ML20137Y160
| ML20137Y160 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1985 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| L-86-93, NUDOCS 8603120172 | |
| Download: ML20137Y160 (26) | |
Text
'
FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1&2 LICENSE NO.
COMBINED SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY 1,1985 THROUGH DECEMBER 31, 1985 8603120172 851231 PDR ADOCK 05000335 PDR R
/
f FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1&2 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE OF CONTENTS DESCRIPTION:
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION VISITOR DOSE ASSESSMENT OFFSITE DOSE CALCULATION MANUAL REVISIONS SOLID WASTE AND IRRADIATED FUEL SHIPMENTS LIQUID EFFLUENT:
SUFDtATION OF ALL RELEASES, NUCLIDE SODIATION BY QUARTER, DOSE SDDIATION UNIT 1 UNIT 2 GASEOUS EFFLUENT:
SUFS!ATION OF ALL RELEASES, NUCLIDE SU}DIATION. BY QUARTER, DOSE SDSIATION UNIT 1 UNIT 2 SOLID WASTE SHIPMENT SUF0tATION
Page 1 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1.
Regulatory Limits 1.1 For Liquid Waste Effluents a.
The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10
- micro curies /ml total activity, b.
The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:
During any calendar quarter to 1 1.5 mrems to the total body and to < 5 mrems to any organ, and During any calendar year to 1 3 mrems to the total body and to 1 10 mrems to any organ.
1.2 For Caseous Waste Effluents:
a.
The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to:
For Noble Cases: <
500 mrems/yr to the total body and 3000 mrems/yr to the skin, and For Iodine-131, Iodine-133 Tritium, and all other radio-nuclides in particulate form with half-lives greater than 8 days:
< 1500 mrems/yr to any organ.
- b.
The air dose due to noble gases released in gaseous effluents f rom each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
During any calendar quarter, to 1 5 mrad for gamma radiation and
< 10 mrad for beta radiation and, during any calendar year to 510 mrad for gamma radiation and < 20 mead for beta radiation.
- c.
The dose to a MEMBER OF THE PUBLIC from lodine-131, Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives >8 days in gaseous ef fluents released, f rom each reactor unit to areas at and beyond the SITE BOUNDARY, shall be limited to the following:
During any calendar quarter to 1 7.5 mrem to any organ, and during any calendar year to < 15 mrem to any organ.
- The calculated doses contained in a semi-ennual report shall not apply to any STS LCO.
The reported values are based on actual release conditions instead of historical conditions that the STS LCO dose calculations are based on.
The STS LCO dose limits are therefore included in Item 1 of the report, for information only.
f l
Page 2 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 2.
Maximum Permissible Concentrations WATER:
As per 10 CFR Part 20, Appendix B, Table II, Column 2, except.for entrained or dissolved noble gases as described in 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 A summary of liquid ef fluent 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 a.
Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated collectively to be less than t 10%.
b.
Analytical Error for Nuclides Type Average Maximum Liquid-t 9%
30%
Gaseous 210%
! 35%
TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Each Batch Principal Camma Emitters p.h.a.
"E Y
Monitor Composite Gross Alpha G.F.P.
Tank 1
Quarterly SR-90, SR-89 Releases C.S.
Composite FE-55 Continuous No. continuous activity releases Releases for this accounting period 1 Boric Acid Evaporator condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to liquid waste effluent totals.
p.h.a. - gamma spectrum pulse height analysis using Lithium Germanium detectors.
All peaks are identified and quantified.
L.S.
- Liquid Scintillation Counting C.S.
- Chemical Separation G.F.P. - Gas Flow Proportional Counting
Page 3 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 4.1 Measurements 'and Approximations of Total Radioactivity (continued) 4.1.b (continued)
TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS CASEOUS SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Waste Gas Principal (G)
Decay Tank Each Tank Gamma Releases Emitters p.h.a.
Containment Principal Gamma (G) -
Purge Each Purge Emitters p.h.a.
Releases H-3 L.S.
' Principal Gamma (G, C, P) -
Weekly Emitters p.h.a.
H L.S.
Plant Monthly Gr ss Alpha P - G.F.P.
Vent Composite (Particulates)
Quarterly SR-90 Composite S,R-8 9 C.S.
(Particulates)
G Gaseous Grab Sample C
Charcoal Filter Sample P
Particulate Filter Sample L.S.
Liquid Scintillation Counting C.S.
~ Chemical Separation p.h.a.
Gamma spectrum pulse height analysis using Lithium Germanium detectors. All peaks are identified and quantified.
Gas Flow Proportional Counting G.F.P.
Page 4 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1&2 SEMI-ANNUAL REPORT-JULY 1, 1985 THROUGH DECEMBER 31, 1985 EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION (continued) 5.
Batch Releases 9"
UNIT 1 UNIT 2 a.
Number of batch releases:
27.5 27.5
^
b.
Total time period of. batch releases:
14,276 14.276 MINUTES c.
Maximum time period for a batch release:
780 780 MINUTES 519
___ 519 MINUTES d.
Average time period for a batch release:
Minimum time period for a batch release:
342-342 MINUTES e.
f.
Average stream flow during periods of 4.0E5 GPM release of effluent into a flowing stream:
4.0E5 ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 5.2 Gaseous 23 49 l
a.
Number of batch releases:
b.
Total time period for batch releases:
J_2,194 11,863 MINUTES 910 797 MINUTES Maximum time period for a batch release:
c.
530 242 MINUTES d.
Average time period for batch releases:
127 8 MINUTES Minimum time period for a batch release:
e.
ALL GASEOUS WASTS RELEASES ARE SUMMARIZED IN TABLES 6.
Unplanned Releases 6.1.
Liquid 0.0 0.0 a.
Number of releases:
0.0 0.0 CURIES b.
Total activity releases:
6.2 Gaseous 0.0 0.0 a.
Number of releases:
0.0 0.0 CURIES b.
Total activity releases:
6.3 See attachments (if applicable) for:
A description of the event and equipment involved.
a.
b.
Cause(s) for the unplanned release, c.
Actions taken to prevent a recurrence.
d.
Consequences of the unplanned release.
Page 5 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1&2 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985-
, EFFLUENT AND WASTE DISPOSAL - SUPPLEMENTAL INFORMATION (continued) 7.
Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary assume the visitor 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 exposure f rom each of the two reactor units on the St. Lucie Site.
VISITOR DOSE RESULTS FOR CALENDAR YEAR 1985 WERE:
CASE 0US PARTICULATES & IODINE EXPOSURE NOBLE CAS EXPOSURE ORGAN DOSE (mrem)
Gamma Air Dose 5.21E-2 mrads Bone 2.28E-5 Beta Air Dose 1.07E-1 mrc.ds Liver 3.70E-4 Thyroid
-8.90E-3 Kidney 1.57E-4 Lung 3.42E-4 GI-LLI 3.43E-4 Total Body 5.16E-4 8.
Of f site Dose Calculation >bnual Revisions:
No changes were issued to the ODCM during the period July 1, 1985 - December 31, 1985.
9.
Solid Waste and Irradiated Fuel Shipments No irradiated fuel shipments were made f rom the site.
Common solid waste from St. Lucie Units I and 2 were shipped jointly. A summation of these shipments is given in Table 3.9 of this report.
Page 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985
' TABLE 3.3-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT l QUARTER #3 l QUARTER #4 A.
Fission and Activation Products 1.
Total Release (not including tritium, gases, alpha)
CI 1.11E-0 8.47E-1
- 2. ' Average diluted concentration during period uCI/ml 4.76E-9 5.07E-9 B.
Tritium 1.
Total Release CI 6.50E 1 4.27E 1 2.
Average diluted concentration during period uCI/ml 2.79E-7 2.56E-7 C.
Dissolved and Entrained Gases 1.
Total Release CI 1.55E 1 8.80E-0 2.
Average diluted concentration during period uCI/mi 6.55E-8 5.28E-8 D.
Gross Alpha Radioactivity 1.
Total Release CI 5.45E-6 7.65E-5 E.
Volume of Waste Released (prior to dilution)
Liters 1.75E 6 1.85E 6 F.
Volume of Dilution Water Used During Period Liters 2.33E 11 1.67E 11
-~.-..-
r Page 7 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. I SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 I
TARLE 3.4-1 LIQUID EFFLUENTS i
CONTINUOUS MODE l
BATCH MODE
,j l QUARTER #3[ QUARTER #4 I UNIT QUARTER #3 i QUARTER #4 NUCLIDES RELEASED l
l l
NA-24 CI 1
1.77E-4 1
- 2. 04 E-4 CR-51 l
-CI 7.85E-2 l
1.03E-1 i
MN-54 I
CI 3.47E-2 7.70E-3
{
f 0
MN-56 CI Co-57 CI 9.1OE-5 0
l 3.36E-1 1.34E-1
}
Co-58 CI 1.25E-1 2.30E-1 i
j Co-60 i
CI i
1.05E-2 2.26E-3 I
Fe-59 i
CI 3.73E-3 l
8.30E-4 j
l Ag-110 l
.CI 5.55E-4 5.15E-4 SN-ll3 CI 9.45E 1.53E-3 Sb-122 CI l
CI 2.33E-3 4.14E-3 i
Sb-124 l
0 0
t l
W-187 CI t
)
Np-239 CI i
I O
5.05E-3 I
f 3.21E-2 4.63E-2 I-131 CI l
6.00E-4 5.55E-5 I
I-132 CI 1.54E-2 3.44E-3 ll I-133 CI 0
l 0
1-134 CI 4.66E-3 0
t l
'I-135 CI l
0 0
Rb-88 CI I
2.03E-2 l
2.80E-2 i
Zr-95 CI l
4.29E-2 3.03E-2 Nb-95 CI J
9 0
Zr-97 CI 4.57E-3 7.60E-4 Nb-97 CI 1
0 5.60E-4 i
Mo-99 CI 2.91E-4 2.52E-3 l
CI Tc-99M 3.55E-4 6.65E-3
)
Ru-103 CI l
1.02E-2 8.75E-3 Sb-125 CI I
}
2.56E-2 5.65E-2 CI Cs-134 A
-..-r..,%,...-...w.m.,4%
y.,v_
,wm
,.-.,__wwy
-.,.._.,y-
,y.,
_y-
.__,-_,_-_m----_rm-,
Page 8 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.4-1 LIQUID EFFLUENTS (continued)
I
. CONTINUOUS MODE BATCH MODE l
NUCLIDES RELEASED UNIT QUARTER 3 i QUARTER 4 QUARTER 3 QUARTER 4 !
5.40E-4 4.41E-4 Cs-136 CI 3.57E-2 8.00E-2 Cs-137 CI I
0 0
Ba-140 CI I
I i
I La-140 CI i
1 2.14E-3 5.85E-3 0
2.05E-3 k
Ce-141 CI i
l l
I 0
5.75E-3 CI Ce-144 l
l 3.14E-1 8.71E-2 i
CI Fe-55 Sr-89 I
CI l
2.76E-4 7.66E-4 3.33E-5 I
0 Sr-90 CI l
0 3.33E-5 Y-90 CI l
f CI UNIDENTIFIED TOTAL FOR PERIOD ABOVE l
CI 0.00E-0 0.00E-0 1.11E-0 8.47E-1 AR-41 l
CI i
1.11E s 3.99E-4 I
1.48E 1 0
I CI KR-85 1
j i
0 2.81E-3 XE-131M 4
CI I
XE-133 CI l
l 6.90E-1 8.70E-0 l
8.05E-3 7.50E-2 XE-133M CI 2.79E-2 l
1.87E-2 XE-135 CI t
I 1.04E-4 0
i KR-85M CI l.73E-3 0
XE-135M CI TOTAL FOR PERIOD ABOVE l CI 0.005-0 0.00E-0 1.55E 1 8.80E-0 NOTE:
If no value is entered for a nuclide, the value equals zero Curies.
Page 9 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.5-1 LIQUID EFFLUENTS - DOSE SU>DIATION Age Group:
Adult Location:
Any Adult Exposure Interval:
From. January 1, 1985 through December 31, 1985 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO DOSE ORGAN (mrem)
Bone 3.25E-1 Liver 1.39 E0 Thyroid 6.73E-2 Kidney 1.38E-2 Lung 1.56E0 GI-LLI 9.34E-1 Total Body 3.96E-1 i
Page 10 FLORIDA POWER 6 LIGHT CottPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.3 2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED l
UNIT l QUARTER #3 -l QUARTER L14 A.
Fission and Activation Products 1.
Total Release (not including tritium, gases, alpha)
CI 1.llE-0 8.47E-1 2.
Average diluted concentration during period uCI/ml 4.76E-9 5.07E-9 B.
Tritium 1.
Total Release CI 6.50E 1 4.27E 1 4
2.
Average diluted concentration during period uCI/ml 2.79E-7 2.56E-7 C.
Dissolved and Entrained Gases 1.
Total Release CI 1.55E 1 8.80E-0,__
2.
Average diluted concentration during period uCI/mi 6.55E-8 5.28E-8 D.
Gross Alpha Radioactivity 1.
Total Release CI 5.45E-6 7.65E-5 E.
Volume of Waste Released (prior to dilution)
Liters 1.75E 6 1.85E 6 F.
Volume of Dilution Water Used During Period Liters 2.33E 11 1.67E 11 k
Page 11 FLORIDA POWER & LIGitT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 1985 TilROUGH DECEMBER 31, 1985 TABLE 3.4-2 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER #3 QUARTER #4 QU RTER #3 QUARTER #4 NA-24 CI 1.77E-4 2.04E-4 CR-51 CI 7.85E-2 1.03E-1 MN-54 CI 3.47E-2 7.70E-3 MN-56 CI O
O Co-57 CI 9.10E-5 0
Co-58 CI 3.36E-1 1.34E-1 Co-60 CI 1.25E-1 2.30E-1 Fe-59 CI 1.05E-2 2.26E-3 Ag-110 CI 3.73E-3 8.30E-4 SN-113 CI 5.55E-4 5.15E-4 Sb-122 CI 9.45E-4 1.53E-3 Sb-124 CI 2.33E-3 4.14E-3 W-187 CI O
O Np-239 CI 0
5.05E-3 I-131 CI 3.21E-2 4.63E-2 I-132 CI 6.00E-4 5.55E-5 I-133 CI 1.54E-2
'3.44E-3 I-134 CI O
0 1-135 CI 4.66E-3 0
Rb-88 CI O
9 Zr-95 CI l
2.80E-2 2.03E-2 4.29E-2 3.03E-2 Nb-95 CI Zr-97 CI O
W Nb-97 CI 4.57E-3 7.60E-4 Mo-99 CI O
5.60E-4 Tc'-99M CI 2.91E-4 2.52E-3 Ru-103 CI 3.55E-4 6.65E-3 Sb-125 CI 1.02E-2 8.75E-3 Cs-134 CI 2.56E-2 5.65E-2
Page L2 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 50. 2 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECE:1BER 31, 1985 TABLE 3.4-2 LIQUID EFFLUENTS (continued)
CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT
~ QUARTER 3 QUARTER 4 QUARTER 3 QUARTER a Cs-136 CI 5.40E-4 4.41E-4 Cs-137 CI 3.57E-2 8.00E-2 Ba-l40 CI 0
0 La-140 CI 2.14E-3 5.35E-3 Ce-141 CI J
2.05E-3 Ce-144 CI 0
5.75E-3 Fe-35 CI 3.14E-l 3.71E-2 Sr-89 CI 2.76E-4 7.66E-4 I
Sr-90 FI O
3.33E-3 Y-90 CI e
3.33E-5 UNIDENTIFIED CI TOTAL FOR PERIOD AB0VE CI 0.00E-0 0.00E-0 1.11E-0 d.a72-!
AR -1 XE-13tM CI J
2.ilE-3 6.90E-l 3.70E-0 XE-133 CI 3.05E-3 7.30E-2 XE-133M CI XE-135 CI 2.79E-2 1.87E-2 1.04E-i 0
KR-35M CI
,3v J
TOTAL FUR PERIOD ABOVE CI 0.00E-0 0.00E-0 L.35E 1 d.SCE-0 NOTE:
If no value is ent.: red f or a nuclide, the value equals sera Curies.
Page 13 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEM3ER 31, 1985 TABLE 3.5-2 LIQUID EFFLUENTS - DOSE SUMMATION Age Group:
Adult Location:
Any Adult Exposure Interval:
From January 1, 1985 through December 31, 1985 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO DOSE ORGAN (mrem)
Sone 3.25E-1 Liver 1.39 EO Thyroid 6.73E-2 Kidney 1.38E-2 Lung 1.36EO GI-LLI 9.34E-1 Total Body 3.96E-1
Page 14 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. I SEMIANNUAL REPOR I Jt'LY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.6-I GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED 1
UNIT t OUARTER f 3 i OUARTER fl4 A.
Fission and Activation Gases l
1.
Total Release l
CI l
1.39 E 4 l
- 8. 0 6 E 3 l
l_
2.
Average Release Rate for Period I uCI/secl 1.7 5 E 3 l
- 1. 01 E 3 l
l lB.
Iodines l
1.
Total Iodine-131 l
CI l
3.2 8 E -2 l
9.9 7 E -2 l
2.
Average Release Rate for Period l uCI/secl 4.1 1 E - 3 l
- 1. 2 4 E - 2 C.
Particulates l
.1.
Particulates T-1/2 > 8 Days l
CI l
8.81 E -5 l
- 1. 5 0 E - 3 l
l 2.
Average Release Rate for Period l__ uCI/secl 1.1 1 E -5 l
1.8 9 E -4 l
I 3.
Gross Alpha Radioactivity I_
CI l
1.9 5 E-7 l
1.9 9 E-7 7,
D.
Tritium l
1.
Total Release l
CI l
3.o 2 E 1 l
1.8 6 E 1 l
{
l 2.
Average Release Rate for Period I uCI/secl
- 3. 8 0 E O J
2.34 E o l
I 4
i 1
l 9
.-,-----,-...w.
~
Page 15 FLORIDA POWER & LIGHT COMPANY ST LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.7-1 CASEOUS EFFLUENTS CONTINUOUS MODE I
BATCil MODE NUCLIDES RELEASED UNIT QUARTER f/3 QUARTER t/4 IQUARTER </3 I QUARTER f/4
[
1.
FISSION CASES l
AR-41 CI 0
0 3.14E-1 1.21E-1 KR-85 CI O
0
,8.60E0 8.55E-l KR-85M CI :7.18El 1.64El
- 1.82E1 6.66E0 KR-87 CI 1.68El 0
'4.82E-1 1.10E-2 KR-88 CI 7.61El 0
1.54El 1.68E-1 XE-131M CI O
0 5.97E0 1.80E0 XE-133 CI 5.39E3 3.06E3
'7.35E3 4.60E3 XE-133M CI O
3.20El fl.05E2 5.56El I 2.42E2 1.40E2 XE-135 CI
- 5.78E2 1.45E2 0
0 0
0 XE-135M CI i
XE-138 CI 0
0 I
0 0
TOTAL FOR PERIOD ABOVE CI
'6.13E3 3.25E3 7.75E3 4.81E3 2.
IODINES I-131 CI 3.27E-2 9.89E-2 I-132 C1 3.30E-2 2.61E-2 I-133 CI 9.75E-2 5.50E-2 1-135 CI 3.65E-2 5.05E-3 OTAL FOR CI 2.00E-1 1.85E-l PERIOD ABOVE 3.
PARTICULATES Co-58 CI 0
5.88E-5 Co-60 CI O
2.60E-5 SR-89 CI O
O SR-90 CI O
0 Y-90 CI 0
0
Page 15a FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. I SEMI-ANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.7-1 (continued)
GASEOUS EFFLUENTS CONTINUOUS MODE 3.
PARTICULATES UNIT QUARTER #3 QUARTER #4 I-131 CI 7.65E-5 8.43E-4 I-133 CI 0
2.39E-4 Cs-134 CI 3.66E-6 8.52E-6 Cs-137 CI 7.90E-6 3.65E-4 Tc-99M CI 0
2.33E-3 Cs-136 CI 0
9.8tE-5 La-140 CI 0
1.02E-4 TOTAL FOR PERIOD ABOVE CI 7.65E-5 4.07E-3
FIDRIDA luer & LIGir QH'#N ST. tilCIE INIT I I TARIE 3.8-4 CASWllS ERUDirS - IMEE fit 9ET10N - QUAIGER f N A ME CiulP:
IWNfr IDQ u2RE INIM VAL: IMM 1-1 -1985 "Dign}{ 12-311985 HDE LIVER h(Yit)lD KIiMN 119 0 Cl-LIL T.10DY PKnMAY (nren)
(aren)
(nresa)
(nrend (wen)
(wm)
(wm) 0 lGranut!I'laic (A) l l
0 3
0 0
l l
0 l
0 l. 9. 6 4E
-4 l
lCras-cow +tilk (H) l 1.13 E
-2 l
- 1. 5 9 E -2 l
4.14E O l
4,2 6 E -3 l 2.31 C
-3 l 2.78 C -3 l
- 9. 7 6E -3 l
l lidialarlem (A) l 112E
-4 l
- 1. 8 4E -3 l
- 4. 33E -2 l
7.8 3 E
-4 l
- 1. 70 t
-3 l
- 1. 71 E
-3 l
- 1. 7 6E - 3 l
l T rrM.
l 114c
-2 l
1.7 7E -2 l
4.18 E O l
5.0 4 C
-3 l
- 4. 01 E
-3 l
4.4 9C -3 l
- 1. 2 5E -2 l
lRMEE:
1.78 miles l l(B) l (liU / GMT lSECITR:
- I d*"'b lR#sE:
l(A) l SECIUR:
4.25 miles l QUMUER CMDAMR YEAR (AllWE T!* INIERVal)
(aral)
MME CASES (nr.ml) l Canssi Air Ihmee l NA l
3.4 7E -1 l
NA l Beta Air Ikeee l l
7.10 E - 1 l
l Sector:
W lRarW:
1.78 miles l M TIE h dme valtas aduve were caln lattst tastig actial meterological sista during time specifial tiue interval witti ET data rakacasi as Reg. Cailde 1.111. Marcli 1976 l
I
Page 17 FLORIDA POWER & LIGHT COMPANY.
ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31, 1985 TABLE 3.6-2.
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED i
UNIT I OUARTER # 3 l OUARTER # 4 A.
Fission and Activation Gases l
1.
Total Release l
CI l
1.9 3 E 3 l
3.0 4 E 3 l
j l_
2.
Average Release Rate for Period I uCI/1ecl 2.4 3 E 2 l
3.8 2 E 2 l
l lB.
Iodines l
1.
Total Iodine-131 l
CI I
1.4 5 E-2 l
9.4 7 E -3 l
2.
Average Release Rate for Period l uCI/secl 1.8 2 E -3 l
1.19 E -3 C.
Particulates l
1.
Particulates T-1/2 > 8 Days
.]
CI l
0 l
1.3 7 E -7 l
l 2.
Average Release Rate for Period l_uCI/secl _ 0 l
1.7 2 E -8 l
3.
Gross Alpha Radioactivity l
CI l
S.6 7 E -7 l
1.0 8 E -7 D.
Tritiuta l
CI l
4.6 5 E 1 l
9.13E o l
l 1.
Total Release l
2.
Average Release Rate for Period l uCI/secl 5,8 5 E o l
1.15E o l
i
--_,,._____..m
=.
Page 18 l
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT JULY 1, 1985 THROUGH DECEMBER 31 1985 TABLE 3.7-2.
GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT OUARTER # 3 i OUARTER f4 00ARTER #3 i OUARTER #4 1.
FISSION GASES AR-41 l CI t
i I 1.39 EO 6_.92 E -1 CI 6
i 1.14 E -1 KR-85 KR-85M I CI
- 1. 7 6 E O
I
- 3. 8 0 E 1
l 3.98 E O I 9.56 E-2 KR-87 CI i 2.0 9 E O 4.0 5 E.
O l 6.92 E-3 i
KR-88 CI I 3.0 0 E 1
4 2.59 E O i
3.58 E-1 XE-131M CI I i
i 1.41 E O I
5.21 E
-1 XE-133 I C1
- 1. 39 E 3
2.4 5 E 3
j 3.49 E 2 1.0 9 E 2 XE-133M CI 2.4 i e 1
l e.s 5 e O i,34 c0 XE-135 C1 1.1 e e 2
3.8 4 c 2
5.33 E 1 1.70 e O XE-135M CI XE-138 CI TOTAL FOR l
- 1. 51 C 3 2.9 3 E 3
4,18 5 2 1.14 E.
2 PERIOD ABOVE I CI 2.
10 DINES I-130 CI I I-131 CI 'I
- 1. 4 5 E - 2 9.47 E-3 9.77 E-3 1-133 I
CI 7.71 E-3 1-135 I CI O M FOR 2,22 E-2 1.92 E -2 PERIOD ABOVE CI 3.
PARTICULATES Co-57 CI I
1.37 E -7 Co-60 CI I
SR-89 CI i
SR-90 CI t
Y-90 CI I
I CI CI CI I
TOTAL FOR i
O
- 1. 3 7 E -7 PERIOD ABOVE CI i
l
9 Page 19 RDRIIM RAER & LIQir UN'##
ST. UJCIE INIT # 2 TABIE 3.8-2 CASEllE EFRJENTS - IXEE SMtAITON - QllAKIER # N A
[
NE GiulP:
IW#fr EXR H RI' LNTERVAL: IMM 1 1985 T1101D1 12 1985 KE LIVER VNICID KIIItX 1190 C1-LII T. IIDDY PrJefWAY (wm)
(uren)
(wesa)
(nrem)
(wm)
(aren)
( rem) l Grimast Pl.ne (A) l l
l 0
l 0
l l
2.09 E4 l
0 0
0 O
l 2,2 8 E -3 l
9.03 E. 4 l
1.2 0 E -3 l
5.27 E-3 lCr.us-Gw-Mllk (H) l 6.2 7 E -3 l
8.to E-3 l
2,4 0 E O l
4 l
Indudartim (A) l
- 4. 7 3 E - 5 l
7.4 5 E-4 l
1.87 E -2 l
3.15 E-4 l
6,8 7 E 4 l
6.9 0 E -4 l
7,37 F. 4 l
'T l
- 1. 5 9 E - 3 l
1.8 9 E -3
.l 6,20E-3 l
l V TrN.
l
- 6. 3 2 E - 3 l
9.15 E-3 l
2.42 EO l
2.b C 5
W lRAME:
1,7 8 miles l l(H) l (EUY G1AT lSECIY1R:
W (de fault) lR#fE.
4.25
,gg,3l l(A) l SECITE:
quaxitR CNnaaR YEAR I
(ABWE TDE INIERVM.)
(aral) a n z cases l
(w i) l C;mani Air lhwe l NA l
6.6 3 E -2 l
l Beta Alr lhee l NA s
1,3 7 E - 1 l
l Sector:
lRame:
1.78 miles l l
l M TIE j
"De dme valtas aluve utre calnilated insirg actini neterological ara &rlig tle specifial tiae interval witti H~.T data rakacal as j
Reg. Gilde 1.111. Kircli 1976 l.
t 4
4
FLORIDA PO!ER AND LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JULY 1985 THROUGH DECEMBER 1985 UNIT 51 AND 2 TABLE 3.9 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFF5ITE FOR BURIAL OR DISPOSAL
- 1. Type of Waste UNIT 6 MONTH PERIOD ER ROR %
3
- a. Spent Resins, Filter Studges m
3.43 E+1 evaporator bottoms, etc.
Ci 9.29 E 2 2.0 E.1 3
2.20 E+2
- b. Dry Compressible Waste m
Ci 2.10 E + 1 2.0 E 1 3
- c. Irradiated Components m
0.00 E0 Control rods, etc.
Ci 0,00 E0
- d. Other l
- 1) Contaminated Oi!
m 4.53 E+1 C1 2.19 E +0 2.0 E + 1
- 2. Estimate of m4jor nuclide composition (by type of waste)
. a.
Co38 33 CsI37 28 Co60 16 CsI34 %
16 b.
Co60
' 26 Fe33 IS Co 3 16 S
CsI37 %
9 C5134 %
8 H3 2
C.
d.
Co60 g
33 Cl4 31 Ni63 6
Cs137 %
3 H3 1
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 13 Sole Use Truck Barnwell, S.C.
6 Sole Use Truck Hanford, W A B. IRRADIATED FUEL SHIPMENT 5 Number of Shipments Mode of Transportation Destination 0
N/A N/A N/A - Not Applicable
~
FIDlllM IOMR Q LIOK CDWANY ST.11Ch.! PLMG S8WIMMEL RERRT JtLY 1985 WHClDiIRBEER 1985 LNITS I MO 2 TABLE 3.9 (Cont.)
50.lD WLSTE SLFPIBOK (Note 1)
Total Total (Notes I, 2)
(Note 3)
(Note 4)
Wasto Volune Curle Principal Type of R. G. 1.21 Type of Solidification or Classification Ft3 Quantity Radionuclides Waste Category Container Absorbent Agent Class A 7584 1.45 None IMR 1.b Non-Spec None Trash Strong Tight Package Class A 1400 0.04 None Oii 1.d Non-Spec Cement Strong Tight Package Class A 200 2.15 Cl4 Oi!
1.d N C Certified Cenent LSA > Type A l4 63 PNI Trash 1.b IP C Certified None Class A 195 19.3 C 90,N l57 Sr Cs LSA > Type A Class A 326 0.686 None PNI lon-1.a Non-Spec None Exchange Resin Strong Tight Package Class B 279 116.64 Cl37, N 63 IMit lon-1.a N C Certified None Sun of Iso-Exchange Resin LSA > Type A topes
< 5 yr Th C1 ass C 242 659.35 I 129, Co 0 IMR Ion-1.a NC Cer t i f ied None 6
63 90 l3I,Sr Exchange Resin Type B N
CS Sun of Isotopes < 5 yr Th Class C 363 153.05 1 129, Co60 PMt Filters 1.a NC Certified None N 63, Sr90, Type B Cl4, Sun of isotopes Isotopes
< 5 yr Th
, TOTAL VJilAE 10,589 FT3 TOTAL /CTIVITY 952.66 (lRIES
I a
FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JULY 1985 THROUGH DECEMBER 1985 UNITS 1 AND 2 TABLE 3.9 (CONT.)
SOLID WASTE SUPPLEMENT NOTE 1 : The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Units 1 & 2 are determined using a combination of qualitative and quantitive 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. Offsite analyses are used to establish scaling factors or other estimates for radienuclides such as 3H,14C, 99Tc, 129, TRU 241 u,242Cm, 63Ni,and 55Fe.
1 P
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 0732, Draf t 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.
s=pe FLORID A PoWE8 & LIGHT COMPANY MR 3 1986 L-86-93 Dr. J. Nelson Grace Regional Administrator, Region 11 U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:
Re: St. Lucie Units 1 and 2 Docket Nos. 50-335, 50-389 Semi-Annual Radioactive Effluent Release Report Please find attached the Semi-Annual Radioactive Effluent Release Reports for the period of July 1,1985 through December 31,1985, as required by the Technical Specifications for St. Lucie Units 1 and 2.
Very truly yours, g g?'
'. O. Woo y
' Group Vice President Nuclear Energy COW /SAV/ae Attachment
% g'>b ec:
ocument Control Desk (? copics of attachment)
Ilarold F. Reis, Esquire P NS-LI-85-87-1 i
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PEOPLE.. SERVING PEOPLE
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