6) 2.
Eatinato of Major Nuclido Composition (By Type of Wante)
Category Nucliden 1
a.
Co 58 2.44 E+1 Ca 137 2.36 E+1 Co 60 1.94 E+1 Ni 63 1.05 E+1 Cs 134 8.24 E+0 Fo SL 6.09 E+0 Sb 12L 4.19 E+0 Mn 54 1.00 E+.
b.
Co 137 3.41 E+1 Fe 55 2.55 Et!
Co 60 1.69 E+1 Co 58 1.04 E+1 Cs 134 7.13 E+0 Ni 63 1.87 E+0 Sb 125 1.09 E40 Mn-94 9.59 E-1 c.
N/A N/A d.
Fe 55 5.45 E+1 Cr 137 2.52 E+1 Co 60 1.10 E+1 Cn 134 5.18 E+0 11 3
2.89 E+0 N1 63 1.16 E+0
. =
Page 2 St. Lucie Plant Semi-Annual Heport i
- 3. Solid Wat>te Disposition Number of !Ihipments Mode of Transportation Destination 4
Solo Use Truck liarnwell, S.
C.
6 Solo Use Truck S.E.G.
Oak Ridge, Tenn.
1 Sole Use Truck Quadrox Corp.
Oak Ridge, Tenn, 11 Irradiated Fuel Shipments Number of Shipmenta Mode of Transportation Destination 0
N/A N/A N/A = Not Applicable a-
7 4
2 FLORIDA POWER AND LIGHT COMPANY ST. LUCIE FLANT SEMI-ANNUAL REPORT JANUARY 1, 1991 THROUGH JUNE 30, 1991 UNITS 1 AND 2, TABLE 3.9 (CONTINUED)
Total Total "rincipal Type of Category Type of Waste Volume Curies talionuclides idaste Reg-Guide Container Solidification Class Cubic Ft.
(Note Is No:es 1 5 2)
(Note 3) 1.21 (Note 4)
Agent lNA Class A 2181.6 1.35 PWR 1.b.
Non-specification None Compactible Strong Tight a
Trash (Note 5)
Package
' Class A 162.3 1.85E-1 NA PWR 1.d.
Non-specification None J
Non-Compactible Strong Tight
. Trash (Note 6)
Package Class A 1349.7 7.2.2E-3 NA PWR 1.a.
Non-specifi ca tion None Ion-Bxchange Strong Tight Resin Package Class A 205.8 5.46 Sr 90, Cs 137 PWR 1.b NRC Certified None compactible LSA 4
Trash Type A i
Class A 205.8 2.89 Ni (13, Cs 137 PWR 1.a NRC Certified None Ion-Exchange LSA Resin Type A Class P 240.6 108.47 Cl4, Co60, Ni63 PWR 1.a NRC Certified None Sr90, Csl37, Ion-Exchange LSA Sum of Nuclides Resin Type A i
T < 5 yr.
FIDHIDA l'OWMH AND I.IGilT COMPANY fit. LUCIE PLANT fiEMI-ANNU AL H EPOHT JANUARY 1, 1991 Tl!HOUGil.IUNE 30, 1991 UNIT!! 1 AND 2 Taut.H 3.9 ( CONTI NtlMD )
f;0 LID WAfiTH SUPPLMMENT Note 1:
The total curie quantity and radionuclido composition of solid waste shipped from the St. Lucie plant, Units I and 2 are determined uning a combination of qualitative and quantitative techniques.
In general, the St.
Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Hranch Technical Position (ItTP) on Radioactive Waste Classification (5/11/83) for these determinationo.
The most frequently used techniques for determining the totai curie quantity in a package are the dose to curie methods and the (concentration) x (volume or mans) calculations.
Where appropriate, engineering type activation analynes may be applied.
Since each of the above methodologien involves to nome extent qualitative parametern, 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 analysen for other radionucliden.
The on-site analynes are perfo*med either on a batch basis or on a routine basin using reasonably representative ramples an appropriate for the waste type.
Off-site analysen are uned to establish scaling factors or other estimates for radionuclides such an 3 11,
14C, 99Tc, 1291,
- TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.
Note 2:
" Principal Hadionuclidos" refer to thone 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 nucliden listed in Table 2 of 10 CPR 61.
Note 3:
" Type of wante" in qenerally specified an described in NUREG 0782 Draft Environment Impact Statement on 10 CFR 61, " Licensing Requirementa for Land Dispanal of Radioactive Waste".
Note 4:
" Type of Container" refers to the transport package.
3 Note 5:
The volt,me and activity listed f or Dry Comprensible Waste represent the quantity
'f material that to date has been sent to the ITarnwell, 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 ' acili ty.
During the reporting period, six shipments of Dry Comprensible Waste (2,668 cubic feet, 6. *' ?
E-1 Curies) and dewatered secondary rouin (2,176.8 Cubic feet, 8.34 E-3 Curies) were made from the St.
Lucie plant to the volume reduction facility.
This material was shipped via S o l o Use Truck" in non-specification strong tight packages.
Note 6: Tho volume and activity linted for non-compressible metal represent N
the quanti ty of material that during the reporting period could not be recycled by the contracted vendor a r.a required disposal at the Barnwell, South Carolina burial facility.
During the reporting period, ene shipment of non-comprescible metal waste (1,280 cubic feet, 2.48 E-2 Curies) wan made from the St. Lucie Plant to the volume reduction facility.
This material was shipped via
" Sole Une Truck" in I
non-specification strong tight packages.
-