L-93-057, Forwards Semiannual Radioactive Effluent Release Rept Jul- Dec 1992 & Revised App C to Odcm: Difference between revisions

From kanterella
Jump to navigation Jump to search
VisualWikitext
StriderTol Bot insert
 
StriderTol Bot change
 
Line 1: Line 1:
{{Adams
#REDIRECT [[L-93-057, Forwards Addl Info Re 931124 Application for Renewal of License SNM-33 on Environ Assessment,Including Explanation of Substantive Changes from Previous Renewal Submittals & Replacement Pages to Renewal Application]]
| number = ML17349A746
| issue date = 03/02/1993
| title = Forwards Semiannual Radioactive Effluent Release Rept Jul- Dec 1992 & Revised App C to Odcm
| author name = Plunkett T
| author affiliation = FLORIDA POWER & LIGHT CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000250, 05000251
| license number =
| contact person =
| document report number = L-93-057, L-93-57, NUDOCS 9303090125
| package number = ML17349A747
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 58
}}
 
=Text=
{{#Wiki_filter:@@car.mam OomMZm OrsY mrs SVSrZM REGULAT INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9303090125 DOC.DATE: 93/03/02 NOTARIZED:
NO FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION PLUNKETT,T.F.
Florida Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET g 05000250 05000251,.
 
==SUBJECT:==
Forwards "Semiannual Radioactive Effluent Release Rept Jul-Dec 1992" a revised App C to "ODCM.",
DISTRIBUTION CODE:
IE48D COPIES RECEIVED:LTR f ENCLj SIZE:
+
D TITLE: Contractor/Consultant Correspondence Re Comanche Peak 50-445 446 NOTES:
S RECIPIENT ID CODE/NAME PD2-2 LA RAGHAVAN,L INTERNAL: NRR/DRSS/PRPB11 RGN2 DRSS/RPB EXTERNAL BNL TICHLER F J03 NRC PDR COPIES LTTR ENCL 3
3 1
1 2
2 2
2 1
1 1
1 RECIPIENT ID CODE/NAME PD2-2 PD REG FI 01 82 FILE 02 EGSG SIMPSON,F COPIES LTTR ENCL 1
1 1
1 1
2 2
0
'S NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HEI.P US TO REDUCE WASTE! CONTACI TIIE DOCUMENT CON'I'ROL DESI, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBU'I'ION LISTS FOR DOCUMENTS YOU DON'T NEED!
D TOTAL NUMBER OF COPIES REQUIRED:
LTTR 15 ENCL 15
 
~;I I
 
y y I
P.O. Box 029100, Miami, FL, 33102-9100 MAR 0 i 1883 L-93-057 10 CFR 50.36(a)(2)
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Semiannual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent,Release Report for the period of July 1,
: 1992, through December 31r 1992r for Turkey Point Units 3 and 4,
as required by Technical Specification 6..9.1.4 and 10 CFR
: 50. 36 (a) (2).
No liquid or gas storage tanks exceeded the limits allowed by Technical Specification 3.11.2.6 during the reporting period.
Changes were made to the Offsite Dose Calculation Manual pursuant to Technical Specification 6.14.
These changes are included in Attachment 1.
No major changes were made to the Liquid, Gaseous, or Solid Radwaste Treatment Systems pursuant to Technical Specification 6.15.
A few new locations for dose calculations and/or environmental monitoring were identified as a result of hurricane Andrew.
No new locations for dose calculations and/or environmental monitoring were identified pursuant to the Land Use Census as required by Technical Specification 3.12.2.
Should there be any questions regarding this information, please contact us.
Very truly yours, T. F. Plunkett Vice President Turkey Point Nuclear TFP/JEK/jk Attachment cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Ross C. Butcher Senior Resident Inspector,
: USNRC, Turkey Point Plant 09012/
$3QgQQ AOQ5Q ADOCQ ggggp@5()
PDR an FPL Group company
~M@I'(
 
TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1992 THROUGH DECEMBER 1992 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY J.
E. Ber adiochemis
+.Al. >+e nkvd)
R.
N.
i ke
~
~
Chemistry Su ervisor V. A. Kaminskas Operations Manager L.
W. Pearce Plant General Manager
 
rg E
7 f
l C
I 0
t k
g I
)1) w ('
8 >"~ II I'
k V
N
 
INDEX 1.0 Regulatory Limits 1.1 Liquid Effluents 1.2 Gaseous Effluents 2.0 Maximum Permissible Concentration 3.0 Average Energy 4.0 Measurements and Approximation of Total Radioactivity
,4.1 Liquid Effluents
'iscussion a.
Unit 3 Liquid Effluents Summation b.
Unit 4 Liquid Effluents Summation
'.2 Gaseous Effluents Discussion a.
Unit 3 Gaseous Effluents Summation
;,,., b.
Unit 4 Gaseous Effluents Summation t
4.3 Estimate of Error 5.0 Batch Releases 5.1 Liquid 5.2 Gaseous 6.0 Unplanned Releases 7.0 Reactor Coolant Activity 8.0 Site Radiation Dose 9.0 Offsite Dose Calculation Manual Revisions 10.0 Solid Waste and Irradiated Fuel Shipments 11.0 Process Control Program Revisions 12.0 Inoperable Effluent Monitoring Instrumentation
 
I g
f 1
C
'&I C
 
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 1 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JULY 1992 THROUGH DECEMBER 1992 1.0 REGULATORY LIMITS 1.1 Li uid Effluents a)
The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentration specified in 10CFR20 Appendix B,
Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble
: gases, the concentration shall not exceed 2.0 E-04 microcuries per milliliter.
~
b)
'The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluent released to unrestricted areas shall be limited as follows:
I I
. Duringany calendar.
: quarter, to less than or equal to,,1.5 mrem,,to the total body and to
,.less.than or equal to, 5 mrem to any organ.
During any calendar
: year, to less than or equal to 3
mrem to the total body and less than or equal to 10 mrem to any organ.
1.2 Gaseous Effluents a)
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
Less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin due to noble gases.
Less than or equal to 1500 mrem/year to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half.'-lives greater than 8 days.
 
/t I
I r
F,
)
f 1'4 4
gl r'<
'a 4
'I 0
<<~
l
 
b)
The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited:
During any calendar
: quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.
During any calendar
: year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
c)
The dose per reactor to a member of the public, due to I-131, I-133, tritium and to particulates with half-lives greater than 8
days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS Water:
As per 10CFR20, Appendix B, Table II, Column 2, 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.
3.0 AVERAGE ENERGY The average energy of fission and activation gases in effluents is not applicable.
4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY All liquid and airborne discharges to the environment during this period were analyzed in accordance with Technical Specification requirements.
The minimum frequency of analysis as required by Regulatory Guide 1.21 was met or exceeded.
When
: alpha, tritium and named nuclides are shown as curies on the following tables, this should be interpreted as "no activity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Level of Detection (LLD) sensitivity for radioactive effluents".
 
f c"I
''I 41
 
4.1 Li uid Effluents Aliquots of representative pre-release
: samples, from the waste disposal
: system, were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.
Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system and the storm drain system.
Nonthly and. quarterly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation.
The monthly composite was analyzed for tritium and gross alpha radioactivity.
Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a
solid state scintillation system.
The quarterly composite was analyzed for Sr-89, Sr-90 and Fe-55 by chemical separation.
All radioactivity concentrations determined from analysis of a pre-release composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released"during the compositing period.
Aliquots of representative pre-release samples from the waste disposal system were analyzed on a
per release basis for dissolved fission and activation gases by use of gamma spectrum analysis.
The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases released.
The liquid waste treatment system is shared by both units at the site and generally all liquid releases are allocated on a 50/50 basis to each unit.
 
I
~
't'
 
4.2 Gaseous Effluents Airborne releases to the atmosphere occurred from:
release of gas decay
: tanks, the instrument bleedline, containment purges, and releases incidental to operation of the plant.
The techniques employed in determining the radioactivity in airborne releases are:
a)
Gamma spectrum analysis for fission and activation
: gases, b)
Removal of particulate material by filtration and subsequent gamma spectrum
: analysis, Sr-89, Sr-90 determination and gross alpha analysis, c)
Absorption of halogen radionuclides on a charcoal filter and subsequent gamma spectrum analysis, and d)
Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques.
All gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the SPlNG-4 radiation monitor and the plant vent process monitor recorder chart and-the current calibration curve for the monitor.
Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit.
Meteorological data for the period January 1992 through December
: 1992, in the form of Joint Frequency Distribution Tables is maintained on-site.
4.3 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 to be collectively less than
+ 10%.
 
I
 
b)
Analytical Error Our quarterly Q.C.
cross-check program involves counting unknown samples provided by an independent external lab.
The errors associated with our analysis of these unknown samples, and reported to us by the independent
: lab, were used as the basis for deriving the following analytical error terms.
NUCLIDE TYPE AVERAGE ERROR MAXIMUM ERROR Liquid Gaseous
+4.3
+F 1
+14.5
+10.5 5.0 BATCH RELEASES
: 5. 1 Liciuid Unit 3
Unit 4
a)
Number of releases, 1.56E+02 1.56E+02
')
Total time period of batch
: releases, minutes 1.26E+04 1.26E+04 c)
Maximum time period for a batch release-,
minutes 1.77E+02 1.77E+02 d)
Average time period for a batch release, minutes 8.13E+01 8.13E+01 e)
Minimum time period for a batch release, minutes 4.30E+01 4.30E+01 Average stream flow during period of release of effluent into a flowing stream, LPM 5.2 Gaseous 4.40E+06 4.40E+06 Unit 3
Unit 4
a)
Number of batch releases 1.45E+01 8.50E+00 b)
Total time period of batch
: releases, minutes 1.89E+03 5.35E+02 c)
Maximum time period for a batch release, minutes 2.40E+02 2.40E+02 d)
Average time period for a batch release, minutes 2.22E+01 6.29E+01 e)
Minimum time period for a batch release, minutes 3.00E+01 3.00E+01
 
6.0 UNPLANNED RELEASES a)
Number of releases b)
Total activity released, curies Unit 3
0 Unit 4
6.2 Gaseous a)
Number of releases b)
Total activity released, curies 6.3 See Attachment 1, if applicable, for:
a)
A description of the event and equipment involved.
b)
Cause(s) for the unplanned event.
7.0 REACTOR COOLANT ACTIVITY 7.1 Unit 3
Reactor coolant activity limits of 100/E-bar and 1.0 microCurie per gram Dose Equivalent I-131 were not exceeded.
7.2 Unit 4
Reactor coolant activity limits of 100/E-bar and.1.0 microCurie per gram Dose Equivalent I-131 were not exceeded.
8.0 SITE RADIATION DOSE The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary assumes a visitor was on site at the "Red Barn" recreational area for 12 hours a day, 2 days each week of the year, receiving exposure from both units at Turkey Point.
The "Red Barn" is located approximately 0.39 miles NNE of the plant site. Specific activities used in these calculations are the sum of the activities in Unit 3, table 3 and Unit 4, table 3.
These dose calculations were made using historical meteorological data.
 
~
~
a 0
3 Hl
 
As a result: of hurricane Andrew, a temporary day care facility was set-up in the site training building.
The assessment of radiation dose from radioactive effluents to the occupants of the day care facility, assumes that a
person was at the facility 10 hours a day, 7 days a week, between September 1,
1992 and December 31, 1992, receiving exposure from both units at Turkey Point.
The site training building is located approximately 0.25 miles SSW of the plant. Specific activities used in these calculations are the sum of gaseous releases
. made from Unit 3 and Unit 4 for the period that the day care facility was occupied.
These dose calculations were made using historical meteorological data.
VISITOR DOSE SUMMATION JANUARY THROUGH DECEMBER 1992 UNITS 3 AND 4 Location:
0 reran Bone Liver Thyroid Kidney Lung GI-LLI Total Body Adult Inhalation Red Barn Dose mRem 1.61 E-05 2.42 E-05 2.07 E-03 1.08 E-05 1.05 E-05 9.09 E-06 1.42 E-05 Child Inhalation Trainin Buildin Dose mRem 1.98 E-06 2.34 E-06 4.77 E-06 2.22 E-06 2.50 E-06 1.97 E-06 2.34 E-06 NOBLE GAS EXPOSURE Gamma Air Dose Beta Air Dose 1.24 E-04 3.26 E-04 1.55 E-03 2.69 E-03 9.0 OFFSITE DOSE CALCULATION MANUAL REVISIONS Attachment 1 is the revision to the ODCM.
10.0 SOLID NASTE AND IRRADIATED FUEL SHIPMENTS No irradiated fuel shipments were made from the site.
Common solid waste from Turkey Point Units 3
and 4
were shipped jointly. A summation of these shipments is given in Table 6 of this report.
11.0 PROCESS CONTROL PROGRAM REVISIONS There were no changes to the Process Control Program during this reporting period..
 
J" k
V
 
12.0 INOPERABLE EFFLUENT MONITORING INSTRUMENTATION
~
~
12.1 Plant Vent Plant Vent System effluent monitoring instrumentation required by specification 3.3.3.6, table 3.3-8, item 4 a through e,
was declared out of service on August 24,
: 1992, due to extensive damage sustained by hurricane Andrew.
A'lternate sampling equipment was placed in service for continuous monitoring of iodine and particulate activity, gas grab samples were obtained at 12 hour intervals to monitor gaseous
: releases, and sampler flow measurements as well as system flow estimates were made at the prescribed frequencies.
Repairs to the system were completed and all calibrations,
: checks, and operability tests were performed prior to placing the equipment back in service on September 26, 1992.
12.2 S ent-Fuel Pit Buildin Vent Unit 3
Spent Fuel git (SFP) effluent monitoring instrumentation required by specification 3.3.3.6, table 3.3-8, item 5 a through d,
was removed from service due to the SFP exhaust fan power supply being removed from service due to the damage of plant equipment by hurricane Andrew. All effluent releases via this pathway were terminated until the power could be safely restored, and instrument checks and operability tests performed on the instrumentation prior to placing it in service on September 26,1992.
 
jlI
,*, ar
: Plh, gt'F
<'1
 
TURKEY POINT PLANT SEMIANNUAL REPORT JUNE 1992 THROUGH DECEMBER 1992 UNIT 3 TABLE 1 LI UID EFFLUENTS
 
==SUMMARY==
A.
FISSION AND ACTIVATION PRODUCTS Units Quarter 3
Quarter 4
Est.Error
: 1. Total Release(not including tritium, ases al ha
: 2. Average diluted concentration during eriod
: 3. percent of applicable limit Ci yCi/ml 2 '5 E-02 1.24 E-02 14.5 9.16 E-10 1.85 E-03 B.
TRITIUM
: 1. Total Release
: 2. Average diluted concentration during eriod
: 3. Percont of applicable limit Ci yCi/ml
: 5. 48 E+01
: 2. 01 E-06
: 6. 71 E-02 3.52 E+01 F 24 E-06 4.13 E-02 8.80
.<c!Qi;Igj;js(ji,')'..;..'j
: 1. Total Release Ci 2.49 E-02 3.93 E-03 14.5
: 2. Average diluted concentration during eriod
: 3. percent of applicable limit yCi/ml
: 9. 16 E-10 4.58 E-04 6. 9 1 E- 0 5
~kg<(::;jg<j'jggj<g)."jj~:,':
D.
GROSS ALPHA'RADIOACTIVITY
: 1. Total Release Ci 9.7 E.
LI UID VOLUMES 1.
Batch waste
: released, prior to dilution liters 1
23 Ey06 1.88 E+06 10 2
Continuous wasto released, prior to dilution liters 10
: 3. Dilution water used during period liters 2.22 E+10 2.84 E+10 10
 
V
 
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 3 TABLE 2 LX UID EFFLUENTS
 
==SUMMARY==
Nuclides Released Units Continuous Mode Batch Mode Quarter 3
Quarter 4
Quarter 3
Quarter 4
Na-24 Cr-51 Mn-54 Fe-55 Co-58 Fe-59 Co-60 Zn-65 Sr-90 Nb-95 RU-103 A -110 Sn-113 Sb-124 Sb-125 I-131 I-133 Cs-134 I-134 Cs-137 La-140 W-187 Total for period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3
~ 18 E-06 3
~ 31 E-04
: 1. 64 E-03 1.79 E-03
: 6. 71 E-03 6.40 E-05 7.48 E-03 3.36 E-06 2.10 E-04 2
~ 12 E-06 3 '0 E-04 1.69 E-06 2.40 E-04 5'4 E-03 2.20 E-03 7.37 E-06 1.83 E-04 1.14 E-03 1.80 E-04 1.59 E-05 2 '5 E-02 1.08 E-04 3.76 E-03 F 08 E-02 7.55 E-03 1-19 E-02 1 '6 E-04 5.75 E-03 4.92 E-04 2.02 E-06 1.92 E-06 3.21 E-03 1.68 E-02 5.93 E-05 2.72 E-05 F 01 E-03 2
~ 95 E-06 4.42 E-02 7.80 E-06 1.24 E-01 10
 
I
~
~
3
~
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 3 TABLE 2 (continued)
LI UID EFFLUENTS
 
==SUMMARY==
LIQUID DISSOLVED GAS Nuclides Released Units Continuous Mode Batch Mode A',r-41 Kr-,85m Kr-87 Xe-133 Xe-133m Xe-135 Total for Period Ci Ci Ci Ci Ci Ci Ci Quarter 3
Quarter 4
Quarter 3
3.12 E-06 2.51 E-06 2.49 E-02 4.28 E-05 1.66 E-05 2.49 E-02 Quarter 4
2.24 E-05 3.57 E-05 3.87 E-02 3.93 E-03 LIQUID EFFLUENTS-DOSE SUMMATION i
~ ''
JANUARY 1992 THROUGH JUNE 1992 UNIT 3 Age group:
Teenager Location: Cooling Canal Shoreline Deposi tion Total Bod Dose (mrem) 2.52 E-03 of Annual Limit 8.39 E-02 11
 
j I
Jg I
V 1
~
I I
t t1
'T
 
I I
~ 'l TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 3 TABLE 3 GASEOUS EFFLUENTS
 
==SUMMARY==
A.
FISSION AND ACTIVATION PRODUCTS Units Quarter 3
Quarter 4
t Error
: 1. Total Release
: 2. Average Release Rate for Period
: 3. Percent of Technical Specification limit Ci yCi/sec 2.62 E+01 F 05 E+01
: 10. 5
: 3. 33 E+00 1
~ 34 E+00
<Pgj<:-P)P@>P>+jjj'j
: 8. 51 E-10 B.'ODINES
: 1. Total Zodine-131
: 2. Average Release Rate for Period
: 3. Percont of Technical Specification limit Ci yCi/soc 6.13 E-06 7.77 E-07 1.67 E-03 3.82 E-05 4.85 E-06 6.58 E-03
: 10. 5 C.
PARTICULATES
: 1. Particulatos Tl/2 8 days
: 2. Average Releaso Rate for Period Ci yCi/soc 4.42 E-06 5.61 E-07 7.41 E-06 10 '
: 3. Percent of Tochnical Specification limit 4.
Gross Alpha Radioactivity Ci
<2.60E-15
< 2
~ o 3E"15
''jN<""8i:>)~<~YjYI<"'"""
D.
TRITIUM
: 1. Total Release
: 2. Average Release Rate for Period
'i yCi/sec 8.47 E-03 1.13 E-02 1.07 E-03 1.43 E-03 8.8
: 3. Percent of Technical Specification limit
( 1) Theso percentages are included in the Iodine limit calculation.
t
 
I a
+4
$2'f'
'y ry.-
 
I 1
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 3 TABLE 4 GASEOUS EFFLUENTS
 
==SUMMARY==
A.
FISSION GASES Nuclides Released Units Continuous Mode Batch Mode Quarter 3
Quarter 4
Quarter 3
Quarter 4
K,r-85m Kr-87 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Total for period Ci Ci Ci Ci Ci Ci Ci Ci 1.77 E+01 1.77 E+01 8.35 E+00
: 2. 85 E-01 8.64 E+00
: 2. 81 E-01 8.05 E+00 1.73 E-02 5.17 E-03 8.50 E+00 1
~ 88 E+00
: 1. 84 E-02 1.86 E-03 1.90 E+00 Nuclides Released Units Quarter 3
Quarter 4
Continuous Mode Br-82 I-131 I-133 Total for period Ci Ci Ci Ci 2.44 E-05
: 6. 13E-06 3.61 E-06
: 3. 41 E-05 2.42 E-05 3.82 E-05 6 '4 E-05 C.
PARTICULATES Nuclides Released Co-58 Units Ci Quarter 3
Quarter 4
6.25 E-07 Continuous Mode Co-60 Cs-137 Total for period Ci Ci Ci I'.31 E-06 2'.1l E-06 4.42 E-06 3.48 E-06 3.31 E-06 7.41 E-06
 
f k
A i
1 4
f I
0 ~
4, I
t~%
z f
 
TURKEY T PLANT SEMIANI REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 3 TABLE 5
'DOSES DUE TO IODINE g TRITIUMg AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow milk-Infant 9.80 E-06 1.32 E-05 1.64 E-03 2.40 E-06 2.59 E-06 2.07 E-06 5.20 E-06 Fruit&Veg Fresh 6.92 E-07 3.17 E-06 6.49 E-05 2.80 E-06 2.30 E-06 2.58 E-06 2.85 E-06 Ground Plane 2.89 E-06 2.89 E-06 2.89 E-06 2.89 E-06 2.89 E-06 2.89 E-06 3.38 E-06 2.89 E-06 Inhalation Adult 1.75 E-08 8.55 E-07 5.08 E-06 8.58 E-07 9.44 E-07 8.72 E-07 8.46 E-07 Totals (mrem) 1.34 E-05 1.93 E-05 1.71 E-03 8.09 E-06 7.78 E-06 7.55 E-06 3.38 E-06 1.09 E-05
%Annual Linit 1.79E-04 2.62 E-04 2.28 E-02 1.14 E-04 1.10 E-04 1.01 E-04 4.51 E-05 1.52 E-04 Dose due to Noble Gases Gamma Air Dose Beta Air Dose 4.81 E-04 mrad 1.25 E-03 mrad of Annual Limit 4.81 E-03 4/yr 0 of Annual Limit 6.24 E-03 4/yr 14
 
I' I
~W t
lt ~
 
I
~
~
TURKEY POINT PLANT SEMIANNUAL REPORT JUNE 1992 THROUGH DECEMBER 1992 UNIT 4 TABLE 1 LI UID EFFLUENTS
 
==SUMMARY==
A.
FISSION AND ACTIVATION PRODUCTS Units Quarter 3
Quarter 4
Est. Error
: 1. Total Release(not including tritium, ases al ha
: 2. Average diluted concentration during eriod
: 3. Percent of applicable limit Ci yCi/ml 2.85 E-02 9.16 E-10 1.85 E-03 1.24 E-02
: 1. 38 E-10 7.80 E-03
: 14. 5
:"-:,!:I.;yqPS:
.'-":,44
",."<<.::pq?i<'H~p)ggA@
B.
TRITIUM
: 1. Total Release Ci
: 5. 48 E+01
: 3. 52 E+01 8.8
: 2. Average diluted concentration during eriod
: 3. Percent of ap'plicable limit yci/ml
: 2. 01 E-06
: 6. 71 E-02 2 4 E
0 6
""p"p4Ycp+<<a $;,'c.$<<e 4
~ 1 3 E-0 2
~,':".,~c4'jg!':,"'ij!Pxc C.
DISSOLVED AND ENTRAINED GASES 4
: 1. Total Release
: 2. Average diluted concentration during eriod
: 3. Percent of applicable limit Ci yCi/ml 2.49 E-02 9.16 E-10 4.58 E-04 3.93 E-03
: 1. 38 E-10 6
~ 91 E-05 14.5 D.
GROSS ALPHA RADIOACTIVITY
: 1. Total Release Ci 9.7 E.
LI UID VOLUMES 1 ~ Batch waste
: released, prior to dilution liters 1.23 E+06 1.88 E+06 10 2.
continuous waste
: released, prior to dilution liters 10
: 3. Dilution water used durin eriod liters 2.22 E+10 2.84 E+10 10
 
I h< '
~
~
0
 
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 4 TABLE 2 LI UID EFFLUENTS
 
==SUMMARY==
Nuclides Released Units Continuous Mode Batch Mode Quarter 3
Quarter 4
Quarter 3
Quarter 4
Na-24 Cr-51 Mn-5'4 Fe-55 Co-58 Fe-59 Co-60 Zn-65 Sr-90 Nb-95 "Ru-103 A -110 Sn-113 Sb-124 Sb-125 I-131 I-133 Cs-134 I-134 Cs-137 La-140 W-187 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 3.18 E-06 3.31 E-04 1.64 E-03 1.79 E-03 6.71 E-03 6 '0 E-05 7.48 E-03 3.36 E-06 2.10 E-04 2.12 E-06 3.90 E-04 1.69 E-06 2.40 E-04 5.94 E-03 2.20 E-03 7.37 E-06 1.83 E-04 1.14 E-03 F 80 E-04 1.59 E-05 2.85 E-02 1.08 E-04 3.76 E-03 2.08 E-02 7.55 E-03
: 1. 19 E-02 1.96 E-04 5.75 E-03 4.92 E-04 2.02 E-06 1.92 E-06 3.21 E-03 1.68 E-.02 5.93 E-05 2.72 E-05 9.01 E-03 2.95 E-06 4.42 E-02 7.80 E-06 1 '4 E-01 16
 
I
~ ~
C 1 ~
~
~
l S
~
I p
(
T, i
 
I
~
~
4 TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 4 TABLE 2 (continued)
LI UID EFFLUENTS
 
==SUMMARY==
LIQUID DISSOLVED GAS Nuclides Released Units Continuous Mode Batch Mode Ar-41
'I Kr-85m Kr-'87 Xe-133 Xe-133m Xe-135 Total for Period Ci Ci Ci Ci Ci Ci Ci Quarter 3
Quarter 4
Quarter 3
3'.12 E-06 2
~ 51 E-06 2.49 E-02 4.28 E-05 1.66 E-05 2.49 E-02 Quarter 4
2 '4 E-05 3.57 E-05 3.87 E-02 3.93 E-03 LIQUID EFFLUENTS-DOSE SUMMATION I
II JANUARY 1992 THROUGH JUNE 1992 UNIT 4 Age group:
Teenager Location: Cooling Canal I
Shoreline Deposition Total Body Dose (mrem) 2.52 E-03 of Annual Limit 8.39 E-02 17
 
.1
 
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 4 TABLE 3 GASEOUS EFFLUENTS
 
==SUMMARY==
A.
FISSION AND ACTIVATION PRODUCTS Units uarter 3
Quarter 4
Error
: 1. Total Release
: 2. Average Release Rate for Period Ci yCi/sec 2.56 E+01 3.24 E+00
: 1. 05 E+01 1.34 E+00
: 10. 5 3.,Percent of Technical Specification limit
: 8. 30 E-10
: 3. 42 E-lp B.
IODINES
: 1. Total Zodine-131 Ci 6.13 E-06 3.82 E-05
: 10. 5
: 2. Average Release Rato for Period yCi/sec 7.77 E-07 4.85 E-06
: 3. Percent of Technical Specification limit 1.67 E-03 6.58 E-03 C.
PARTICULATES
: 1. Particulates Tl/2 8 days
: 2. Average Release Rate for Period Ci yCi/sec 4 '2 E-06 7'1 E-06 10.5 5.61 E-07 9. 4 P E-P 7
~g().'8$";@~j".3~)~g
: 3. Percent of Technical Specification limit
: 4. Gross Alpha Radioactivity Ci D.
TRITIUM
: 1. Total Release Ci 8.47 E-03 1.13 E-02 8.8
: 2. Average Release Rate for Period yCi/sec 1.07 E-03
: 3. Percent of Technical Specification limit (1) These percentages are included in the Iodine limit calculation 18
 
TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 4 TABLE 4 GASEOUS EFFLUENTS
 
==SUMMARY==
A.
FISSION GASES Nuclides Released Units Continuous Mode Batch Mode Quarter 3
Quarter 4
Quarter 3
Quarter 4
Kr-85m Kl-87 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Total for period Ci Ci Ci Ci Ci Ci Ci Ci 1.73 E+01 1.73 E+01 S.35 E+00 2.85 E-01 8.64 E+00
: 3. 37 E-01 7.92 E+00 4.35 E-03 8.26 E+00 1.8S E+00 1.84 E-02 1.86 E-03 1.90 E+00 Nuclides Re'leased Units uarter 3
uarter 4
Continuous Mode
" Br-82 I-131 I-133 Total for period Ci Ci Ci 2.44 E-05 6.13 E-06
: 3. 61 E-06
: 3. 41 E-05 2.42 E-OS 3.82 E-05 6.24 E-05 C.
PARTICULATES Nuclides Released Units Quarter 3
Quarter 4
Continuous Mode Co-58 Co-60 Cs-137 Total for period Ci Ci Ci Ci 2.31 E-06 2.11 E-06 4.42 E-06 6.25 E-07 3.48 E-06 3.3) E-06 7.41 E-06
 
I Pz eI I
~
.OX!K. '~. 4'3
 
TURKEY NT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNIT 4 TABLE 5 DOSES DUE TO IODINE, TRITIUM, AND PARTICULATES Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Total Body Cow milk-Infant 9.80 E-06 1.32 E-05 1.64 E-03 2.40 E-06 2.59 E-06 2.07 E-06 5.20 E-06 FruitSVeg Fresh 6.92 E-07
: 3. 17 E-06 6.49 E-05 2.80 E-06 2.30 E-06 2.58 E-06 2.85 E-06 Ground Plane 2.89 E-06 2.89 E-06 2.89 E-06 2.89 E-06 2.89 E-06 2.89 E-06 3.38 E-06 2.89 E-06 Inhalation Adult 1.75 E-08 8.55 E-07 5.08 E-06 8.58 E-07 9.44 E-07 8.72 E-07, 8.46 E-07 Totals (mrem) 1.34 E-05 1.93 E-05 1.71 E-03 8.09 E-06 7.78 E-06 7.55 E-06 3.38 E-06 1.09 E-05
%Annual Limit 1.79E-04 2.62 E-04 2.28 E-02 1.14 E-04 1.10 E-04
: 1. 01 E-04 4.51 E-05 1.52 E-04 Dose due to Noble Gases Gamma Air Dose Beta Air Dose 4.73 E-04 mrad 1.26 E-03 mrad 4 of Annual Limit 4.73 E-03 0/yr 0 of Annual Limit 6.28 E-03 0/yr 20
 
N
'I 1
 
FLORIDA POWER AND LZGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 1.
TYPE OF WASTE
, UNITS 6 MONTH PERIOD a.
Spent resin, filters m
: 4. 16 El
: sludge, evaporator bottoms Ci 2.28 E2 b.
Dry Compressible waste m~
5.22 E1 (Note 1)
Ci 7.23 E-1 c.
Irradiated components m'.00 EO Control rods, etc.
Ci 0.00 EO d.
Other non-compressible m~
0.00 EO Waste (Note 2)
Ci 0.00 EO t
2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE UNITS VALUE 20 20 a ~
Co-60 Fe-55 Ni-63 Co-58 Cs-137 Cs-134 68 11 8
6 5
2 b.
c ~
Fe-55 Co-60 Ni-63 Cs-137 Co-58 Cs-134 Mn-59 Ag-110m Sb-125 Nb-95 43 31 16 2
2 2
1 1
1 1
21
 
J
 
Page 2
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNITS 3 AND 4 TABLE 6 UNITS VALUE 3.
SOLID WASTE DISPOSITION NUMBER OF SHIPMENTS 7 (Note 3) 2 6
MODE OF TRANSPORT Sole use truck Sole use truck Sole use truck DESTINATION Oak Ridge, TN
: Barnwell, SC
: Hanford, WA B.
IRRADIATED FUEL SHIPMENTS None RKR/eb/212 22
 
I 4
st y Pirl
 
FLORIDA POMER 8 LIGHT COHPAHY TURKEY POINI'LANT SEHIANHUAL REPORT JULY 1992 THROUGH DECENBER 1992 UNITS 3 tc 4 TABLE 6 SOLID IIASTE SUPPLENEHT Total llaste Volpe Classification Ft (NOTE 4)
(NOTE 5)
, Total Principal Curie Radionuclides Quantity (HOTE 6)
Type of Ilaste (NOTE 7)
R.G.
1.21 Type of Solidification Category Container or Absorbent Agent Class A
1196.4 22.88 Ni-63 Sr-90 Cs-137 Solidified Sludge 1a.
>Type A, Envirostone LSA Gypsua Cask Cement Class 8
271.6 1844.3 203.3 Co.60 Hi-63 Sr-90 Cr-137 C-14 0.723 Hone DeMatered Resin Compactable and Non-Conpactable Trash 1a.
>Type A LSA Cask 1b.
Strong Tight H/A H/A RKR/eb/213 23
 
I I
 
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNITS 3 AND 4 TABLE 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Ae SOLID WASTE SHIPMENT OFFSITE FOR BURIAL OR DISPOSAL Note 1:
Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility.
Volume shipped to the waste processing facility was 507.4 m~
Note 2:
Other noncompressible waste indicates volume shipped to a
waste processing facility for disposal via incineration.
Material transported to Oak
: Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities.
The material remaining after processing was transported by the processor to Barnwell, South Carolina, for burial.
Note 4:
The total curie quantity and radionuclide composition of solid waste shipped from the Turkey Point Plant Units 3
and 4 are determined using a combination of qualitative and quantitive techniques.
The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/11/83) for these determinations.
The most frequently used techniques for determining the total activity in a package are the dose to curie method and inference from specific activity and mass or activity concentration and volume.
Activation analysis may be applied when it is appropriate.
The total activity determination by any of these methods is considered to be an estimate.
24
 
Page 2
FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JULY 1992 THROUGH DECEMBER 1992 UNITS 3 AND 4 TABLE 6 Note 5:
The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficultto measure isotopes.
The on-site analyses are performed either on a batch basis or on a routine basis using representative samples appropriate for the waste type.
Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.
Principle radionuclide refers to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclide listed in Table 1 or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.
Note 6:
Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".
Note 7:
Type of container refers to the transport package.
25
 
TURKEY POINT PLANT UNITS 3 AND 4 SEMIANNUAL RADIOACTIVE RELEASE REPORT JULY 1992 THROUGH DECEMBER 1992 ATTACHMENT 1 This attachment contains the following information for the Offsite Dose Calculation Manual (ODCM):
1., Verification of PNSC approval of the revision to the ODCM.
2..An outline of the changes made to the ODCM.
3;..A complete copy of the revised portion of the ODCM.
1I No changes have been made which would reduce the accuracy or reliability of dose calculations or setpoint determinations.
 
l}}

Latest revision as of 17:35, 26 May 2025

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=L-93-057,_Forwards_Semiannual_Radioactive_Effluent_Release_Rept_Jul-_Dec_1992_%26_Revised_App_C_to_Odcm&oldid=5510204"