ML20236E873
| ML20236E873 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/31/1985 |
| From: | Leslie Hill, Westafer G FLORIDA POWER CORP. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 3FO286-15, NUDOCS 8708030123 | |
| Download: ML20236E873 (77) | |
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i SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT , 7/1/85 - 12/31/85 FLORIDA POWER CORPORATION CRYSTAL RIVER - UNIT 3 - FACILITY OPERATING LICENSE N0. DPR-72 DOCKET N0. 50-302 MARCH, 1986 N Approved by: DirectMr Sip Nuclear 0 rations Date: M P/ '
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Date: 1/16/ff, Approved by: hk Manage Si Nuclear Services Date: --bu a , Nw%\n Semieffland2 , 8708030123 851231 'W PDR ADOCK 05000302 l ' R PDR l _ _ _ _ i
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TABLE OF CONTENTS PAGE I Int'roduction . 1 II' ReleasesLof.and Doses from Gaseous Effluents. 5 .i 1 u IIIL Releases of and Doses from Liquid Effluents' 16' ; IV - Solid Waste Shipments 29' ; V Meteorological Data 32 VI . Technical Specification Reports 63-
-j VII ODCM and PCP Changes -
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i 1 LIST OF TABLES ! PAGE I-1A- Sumation of Doses to Individuals from Gaseous and Liquid Effluent Releases - First and Second Quarters 2 1-1B Sumation of Doses to Population from Gaseous and Liquid Effluent Releases - First and Second Quarters 3 11-1 Gaseous Effluents - Sumation of All Releases 9 ) 11-2 Gaseous Effluents - Ground Level Releases 10 111-1 Liquid Effluents - Sumation of All Releases 22 l III-2 Sumation of Nuclides in Liquid Effluent Releases 23 { III-3 Doses to Individuals from Liquid Effluent Releases - First and Second Quarters 26 III-4 Doses to the Population from Liquid Effluent i Releases - First and Second Quarters 27
)
IV-1 Sumation of Solid Waste Irradiated Fuel Shipments 29
. IV-2 Effluent'and Waste Disposal Report' Shipment Summary. 30
( V-1 Summation of Meteorological Conditions at 33' (10 Meters) - First Quarter 33 j 1 V-2 Summation of Meteorological Conditions at 33' (10 Meters) - Second Quarter 41 V-3 Summation of Meteorological Conditions at 33' (10 Meters) Concurrent With Batch Gaseous Effluent Releases - First Quarter 48 i V-4 Summation of Meteorological Conditions at 33' (10 Meters) Concurrent With Batch Gaseous Effluent Releases - Second Quarter 56 i l ii 1 I _ _ _ _ - - _ _ ---_-------_________________.___________---_----J
LIST OF FIGURES ' PAGE I-1 Whole Body Doses to the Population From Gaseous H Effluent Releases 4 I-2 Whole Body Doses to the Population From Liquid Effluent Releases 4a - II-1 Gaseous Releases-Fission and Activation Gases and Tritium 11 111-1 Methods of Meeting 10 CFR 20, Appendix B, Table II, Column 2, MPC Limits 21 III-2 Liquid Releases-Fission and Activation' Products (Excluding H3 , Gases, Alpha) 25 IV-1 Volume of Solid Waste Shipped Off-Site 31 i IV-2 - Ratio of Content to Volume of Waste Shipped Off-Site 31 i i il iii I _ _ _ _ _ _ _ _ _ _ _ _______________________________.______U
m I. ' INTRODUCTION This Effluent' and Waste Disposal Report is' submitted as required by Techni-
--cal. Specification 6.9.1.5.d to the Crystal River. Unit 3 Facility Operating License No.' DPR-72. The. data in this report covers the period from July.1, to December 31, 1985.
There have been no changes to the Technical Specification Requirements for effluents and' waste disposal of the Faci.lity Operating License during the period of' this ' report.
- Crystal' River Unit 3 has had no significant measurable radiological impact
'on the surrounding environment during.the reporting period. This is based
- on the --Radiological Environmental Monitoring Program data and the doses calculated for . individuals and the population due to effluent releases-being significantly below the levels required by 10 CFR 50, Appendix I.
The summations of gaseous and. liquid effluents and solid waste shipments are Lin accordance with the tables in Regulatory Guide 1.21 (Rev.1, 6/74) Appendix B. The individual and' population doses were. calculated using GASPAR (for gas-eous. effluents) and LADTAP (for liquid effluents) computer codes obtained
'from the Nuclear. Regulatory Commission and revised to include site sp,ecific-data wherever possible. These doses are summarized in Tables 1-1A and B.
The values reported for the activity of nuclides released are the actual measured activities.- If no activity for a principle nuclide was detected for. a . quarter,' the total of the lower limits of detection for all samples is reported as "<X.XXE-X". The totals of activity released is a total of only the nuclides that had measured activity. l I 1 1 l i 1 i L l 1 i I L b ,, i
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7 l II. RELEASES OF AND^ DOSES FROM GASE0US EFFLUENTS
- 1. Regulatory Limits
The Technical Specification limits for gaseous effluent releases are as f oll ows:.
' A .- . Specification 3.11.2.1 The dose rate: at. or beyond the SITE B0UNDARY, du'e to radioactive
- materi al s released in gaseous effluents, shall be limited as !
follows: I
- a. Noble gases: less than or equal to 500 mrem / year total body and less than. or equal. to 3000 mrem / year to the skin.
- b. Iodine-131, Tritium, and radioactive particulate. with half-lives of greater than 8 days: less than or equal to 1500 mrem / year to any organ.
L B. Speci fication' 3.11.2.2 The air dose at or beyond the SITE B0UNDARY, due to radioactive noble gases released in' gaseous effluents shall be limited. to:
- a. During any calendar quarter: less than or equal to 5 mrad gamma and less than or equal to 10 mrad beta radiation, and
- b. During any calendar year: less than or equal to 10 mrad gamma and less tnan or equal to 20 mrad beta radiation.
'C. Specification 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Tritium, radioactive particulate with half-lives ' greater than 8 days in gaseous effluents released from the site to areas at or beyond the SITE B0UNDARY shall be limited as follows:
- a. During any calendar quarter: less than or equal to 15 mrem to any organ.
D. The maximum activity to be contained in one waste gas storage tank shall not exceec 39,000 Curies (considered as Xe-133).
- 2. Maximum Permissible Concentrations The maximum permissible concentrations of nuclides in gaseous releases is based on ' the resultant doses at the site boundary as determined from the concentrations of nuclides at the release point. The 0FFSITE DOSE CALCULATION MANUAL pr'ovides the equations and dose factors that relate to the gaseous activity to be released to doses at the site 5
1
n boundary, and restrictions are placed on quarterly and yearly release rates. The gaseous releases ,do not exceed the concentration limits specified in 10 CFR 20 and are as low as reasonably achievable in accordance with the requirements of 10 CFR' 50. The total dose and
' dose rate calculations are derived from the methodology in NUREG-0133 and 'the dose factors in Reg. Guide 1.109. ;
- 3. Measurements and Approximations of Total Radioactivity The. gaseous effluent release via the Auxiliary Building Exhaust is treated as. a continuous release subdivided into discrete periods of filter changes and the radioactivity measured as follows:
A. Fission and Activation Gases - The total activity released is based on the total . vent flow and . the activity of the individual 'nuclides , obtained from an isotopic analysis of a grab sample taken at least weekly.
- Iodines - The activity. released as Iodine-131,133, and 135 is based B.
on the charcoal cartr.idge activities (RMA-21), the particulate filters activities (RMA-2P) and the total vent flow. C. Particulate '- The activity released via particulate with. half-lives greater than eight days is determined by isotopic analysis of particu-
~
late filters (RMA-2P) and the total vent flow. The radioa'ctivity released by batch releases of the Waste Gas Decay. Tanks via the Auxiliary Building Exhaust is measured.as follows:- A. Fission and Activation Gases - The activity released is . based on the volume released and the activity of the individual nuclides obtained
, from an_ isotopic analysis of a grab sample taken prior to the release.
B. lodines - The iodines from batch releases are included in the iodine determination from the continuous Auxiliary Building releases. C. Particulate - The particulate from batch releases are included in the particulate determination from.the continuous Auxiliary Building release. D. Tritium - The activity released as tritium is based on a grab sample analysis of each batch and the batch volume. The radioactivity released by purge releases of the Reactor Building through the Reactor Building ' vent is measured as follows: l A. Fission and Activation Gases - The total activity released is based on the total vert flow and the activity of the individual nuclides [ obtained from an isotopic analysis of a grab sample taken prior to the i beginning of the Reactor Building purge and at least weekly during continuous yenti1ation. 6 l 4 l 1
B. ~ lodines - The ' total curies released as. iodine-131,133 and 135. were determined from - the charcoal cartridge activities (RMA-11) and the particulate filter activities (RMA-1P). C. Particulate - The total ' curies released via particulate with half-lives ' greater than eight days are determined by isotopic _ analysis of each' purge particulate filter (RMA-1P). D. Tritium - - The total curies ' released as tritium are based on grab
. samples taken for each' purge (or the average if more than one grab sample was taken).
Estimated , errors are based on errors in counting equipment calibration,
-counting statistics, vent flow rates, vent sample flow rates, nonsteady re-lease rates, chemical yield factors and sample losses for such items as charcoal cartridges.
A .' Fission and Activation Gas Total Release as calculated from process ; monitor readings and grab sample isotopics. i Monitor Statistical Error 30% Monitor Error in Calibration 50% Vent Flow Rate 10% Non-Steady Release Rate 20% ITOY
. B. .I-131 Total Release as calculated from charcoal and particulate filter a'cti vi ty.
Statistical Error -60% Counting Equipment Calibration- 10% Vent Flow Rate 10% Vent Sample Flow Rate '10% Non-Steady Release Rate 10% losses from Charcoal Cartridge 10% TfDT i 5 7
C. Particulate 'with half-lives greater than eight days release as' calcu-lated, from particulate filter activities'.
. Statistical Error 60%
Counting Equipment Calibration 10%
- Vent Flow Rate 10%
. Vent Sample Flow Rate 10%
Non-Steady Release Rate 10% T6DT
- 0. Total Tritium release' as calculated from periodic grab sample analy-ses.
Water Vapor in Sample Stream , Determination 20% Vent Flow Rate 10% Counting Calibration and Statistics 10%
, Non-Steady Release Rate. 50%
90%
- 4. Batch and Unplanned Releases The batch gaseous effluent releases may be suninarized as follows:
7/1/85 - 12/31/85 Number of Batch Releases 1.30E+01 . Total time for all releases (minutes) . 1.14E+04 Maximum time for.any one release (minutes)' 1.51E+03 Average time for all releases (minutes)- 8.80E+02 Minimum time for any one release (minutes) 1.61E+02 j Number of Unplanned Releases 8.00E+00
' Total Unplanned Activity Released (Curies) 4.16E-04 The sungnation of gaseous effluent releases is in Table 11-1 and the summa-tion of nuclides in gaseous effluent . ground level releases is in Table t 11-2. .
The unplanned release for the third and fourth quarters of 1985 are listed '. below giving the date, the Nonconforming Operations Report Number, and the cause of the release. Date NCOR # Description 8-20-85 85-174 Steam release due to plant trip 8-20-85 85-175 Steam release due to plant trip 8-21-85 85-175 Steam release due to plant trip 10-9-85 85-203 Steam release due to plant trip Steam release due to plant trip L 10-26-85 85-216 11-8-85 85-224 Steam release due to plant trip 11-22-85 85-234 Steam release due to plant trip 12-3-85 85-239 Steam release due to plant trip 8 p ,
i TABLE I1-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/85 - 12/31/85~ ] GASE0US EFFLUENTS'- SUMMATION OF ALL-RELEASES 1 Unit Quarter Quarter Est. Total i 3 4 Error %
]
i
."A. Fission and Activation Gases ]
* ~ 1. Total Release Ci 6.50E+00 2.46E+02 .1.10E+02
- 2. Average Release Rate for Period pCi/sec 8.17E 3.35E+02
- 3. Percent of Technical Specification Limit % 7.98E-03 2.12E-01 )
l B. Iodines 1.- Total Iodine - 131 Ci 0.00E+00 1.38E-04 1.10E+02 1
~
2.- Average Release Rate for Period pCi/sec 0.00E+00 4'.35E-02 .i 1
'3. Percent of Technical Specification Limit % 1.30E-02 1.18E+00
.C.-. Particulate l
-1. Particulate with half-lives > 8 days- Ci 3.56E-05 2.26E-04 1.00E+02 l
- 2. Average Release Rate for Period uCi/sec 1.10E-02 6.51E-02 -;
I
- 3. Percent.of Technical Specification Limit % 1.30E-02 1.18E+00 !
.4. Gross Alpha Radioactivity Ci 1.19E-07 4.40E-08 D. Tritium J
- 1. Total Release C1 3.81E+00 8.82E-01 9.00E+01 2, Average Release Rate for Period pCi/sec 6.98E-01 1.12E-01 .:
- 3. Percent of Technical Specification Limit % 1.30E-02 1.18E+00 9
l _ .. .I
i TABLE II-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/85 - 12/31/85 GASE0US EFFLUENTS - GROUND-LEVEL RELEASES CONTINU0US MODE BATCH MODE Nuclides Released Unit Quarter 3 Quarter 4 - Quarter. 3 Quarter 4
- 1.-. Fission gases.
krypton-85 C1 3.51E+00 krypton-85m C1 1.74E-03 krypton-87 C1 <5.46E+01 <5.04E+01 <6.87E-03 <2.18E-04 krypton-88 Ci <3.15E+01 <2.91E+01 <3.97E-03 <1.26E-04 xenon-133 Ci 5.84E+00 1.32E+02 <2.81E-03 1.01E+02 xenon-133m Ci <5.08E+01 <4.68E+01- t6.39E-03 6.16E-01 xenon-135 C1 6.53E-01 5.57E+00 <8.38E-04 3.38E-01 xenon-135m C1 xenon-131m C1 2.27E+00
!~ xenon-138 Ci <7.40E+02 <6.83E+02 <9.31E-02 <2.95E-03 argon-41 Ci ,
unidentified Ci
. Total for Perioo ci 6.50 E+ 00 1.38E+02 <1.14E-01 1.08E+02 Iodines iodine-131 Ci <9.50E-06 1.38E-04 y iodine-132 C1 iodine-133 C1 8.61E-07 3.18E-05 Total . for Period Ci 8.61E-07 1.70E-04
- 3. Particulate colbalt-58 Ci cesium-134 C1 1.06E-06 4.62E-06 3.31E-06 1.80E-05 j cesium-137 C1 manganese-54 i Ci <2.65E-05 <2.45E-05
_i_ron-59 C1 <7.71E-05 <7.11E-05 cobalt-60 Ci 5.37E-07 6.79E-07 zinc-65 Ci <5.05E-05 <4.66E-05 molybdenum-99 C1 <1.83E-05 <1.68E-05 cerium-141 Ci <1.12E-05 <1.03E-05 ! cerium-144 C1 <2.83E-05 <2.61E-05 strontium-89 Ci 1.40E-07 5.24E-08 strontium-90 Ci <6.17E-03 <5.69E-03 unidentified Ci 3.05E-05 2.03E-04 Total C1 3.56E-05 2.26E-04 l l 10
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0 b TABLE 11-5 h ' Dosesito.the. Population ;from. Continuous Gaseous Effluent Releases THIRD QUARTER H
< Wh'ble Body Doso .
Organ Dose Pathway > (Man-Rem) . Organ Dose (Man-Rem) Plume Immersion 1.02E-04 Skin '3.43F-04 Ground Contamination - 1.18E-05 Skin 1.38L-05 Inhal ation . , 9.04E-08 Lung 1.99E-07 Vegetable' Consumption 3.52E-06 Liver '7.57E-06
' Milk . Consumption' 1.50E-06 Liver 3.60E Meat Consumption 5.81E-07 Liver' 1.00E-06 Total. '1.20E-04 Skin 3.57E-04 FOURTH QUARTER Whole Body Dose Organ Dose Pathway (Man-Rem) Organ Dose (Man-Rem)
. ' Plune Immersion- - 3.4.4E-03 Skin 1.16E-02 .
, ~ Ground Contamination 1.20E Skin 1.40E-04
- Inhalation 1.67E-04 Thyroid 3.86E-04 Vegetable Consumption 1.24E-04 Thyroid 2.23E-03 Milk Consumption 4.30E-05 Thyroid 1.75E-03
- ' Meat Consumption 2.51E-05 Thyroid 1.77E-04 i Total 3.92E-03 Skin 1.21E-02 s
a o9 I 14
p
, )'N S TABLE II-6 ,
Doses' to the Population from Batch Gaseous Effluent Releases'- l: THIRD QUARTER Whole Body Dose' Organ Dose
- . Pathway ~(Man-Rem) ~0rgan' Dose (Man-Rem)
P1ume Immersion- 0.00E+00 - 0.00E+00 Ground Contamination 0.00E+00 - 0.00E+00 3 Inhalation . 0.00E+00 - 0.00E+00 Vegetable Consumption - 0.00E+00 - 0.00E+00 Mi1L Consumption 0.00E+00 - 0.00E+00 Meat. Consumption 0.00E+00 -- 0.00E+00 Total 0.00E+00 - 0.00E+00 FOURTH QUARTER
' Whole Body Dose Organ Dose Organ Pathway (Man-Rem) Dose (Man-Rem)
P1ume Immersion ~ 2.23E-03 Skin 8.48E-03 Ground Contamination 0.00E+00 - 0.00E+00 Inhal ation - 0.00E+00 - 0.00E+00 Vegetable Consumption 0.00E+00 - 0.00E+00 Milk Consumption 0.00E+00 - 0.00E+00
-Meat Consumption 0.00E+00 - 0.00E+00
- Total 2.23E-03 Skin 8.48E-03 15
III. RELEASES OF ' AND DOSES FROM LIQUID EFFLUENTS There are four sources of' liquid effluents released to the discharge canal:
- 1) the Laundry and. Shower Sump Tanks, 2) the Evaporator Condensate Storage Tanks, 3) the Regeneration Waste Neutralization Tank, and 4) the Condenser
-Hotwell. The Laundry Tanks and Evaporator Condensate Storage Tanks are batch type releases made through the plant liquid release monitor RML-2.
The Regeneration Waste Tank discharges are batch type, the Candenser- Hot-well' discharges are continuous types, both of which are made through plant
. liquid release monitor RML-7.
- 1. Regulatory Limits The Technical Specification limits for liquid ef fluent releases are as ,
- follows:
Specification 3.11.1.1 The concentration of radioactive material released to UNRESTRICTED AREAS shall be less than or equal to the concentrations specified in 10.CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained nobig gases, the concentration shall be less than or equal to 2 x 10-* microcuries/ml. total activity.
- Speci fi cati on '3.11.1.2 -
The dose or' dose commitment to a MEMBER OF THE PUBLIC from radioactive material is in -liquid effluents released to UNRESTRICTED AREAS shall be limited as follows:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ,
- b. During any calendar year to less than or equal to 2 mrem to the total body and to less than or equal to 10 mrea to any organ. ;
l 16
1
- 2. Radionuclides Concentrations The maximum. permissible concentration values used in determining allowable liquid release concentrations are taken from 10' CFR '20, Appendix B, Table II, Column 2. Release rate and dilution ratio for each batch are determined by a mixed nuclide MPC c'alculation performed before the release of the. batch.
The concentration of each of the gamma emitting nuclides specifically noted f in. Figure 111-1 is measured individually due to the requirements of the l Technical Specification. If any of the following radionuclides, mang- l anese-54, i ron-59, cesium-137, ceri um-141, or cerium-144, are less than j their LLD value, an a-priori system LLD for each isotope is used to calcu- l late the minimum detectable release activity. i Individual measurements are made on proportional composite liquid radwaste samples to determine the Fe-55, Sr-89 and Sr'-90 concentration to be applied to individual release calculations. 4
'A distillation and liquid scintillation counting technique is used to {
measure the tritium concentration on each batch release. ]
. - Th. measured and calculated concentration values for each batch are used to calculate the dilution ratio, release rate, and dilution rate, and expected doses prior to the release. The release data is then updated with actual release conditions and stored on a computer disc file. The disc' file data ,
is used to assure that quarterly and annual release limits are not i exceeded. A. Fission and activation products - The total release values (not includin' tritium, gases, gross alpha) are comprised of the sum of the indi.edual radionuclides activities released to the discharge canal for the respective quarter. These values represent the activity known to be present in the liquid radwaste effluent. Percent of applicable limit' is determined by dividing the calculated' total body or organ dose by the applicable Technical Specification limit and then multi-plying the result by 100. The most restrictive percent of limit is then used. B. . Tritium - The measured tritium concentration is used to calculate the total release- and average diluted concentration during each period Average diluted concentration divided by the MPC limit, 3 x 10-8 pCi/ml, is converted to. give the percent of applicable limit. 17
i l C. Dissolved and entrained gases - Concentrations of dissolved and en-l trained gases in liquid effluents are measured by Ge(L1) spectroscopy on a sample from each liquid release. Dissolved and entrained gases for which measured concentrations are determined include noble gases with half lives greater than 8 hours. Iodine radionuclides in any form are determined during the isotopic analysis for each release, therefore a separate analysis for possible gaseous forms is not per-formed. l The average diluted concentration of the dissolved and entrained gases is divided by the MPC limit, 2 x 104 pCi/ml, and converted to give the percent of applicable limit.
- 3. Measurements and Approximations of Total Radioactivity Details of the analytical procedures for liquid radwaste analysis are as follows:
Measurement Frequency Method
- 1. Ganna Isotopic Each Release Ge(Li) spectrometry with on-line
, computer
- 2. Gross Beta Each Release Liquid scintillation
- 3. Sr-89 Monthly ' Composite Chemical separation and gas flow proportional counting
- 4. Sr-90 Monthly Composite Chemical separation and gas flow proportional counting
- 5. Tritium Each Release Distillation and liquid scintillation counting
- 6. Alpha Monthly Composite Alpha scintillation
- 7. Dissolved Gases Each Release Ge(Li) spectrometry with on-line' computer
- 8. Fe-55 Each Release Chemical separation and liquid scintillation counting Estimated errors are based on errors in counting equipment calibration, counting statistics, nonsteady release flow rate, chemical yield factors, sampling and mixing losses, and volume determinations.
A. Fission and Activation Products Total Release as calculated for each batch. Statistical Error at MDA 60% Waste Volume 10% Counting Equipment Calibration 10% Sampling and Mixing 20% 100% 4 18
i
.;, ; -B. Total Tritium Release as calculated from a monthly composite.
Waste Volume 10% v Counting Equipment . Calibration 10% Sampling and Mixing 20% 40% ) C.. Dissolved and Entrained Gases Total Release as calculated from each
. release.
t'
~ Statistical Error at MDA 60%
Waste Volume 10% Counting Equipment Calibration 10%
- Sampling and Mixing 20%
100% p D. Total Gross Alpha Radioactivity Release as calculated from a monthly composite. Statistical Error at MDA 60% Waste Volume 10% Counting Equipment Calibration 10% Sampling and Mixing 20% 100%
. 4. Batch and Unplanned Releases The batch liquid effluent releases may be sumarized as follows:
7/1/85 - 12/31/85. Number.of Batch Releases 3.91E+02 Total Time for all Releases (minutes) . 5.08E+04 Maximum Time for any one Release (minutes) 6.10E+02
. Average Time for all Releases'(minutes) 1.30E+02 Minimum time for any one Release (minutes) 1.00E+00 Average dilution flow of Units 1, 2, and 3 during all Releases (liters / minutes) 4.68E+06 Number of Unplanned Releases 0.00E+00 l
Total Unplanned Activity Releases (Curie) 0.00E+00 The sumation of liquid effluent releases is in Table 111-1 and the suma-tion of nuclides 'in liquid effluent releases is in Table III-2. These re-leases are based on the dilution of- the radioactive liquid effluent by the j nuclear services sea water of Unit 3. l 19 f
.The doses to individuals from liquid effluent releases are in Table III-3 and the doses to the population . from liquid ef fluent releases are in Table 111-4. These doses are based on the dilution of the radioactive liquid effluents by the condens'er cooling water of Units 1, 2, and 3.
There were no unplanned releases for the third and fourth quarters of 1985. 4 e i i 20 l l \ _ _ _ _ _ _ -
1
- I Figure 111-1 !
-[
METHODS.0F MEETING 10 CFR 20, APPENDIX B, TABLE II, COLUM 2 MPC LIMITS . 1: MPC RANGE GAMMA-RAY BETA ALPHA (uC1/ml) EMITTERS EMITTERS EMITTERS I-131, 1-132, 1-133 Sr-89, Sr-90 I-135 Cs-134 (Separation and Beta
<9 x 10-6 Scintillation Counting)-
(Ge(Li) Gama-Ray Fe-55 Spectroscopy) (Separatien and All Liquid Scintil- (Al pha lation Counting) ' Counting Sensitivity 10-7 uCi/ml. as Pu-239) Ba-La-140, Na-24, Cu-64 Tritium-Co-60, Fe-59, Zn-65 (Distillation and - Liquid Scintillation 19 x 10-6 Ag-110m, Mn-54, Co-58 Counting 10-5 uCi/ml) Z r-Nb-% , Cs-Ba-137 As-76, F-18, Cr-51 All others , Np-239, Ce-141 (L.iquid Scintillation Counting 10-5 pCi/mi as Cs-137) Mo-Tc-99, Ce-Pr-144 (Ge(L1) Gama-Ray Spectroscopy) i 21
l-l TABLE III-1 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/85 - 12/31/85 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3 4 Error % A. Fission and Activation Products
- 1. Total Release (not including tritium, gases, alpha) Ci 9.54E-01 1.51E-01 1.00E+02
- 2. Average diluted concentration during period uCi/ml 8.41E-08 2.13E-08
- 3. Percent of applicable limit % 6.22E+00 4.86E-01 B. Tritium
- 1. Total Release Ci '3.20E+01 9.93E+01 4.00E+01
,2. Average diluted concentration during period uC1/ml 2.68E-06 1.01E-05
- 3. Percent of applicable limit % 8.93E-02 3.37E-01 4.00E+01 C. Dissolved and entrained gases
- 1. Total release Ci 5.76E-02 8.42E-01 1.00E+02
- 2. Average diluted concentration during i period uCi/ml 4.09E-09 8.32E-08
- 3. Percent of applicable limit % 2.05E-03 3.78E,03 D. Gross alpha radioactivity
- 1. Total release Ci 4.20E-05 6.45E-05 1.00E+02 E. Volume of Waste released (prior to dilution)
- 1. Batch and Continuous Modes Gallons 6.88E+06 4.19E+06 1.00E+01 F. Volume of dilution water used during period
- 1. Batch and Continuous Modes Gallons 1.06E+10 7.59E+09 1.00E+01 22
/
TABLE 11I-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/85 - 12/31/85~ i-LIQUID EFFLUENTS l_ CONTINUOUS MODE BATCH MODE Nuclides Released. Unit Quarter 3 Quarter 4 . Quarter 3 Quarter 4 sodium-24 C1 1.12E-04 chromium-51 C1 3.26E-03 7.38E-04 manganese-54 Ci <6.47E-04 <2.84E-04 1.97E-02 2.87E-03 iron-55 C1 2.96E-03 9.30E-06 3.18E-04 5.39E-03 iron-59 Ci <1.78E-03 <7.80E-04 1.72E-04 <1.24E-03 cobalt-58 Ci <7.78E-04 <3.41E-04 2.36E-01 2.23E-02 cobalt-60 Ci <8.69E-04 <3.81E-04 1.46E-01 2.76E-02 zinc-65 C1 <1.21E-03 <5.31E-04 <1.08E-03 <8.47E-04 rubidium-88 Ci stronti um C1 <6.90E-04 <3.03E-04 1.70E-04 1.16E-04 stronti um-90 C1 <6.90E-04 <3.03E-04 6.15E-05 2.84E-05 strontium-92 Ci 1.27E-02 2.45E-03 . zi rconi um-95 Ci 4.87E-03 2.38E-04 ) zirconi um-97 C1 3.89E-04 niobium-95 C1 1.21E-02 7.01E-04 molybdenum-99 Ci <4.58E-03 <2.01E-03 <4.08E-03 <3.20E-03 techneti um-99m C1 1.33E-04 5.50E-04 technetium-101 Ci ruthenium-103 Ci silver-110m C1 1.44E-02 1.40E-03 tellurium-132 Ci 7.82E-05 iodine-131 Ci <6.18E-04 <2.71E-04 <5.51E-04 1.65E-03 iodine-132 Ci iodine-133 Ci 5.12E-06 cesium-134 C4 <9.48E-04 <4.16E-04 9.88E-03 9.89E-03 cesium-137 Ci <8.94E-04 <3.92E-04 1.75E-02 1.36E-02 barium-139 Ci barium-140 lanthanum-140 C1 r 2.73E-03 ceri um-141 Ci <1.05E-03 <4.62E-04 <9.38E-04 <7.36E-04 cerium-144 Ci <4.79E-04 <2.10E-04 <4.27E-04 1.60E-04 praseodymium-144 Ci unidentified Ci 1.79E-03 1.04E-04 4.72E-01 < 6.08E-02 { l . Total for period (above) Ci 4.75E-03 1.13E-04 9.50E-01 1.51E-01 23 l
TABLE 111-2 (Continued) EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/85 - 12/31/85 l LIQUID EFFLUENTS CONTINU0US MGDE BATCH MODE Dissolved & Entrained Unit Qucrter 3 Quarter 4 Quarter 3 Quarter 4 Gases xenon-133 Ci 5.57E-02 8.24E-01 xenon-135 Ci 1.49E-03 4.59E-03 xenon-133m C1 3.59E-03 krypton-85 Ci krypton-85m Ci xenon-131m Ci 8.91E-03 argon-41 Ci 5.64E-06 l 24
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g TABLE III-3 ' Doses to Individuals from Liquid Effluent Releases THIRD QUARTER - CONTINUOUS RELEASES Whole Body Dose _ Organ Dose Dose Dose Pathway Age Group prem/yr) Age Group Organ (mrem /yr) Fish' Adult 1.74E-04 Adult GI-LLI 4.27E-03 Invertebrates Adult 2.75E-04 Adult GI-LLI 6.78E-03 Shoreline Use - 0.00E+00 - - 0.00E+00 Total Adult 4.49E-04 Adult GI-LLI 1.10E-02 ; FOURTH QUARTER - CONTINU0US RELEASES i Whole Body Dose Orgar. Dose l Dose Dose Pathway Age Group (mrem /yr) Age Group Organ . (mrem /yr) j l Fish Adult 4.25E-04 Adult GI-LLI 3.06E-03 Invertebrates Adult 1.98E-04 Adult GI-LLI 4.86E-03 ) Shoreline Use - 0.00E+00 - - 0.00E+00 l
' Total Adult 3.22E-04 Adult GI-LLI 7.92E-03 .
THIRD QUARTER - BATCH RELEASES Whole Body Dose Organ Dose Dose Dose Pathway Age Group (mrem /yr) Age Group Organ (mrem /yr) Fish Adult 8.43E-03 Adult GI-LLI 4.24E-01 Invertebrates Child 1.10E-02 Adult GI-LLI 1.15E-01 Shoreline Use Teen 2.69E-02 Teen Skin 3.16E-02 Total Teen 4.38E-02 Adult GI-LLI 5.43E-01 FOURTH QUARTER - BATCH RELEASES Whole Body Dose Organ Dose Dose Dose Pathway Age Group (mrem /yr) Age Group Organ (mrem /yr) ; Fish Adult 4.115-03 Adult GI-LLI 3.53E-02 Invertebrates. Adult 2.23E-03 Adult GI-LLI 2.32E-02 Shoreline Use Teen 5.54E-03 Teen Ski n 6.51E-03 1
. Total Teen 1.01E-02 Adult GI-LLI 5.95E-02 j 26 i
i
p l li j TABLE.III-4 Doses to the Population .from Liquid Effluent Releases-THIRD QUARTER - CONTINUOUS RELEASES 'l Whole Body Dose Organ Dose h Pathwayi (Man-Reni) Organ Dose (Man-Rem) l Sport Fish 2.62E-02 GI-LLI 6.45E-01 Comercial Fish -2.70E-05 GI-LLI 6.64E-04 Sport Invertebrate 1.16E-02 GI-LLI 2.87E-01 Commercial Invertebrate 8.39E-05 GI-LLI 2.06E-03 Shoreline Use 0.00E+00 - 0.00E+00 Swi ming ' 1.19E-10 Thyroid -1.19E-10 Boating 1.19E-10 Thyroid 1.19E-10 Total 3.79E-02 GI-LLI 9.35E-01 FOURTH QUARTER - CONTINU0US RELEASES' Whole Body Dose Organ Oose Pathway (Man-Rem) Organ Dose (Man-Rem) Sport Fish 1.88E-02 GI-LLI- 4.62E-01 Commercial Fish 1.94E-05 GI-LLI 4.76E-04 Sport Invertebrate 8.35E-03 GI-LLI 2.05E-01 Commercial Invertebrate 6.01E-05 GI-LLI 1.'48E-03 Shoreline Use 0.00E+00 - 0.00E+00 l Swi m ing 8.56E-11 Thyroid 8.56E-11 Boating 8.56E-11 Thyroid- 8.56E-11 i Total 2,.72E-02 GI-LLI 6.69E-01 THIRD QUARTER - BATCH RELEASES Whole Body Dose. Organ Dose Pathway (Man-Rem) Organ Dose (Man-Re_m_)_ Sport Fish 1.35E+00 GI-LLI 5.73E+01 Comercial Fish 1.38E-03 GI-LLI 5.68E-02 Sport Invertebrate 5.17E-01 GI-LLI 4.58E+00 Comercial Invertebrate 3.69E-03 GI-LLI 3.20E-02 Shoreline Use 1.21E-01 Skin 1.42E-01 Swimming 6.86E-04 Thyroid 6.86E-04
. Boating 6.86E-04 Thyroid 6.86E-04 Total 1.99E+00 GI-LLI 6.76E+01 FOURTH QUARTER - BATCH RELEASES Whole Body Dose Organ Dose Pathway (Man-Reni) Organ Dose (Man-Rem)
Sport Fish . 6.12E-01 GI-LLI 4.96E+00 Commercial Fish 6.30E-04 GI-LLI 4.93E-03
' Sport Invertebrate 1.05E-01 GI-LLI 9.51E-01 Commercial Invertebrate 7.55E-04 GI-LLI 6.83E-03 Shoreline Use 2.48E-02 Skin 2.91E-02 Swiming 1.09E-04 Thyroid 1.09E-04 Boating 1.09E-04 Thyroid 1.09E-04 Total 7.44E-01 GI-LLI 5.92E+00 27
-a___--------_____---.a
b IV. SOLID WASTE SHIPMENTS
~
Solid waste shipments from the plant may include solidified liquid waste,
. dry compressed waste, spent resins, irradiated components and spent fuel.
- 1. Regulatory Limits
. The ' Technical Specification for solid waste shipment reporting is as
' follows:
Specification 6.9.1.5(d) r The radioactive effluent release report' shall. include the following information for each type of solid waste shipped offsite during the report period; i
- 1. ' container volume,
- 2. total curie quantity.' (specify whether determined by measurement
- or. estimate),
3, principle radionuclides's (specify whether determined by measure-ment or estimate),
- 4. type of wa'ste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- 5. type of container (e.g. , LSA, Type A, Type B, large quantity),
and
- 6. solidification agent (e.g., cement).
The sumation of solid waste and irradiated fuel shipments is presented in Table IV-1 and Shipment Summaries in Table IV-2. i I I 28 !
TABLE IV-1 EFFLUENT AND WASTE DISP _0 SAL' SEMIANNUAL REPORT - 7/1/85 - 12/31/85 ; l SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
.A. SOLID WASTE SHIPPED 0FFSITE FOR BURIAL OR _ DISPOSAL (Non irradiated fuel)
Second
- 1. < Type of waste Unit 6-month Est. Total l period Error, %.
{
- a. Spent resins, filter sludges, evaporator m3 1.37E+02 ]
' bottoms,.etc.- Ci 8.61E+02 2.00E+01
- b. Dry compressible wast.e, contaminated m3 1.40E+02 equip, etc. Ci 7.08E+00 5.00E+01
- c. Irradiated components, control m3 .3.70E-01 rods, etc. Ci 3.54E+03 .5.00E+01 ,{
- d. Other (describe) Liquid scintillation m3 2.34E+00 vials Ci 7.71E-03' 2.00E+01 =
; 2.. Estimate.of major.nuclide composition (by type of waste)
- a. Co-58 1.16E+01% Cs-137 1.85E+01% E % 1 Co-60 2.28E+01% E % E %
N1-63 6.70E+00% E % E % Cs-134 5.80E+00% E % E %
- b. Co-58 '2.09E+01%. E % E. % {
i Co-60 2.67E+01% E % E % Ni-63 1.63E401% E % E % Cs-137 1.80E+00% E % E %
- c. Cr-51 2.00E+01% E % E '%
FE-55 5.80E+01% E % E % Co-58 1.20E+01% - E % E % , d. Cs-137- 6.39E+01% E % E % H-3 2.30E+01% E % E % E % E % E %
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 27 Transport Truck - Chem-Nuclear Systems, Inc.
Exclusive Use Vehicle Barnwell, SC 1 Exclusive Use Vehicle U.S. Ecology, Inc. Richland, WA B. IRRADI ATED FUEL SHIPMENTS (Disposition) Number of Shipments Mode of Transportation Destination None NA NA 29
- TA8LE IV . EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 7/1/85 - 12/31/85 SHIPMENT SUPMARY DATL'AND: CONT AINER TOTAL WAs71 CoRTA1 NER sol 1DIF.
soirncNT no. votout etntles isororts Tyrt Tyrt ac m 7/2/85 . 2.86 85-36 322 ft3 E-1 Co-58, Co-60, Cs-134, Cs-137, Mn-54 NW LSA N/A 7/15/85 3.54
.85-37 13 ft3' E3- Cr-51, Mn-54, Fe-55, Co-58, Ni-63 IC B N/A 7/11/85- 86 x 1.87 Co-58 85-38: 7.5 ft3 E0 Cs-131,Co-60,Cs-134, Mn-54, Ni-63 CW LSA N/A 7/23/85. '
4.82 Co-58, Co-60, Mn-54, 85-41 121 ft3 El Nb-95, Zr-95, Ni-63 F LSA N/A' 7/25/85 86 x 9.14 Co-58, Co-60, Mn-54, 85-42 7.5 ft3 E-1 Sb-125, Ni-63 CW ISA N/A 7/30/85 8.18 Co-58, Co-60, Mn-54, 85-43 121 ft3 El- Nb-95, Zr-95. Ni-63 F LSA N/A 9x92 ft 8/8/85 4x98 ft3 6.94 Co-58, Co-60, Cs-I34, , 85-45 1x107ft3 E-1 Cs-137, Mn-54, Ni-63 NW LSA N/A 8/26/85 1.44 85-46 322 ft3 E Cs-134, Cs-137, H-3 SC LSA N/A 8/27/85- 86 x 1.11 85-49 7.5 ft3' E0 Cd-58, Co-60, Mn-54, Sb-125, Ni-63 CW LSA N/A 8/29/85 3.04 Co-60, Cs-134, Cs-137, 85- 50 121 ft3 El Sb-122, Ni-63 - SR LSA N/A 9/5/85 3.06 85-52 322 ft3 E-2 Co-60 Mn-54. C-14. Ni-63. Fe-55 SC 1SA N/A 9/12/85- 6.38 Co-58, Co-60, Mn-54, 85-54 121'ft3- El Nb-95, Zr-95, Ni-63 SR LSA N/A 9/20/85 4.21 Co-58, Co-60, Cs-134, Ni-63, Cs-137, 85-55 200 ft3 E-2 Mn-54. Nb-95. Sb-125. Zr-95 SR LSA N/A - 9x92 ftJ 9/-24/85 5x98 ft3 1.72 Co-58, Co-60, Mn-54, 85-56 1x107ft3 E-1 Nb-95 Ni-63. Fe-55 NW LSA N/A 9/26/85 86 x 1.73 Co-58, Co-60, Cs-134, 8 5-57 7.5 ft3 E0 Cs-137, Mn-54, Nb-95 . CW LSA N/A 10/1/85 1.88 Co-60, Cs-134, Cs-137 85-58 322 ft3 E-4 Sb-122. H-3, C-14, Fe-55 SC LSA N/A 11x7. 5f t3 Co-58, Co-60, Cs-134, Cs-137, 10/18/85 5x92 ft3 2.43. f1n-54, Nb-95, C-14, 85-59 3x100ft3 E-1 Ni-63. Fe-55 NW LSA N/A 10/21/85 8.63 85-60 121 ft3 El Co-58, Co-60, Mn-54, Ni-63 SR LSA N/A WASTE TYPE: SR - Spent Resin EB - Evaporator Bottoms ' SC - Secondary Resin CE - Contaminated Equipment CW - Compacted Waste IC - Irradiated Components NW'- Non-Compacted Waste F - Filters 30
TA8LE IV-2 (Continued) DATE AND CONTAINER TOTAL WASTE CONTAINER SollDir. SU I PM E NT 90. TOLimt Ctntit$ I SO70 Pts TYPE TTPE ACENT 10/24/85 8.59 Co-57, C0-58, Co-60, Mn-54, 85-61 -121 ft3 El Nb-95, Zr-95, Ni-63 SR LSA N/A 11/14/85 9.47 ; 85-63 121 ft3 El C0-58, 00-60 Mn-54, Nb-95, Ni-63 SR LSA N/A 11'/21/85 2.87. 85-66 121 ft3 El Co-60, Cs-134, Cs-137, Ni-63 SR LSA N/A 12/19/85 5.05 Co-60, Cs-134, Cs-137, Sb-122,.
.85-67 402 ft 3- E-4 H-3, C-14, Fe-55 SC LSA N/A 11/26/85 9.07 Co-58, Co-60, Cs-134, Cs-137, 85-68 121 ft3 El Mn-54, Nb-95, Ni-63 F LSA N/A 12/3/85 9.24 85-70 121 ft3 El Co-58, Co-60, Cs-137, Mn-54, Ni-63 F LSA N/A 12/5/85 9.00 Co-58, Co-60, Cs-134, Cs-137, 85-71 121 ft3 El- Mn-54, Hb-95, Ni-63 F LSA N/A 12/12/85 5.16 85-72 402 ft3 E-4 Cs-134, Cs-137, Sb-122, H-3, C-14 SC LSA N/A 12/18/85 .
2.56 Co-58, Co-60, Cs-134, Ni-63, 85-73 200 ft3 El Cs-137, I-131, Mn-54, Nb-95, H-3 SR LSA N/A
. WASTE TYPE: SR - Spent Resin EB - Evaporator Bottoms SC - Secondary Resin CE - Contaminated Equipment CW - Compacted Waste IC - Irradiated Components NW - Non-Compacted Waste F - Filters 30a
m
- FIGURE IV V0'.UE OF SOLID WASTE SHIPPED OFF-SITE 892
- 800 .
Waste V lure,
- 408 400 .
376 289 254 250 223 218 200 - 188
.A B A- B A B A B A B 1981 1982 1983 1984 1985 l
- FIGURE IV RATIO 0F CURIE CONTENT TO VOLUME OF WASTE SHIPPED OFF-SITE 9.95 15.76 -
f l 3.0 2.5 2.0 1.8 1 77
~
' Ci/m3 1.57 1.5
- 24 )
i 1.0 0.86 0.72 - 0.56 , 0.5 0.21 1 I A B A B A B A B A B { 1981 1982 1983 1984 1985 1 A'- First Half j B - Second Half ) 31 i i
') . [, )
S V METEOROLOGICAL DATA
- The meteorological 1 ' data at 33 feet.(10 meters) is summarized in Tables V-1, V-2, V-3,:and V-4 ..
. The classification of atmospheres ' tability is. as follows:
Stability Pasquill. Temperature change-Classification Categories with height (*C/100m)' , Extranely unstable' A <-1.9 Moderately _ unstable B >-1.9 to <-1.7 Slightly unstable C _ >-1.7 to <-1.5. Neutral D- T-1.5 to <-0.5 Slightly stable . E 17-0.5 to < 1.5 Moderately stable F T 1.5 to < 4.0
~
Extranely stable G 4.0 .. The d'ata recovery rates are: Thi rd Quarter .. . . . . 74% . Fou rth Qua rt er . . . . . . 69.5% The meteorological data for this period was manually recovered frap strip charts.
'l 1
32
g, . . . _ _ _ . _ _ _ . _
; .J
'] TABLE V-1
'i 1 O 2 :-F L'OR ID A? P OWER ORPORATION
)
3 ~
~
4 h0VRS AT EACH WIND SPEED AND DIRECTION T T PERIOD OF RECCR0 JULY 1,1985 THROUGH DECEMBER 31,1985 St. ABILITY CLASS ' -A 9 3 ELEVATION - 33 FT. q n E WIND WIND SPEED (mph) 13; DIR3 1 4- 7,. 8-12n 13-18 19-24. 24+ TOTAL g _ _ _ _ - .____ , _ _ _ iil i6 h 0 1 0 0 0 0 1 ii 3 NNE O 2 2 0 0 0 4 h. NE. f0 " 23- f2' .1- .0 0 6 5 - 22 ENE O 5 21 8 0 0 34
~5
% E O 4 3 0 0 0 7 Ei E ESE- 0l De .: 0 O -0 0 C
[iil .
~ ~ ' '
N 5'E O 1 0 0 0 0 1 h fai SSE O O 1 0 0 0 1 Sit ... .. .. G 5 0~ O' . 3 'O O O 3 2 ~ g 55h o z 1 0 0 0 3 ~~ ~ ~~
'as f7 3 SW 0 10 13 0 0 0 23
. an 8' WSW 0 10- 10' O O O 20 f37 ~ ~ - -
!c h 0 6 12 0 ~0 0 1~8 ~
E Ei khh 0 1 11 0 C 0 12 _ _ _ _ _ _ _ _ _ M
- w .- Nh- 0 -1L 3 -0 -0 0 4 I47 --
gi hNW 1 1 0 0 0 0~ 2 h TOTAL 1 47 82 9 0 0 139 g v [m iil PERIODS OF CALM (HOURS)~-: 12 -- w v
!:st..
- s. : 9 33
s c
] t TABLE V-1
'l <
. . . . . . . . . , . . 4. .
l T 1, 'C
.: FLORIDA!POWERICORPORATION! ' '
;; y - -
l 3 l 1 HOURS AT EACH WIND SPEE0 AND DIRECTION 5 T PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 .__ 7 Tt STABILITY CLASS -B W --...-
. imi ELEVATION - 33 FT.
~ iii
[ii WINO WIND SPEED (MPH)
'OIR . 4-7 : 13-18 24+ TOTAL
!n; - l-3 12 '19-24 Ii2. : . . .
G ~~ 16 N O 1 0 0 0 0 1 Ti
;is NNE 1 0 1 1 0 0 3 19l NE. .01
.1) ,
--l- '1 0 0 3
[2: ENE O O 4 4 0 0 8
. f2i Ei E O -
1 1 0 0 0 2 I25 ~ Isi- :ESE :0: ',L O : < f: 1 0 0- 0 1 V V SE O 2 0 0 'O O 2 h si SSE O O O 2 0 0 2 _ h
~
E' S 01 2. . 2- l'- 0: 0 5
~ ~ - ""~'
4 55W 0 3 3 0 0 0 6 iii SW 0 6 4 1 0 0 11 g' WSW- 0 3 2- 0 0 0 ,5
~ ~ ~
lc W 0 0 1 0 0 0~ 1-7 [Td Whh 0 0 1 0 0 0 1
~
!ai . . .
27 hW ,0 : 1- 0' O O O 1 II - ~~ . c hhW 0 2 0 0 0 0 2 if H TOTAL 1 22 21 10 0 0 54 d
~ 'sm ii PERIODS OF 'C ALM (HOURS)?- 7 E
E s' -- - N 51 ft 34
' r] TABLE V-1
's ;j >
P, . _2 lFLO'RIDA' POWER? CORPORATION 4 h0VRS AT EACH WIND SPEED AND DIRECTION D T T PERIOD OF RECORD - JULY 1,1965 THROUGH DECEMBER 31,1985 7 l r' T STABILITY'CLASSL - CL i it j n ELEVATION - 33 FT. l E I E WING WIND SPEE0 (MPH) I 13 DIR. 1- 3 .- 4-7 8- 12 -- 13-18 19 24+ TOTAL r- E. . _ _ - _ _ . . ,. .... 16 h 0 0 'O O O O O l (' 5. 18 NNE 1 0 0 0 0 0 1 19 . . . . (~ { ~NE J. 0. , ' 11'
.'O :01 0 0 1 v
22 ENE O 2 7 4 0 0 O f E'~ 51 E O 3 0 0 0 0 3 ESE- -0 0 01- 01 0 0 0
- g. .
-~~~~
- s SE o 1 0 0 0 0 1 Ei pq SSE O 1 0 0 0 0 1 bil ihl mt 5 0 .' 2 '4 1 0 0 7
!y 55n 0 2 2 0 0 0 4
, i25
$ Sk 0 8 5 0 0 0 13
!37i
(. . _ [Ej WSW 0 6! 3 0 0 0 9
~ ~~
W 3 2 0 0 0 6 _4_: ( .41 p- Whh 0 0 1 0 0 0 1 I43 ( E4] hk' O O O O O O O e hhh 0 0 0 0 0 0 0 L, ~c H TOTAL 2 29 24 5 0 0 60 yk
$ PERIODS OF CALM'(HOURS).- 6 ___
C$ 54 55 OE - ei - ---- 37
,C- _ . . _ - _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ _
Rr ( ~_ _ h TABLE V-1
?, u . , , .
l PT l , (FLORID'A POWER 3 [ CORPORATION: 3 '. - 1 HOURS AT EACH WIND SPEEC AND DIRECTION i (' s l 6 DERICD OF RECCRD - JULY 1,1985 THROUGH DECEMBER 31,1985 ___ 71 . .
fil STABILITY CLASS. - 'D P _
- n ELEVATION - 33 FT.
< 5 E WIND WIND SPEED (MPHI h3t DIR- 1-3 4-7 8-12.- 13-18 19 24+ TOTAL r T; ... ... . -
1-Isi -~ 16 N 0 5 2 0 0 0 7 ("^ if Ii NNE O 4 16 1 0 0 21 19! f .NE- . 3 .19; l273 .- 31 0 0 52 (22 EhE 2 18 23 0 0 0 43 g E E 3 11 9 0 0 0 23
.25 Bi . .ESE: ' .. 0 - ~ 8 :-- 14' .'O O O 22 Q 5E 1
6 5 0 0 0 F2 bg i' 29 si SSE O 5 8 3 0 0 16 __
,31 .
, Gi 5 1 217-. l12 - 9 0 39 33,
- - - ~ ~ -
n 55W z 19 9 L 0 0 3r (. . 35 E Sk 1 35 4 0 0 0 40 _ 37; ('; .iil WSW 0 23 6' O O O 29 E _f3 g I W 0 7 6 0 0 0 L., M c kNk 1 9 8 0 0 0 18 (, H NW~ 3 E7- O3 0. 0 0 13 is e NNW 0~ 5 1 0 0 0 ~ ~~ ~ 6' (; ii ' H TOTAL 17 198 153 17 0 0 385 C si PERIODS OF CALM (HOURS)'- '40-5,' C H
.O E :
e 36 O
'] <
TABLE V-1 b . . . . . . .~ , . . ,
- 2
-FLORIDA'POWERdCORPORATION 7 - ,
4 HOURS AT EACH WIND SPEED AND DIRECTION p, 7 i PERIOD-OF RECCRD - JULY 1,1985 THROUGH DECEMBER 31,1985 7 T ' STABILITY CLASS -L E T-io E L E V A TTON - 33 FT. II ' E WINO WIND SPEED (mph) - isi 0IR- 1-3 4 :8-12 18 19-24 24+ TdYAL e Tj ; ..... ....z . . . . . _ . . . ..... .... ..... II 16 N 5 6 2 0 0 0 13 Ti H NhE 2 34 11 0 0 0 47 19 111 ii NE .' 18 ' 'f63- E30 ' LO- 0 0 ii' 22 EhE 26 61 15 0 0 0 fd2 5 E E 24 39 2 0 0 0 65
!2sj .-
Is} ESE. 4 J51; -4 l' - O' O 60
~ ~ ~ ~ ~
ps 5E 4 22 1C 0 0 0 3 ~6- --~~ ' I5 bl SSE 4 15 4 0 0 0 23 31 . s ,i- .S 2 13 9 0 0 0 24 I27 b; ssh 3 14 9 0 0 0 2 6 - ~~ - -- -- " s Sil Sk .
. ~ .
4 27 10 0 0 0 41
; Ei! WSh~ -2 25- :3- 0 'O O 30 "E -
4c W 3 10 2 0 ~0 0 1 5 '--- L E '
% WNW 2 6 8 0 0 0 16
'43:
(j hk 5 14 1 0 0 0 20 46 hhW 7 10 0 0 0 0 f7 C [ 4s TOTAL 115 410 120 1 0 0 646
.. , l sci u ;Til . PERICOS OF: CALM (HOURS)'- 56 _ . _ . . _ - _ _ _ _
O E 54 SS O pc. _ __ h - _____-__ - _ ___ -
Or TABLE V-1 T]kr,
~
l _2 . fFLOR.!dA 50WER ,. CORPORATION. l- 4 HOURS AT EACH WIND SPEED AND DIRECTION l rT ! 7 PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 . . . -. -.- Il STABILITY CLASS' -- F f91 ~ _ _ _ . _ _ _ h: ELEVATION - 33 FT. g E WIhD WIND SPEED (MPH) itt :DIR. 1-3 4 8-12 13-18 19 24+- TOTAL 3 r7 .... . --. ...... .- . .- .... ...... i Ii u h 2 2 0 0 0 0 4
! Ti l ii NhE 1 10 0 0 0 0 11 j 191 N JNET 9 12 61- -Oc 0' .0 0 35
$ii: ~ ~ ~ ~ ~
!22' ENE 25 20 0 0~ 0 0 45 IIi E E 27 12 0 0 0 0 39 bs '
s' ..
"fi " E ,S E - 8 '.c ':135 "0- 0 0 21 271 23 SE 2 5 0 0 0 0 7 l h SSE 2 2 0 0 0 C 4 1
at
~
4 5 -l 0 :- .t 0 10:' O C 1 E - g I 55h 0 0 0 0 0 0 0 ~~~-~~] s l2s j fii SW 1 0 0 0 0 0 _, 1
)
l37 WSh O' O 0 0 0 0 C C Gi. R '~ ~ c h o 0 0 0 0 0 ~~"~~C l'
}
i E WhW 0 0 0 0 0 0 C j l43.
.C H Nk: .0 .0 0 0 0 0 0 l
$ nth 2 1 0 0 0 0 -~3 ca3 TCTAL 79 92 0 0 0 0 171
.. d VM ;5i PER1005 0F CALMi(HOURS} -
31 s2 O E u _ _ . _ _ _ _ _ 55 O E F __ r 38 L)
4
] TABLE V-1 r.
..,.,f...:..> . i. .sf ..>.h ,..,.h'-
./,.,...J -
r FLORIDA? P. OWER f. CORPORATION - 2 F- ' y $ - ' , - - 3 > 4 HOURS AT EACH WIND SPEED AND DIRECTION T PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 7 _ T STABILITY CLASS. -7G T to ELEVATION - 33 FT. ii E WIND WIND SPEED (MPH) jy :DIR:
.1 6 4 -7, L8 13 (19 .24+. TOTAL
. . . .~.: - - - , ._
,a 3 ,,-
0 h 0 0 0 0 0 0 16 i~r E NNE O 1 0 0 0 0 1 g-E' '
' h E' S( (31 0; 0: 0 0 . 5 it ENE O 5 0 0 0 0 5 n
33 5 4 0 0 0 0 9 [s' E
~
i:5 . .. . [:1, .ESE :li
< JJ 0 ..0- 0. 0- 0 1 5 5E Z 1 0 0 0 0 3 bs h
ba SSE O O O O O O O bs; .. - .. . .. . i
'0- ;0 0 -. O. 0 0
@' S '- . 0 -:
E 0 0 0 0
~ ~~
a 55w 0 0 0 is [E Sh 0 0 0 0 0 0 C_ _] El ~ 0 'O O {- g I 391 WSW 0 0 'O O ac h 0 0 0 0 0 0 0-~ (~ Tr
" ~
WNW 0 0 0 0 0 0 0 _._ 43 l0 0 0 L~ & .0' NW 0 0 0 45- - hhh 0 0 0 0 0 0 0 46 4
- m TOTAL 10 14 0 0 0 0 24 E' _
.... U Q '
ii50l-- PERIODS OF' CALM.(' HOURS) l' _ _
.s:1 -
O? 54 55i oE n 39
,b _
FLORIDA P0 DER CORPORATION dINC SPEED AND DIRECTION
SUMMARY
]. THIS REPCRT INCLUDES DATA CCMPILEC DURING THE FOLLOWING PERIDOS -
(
'i '
a $fflff1NGs ' STARTING. EhDING: ENDING. I ;
'~
IDAY,.. , .' H OU R" . DAY ,* <;h00R-
;T L........ .
nl.. -. .-- i4l < Is 196 19 196 21 7 I7 3_. 191 _ _ _ _ _ _
. hai HOURS OF MSSING DAT A - 0 w
4 15-16l E IB , 19l
.I , .
k __ c 4 a2
~$ l lii ~
b5 ,: Q .V - 4 E8
!?
30 1 3 32 C.~ . , __ 2_5 u --- E,, 90 E I4 __ b') #,' 44 ... h 45 b id7 b . ,_ i i g v s 2l.. < 51 ' - Ti f.
%J _
54 .s _ _ _ 55 C5 - t'
- 40 J
] y
. ,., t TABLE V-2 T' < .
Te h
^ ~
1 .- '!:FLORIDAhPOWERIC.ORP' ORATION? 3 c . . 4 HOURS AT TACH WIND SPEED AND DIRECTION I T PERIOD OF RECCRD - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES 7 .. . . T STABIL~ITY CLASS.e a ' Ai - 4 e
. ie ELEVA7TDN - 33 FT.
ii E .h!NU WIND SPEED (MPH) ish , . . D I R. 1 14- 7. - .---- 8-12.1 ' 13 24 24+ Tift AL y.,' ----- . .... .----; : --- . .... ---- ----- TD i t, N 0 0 0 0 0 0 0 Ti H NNE O O O O O O O 19 El E ,,' NEJ
~ ..0 -.
;-_0 : ;0 ,J ^ 0 0 0 0 5.
c
;,( . .;' . >'
2: ENE O O T~ 0 0 0 0 3 Ei E O O O O O O O b5 - -
.E 4ESE'- 'O' ;0: .
;0- 0' 0 0 0 y .-
s. G g SSE 0 0- 0 0 0 0 0 bi -< - . g S-. . . 0- #0; , .0 0 0- O' O ba '
- g. 33n O O O O O O O__
35 g Sh 0 0 0 0 0 0 C
'WSW -O' .0 0- 0 0 0 C
- 39. . _ . _ _ _ _
e W D 0 0 0 0 0 G 7i Ii kNW 0 0 0 0 0 0 0 b Nh ~0. O' O O O O O M 0 0 0 Iui hhW 0 C C' O 2 Ts TOTAL 0 0 0 0 0 0 0 G. - h PERIODS'0F' CALM (HOURS) -- ~0 _ _ l u ee$ (5 .<
..)F-h'I ;
- _ . .
41 V _
r _ - _ ____._ - _ - _. . ._ - _ . . ._ _ l TABLE V-2 l 2 7, .' FLORIDA! POWER' C0kPORATION ' j 3 ) 4 HOURS AT EACH WIND SPEED AND DIRECTION 1 i s . l T PERIOD OF RECCRD - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES ____. l
.?J '
is. STABILITY CLASS.'- B T a ELEVATION - 33 FT. Ii 5 WIND WIND SPEED (MPH) is! DIR- .1-3 4-7~ 8- 12 -- 13-18 19-24 ~ ?. 4 + TOTAL g ---- ---- --- . ---- ---- ---- -- ----- Ei ~ 16 N O O O O O O O l iT E NNE O O O O O O O i 19 3L NE O ,0; ~0- 0 -0 0 0 g.
~
g ENE O O O O O O 0
!23
$ E O O O O O O O b5 .
'Ot E ESE' 10-c ' .: 0 -
'O O O O 3 .
- -~
- s SE O O O O O C 0 79 E SSE O O O O O O O __
h S' 0 'O' C O' O 0 0 G 0 0
~ ~ ~ ~ ~ ~
lu 55W D 0 0 0 0 Is E SW 0 0 0 0 0 0 0 _ h WSW 0- .0- O' '
.' O O O O E - - ~
4: W D 0 0 0 0 0 0 E E kNW 0 0 0 0 0 0 C 43 L NW 0 0 0 0 0 0 0 E ~~ e hhw 0 0 0 0 0 0 0 U 2 TOTAL 0 0 0 0 0 0 0 lL
,..., 50 . . ., .. .
H .. PERIODS OF~ CALM.(HOURS) = 0 _, s: 54 h : !. g __ 42 J
] TABLE V-2 "i .
* ~
' FLORIDA?P.OWER. CORPORATION ~
T_ , c 4 HOURS AT EACH WIND SPEED AND DIRECTION m - I PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES 7 i STABILITY' CLASS'" ;C. 9' 3 ELEVATION - 33 FT. 11 E WINO WIND SPEED (MPH) 13 DIR -l :4-7 - 8 13-18 24 24+ TOTAL 5 .... .. ... : .. ... . .... .... ..... E -
, l 16 h 0 0 0 0 0 0 0 5
E NhE O O O O O O O 1Y
'0' E 'NE 'O'. -
-O O O- 0- 0 ii
- 2: ENE O O O O O O C 3
9 E O O O O O O O b5 . . .. . E 'ESE l0. ;0 ' 0 E, .0 0. 0 0 g .
- - ~ ~ ~
bs SE O O O O O O O'~~' 9
$ SSE O O O O O O O si E -S 0. 0- 0 0 0 0 0 i3 -"
% 55h 0 0 0 0 0 0 0~~'
Ti E Sh 0 0 0 0 0 0 0 fisi WSW 0 0 d 0 0 0 0 g.-
- - - - ~
po W D 0 0 0 0 0 0 f4I Ei kNW 0 0 0 0 0 0 0
~
b3j -
;44; hk- - O '. 'O O- 0 0 0 0 4si 46 Nhh o 0 0 0 C 0 0 D
H TOTAL 0 0 0 0 0 0 0 b
'PERICDS OF CALM.(HOURSi'- -
0 55
.. J' k 15d -
Iss: 43
r 1 ~] TABLE V-2 s, ' l FLORIDA; POWER.; CORPORATION
~
T y2T HOURS AT EACH WIND SPEED AND DIRECTION 15 iT PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES STA'BILITY CLASS ~ ~ D iTI hoi ELEVATION - 33 FT. Ti U WIhD WIND SPEED (MPH) at DIR 1-3 4-7' : 8 13 :19-24 24+ TOTAL U; .... .. .... . ..... . _ _ . .. .... b 16 h 0 0 0 0 0 0 0 ii 3 NNE O O O O O O O d9j' , 12c NE- 0 ; 0 :: 0- . O' O O O ii 22 ENE O O O O O O O ii Fi E O O O O .0 0 0
!251 El ' ESE- 50 Lol- :' 0 0. 0 0: 0 Ti ~~
- s SE O O C 0 0 0 0 E
E SSE O O O O O O O bi E S. ,'0- '. 0 ;- 'O. 0. 0 0' O 9
% 55W 0 0 0 0 0 0 0
[s] Sh 0 0 0 0 0 0 0 _ WSW 0 0- 0 0 0 0 0 W; ~ ~ ~ ~ - i4: W 0 0 0 0 0 0 ~D C l
@ hhh 0 0 0 0 0 0 0 l 14 3 D- hk 0" 0- 0 0 0 0 0 N ~~
A hhh- 0 0 0 0 0 0 C' fl7 R TOTAL 0 0 0 0 0 0 0 4 si - PERIODS OF CALM (HOURS) - 0-1 E P -- O ' e 44 V
c _,
~] TABLE V-2 l
T
- FLORIDA? POWER' CORPORATION.
14 HOURS AT EACH WIND SPEED AND DIRECTION
'f7 T PERICO OF RECCR0 - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES I STABILITY CLASS":--E.
l T l ic ELEVATION - 33 FT. 5 l E WIhD WIND SPEED (MPH) ul- - DIR- -l-3 . 4-77 '
.8 12L 13-18 19-24 24+ TOTAL T2 . . .
g , . 16 h 0 0 0 0 0 0 0 Ti H NNE O O O O O O O 19 . E, NE 0- .O :0 0: . 0 0' O ii
- ENE O O O O O O O 3,
Si E O O O O O O O _ ks.
}6i ESE 0' - 0 .- - .0:
0 -. 0 0 0 g . _- ~ ~ ~ ~ ~ ~ be 5E o 0 0 0 0 0 0 G E SSE O O O O O O O bu . G S 0 . O' 0- 0 0 0 0 E1
- iin 55h o 0 0 0 0 0 0~ ~ "~~ ~ -
9 52 Sk 0 0 0 0 0 0 0 an
@ hSW 0 0 0 0 0 0 0
% ~0
~ ~ ~ ~
M w 0 0 0 0 0 0 G WNW 0 0 0 0 0 0 0 fii hk 0 0 0' O O O O G ~ g i KG D 0 0 0 0 0 0 47
$ TOTAL 0 0 0 0 0 0 0 E
&' 'PERICOS OF CALM (HOURS):-' '3 tsu - -
a us . . J , 45 J
Rr j TABLE V-2 l ~ (\ \ . [T :. FLORIDAlPOMERSCORPORATIOh ' fi f7 HOURS AT EACH WIND SPEED AND DIRECTION ri
.I PERIOD OF RECORD - JULY 1,1985 THROUGH OECEMBER 31,1985 BATCH _ RELEASES._
7 . Tr? STABILITY' CLASS - F 7 -..-
!g ELEVATION - 33 FT.
11 E h!ND WIND SPEED (MPH) ir- DIR 1-3 .4-7c ,8-12 13-18 19-24 24+ Tift AL ,
~~
16 h 0 0 0 0 0 0 0 Ti H NNE O O O O O O O 19 ic' NE! !O 01 .0 0- -0 0 'O
.21 ~
l2: BhE O O O O O O C Ei [fi E O O O O O O O b5 . . E LESE :0' 'O
- 0. .0 0.
0- 0
's ,
~
- s SE .0 0 0 0 C 0 0
- 9 E SSE- 0 0 0 0 0 0 0 _ _
'. 5 - O. 01 0 0~ O' O C c
h 55W 0 0 0 0 0 0 0
~~ '
s 0 0 [ii 5W 0 0 0 0 0 b7l Ii? WSk O' O. 0 0 0 0 0 07 - ~~ cl h 0 0 0 0 0 0 0 b p2 hNW 0 0 0 0 0 0 0 143i . NW -0~ 0 -.- O, 0 0 0 0
]
hhW 0 0 0 0 0 0 0 I 2 G TOTAL 0 0 0 0 0 0 C E
"N PER1005 0F CALM.(HOURS) - 0 E
U 13 54 b u sa g7-4'6
.)
] TABLE V-2
>i T .. , , < ,; FLORIDA; POWER l CORPORATION; 3 '
a HOURS AT EACH WIND SPEEC AND CIRECTION T T PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEAS_ES 7 T STABILITY CLASS. -'G. T 1: ELEVATION - 33 FT. II E hIhD WIND SPEED (MPH) i ia- DIR- 1 4- 7. . 08 13-18 19-24 24+- TOTAL l' UI l T2 i6 h 0 0 0 0 0 0 0 if ii hhE O O O O O O O
~
-NE Of , 0: 01 :0 0 0 0 21
- ENE O O O O O O O E
F4 E O O O O O 0 0 N~ IESE- 0 -0 JO 'O O' C 0
- 6 5 '
~ ~~ 1
- s SE O O O O O 0' 0 I23 E SSE O O O O O O O M,L e -S 0.- 'O' O 0 0 0 0
- - -~
55h 0 0 0 0 0 0 0 ill ED SW 0 0 0 0 0 0 0 .. WSW 0 0 0 0 0 0 0
~~ ~~~
h 0 0 0 0 0 0 0-m 2 kNW 0 0 0 0 0 0 0 _ _ d 24t hW 0: .0 0- 'O O O O
?$ - ' - -
W hhh 0 0 0 0 0 0 0 w ifps TOTAL 0 0 0 0 0 0 0 d' l
h -' PERI 005 0F CALM (HOURSl- O g . _ _ .
N 54 , b a & M . . _ s
- _ - - _ _ _ _ _ _ . _ - _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _--__
FLORIDA POWER CORPORATION WING SPEEC AND DIRECTION SUFMARY [] THIS REPORT INCLUDES DATA COMPILEC DURING THE FOLLOWING PERIODS -
;iTTKilNGo-
~
(i . STARTING 7 6 DING.. ENCING II DAY- ' JHOUR: + :s D A Y.? HOUR X '._..-.;- l . _. ~ ~. ... . . . . _ . . 44i II} 287 8 288 8 71 . _ _ _ . ITi 291- ^21 292 18 R _ . _
.10 E 315 8 316 2 IS
.i3 1 OATA MISSING FOR DAY ;315.- HOUR 18 is! 322 3- -323 1 _ _ _ _ _
li 17 ii 330 10 330 21 __ 11 -
.c<
12 0; . [fi "331 214 332' 14- _. I 22 5 5 346 12. 347 1 Ei .
-DATA MISSING FOR DAY ' 346 : . HOUR 16 p .- .
~~~
Es 350 10 350 15 ai bi 3 ff0 22. 351. 8 k, as . _ - . - . . - . . .
. .l ii si 37 350 11 .359~ 14 Si: - .
Gil CATA MISSIhG FOR DAY 359'- HOUR 4 E 363 12 364 10 [5 363 - H0lTR l8-
!43! CATI ~MIT5T W FUR DAY I47 Ti - . _ - - . -
HOURS OF FISSING DATA - 4 m p q . . _ . . _ _ _ _ U be f 47- _ , 48 J
TABLE V-3 1] ll. .. , . . .
. , , , ,, b .[: . , . .,
T ;, ,cFLORIDA* POWER 4 CORPORATION ~ 3 14 HOURS AT EACH WIND SPEE0 AND DIRECTION fi fi PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 7 . . T- STABILITY.. CLASS - A. 9} m ELEVATION - 33 FT. i ' E WINO WIND SPEED (MPH) ul- DIR- 1 4 8-12. 13-18 19-24 .24+ TOTAL g - - 3 . _ __ _ : ___ .____ ____ _____ q g; 16 N 0 10 4 0 0 0 14 ! 7 3 NNE O 6 12 3 0 0 21 ! ib EL . NE 0: 5f 113 '5- 0 0 23 li > 22 EhE 1 8 41 18 C G E8. l 32 31} E O 6 20 54 1 0 81 f bs . 7 ESE: 0 11 2 '. 4 0 0 a r17 0 13 bs 5E o 1 6 6 0
$ 5 3 5 0 13 E SSE O O _ . .
3: , 0' 5 - O' 0? '9 1.. 1 11 37 9 4 2 1 10
-~~
t 55W 0 2 1 he j SW 0 11 13 6 0 0 30 Eisl IIE
- WSW 0 10 14 4 0 0 .28
[3] 9 0 3 2-- ~~~~~~ ~ ~ ~ ~ c h a 9 17 6 0 Ti E WNW 0 4 18 7 1 0 30 .-- 43. E NW 0: 5 10: 3 9 2 29 4 4$f ~ - 46 Nhh 1 3 7 8 4 0 23 N us TOTAL 2 81 192 132 23 3 433 . a n . fiil PERIODS OF CALM (HOURS) - 12 _ {} 5si _
~
55 e E _ . _ _ _ _ - .
TABLE V-3 }L ' 7 + T, LFLORID'A] POWER CORPORATION';
,3 > 4 I4 HOURS AT EACH WIND SPEED AND DIRECTION f5 17 PERIOD OF RECORD ' JULY 1,1985 THROUGH DECEMBER 31,1985 ._._
l7
- - -B fi! , STABILITY CLASS 51 ~
in ELEVATION - 33 FT. II E WIND WIND SPEED (MPb) ~ - hs - DIR. 1-3 4-7. 8-12 13-18 .19-24 24+ T0'TAL E .... - - . . . . . . ._ .. .... _.. . .. T5i 16 N O 3 4 0 0' O 7 Ti E NNE 1 0 1 1 0 0 3
- 19) .
IiEI ' N E' :0 Jl 5 f51 2' [- 0 0' 12
- p. ,<
22 ENE O 4 9 8 0 0 21 T3 5 E 1 2 8 25 1 0 37 25 ' 0 0 13 E: 'ESE, j. 0 - L li 7 5 27!
- s SE O Z 0 1 0 0 3 29 SSE O 1 4 4 0 0 9 E
31 .. .
~
cS' 0 '2' 5' 3 0 0 10 ci . E 0 2 1~3 ~ ~ ~ '~ ~ ~ ~ bl 55W D 4 6 1 m u, E SW 0 7 8 2 0 0 17 . . . . . _ . . _ 371' Esi :WSW O 3 5 0 0 .0 8 y.
' - ~ ~
h 0 0 5 0 0 0' 5 [.c TE WNW 0 0 2 1 2 0 5 [5 ._ _._._.
!43,
. Nh! 0 I?- ,5- 14 1 3 24
~Q 2 ~
~~
46 NhW 0 2 2 3 1 1 9-
,. T1 196 H TOTAL 2 37 76 70 5 6 49 Udsi .
PERIODS OF CALM'(HOURS) - 7-U 54 . . - . . . _ , 55 ' t' - 5D U
'] TABLE V-3 1 . T _FLORIDAMPOWER:CORPORAT10h 1 l 3 HOUR $ AT EACH WIND SPEEC AND DIRECTION ! 4: T T PERIOD OF RECCR0 - JULY 1,1985 THROUGH OECEMBER 31,1985 _ 7 . T STABILITY CLASS' - .C T l to ELEVATION - 33 FT. j II i E WIND WIND SPEED (MPH) ~~ { is DIR .1 :4 ,8-12, 13-18 19-24 24+ -T0TAL g. I[ .* 16 N 0 0 1 0 0 0 1 Ti E NNE 1 0 1 0 1 0 3 19 . . .. ii - 'NE 0 '. 1. 2 -l
-! 6' . - ~0 0. .0 . 8 ii 22 EhE O 4 11 7 0 0 22
~i fi4} E 1 6 8 7 0 0 22 b51
.ESE ' 3 ; .5 0 0 9 0 1
- e SE O 3 3 1 0 0 7~ ~ ~
IN SSE O 1 4 1 0 0 6 E bi -- . Ei :S 0 '2 '4 . 4 10. 0- 10 ET' 5 55h 0 2 3 0' o O T~~~ ~~ Si Sk 0 9 5 1 0 0 15 E_ .. Oll r est - WSW. 0 6 4' 1 0 0 11 Gi! ' ~ ~ ~ ~ i40 h 1 3 2 0 0 0 6~ u 41 If kNW 0 0 3 4 0 0 7 43 Ei Nk ~.0 0 5 3 1 0 9 4 + a NNn 0 0 1 1 0 0 2 Ti E TOTAL 3 41 62 35 2 0 143 49 Q. sft PERIGOS'0F CALM (HOURS) - 6 is:
+.fE 54, 55I i N E
5E i
- _ - - _ - - _ - _ _ - _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - _ _ _ _ _ _ _ _ _ _
TABLE V-3 }L.
"i T - FLORiDAIPOWER CORPOR'ATION.
3 ~
. iel HOURS AT EACH WIND SPEED AND DIRECTION ii
[i PERIOD OF RECCRD - JULY 1,1985 THROUGH DECEMBER 31,1985 _ __ 11 II . STABILITY CLASS -D R . _ _ . _ . _ he ELEVATION - 33 FT. Iii Iii WIND WIND SPEED (mph) -~ ~~
- g. DIR 1-3 - . 4- 7 8-12 .13-18 19-24 24+ T0TAL i
ti 15 ' - 16 N O 6 8 1 0 0 15 Ti H NhE O 8 22 7 2 0 39 19l - , . . . . iij . NE .4. : 2 4 -' , . 3 7. . 5. 0 0 70 PT ~ ~~~ g EhE 3 25 40 20 0 0 88 I23 [fi E 4 18 39- 48 0 0 109 -
!:5
.0'
$l ESE. 0 10- 29 9 'O 48 fill 1g SE 1 10 21 3 0 0 35-'
29 E SSE O 8 13 9 1 0 31 --, 31 5 _S. -.1'- .- 18 '
.27 24 2 0 72 bl: ~ ~ ~ ~ - ~ ~ ~
i u 55w 2 24 24 6 4 -I 6~3 E H SW 2 37 17 19 1 4 80 2: . [s .- WSW 0 . 25 .13 5 1 0 44 ' Gi - ~ ~ '
.c h 0 8 13 0 0 0- 21~
Ti Ti Whh 1 12 14 6 5 1 39 _ _ . E 44 N W' 5 8' 20 5 7 1 46 Ti -.-_.__.._.4.,__.._. . . _ . . . Ti E TOTAL 23 248 346 177 26 9 829 d' - E si PERIODS OF CALM'(HOURS)'- 40-' E
.. s 3 54 ,
M e 52
] TABLE V-3 9 .
~
T_. . g. F LO RID A./ P OWE R[ COR P ORA T IO N. - 4 HOURS AT EACH WIND SPEEC AND DIRECTION I I T PERICD OF RECCR0 - JULY 1,1985 THROUGH DECEMBER 31,1985 7 i STABILITY CLASS ~- 'E' 9 io ELEVATION - 33 FT. II E WIND WIND SPEED (MPb) is : DIR- 1 >
. 4 :8-12 13-18.- 19-24 24+ . TOTAL U ... = .:...- ._,
- y. . : ..
15 16 N 5 21 26 2 2 0 56 II E NNE 2 43 26 6 1 0 78 19
. m 194 20 NE .' 2 0 . 7. 2 93 . _8 - la 0 21 2: EhE 27 91 67 32 0 0 2T7 3
5 E 24 46 99 38 0 0 207 -
!:s . .
Fi ESE! 6- 52: 35: 9 0 103
~ " - ~ ~ ~
5E 4 25 22 9 2- 0 6'2 s SSE 4 17 45 4 0 1 71 no bi . . . Ei . .S 3 20 19 '6 8- 0 56 E EJ 55h 3 la 11 2 1 5 40 2
$ Sh 4 30 19 7 4 1 65 _
37 s hSh- 2 28 9' 3 1 0 43 if
, , , g g __ _3.y _ __ _ . .. _ .
Ti fii khk 2 11 19 4 3 0 39 _ _ _ _ . . _ l43i G .' N W .- 5 15- -14 9 5 0 48 d ~~~ 4.s Nik 7 16 14 6 1 0 44 E Ti TOTAL 121 516 523 145 30 7 1342 _ R
,9
- sii : PERIODS OF' CALM.(HOURS) -- 56 _. _
is: JY P
!55 Ofa _
..s , ~
_]. TABLE V-3 s esa-*-W.
' 'fFLORIDIFPOWER[CCRPGRATION-n:p - ,
7 4 HOURS AT EACH WIND SPEED AND DIRECTION T - T PERIOD OF RECCR0 - JULY 1,1985 THROUGH OECEMBER 31,1985 17 f. It STABILITY CLASS - F 9l _....._ ic ELEVATION - 33 FT. Ti 5 WIND WIND SPEED (MPF) ~ ~
,isi -DIR < 1-3 : 4-7c 12- '13-18 19-24 24+ T0TAL
, D .: ,- iii - id N 2 6 5 0 0 0 13 iT U NNE 1 13 24 1 0 0 39 19I ' fist NEi 9' f30 k :.12 :- '4^ -0 0 55 ,
$E ~~~~
;22 ENE 25 43 10 8 0 0 8T IE s E 29 25 66 2 0 0 122 25 .
E ESE- :. 9 ? 11 7 - .29l 0. 0 0 55
~??
27" , . s SE 2 Il 7 0 0 0 22 29 E SSE 2 21 12 0 0 0 35 31 .
,,8'
~. '
E S '0 1 SI. 0 1. 0 10 Ti -. ----.. .- . C
$ SW 1 3' O O O O 4 37 . . ,. . ,
E WSW -0 .0 0" 0 0 0 0 Til ~~ '~~~~~ e h 0 0 1 0 0 0" l E Ti WNW 0 1 3 0 0 C 4 43 L NW- O' 'll '2- 0 0 0 3 45 ~~ e.s hhW 2 7 0 0 0 0' 9
~
. Ti
, 7i ' TOTAL 83 191 172 15 1 0 462 Gi v s:
si PERIODS OF CALM 4(HOURS) - .31 _
. 5I v 53 54 ._ .._ _
55 0 5 2 - - - 54 v
s, _. . _ . _ . .] TABLE V-3
>i . . ..
T FLORIDAlPOWER CORPORATION.
~
3 _ e hCURS AT EACH WIND SPEEC ANC DIRECTIOh 7 T PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 7 T [ STABILITY CLASS- -G 9 to CLEVATION - 33 FT. ii E WIhO WIND SPEED (MPH) isi . - DIR 1-3 7.- '8-12 .I.3-18 19-24 24+ flit ~AL g-15 16 N O 5 0 0 0 0 5 ii E NNE 2 4 1 0 0 0 7 19 is 'NE l7 ..7 1 0 0- 0 15 ii ~ 22 ENE 3 13 4 0 0 0 20 E fs} E 12 11 12 0 0 0 35 _ _ l261 ESE- '6 '6s '4 , 0 0: 0 16 g ~ ~ ~ ~ - ~ ice 5E 5 12 1 0 0 0 18~ ~ [2] is SSE 2 2 1 0 0 0 5 31 . is 'S'. ' 11- .. -0.' LO- 0' O O 1 3 - - ~ ~ g 55h 0 1 0 0 0 0 1
!ss SW 2 2 0 0 0 0 4
!E . _ _ __
l37! [isi .WSW 2 5- 0 -0 0 0 7
# 0
~ ~ - - "
- c. W 0 6 0 0 0 6 hhW 1 3 3 0 1 0 8
\" .
+w hk 0 ' 7. 2 0 0 0 9 45 kNW 0 2 0 0 0 0 1-~ ~ -- - !
9 [ii TCTAL 43 86 29 0 1 0 159
!a9 p..
v -m . FI PERIGOS'0F' CALM . ( H O U R S I ' '- 1 _ _ _ _ _ _ . _ _ . _ _ . . . Q 53 54 35 55
-] s TABLE V-4
, ,s ,. ., ... .., ....h--
~'
T ' 1 'FLORI.DA!P0WER(CORPORATION T < C 4 HOURS AT EACH WIND SPEEC AND DIRECTION T T PERIOD OF RECORO - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES 7 . . .. s_.. STABILITY CLASS: - A , 9 3 ELEVATION - 33 FT. 11 s HIND WIND SPEED (MPH) 3 -
.0IR 1-3 .
.4-7 12 13-18 .19-24 24+ TOTAL g . .. . . . . ._- .... ... . ...... .... .....
is 16 N 0 2 0 0 0 0 2 5 3 NNE' O 1 0 0 0 0 1 19 - g .
, N E' /0' [0 I.1 i 0 . 'O 0; 1 i ii 2: EhE O O 3 0 0 0 3 3.
fiil E O O 3 8 0. 0 11 _ i i,3 . k LESE- 0 :0; 10: l' O O 1
- p. -- '
b SE O O O o 0 0 0 - ~~~~~ 9 E SSE O O O O O O O 1 bi .. . .
~~l 5?, S' 10 ^0 1~ 0 0 0 1 l iD -
\
6; 55W o o o o o 0 0 ) 53! Q Sh 0 1 0 0 0 0 1 h WSW -0~ 0 0 0' O O O
}i-
~~~~~~~~~ ~ ~
n a o o 0 0 0 C Iii E hhh 0 0 C 0 0 0 0 43 N Nh 0- 'l 1 0- 5 0 7 W ~~~ g I hhW 0 1 0 0 0 0 1 l47 ps TOTAL 0 6 9 9 5 0 29 If - v u,- . . .. . . Til ' PERIODS OF CALM'(HOURS)- '- 0 __ vE 55 O ii Fe 56~ _ _ - - . - - - - - . - - . . . . .. a
r Of TABLE V-4 n . T ,
/ FLORIDA-. POWER; CORPORATION 3 _.
4 HOURS.AT EACH WIND SPEED AND DIRECTION T PERIOD OF RECCR0 - JULY 1,1985 THROUSH DECEMBER 31,1985 BATCH RELEASES 7 .-
~
STABILITY. CLASS ~ .. B ac ELEVATION - 33 FT. Ii E WIhD WIND SPEED (MPH) ~ - nac OIR 1-3 14- 7..- :8 13-18 19-24 -24+ T0TAL D . IE -
~ ~ ~ ~
i6 h 0 0 0 0 0 0 0 if E NNE O O O O O O C 19} ' 531 .' lNE:
;0 0D LO :0 .0 0 O 2i' 22 ENE O O 3 0 0 0 3 E
ii E O O 3 2 0 0 5 25 . ESE: . 0: c0 To ~1' 0 0' 1 [ ' 27 "- SE O O O O C 0 0 2_3 29 E SSE O O O O O O O 31 . . .. < , , E S -Or '0i 'OL
- 0 '. 0 0 C N 0 0 0 0 1 ~~~~
~ ' ' - - ~
Lul 55W 0 1 9 E SW 0 0 0 0 0 0 0 07 . . E WSW- 'O 10 0. 0 0 0 0 s ~ ~ ~ - ~ ~ ~ ~ c w 0 0 1 0 0 0 1 s
'li ii WhW 0 0 1 0 0 0 1 43
( 44 hk 0- 0 1- 4 0 0 5 is e hhh 0 0 0 0 0 0 ~ ~~ ~ -~~' 0 ( '~ E Ta TOTAL 0 0 9 8 0 0 17 49 . si PERIODS OF. CALM (HOURS) - 0 _. 52 54 O e [ g .- u.i
-] s TABLE V-4 L . . .. .: .. . . .. . l P- [h >
.FLDRID A : POWE R:l CORPOR AT IONi 3 .
4 HOURS AT EACH WIND SPEED ANO DIRECTION n 7 i PERIOD OF RECCR0 - JULY 1,1985 THROUGH OECEMBER.31,1985 BATCH RELEASES 7 i STABILITY ~ CLASS'-'C 9 to ELEVATION - 33 FT. Ii' E WIND WIND SPEED (MPH) is 0IR .1 .4-7 .8-12c 13-18 19-24 24+ TTiT AL g..
- - . . - ,3 ; .
Ii 16 N O O O O O O O 3 3 NNE O O O O O O O 19 E NE 'O' 102 1 ,0 0- 'O- 1 21
- ENE O O 2 0 0 0 2 i 3
E4' E O O 4 0 0 0 4 l25 . lEl 'ESE: 0- 01 0; O- 0 0 0 p_ - -
~ ~ ~ ~ ~ '
bal sE O O 0 0 0 0 0 f5
$ SSE O O 1 0 0 0 1 .
bi '
- 0. ~0' 0: 1 0 O 1 E.
S l h ssh a 0 0 0 0- 0 0~ ~l 9 Q Sk 0 0 0 0 0 0 0 37
]- 0 rl WSW 0 - O' O O- 0 C I
[s! . _ -.._._ _ ._._._ _ __. g g w l E WNW 0 0 0 0 0 0 0 4T
, F NW =0 0 2 1 1 0 4
' fisl ,
la hhw 0 0 0 0 0 0 e r.~ N E TOTAL 0 0 10 2 1 0 13
.n. ~7 v N0, PERIODS'0F CALM'(HOURS) - 0 I
- s:
05 >< ..
!ss OG W~ _ . . - .
mr j
)
] TABLE V-4 ~ '
;FLORIDAlPOWERTCORPORATI0h 3
4 HOURS AT EACH WINO SPEEC AND DIRECTION T T PERIOD OF RECCR0 - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH R_ELEA_S.ES 171 1 Is1 STABILITY-CLAST -'O l W 1 5 ELEVATION - 33 FT. l in iii WINO WIND SPEED (MPH) ~ 43; DIR 3' 4-70 8-12 13-18 19-24 24+ Td~TAL ip ____ _ ____ _ _ _ _ . . ____ . ____ ____ ____ _____ is ~ ~ ~ ~ 16- N O 1 0 0 D 0 1 l Ti 3 NNE O O 1 0 0 0 1
-O.
, NEL l.0 .. L2/ . 0 0 0 2 jy .
~ ~ ~ ~
g ENE O O 4 0 0 0 4~
- 23
% E O O 5 4 0 -
0 9 L21 ' 26 ESE. l0- < '0; 0 1 .- .0. 0 1 ii
- s SE O O O O O 0 0 f:9 El SSE O O O O O O O h 5 :o-
.0 -3 11 0 0 4 fiP ' ~ ~ ~ ~ ~ ~ "
{ 55W 0 1 1 0 0 0 2 ct
$ SW 1 0 1 4 0 0 6 El WSW 0 0 1~ 0 0 0 1 51
.c W 0 0 2 0 0 0 2-Ti 3 WNW 0 0 1 0 0 0 1 43\
Y Nh 'O O' 3 0 1 0 4 Ti ~ NNW 0 0 1 0 0 0 1~ ~~ TCTAL 1 2 25 10 1 0 .. 39 49 H s,,, 50' si P E R ICD S' 0F C AL M (HOURS'l - d _,
's ; 53 54 ,
y ~ _ 59
l s r l
'] TABLE V-4 h - h.
5FL0k!DA/POWdRiCORPORAT10Ni T ~ 4 HOURS AT EACH WIND SPEED AND DIRECTION
-s 7
i PERIOD OF RECCR0 - JULY 1,1985 THROUGH OECEMBER 31,1985 BATCH RELEASES _' STABILITY CLASS - lE - , 9 3 ELEVATION - 33 FT. 11 E WINO WIND SPEED (MPH) is t DIR. 1-3.- 4 12.- 13-18 19-2.4 24+ TOTAL y ____ . is N O 4 2 0 0 0 6 3 H NNE O 2 2 0 0 0 4 19 g NE 'Q. t2e W 'O O O' 6 21. 22 ENE O 3 7 2 0 0 l~2 E 5 E O 2 9 0 0 0 11 {l'5
- $i. : - .ESE ~0' 4
_.0 .. , .1- 3 O O
% 2 0 0 0 2
~
bs 5E O O f5 E SSE O 2 8 0 0 0 10 __ b1 E. S .;11: .4~ 5: 0 'O O 10 9 0 0 0 1-~
~
i 3 55W 0 1 0~ b.d Q Sk 0 1 2 0 0 0 3 in: Ei .WSW O' 1 0 0 0 0 1 9 ~~ c W 0 0 0 0 0 0 0~
'fi
$ WNW 0 0 3 0 0 0 3 0 0 4
.._. g hh. 0 0: 4. 0 45! ~
u Khh 0 1 2 2 C- 0 5 n 5 TOTAL 1 24 53 4 0 0 82 d. h PERIODS OF. CALM (HOURS)'- .0 _ _ _ _ , _ b: OE l54 f55! O EL b _ __ 60 4,
~, TABLE V-4 J
@ FLORIDA POWER CORPORATIch 13!
I4i h00RS AT EACH WIND SPEE0 ANO DIRECTION IT [i PERIOD OF PECCR0 - JULY 1,1985 THROUGH OECEMBER 31,1985 BATCH RELEASES l71 IE STABILITY CLASS -F fil t ELEVATION - 33 FT. iii Ig- WIND WIND SPEED (MPH) ~
~ ~ " ~ ~ ~
hr DlR 1-3 .4-7 8-12 13-18 19-24 24+ 'T0TAL n ---- ---- ---- ----. ---- ---- ---- ...-- G _ . _ _ _ . 9 E [iil hhE O O 4 0 0 0 4 ___ d NE O 1 0 0 0 0 1
- 20:
EF - ~ ~ ~ - - ' ~ - -
!22 EhE O 2 0 0 0 0 2 5
9 E O 2 5 0 0 0 7 m ESE O O 1 0 0 0 1 Ei l:3 5E O O 2 0 0 0 2-~~~~~--- E SSE O 1 1 0 0 0 2 bii E! S 0 2 1 0 0 0 3 E
~ 3 ~ ~~ ~
~ ~ '
1, g
. 55W 1 2 0- 0 0 ~~~0 E
Q Sh 0 0 0 0 0 0 0
.37\ .
3 WSW 0 0 0 0 0 0 0 5 lj w 0 0 0 0 0 0 ~~ ~~~0~-~~~~~~ 41)
% WNW 0 0 1 0 0 0 1
!431
- 9. hk 0 0 0 0 0 0 0
' d - ~-~~ ~ ~~
1 Nh h 0 2 0 0 0-- 0 ~2~~~ 5
% TOTAL 1 12 16 0 0 0 29 bol
(/ * [si' PERIDOS OF CALM (HOURS) - 0 ____ . _ _ _ _
'54 O si t' - - . _ . - _ .
61 a
O b , P] TABLE V-4
>i . .
O 2 FLORIDA-POWER CCRPORATI0h
.y 4 HOURS AT EACH WIND SPEED AND DIRECTION l T '
i T PERIOD OF RECORD - JULY 1,1985 THROUGH DECEMBER 31,1985 BATCH RELEASES , 7 { STABILITY CLASS -G l 9 ml ELEVATION - 33 FT. li l U hlND WIND SPEED (MPH) _ isi - :DIR' .1-3 4 12-.- 13-18. 19-24 24+ TOTAL Q . Ti , . 16 N 0 0 0 0 0 0 0' ii H NNE O O O O O O O h
~
, JNE 0- ,: 01 : O' .. -O' OL 0 0 ii 2: ENE O 0 0 0 0 0 0 3
El E O O O O O O O _ ESE 'O. '1' O O O 1
- g. '.0 - .
' - ~ - ~ ~
bs 5E o 0 0 0 0 0 0 I5 E SSE O O O O O O O bi
.E 5 0l 0; _0 0 0 0 0 E ~ ~ '
a 55W o 1 o o 0 0 1
.2 s El SW 0 1 0 0 0 0 1 Q- WSW 0 1 0 0 0 0 1 (9
j4c W o 0 0 0 ~o 0 0 ~ ~ - -- ~ ~ ~ ~~ l (~ E E kNW 0 1 0 0 0 0 1 NW 0 4 1 0 0 0 5 L. 45l 3 46 hhh 0 0 0 0 0 0 0 ~~~', g i
~E TOTAL 0 8 2 0 0 0 1C f
I.1 L:50 E PERIOuS OF CALM (HOURS)'- 0 - . _ - OE $4 \ SS OE Fi-sr --
i .. VI' TECHNICAL SPECIFICATION REPORTS l: Technical Specification Sections 3.3.3.8, 3.3.3.9, and 3.12.1.2.b requi re "j reporting ' out.~ of . specification conditions: in the Semiannual Radioactive Effluent . Release Report. There were no reports as . required by the above specifications for .the period of this report. i i 1 q q l e
)
.j l
l
.i i
63 1
E s
. .VII ODCM AND PCP CHANGES l
' Te'chnical Specifications Section 6.9.1.5.d requires reporting of changes to
' the Offsite. Dose . Calculation Manual (00CM) and the Process Control Program ~'
(PCP) .in the Semiannual Radioactive Effluent Release Report. l: .
' Revisions to the ODCM for the: period .of this'. report are ' included ~ in this , section. The changes are marked for. ease of' review.
The entire' Process ~ Control ' Program was revised and -is- included in- this' j l: section. i t i i I I l 64 1
1 l l- NUCLIDE ANALYSIS 1.2-1 l REACTOR BUILDING PURGE EXHAUST l l NUCLIDE' SAMPLE SOURCE LLDN(uC1/cc) A. Principal Gamma Emitters (a) Mn-54 lx10-4/lx10-Il Fe-59 1x10-4/1x10-Il Co-58 Pre-release grab sample for Batch ! lx10-4/1x10-Il Co Type release. Weekly Particulate lx10-4/1x10-Il ; . Zn-65 Filter Analysis for continuous (c) lx10-4/lx10-Il Mo-99 type release. lx10-4/lx10-Il Cs-134 lx10-4/1x10-Il Cs-137 lx10-4/lx10-Il Ce-141 lx10-4/lx10-Il i Ce-144 . lx10-4/lx10-Il K r-87 Pre-release grab sample for Batch lx10-4/lx10-6 Kr-88 type release. Noble. Gas monitor lx10-4/1x10-6 Xe-133 during batch and continuous releases 1x10-4/lx10-6 Xe-133m Grab sample within 2-6 hr. following lx10-4/lx10-6 Xe-135 - startup, shutdown or >15% RTP lx10 4/lx10-6
' Xe-133 change in 1 hr. lx10-4/lx10-6 q B. Iodine 131 Pre-release grab sample for Batch 1x10-l'2 {
type release. Weekly charcoal filter I and once per 24 hr for 7 days following startup shutdown or >l5% RTP change in I hr unless 1-131 concentration at j site boundary (10% 10 CFR 20 limit. ! l C. Tritium Pre-release Grab Sample and within lx10-6 l 12-24 hr following flooding of refueling canal and once per 7 days while canal is flooded. D. Gross Alpha Monthly Particulate Filter Composite 1x10-Il E. Sr-89 Quarterly Particulate Filter Composite Ix10-Il F.. Sr-90 Quarterly Particulate Filter Composite Ix10-Il (a) Other identified Gamma Emitters not listed in this table shall be included in dose and setpoint i calculations. l (b) The first value refers to the LLD for pre-release grab sample; the second value refers to the LLD for weekly Particulate Filter Analysis or the Noble Gas Monitor durirg continuous purge. (c) Reactor Building Purge is considered continuous af ter a minirnum of one Reactor Building volume has been released on a continuous basis (i.e., first volume is a batch type). REV.SKS 5
NUCLIDE ANALYSIS 1.2-3 i WASTE GAS DECAY TANKS NUCLIDE SAMPLE SOURCE LLD(b)(pC1/ml) '
-A.- Principal Gamma Emitters (a)
Mn-54 1x10-4/1x10-11 Fe-59 1x10-4/lx10-11 Co-58 1x10-4/1x10-11 Co-60 lx10-4/lx10-11 Zn-65 Pre-release Grab sample and 1x10-4/1x10-Il Mo-99 Weekly Particulate Filter Sample from RM-A2. lx10-4/1x10-Il Cs-134 1x10-4/lx10-Il Cs-137 lx10-4/1x10-Il Ce-141 lx10-4/lx10-Il Ce-l'44 1x10-4/1x10-Il K r-87.- lx10-4/1x10-6 K r-88 lx10-4/lx10-6 Xe-133 - Pre-release Grab sample. lx10-4/lx10-6 Xe-133m - . lx10-4/1x10-6 Xe-135 'lx10-4/lx10-6 Xe-138 lx10-4/1x10-6 B. Iodine 131 Pre-release Grab sample and 1x10-12 i Weekly Charcoal Filter from RM-A2. l I l (a) Other identified Gamma Emitters not listed in this table shall be included in dose and setpoint calculations. i I (b)~ The first value refers to the LLD for pre-release grab sample; the second value refers to the LLD for weekly Particulate Filter Analysis or the Noble Gas Monitor during continuous purge.
... REV S C N 5
"';.-_- - - - a :-w.--.u< - + + . , - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NUCLIDE ANALYSIS 4.2-1 REACTOR BUILDING PURGE EXHAUST NUCLIDE SAMPLE SOURCE LLD(b)(WCl/ml) A. Principal Gamma Emitters (a) , Mn-54 1x10-4/1x10-1I Fe-59 1x10-4/1x10-11 Co-58 Batch release particulate filter lx10-4/1x10-Il Co-60 for Batch Releases. Weekly lx10-4/lx10-Il In-65 Particulate Filter Analysis for lx10-4/lx10-Il Mo-99 continuous (c) type release. lx10-4/lx10-Il , Cs-134 lx10-4/1x10-11 Cs-137 lx10-4/lx10-11 Ce-141 , Ix10-4/lx10-11 , Ce-144 1x10-4/lx10-Il Kr-87 Pre-release grab sample for Batch lx10-4/1x10-6 Kr-88 type release. Weekly grab sample Ix10-4/lx10-6 Xe-133 for continuous type release. lx10-4/1x10-6 j Xe-133m lx10-4/lx10-6 j Xe-135 1x10-4/1x10-6 i Xe-138 1x10-4/lx10-6 I B. todine 131 Batch release charcoal filter for 1x10-12 Batch Releases. Weekly charcoal : filter for continuous releases. , C. Tritium ' Pre-release Grab Sample. lx10-6 D. Gross Alpha Monthly Particulate Filter Composite Ix10-Il
/
E. Sr-89 Quarterly Particulate Filter Composite Ix10-Il F. Sr-90 Quarterly Particulate Filter Composite Ix10-Il (a) Other identified Gamma Emitters not listed in this table shall be included in dose calculations. (b) The first value refers to the LLD for pre-release grab sample; the second value refers to the LLi for weekly Particulate Filter Analysis or the Noble Gas Monitor during continuous release. (c) Reactor Building Purge is considered continuous af ter minimum of one Reactor Building volumq have been released on a continuous basis (i.e., first one volume is a batch type). l
. REVISION 5
( i s NUCLIDE ANALYSIS 4.2-2 AUXILIARY BUILDING AND FUEL HANDLING AREA EXHAUST NUCLIDE SAMPLE SOURCE LLD(b)(uCi/ml) A. Principal Gamma Emitters (a) Mn-54 lx10-4/lx10-Il Fe-59 lx10-4/lx10-Il Co-58 Weekly Particulate Filter Analysis. lx10-4/lx10-Il Co-60 1x10-4/lx10-Il Zn-65 lx10-4/lx10-Il Mo-99 . lx10-4/1x10-Il Cs-134 1x10-4/1x10-Il Cs-137 lx10-4/1x10-Il
' Ce-141 lx10-4/1x10-Il
'Cc-144 lx10-4/1x10-Il K r-87 Monthly Grab Sample. lx10-4/lx10-6 Kr-88 -
lx10-4/lx10-6 Xe-133 lx10-4/1x10-6 Xe-133m
^
lx10-4/1x10-6
. Xe-135 1x10-4/1x10-6 Xe-138 lx10-4/lx10-6 B. Iodine 131 Weekly Charcoal Filter Analysis. lx10-12 C. Tritium MontNy Grab Sample. lx10-6
~
D. Gross Alpha Monthly Particulate Filter Composite Ix10-Il E. Sr-89 Quarterly Particulate Filter Composite Ix10-Il F. Sr-90 Quarterly Particulate Filter Composite Ix10-Il j (a) Other identified Gamma Emitters not listed in this table shall be included in dose calculations. (b) The first value refers to the LLD for pre-release grab sample; the second value refers to the LL@ for weekly Particulate Filter Analysis or the Noble Gas Monitor during continuous release. l REVISION 5
NUCLIDE ANALYSIS 4.2-3 WASTE GAS DECAY TANKS NUCLIDE SAMPLE SOURCE LLD(b)(uCi/ml) A. Principal Gamma Emitters (a) ' Mn-54 1x10-4/1x10-11 Fe-59 '1x10-4/1x10-11 Co-58 1x10-4/1x10-11 Co-60 1x10-4/1x10-11 j Zn-65 1x10-4/1x10-11 Mo-99 Weekly Particulate Filter sample (from RM-A2) lx10-4/lx10-Il Cs-134 1x10-4/lx10-11 Cs-137 lx10-4/1x10-11 Ce-14f 1x10-4/lx10-11 Ce-144 1x10-4/1x10-11 Kr-87 1x10-4/1x10-6 Kr-88 1x10-4/lx10-6 Xe-133 Pre-release Grab sample lx10-4/lx10-6 Xe-133m lx10-4/!x10-6 I> Xe-135 1x10-4/1x10-6 Xe-138 - 1x10-4/1x10-6 , l B. todine 131 Weekly Charcoal Filter (from RM-A2) lx10-12
)
(a) Other identified Gamma Emitters not 11sted in this table shall be included in dose and setpoint calculations. (b) The first value refers to the LLD for pre-release grab sample; the second value refers to the LLD, ' for weekly Particulate Filter Analysis or the Noble Gas Monitor during continuous release. 3EVIS10N 5 i
TABLE III GASEOUS AND LIQUID EFFLUENT REPRESENTATIVE SAMPLING RELEASE TYPE REPRESENTATIVE SOURCE OF SAMPLING EFFLUENT BATCH CONT. METHOD Evaporator X 3.1-1 Condensate Storage
. Tanks Laundry. and .X 3.1-1
, Shower Sump Tanks SScondary X- X 3.1-1, 3.1-2 Drain Tanks Plant Condensate X 3.1-2 Waste Gas X 3.13 Decay Tanks Reactor Bldg. X X 3.1-4 Purge Exhaust Auxiliary Bldg. X 3.1-4
& Fuel Handling <
Area Purge Exhaust Reactor Bldg. X 3.1-5 with Both Personnel and Equipment Hatches Open l
- 3, . REV S ON 5 r
REPRESENTATIVE SAMPLING METHOD NO. 3.1-5 (REACTOR BUILDING WITH PERSONNEL AND EQUIPMENT HATCH OPENED) To obtain representative samples and previde reasonable monitoring of the Reactor Building atmosphere during periods when the personnel and equipment hatches are both open, the following activities will be conducted or in progress: o The Reactor Building purge exhaust fans are operational and the make-up fans are shut down; o The initial Reactor Building purge beginning the outage has been running for at least 7 days; or if the purge was shut down during the outage, it must be in operation for at least 8 hours prior to having both hatches open. o- The Reactor Coolant System is degassed and depressurized; o The Reactor Building recirculation system is continuously monitored by RM-A6 (all channels); or air samples are taken daily on each elevation of the Reactor Building;
- o A particulate sampler is Installed and operating on the Reactor Building refueling floor; o Air samples are taken as jobs in the Reactor Building necessitates (i.e., jobs that risk increasing the particulate, iodine, or gaseous concentrations of radionuclides in the Reactor Building);
I o Flow direction at the hatches will be monitored, and samples taken if flow is out of the building through the hatches.
Reference:
Telecon-FPC (Dan Green, Dan Wilder) to NRC (Charles Willis) dated 03/15/85 at 0930;
Subject:
Personnel and Equipment Hatch Openings. I I J
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EV S.0 \ S i
l Table 5.1-1 Environmental Radiological Monitoring Stations Locations i DIRECTION DISTANCE STATION LOCAT10N FROM PLANT FROM PLANT (mi)- C04 State Park Old Dam on River ENE 6.3 near road intersection C07 Crystal River Public Water Plant ESE 7.5 C09 Fort Island Gulf Beach 5 4.0 C10 Indian Waters Public Water Supply ESE 5.9 Cl3 Mouth of Intake Canal WSW 3.4 C14H Head of Discharge Canal NW 0.1 C14M Midpoint of Discharge Canal W l.2 Cl4G Discharge Canal at Gulf of Mexico W 2.8 C18 Yankeetown City Well N 5.2 C19 NW Corner State Roads 488 & 495 ENE -8.5 C29 Discharge Area N 2.0 C30 Intake Area WSW 3.6 C40 Near N.E. Site Boundary E 3.5 near excavated pond & pump station C41 Onsite meteorological tower SSW 0.4
.C46 North Pump Station N 0.4 C47 University of Florida, Gainesville NNE 52 C48A Onsite North of CR 4 & 5 N' O.8 C48B Onsite NNE of CR 4 & 5 NNE 0.8 80 -
REV S M 5
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k Vwn r.m;:~. m axw ..., cmy'~nr'n.M , 4 CRYSTAL RIVER UNIT 3 PROCESS CONTROL PROGRAM
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N. i l Approved by: , dfies/ Rad Supt. DaSe*:
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- Approved by: 'N-PRC'. Chairman Date: \'2.- \~">- $7 s.
, Approved by:
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.Nilclndr Jf2' ant Mgr[ '
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* - .. Date: /,2///,/w- - t
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TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
. .. ... ... . . . .... .. .. . . . . . ... 1 2.0' REFERENCES . . . ....... . .................. 2 3.0 REGULATORY REQUIREMENTS. . . . . .................. 3 4.0 ADMINISTRATIVE CONTROLS. ...... . .. . .. ... . . . . .. . 5 4.1.. Responsibility / Revisions. . .................. 5 4.2 Reporting . . ... ... . .................. 5 4.3 Documentation . . . .. .. .................. 5 4.4 Definitions . . . . . . . . . . . . . . . . . . . . . . . . . . 5-5.0 SOLIDIFICATION . . .. .... . .................. 6 5.1 System Description. . . . . . . . . . . . . . . . . ... . . . 6 5.2 ' Process Description . . . . .................. 6 5.3 Process Control Program Testing . . . .. . ... . . . . . . . 8 5.3.1 Process Testing. . . .................. 8 5.3.2 Test Frequency . . .. .................. 9
(, _,' . 5.3.3' Acceptance Criteria. . . . .. . . . . . . . . . . .. . 9 L.. < 5.3.4 Corrective Action. . . . . . . . . . . . . . . . . . . . 9 5.3.5 Reporting. . .. . . . . . . . . . . . . . . . . . . . 10 6.0 DEWATERING . . . . ...... .. ....... .., . .. .. . . 10 6.1 System Description. . . . . . . . . . . . . . . . . . . . . . . 10 6.2 Process Description . . . .. ... .. ... . .. . . . . . . 11 6.3 Dewatering Program Testing. . . ... . . . .. .. . . . . . . 12 6.3.1 Sample. Testing and Frequency . . ... . . . . . . . . . 13 6.3.2 Acceptance Criteria and Corrective Action. . . . . . . . 13 6.3.3 Reporting. .... . .. .... . .. . . . . ... . . 13 7.0 SHIPPING . .. ... .. . . . .. . . .. .... .. . . . . . . . 13 l I r 5 REVISION 0 4 1
1.0 ' INTRODUCTION b The Process Control Program (PCP) is provided to support the implementation of the Crystal / River Unit 3 Radiological Effluent Technical Specifications. The
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. PCP contains~ the methodology and boundary conditions to assure that. all activities related to the solidification of radwaste are regulated and directed. toward a satisfactory result.. The PCP also contains the overall guidance for the dewatering of radioactive bead resin to meet the disposal criteria of the low-level radioactive waste burial facilities.
The PCP 'is . not. intended to be used as an operating waste procedure. This document satisfies the requirements'of Technical Specification 3.7.13.4.
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t O-9 REVISION 0 : t i
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2.0 REFERENCES
U 2.1.' NUREG 0472, ' Radiological Effluent Technical Specifications for PWR's" 2.2 VP 101, " Packaging, Storing, and Shipping of Radioactive Materials *
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2.3 WP 102, " Radioactive Shipments Certificates of Compliance" 2.4 WP 201, " Processing with the Nuclear Waste Demineralized System" 2.5 WP 202, " Liner Dewatering Leg Construction" 2.6 WP 301, " Radioactive Waste Solidification" 2.7 OP 413, " Waste Drumming System 2.8- OP 601B, ' Secondary Resin Liner Dewatering" 2.9 SP 743, ' Solidification Test Batch Verification Program" 2.10 Bartlett PCP
' 2.11 CNSI Bead Resin Dewatering Procedure ,
_ 2.12 .10 CIR 61, " Licensing Requirements for Land Disposal of f' Radioactive Watte" 2.13 Crystal River Unit 3 Technical Specifications 2.14 South Carolina Department of Health and Environmental Control, Radioactive Materials License #097, Amendment #34 O j lECl0N O
3.0 REGULATORY REQUIREMENTS
.3.1 Technical Specifications 3.7.13.4 l
The. solid radwaste system shall be used in accordance with a Process Control j Program to process wet radioactive wastes to meet shipping and burial ground requirements. The Process Control Program shall be'used to verify the solidification of at l least one representative test specimen from at least every tenth batch of each ] type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, and boric acid solutions). 3.2 Technical Specification 6.14
]
The PCP shall be approved by the Commission prior to implementation. Licensee initiated changes to the PCP:
- a. Shall be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.
- b. Shall become . effective upon review and acceptance by the Plant Review Committee.
3.3 Technical Specification 6.9.1.5 (d) The Semiannual Radioactive Effluent Release Report shall include a description 7 of any changes to the Process Control. Program (PCP), the Radioactive Treatment Systems, the Offsite Dose Calculation Manual (ODCM), as well as a listing of new Environmental Radiological Monitoring Program dose calculation location changes identified by the land use census made during the reporting period. 3.4 10 CFR 61.56, ' waste Characteristics * (a) (2) Liquid waste must be solidified or packaged in sufficient absorbent saterial to absorb twice the volume of the liquid. (a) (3) Solid waste containing l'iquid shall contain as little free-standing and noncorrosive liquid as reasonable, but in no case shall the liquid exceed it of the volume. (b) (2) Notwithstanding the provisions of (a)(2) and (3), liquid wastes or wastes containing liquid must be converted into a form that contains as little free-standing and noncorrosive liquid as is reasonably achievable, but in no case shall the liquid exceed it of the' volume of waste when the waste is in a container designed to assure stability, or 0.5% of the volume of the waste for waste processed to a stable form. j lEViC!ON O _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ ___.m_.__m___m__
l f' . l 3.5. South Carolina Department - of Health and Environmental Control, i O Radioactive Material License #097, Amendment 34. s.;./ - 26.A. Unless otherwise specified in this license shall not receive any liquid radioactive waste regardless of chemical or physical form. Solidified radioactive waste shall have no detectable free-standing liquids. For purposes of this condition, the terminology
'to detectable free-standing liquids' means one-half percent (0.5%) by waste. volume of noncorrosive liquids per container.
B. In lieu of the requirements of paragraph A above, solidified waste containing noncorrosive liquids in excess of one-half percent
-(0.5%) by waste volume, and' less .than one percent (1.0%)
noncorrosive liquids by waste volume, may be received and disposed of in high integrity containers approved by the Department.
- 29. Ion exchange resins and filter media may be received in a dewatered form for transportation and subsequent burial provided that the requirements of Conditions 26 and 31 are met. .!
- 31. Ion exchange resins and filter media containing isotopes with !
greater that five (5) year half-lives having a specific activity. of all these isotopes of 1 microcurie per cubic centimeter or greater must be stabilized by solidification. However, in lieu of solidification, the Department will authorize disposal of these waste forms meeting the free-standing liquid requirements of Condition 26' in approved high integrity containers or other appr'oved methods of stabilization. {J d i J EVIGiON 0 _4_
.- a-~._. -- . _ . _ .- ,
4.0 ADMINISTRATIVE CONTROLS 4 .1. Responsibility / Revisions Changes to the Process Control Program ,PCP) ( are the responsibility of the Chemistry and Radiation Protection Superintendent. Technical Specification 6.14 stipulates the required approvals necessary to modify the Process Control Program prior to implementing any changes to the process (See Section 3.2). 4.2 Reporting Changes to the PCP are submitted to the Nuclear Regulatory Commission in the next Semiannual Radioactive Effluent Release Report as per Technical Specification 6.9.1.5 (d). Reporting of nonconformances are to be done in accordance with the applicable Plant procedures. 4.3 Documentation All documentation associated with the verification of the Process Control ! Program is controlled in accordar.ce with the appropriate ' implementing procedures. 4.4 Definitions Batch - (1) For sampling or processing, a batch is the largest homogeneous volume of waste that has been recirculated and controlled as per the PCP. .._- (2) For solidification testing, a Ltch is taken to be a disposal ! container (i.e., 55 gallon drums, etc.) utilized in the solidification of the waste. l 9 2 4 . lEVlS!CN 0 U 4
t . p 5 . 0. SOLIDIFICATION -I.
- d. 5.1- Systen Description ,
'5.1.1 The system utilized at Crystal River' Unit 3, for the solidification of wet radioactive waste, consists of a sixing station with associated piping, controls and monitoring equipment. The waste is solidified in 55 gallon drums in accordance with WP 301, ' Radioactive Waste Solidification".
The waste stream is. measured.into the receiving 55 gallon drum while the mixer is. in operation and any retreatment chemical' may be added to conform to the Process Control Program requirement for proper solidification. The Modified Portland Cement ;(MPC-1) is added to the waste until- the required ratio is reached per ' the PCP requirement. The actual sequence of additions may vary per the process test results. 5.1.2' Resin Solidification The primary resin transferring system for solidification is contscued by OP , 413, ' Waste Drumming System." This Operation Procedure gives, the valve and pump lineups, and provides an overview of the resin flow path from the spent resin tank to the shipping container and the return path of the excess water. The resin can be recirculated in the spent resin tank (7000 gallon capacity) using the resin slurry pump to obtain a homogenous.aixture. Decant water can be added to the suction side of 'the pump .to insure that the proper water to resin ratio is obtained for transfer to the solidification container. Resin transfer . from the spent resin tank to 'the solidification apparatus is s made using the resin slurry pump. Water is decanted before solidification and returned to the spent resin tank. 5.1.3 Liquid waste Solidification FPC procedural guidelines concerning the transfer of liquid waste for solidi-fication are given in Op 413, ' Waste Drumming Systea.' This procedure gives an overview of the flow paths of liquid wastes from the various tanks to the solidificat,lon apparatus. Liquid wastes can be stored in two concentrated boric acid storage tanks (CBAST - 7000 gallon capacity each) and in two' concentrated waste storage tanks (CWST . - 7000 gallon capacity each). The CVST's are utilized as concentrated boric acid storage tanks whenever possi-bla. Waste is transferred to the solidification apparatus utilizing the waste transfer pumps at the CBAST's or the CWST's. 5.2 Process Description The solidification system is designed to solidify radioactive waste including, boric acid waste, evaporator bottons,. ior exchange resin, sludges, oils and
, various solids for encapsulation and immobilization. The waste products are solidified using the commonly available Portland I cement modified with the necessary process additives. The Modified Portlant Cement (MPC-1) and addi-tives~ can be adjusted to optimize the waste to cement ratio or to perform the -
solidification in a specified manner. _g , U D REVISION 0 1 I
The reactions from cement and waste form very stable hydrates from the chemical combination of calcium, silicon, and aluminium with oxides. The s reactions are exothermic and are not readily produced unless strong alkalines are present at a pH of 11 to 12. Other chemicals in the waste stream may inhibit or accelerate the set. These chemicals must be controlled by modifying the additives to ensure a controlled, homogenous, free-standing monolith, dry, and with the final product able to resist penetration when probed by a firm object. At the conclusion - of each transfer of waste, the piping forward of the recirculation line must be flushed. This is necessary to reduce personnel exposure, plugging of the pipes, and pipe corrosion. 5.2.1 Sampling The waste tanks sho'ad be recirculated to obtain a representative, homogenous sample. A volume of waste is considered to be homogenous when three (3) tank-volumes have be:,a recirculated on an isolated batch of material. The waste tanks should te. maintained'on recirculation yntil sampling and solidification are complete. If the previously analyzed waste tanks receive additional material,' the new mixture must be recirculated, resampled, and reanalyzed. The following samples and analyses are necessary to prepare waste for solidification and disposal:
- Sample for isotopic analysis and curie content g
- Sample for chemistry parameters and PCp test. solidification 5.2.2 Chemistry of Waste Products !
l Chemistry analyses are necessary for successful solidification since the process can be dependent on specific lons, pH, and oil. Cement solidification of wastes requires the consideration of the parameters listed below: Chlorides Oils j Boron Organic Solvents l Ammonia Decontamination Solutions Soap / Detergents N'eutralizer Compounds Waste chemistry should be collected and analyzed as per section 5.2.1. I I O REV S ON 0 L f i - - _ - - - - - - _ .-
'5.2.3 Waste to. Cement-Ratio The' waste to cement ratio will . vary due to the. chemistry of the waste stream.
The approximate ratio of solidification media to waste is listed in the
..e following table:
Binder / Media Waste Type Waste: Media Cement- Evaporator Bottons 2 :'1 Cement Ion Exchange Resins 2.5 : 1 Cement 011 2: 1 5.2.4' Cure Time The cure time for the solidification of waste will vary depending on the type waste being processed. The completion of the' solidification process may be verified by monitoring the initial curing process temperature rise and fall; thus indicating a safe, capable product.'.As an. example,..the initial cure. time for a test sample is'approximately 30 minutes to 4 hours, and for full scale solidification approximately 6 to.24 hours. 5.3 Process Control' Program Testing 5.3.1 Process Testing 5.3.1.1 Initial Process Testing
' /~' . Prior - to solidification', each. batch 'of homogenous waste is to be tested to
(- assure that proper solidification of the waste will result. The* process tests are to include all additives and - the appropriate Modified Portland Cement (MPC-1) volumes mixed and adjusted as described below: Additive volume and constituents measured and recorded
- Modified portland cement volumes measured and recorded Waste volume measured and recorded
- Waste pH adjusted to within 10.5 to 11.5 range and recorded
- MPC-1 addition with mixing
- Appropriate cure time (30 minutes or more)
- Testing of sample as per Section 5.3.3 and results recorded l j
Several' tests should be performed on the same waste stream, varying the j additives and 'MPC-1 mixes in. order to develop. the best end product. 1 Evaluation of the test specimen for waste to binder ratio, free-standing water and maximum hardness should be made to determine the appropriate matrix. The selected test sample should be repeated for verification of performance. Full scale solidification would. commence following the evaluation of sample tests j against the Acceptance Criteria of Section 5.3.3. 5.3.1.2 Solidification Testing
'During full scale solidification, a representative sample of waste is to be l solidified as per the FCP requirements at the frequency specified in Section
.gs 5.3.2.2. The test specimen is to be evaluated against the Acceptance Criteria of Section 5.3.3.
R:V Sl0N O ; 5 l
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.5.3.2 Test Frequency 1
5.3.2.1 Process Test Frequency 'f A process test solidification.shall be made prior to full scale solidification to. determine ratio.s and additives as per Section 5.3.1.1. 5.3.2.2' solidification Test Frequency The . PCP shall' be used to verify the solidification of -at least one (1) representative ~ test : specimen from every tenth batch of each type of _ wet radioactive waste. 5.3.3 ' Acceptance criteria ; l
- SP 743, ' solidification Test Batch . Verification Program," stipulates the l activities and documentation necessary to verify acceptance of solidified !
waste.. The. solidified waste acceptance criteria is verified by: q i
- a. Visually inspecting for defects in the structure. i
- b. Uniformity in color and dentity.
- 4. No~ free-standing liquid ((0.5% of total waste volume).
- d. Free-standing monolith,
- e. Af ter 24 hours from solidification, the final cured product shall resist penetration when p'tobed by hand wi'h a spatula or firm object (>50 psi) .
gv If any portion ' of the specimen f ails to. pass the Acceptance criteria, the applicable actions of.Section 5.3.4 aust be met. , 5.3.4 Corrective Action
- a. If the initial test specimen from a batch of waste fails to verify solidification, representative test specimens from each consecutive batch of-the same type of wet waste shall be collected and tested until at least 3 consecutive initial test specimens demonstrate solidification. The process and/or additives shall be modified as required, as provided in l Section 4.1, to assure solidification of_ subsequent batches of waste.
- b. If any test specimen fails to verify solidification, the solidification of the batch under test shall be suspended until such time as. additional test ..
specimens-'can be obtained, alternate solidification parameters can be determined in accordance with the Process Control Program, and a subsequent' test verifies solidification. Solidification of the batch may then be resumed ' using the alternative solidification parameters determined by the Process Control Program.
- c. With installed equipment incapable of meeting Technical Specification 3.7.13.4 or declared inoperable, restore the equipment to operate status or j
- provide for contract capability to process wastes as necessary to satisfy ;
p all applicable transportation and disposal requirements.
.REV8l0N 0 n _ _ _ _ _ _ _ _ . _ _ ____
1 I 4 ) l . . 5.3.5 Reporting The reportingof nonconforming.results of the solidification process is to be *
.done in accordance with Section 4.2.
L :6.0 DEWATERING 6.1 System Description The. bead resin dewatering systems utilized at Crystal River Unit 3 are comprised ~ of two separate processes. One for the secondary cycle condensate resin and the other for primary or radioactive waste ion exchange resin, j Secondary Cycle Condensate Resin Dewatering System
.This system ~1s utilized to - dewater bead resin from the secondary cycle condensate domineralizer system in accordance with op 601 (B). The condensate desineralizer system is comprised of ~ holding vessels that provide full flow demineralization 'of the ' secondary cycle water. The resin - in . each
- demineralized vessel, once expended, is transferred to a shipping container
-for dewatering and' disposal.
The expended resin is transferred into a ' shipping container that has been prepared with dewatering lines, and a tube called a 'QC tube' for verification
.of dewatering performance. The dewatering lines are designed to remove the water from the botton . of the container via a network of tubes that are connected to a center dewatering line. The QC tube .is a separate line that .A terminates at the bottom edge of the container.
k.) The dewatering manifold and QC tube are constructed of corrosion resistant material and of sufficient length to reach the bottom of the container, and extend through the access port at- the top. The bottom legs of the manifold are modified (slits, holes, etc. ) to allow. flow to enter the entire length.of the pipe. The modified pipes are then covered with a filter material with a mesh size that: precludes the entry of resin beads. The piping is connected together and to a vertical line in such a way as to provide adequate coverage of the container floor. The openings in the manifold legs must face the floor of the container. The QC tube is secured along the center post of the manifold and angled across the bottom legs to a distance equal of the radius or corner measurement of the container. The outside of the container is marked to locate the QC tube end point af ter the dewatering unit is outlined
;in.0p 601 (C), ' Liner Dewatering Leg Construction '
The ' vacuum source for the dewatering is supplied by a portable vacuun pump. The overpressure of the containers is accomplished using station / instrument air or a portable air pump. 1
~
REV SION 0
I Primary and Radwaste Resin Dewatering Systems J This system is utilized to dewater bead resin from the primary plant clean up system or the radioactive waste processing system. The primary plant clean up resin is utilized internal to the reactor water clean up system and must be transferred to a shipping container prior to dewatering. The radwaste processing resin may be housed in its own shipping container or transferred for dewatering. The expended ion exchange resin is transferred, if n.ecessary into a container to be used for shipment and burial by means of resin transfer pumps. Prior to resin addition, the receiving container is outfitted with dewatering devices that allow for the removal of free-standing water. A primary dewatering tube with its distribution legs is located in the center of the container. A much smaller secondary dewatering line, if available, is also connected to the dewatering header for removal of the final water volumes and verification of dewatering criteria. The disposal container has level alarms to monitor filling operations, and visual observations are possible. All lines are flushed to the container following any resin transfer for dewatering. The dewatering process is performed in accordance with OP 413, " Waste Drumming System.' The vacuum source for dewatering is supplied by a portable pump. 6.2 Process Description 1 Secondary Cycle Condensate Resin Dewatering System The shipping container is filled to the proper level with the resin slurry in accordance with OP 601. Utilizing the dewatering line in the container, the resin is initially dewatered as per OP 601. The remaining water is removed from the container via vacuum pumps and overpressurization as follows:
- a. The container is pressurized (~2 psig) and dewatered utilizing the dewatering line'for a minimum of 5 hours.
- b. The container is depressurized and allowed to settle for at least 1 hour.
- c. Steps a la b are repeated two additional times with dewatering being performed for a minimum of 1 hour instead of 5 hours.
- d. The container is then blown down with a slight overpressure of compressed air (~ 3 psig) for a minimum of 4 hours,
- e. The container is allowed to settle for a minimum of 1 hour.
- f. The blowdown is repeated two additional times for 1 hour each time.
- g. The container is then titled on a support frame and allowed to settle for at least i hours.
- h. The QC tube is connected to a vacuum pump and run for at least 3 hours.
Hourly volumes are measured and compared against the acceptance criteria in OP 601(B). O WSION O < l
s :
..~ i. If,the acceptance criteria is met, dewatering is complete, i
\ ' " .
. j. If the ' acceptance criteria is not met, the dekatering process must. be repeated.
1 If the acceptance criteria in Section 6.3.2 is met, the container is sealed, .f labeled, and placed in a storage area for shipment.
~
Primary or Radwaste Resin Dewatering System 1' The shipping container is filled to the proper level with the resin slurry. Utilizing the-primary dewatering lines in the container, the water is removed from the vessel via a vacuum pump as follows: I
- a. .The first pump down utilizes the primary dewate' ring line. (8 hours !
ninimum and record times of' pumping.)
- b. A settling period follows. (8 hours minimum.)
- c. A second pump down utilizing the primary dewatering line is performed. '(8 hours minimum and record times of pumping.) .
- d. Another settling period follows. (8 hours minimum.)
- e. A third pump down utilizing the secondary dewatering line, if available, is accomplished. (8 hours minimum and record pump times.)
f.. The remaining volume of water is collected and measured as p'er section 6.3.1.
- g. An evaluation of the volume of water collected against the acceptance criteria of Section 6.3.2 is performed. ,
- h. If the acceptance criteria is met, dewatering is complete.
- i. If the acceptance criteria is not met, the vessel is allowed to settle for a minimum of 8 hours and the third pump down process is repeated until the acceptance criteria is satisfied.
Once the acceptance criteria of Section 6.3.2 is met, the vessel is sealed, labeled and stored for shipment offsite. 6.3 Dewatering Program Testing i 6.3.1 Sample Testing and Frequency Following the dewatering process, the water is measured on a volume basis for comparison against the acceptance criteria. Numerous measurements / evaluations may be necessary based on the results of the comparison against the acceptance criteria. O' REVIS.O NI O
d 6.3.2 Acceptance Criteria and Corrective' Action op 601(B),. " Secondary Resin Liner Dewatering," and' WP stipulates the . activities ~ and documentation necessary ..to verify acceptance . of dewatering
~
I criteria. The dewatered resin must meet ' the conditions . applicable to the co: stainer used for disposal as follows. 6.3.2.1 1%-Free-Standing Water er Less (High Integrity Container only) The ' acceptance , criteria for dewatered resins in High Integrity Containers. (HIC)' is .1% free-standing water or less (by volume) as specified in . Section -
-3.5, Items 29, 01 and 26 (B).
6.3.2.2 0.5%' Free-Standing Water or Less (Non-High Integrity Containers)
-The acceptance criteria for dewatered resins in containers that' do not meet i." . L the, requirement's for High . Integrity Containers (HIC) is 0.5% free-standing water or less (by volume) as specified in Section 3.5, Items 29 and 26 (A).
6.3.3 Reporting. The reporting of nonconforming results of the dewatering process is to be done
-in accordance with Section 4.2 7.0 ' SHIPPING The shipment of solidified and dewatered radioactive waste is controlled by Wp 101, ' Packaging, Storing and Shipping of ' Radioa'ctive Materials.* Activities
- t. and documentation of radioactive shipments'is maintained under this procedure.
REV Sl0N O J-
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,__,......e-l RETS MASTER FIL% l c ; ;
g', y Eff- 8sB } t : 1
.i x , ... ! %dd8 Power C OM POR AtiON February 26, 1986 3F0286-15 j
Dr., J. Nelson Grace ' Regional Administrator, Region Il Office of Inspection & Enforcement U.S. Nuclear Regulatory Connission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30323
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Semiannual Radioactive Effluent Release Report
Dear Sir:
Pursuant to Title 10, Code of Federal Regul atorys , Part 50.36a(a)(2) and Crystal River Unit 3 Technical Specifications, Section 6.9.1.5d, Florida Power Corporation's Crystal River Unit 3 Semiannual Radioactive Effluent Release Report for the period July 1, 1985 through December 31, 1985 is hereby submitted. Si ncerely, i G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management i GMF/feb Enclosure [ M
<t? 41 0 xc: . Director; Office of' Inspection and~ Enforcement (3) # e .s) N -
U.S. Nuclear Regulatory Commission d. C ' Attention: Document Control Desk Washington, DC 20555 I GEN ERAL OFFICE 3201 Th6rty.tourth street south e P.O. Box 14o42, St. Petersburg, Florida 33733 e 813-8665151 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - . _ _ _ _ _ - . _ _ _ _ .--__J}}