ML20099L298
| ML20099L298 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/31/1984 |
| From: | Fuller R, Mckee P FLORIDA POWER CORP. |
| To: | |
| References | |
| NUDOCS 8503200555 | |
| Download: ML20099L298 (36) | |
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' ' u,. 4 p SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 7/1/84 - 12/31/84 FLORIDA POWER CORPORATION CRYSTAL RIVER - UNIT 3
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FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 FEBRUARY, 1985 Approved by:
MS M Nuclear Plant Manager Date:
2/2 f/ I Approved by:
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Manager, Site Nuclear Services Date:
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Semieffland2 8503200555 841231 PDR ADOCK 05000302
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TABLE OF CONTENTS
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PAGE I
Introduction 1
II
. Releases of and Doses from Gaseous Effluents 4
III Releases of and Doses from Liquid Effluents 14 IV Solid Waste Shipments 24 V
Meteorological Data 28 VI Technical Specification Reports 29 lVII ODCM and PCP Changes 30 i
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Semieffland2
LIST OF TABLES PAGE I-1A Summation of Doses to Individuals from Gaseous and Liquid Effluent Releases - First and Second Quarters 2
I-18 Summation of Doses to Population from Gaseous and Liquid Effluent Releases - First and Second Quarters 3
II-1 Gaseous Effluents - Summation of All Releases 8
II-2 Gaseous Effluents - Ground Level Releases 9
111-1 Liquid Effluents - Summation of All Releases 20 III-2 Summation of Nuclides in Liquid Effluent Releases 21 III Doses to Individuals from Liquid Effluent Releases -
Third and Fourth Quarters 22 III-4 Doses to th.e Population from Liquid Effluent Releases - Third and Fourth Quarters 23 IV-1 Summation of Solid Waste Irradiated Fuel Shipments 25
]
IV-2 Shipment Summary 26 O
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q I.
INTRODUCTI0'N V
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, 1984.
There have been no changes to the Technical Specification Requirements for effluents and waste disposal of the Facility 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 in 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 specific O
data aerever Possibie-Taese doses are su==arized ia rabies t-ta aad 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.
O 1
O-TABLE I-1A SUMMATION OF DOSES TO INDIVIDUALS FROM GASE0US AND LIQUID EFFLUENT RELEASES Third Quarter Beta Air Dose = N/A (Design Objective = 2.00E+01 mrad /yr)
Gamma Air Dose =. N/ A (Design Objective = 1.00E+01 mrad /yr)
Whole Body Dose Distance (Mi.) and Design Effluent Release Direction Age Group Organ Dose Objectives (mrem /yr)
(mrem /yr)
N/A 5.00E+ 00 Continuous Gaseous N/A N/A Batch Gaseous.
N/A Continuous Liquid Adult 8.84E-09 5.00E+00 2.26E-02 Teen Batch Liquid Organ Dose N/A 1.50E+01 Continuous Gaseous N/A N/A N
Batch Gaseous N/A Adult GI-LLI 8.84E-09 5.00E+00 Continuous Liquid Adult GI-LLI 1.38E+00 Batch Liquid Fourth Quarter
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Beta Air Dose = N/A (Design Objective = 2.00E+0 mrad /yr)
Gamma Air Dose = N/A (Design Objective = 1.00E+01 mrad /yr)
Whole Body Dose N/A 5.00E+ 00 Continuous Gaseous N/A N/A Batch Gaseous N/A Adult 5.02E-05 5.00E+00 1
Continuous Liquid Batch Liquid Teen 3.79E-02 Organ Dose Continuous Gaseous N/A N/A 1.50E+01 N/A Batch Gaseous N/A Adult GI-LLI 1.23E-03 5.00E+00 Continuous Liquid Adult GI-LLI 6.04E-01 Batch Liquid NOTE: The gaseous doses are not available due to delays in obtaining meteorological data.
A supplemental report will be issued with the gaseous doses when the data is available.
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TABLE I-1B SUMMATION OF DOSES TO THE POPULATION FROM GASEOUS Af0 LIQUID EFFLUENT RELEASES Third Quarter -
Whole Body Dose Organ Dose Effluent Release Dose Design Objectives Organ Dose Design Objectives (MAN-REM /YR)
(MAN-REM /YR)
(MAN-REM /YR)
(MAN-REM /YR)
N/A 5.00E+02 Continuous Gases N/A 5.00E+02 N/A Batch Gaseous N/A Continuous Liquid 1.17E-06 GI-LLI 1.17E-06 GI-LLI 1.72E+02 Batch Liquid 1.38E+00
'3 Fourth Quarter Continuous, Gaseous N/A 5.00E+02 N/A 5.00E+02 N/A Batch Gaseous N/A Continuous Liquid 4.24E-03 GI-LLI 1.04E-01 Batch Liquid 3.55E+00 GI-LLI 6.54E+01 NOTE: The gaseous doses are not available due to delays in obtaining meteorological data.
A supplemental report will be issued with the gaseous doses when the data is available.
-(V7 II. RELEASES OF AND DOSES FROM GASEOUS EFFLUENTS 1.
Regulatory Limits The Technical Specification limits for gaseous effluent releases are as follows:
A.
Specification 3.11.2.1 The dose rate at or beyond the SITE B0UNDARY, due to radioactive materials released in gaseous effluents, shall be limited as follows:
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.
- Tritium, and radioactive particulates with half-lives of greater than 8 days: less than or equal to 1500 mrem / year to any organ.
B.
Specification 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:
fm a.
During any calendar quarter: less than or equal to 5 mrad U
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 than 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 particulates 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 exceed 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 OFFSITE DOSE CALCULATION MANUAL provides the equations and dose factors that relate to the gaseous activity to be released to doses at the site b
u 4
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boundary, and restrictions are placed on quarterly and yearly release V
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.
B.
Iodines - The activity released as Iodine-131,133, and 135 is based on the charcoal cartridge activities (RMA-21), the particulate filters activities (RMA-2P) and the total vent flow.
C.
Particulates - The activity released via particulates with half-lives greater than eight days is determined by isotopic analysis of particu-late filters (RMA-2P) and the total vent flow.
O The radioactivity 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.
Iodines - The iodines from batch releases are included in the iodine determination from the continuous Auxiliary Building releases.
C.
Particulates - The particulates 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.
Tlie; ' radioactivity released by purge ' releases of the Reactor Building
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through the Reactor Building vent is 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 prior'to the beginning of the Reactor Building purge and at least weekly during continuous ventilation.
5
F-f B.-
Iodines - The total curies released as iodine-131,133 and 135 were d
determined f rom the charcoal cartridge activities (RMA-11) and the particulate filter activities (RMA-1P).
C.
Particulate - The total curies released via particulates 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.
Monitor Statistical Error 30%
Monitor Error in Calibration 50%
Vent Flow Rate 10%
Non-Steady Release Rate 20%
TIIK O
B.
1-131 Total Release as calculated from charcoal and particulate filter activity.
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%
110%
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Particulates with half-lives greate. than eight days release as calcu-V 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%
100%
D.
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%
W 4.
Batch and Unplanned Releases The batch gaseous effluent releases may be summarized as follows:
7/1/84 - 12/31/84 Q
Number of Batch Releases 2.30E+01 Total time for all releases (minutes) 1.70E+04 Maximum time for any one release (minutes) 1.26E+03 Average time for all releases (minutes) 7.38E+02 Minimum time for any one release (minutes) 8.00E+01 Number of Unplanned Releases 0.00E+00 Total Unplanned Activity Released (Curies) 0.00E+00 The summation of gaseous effluent releases is in Table II-1 and the summa-tion of nuclides in gaseous effluent ground level releases is in Table
!I-2.
There were no unplanned releas5s for the third and fourth quarters of 1984.
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TABLE II-1 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT - 7/1/84 - 12/31/84 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 3
4 Error %
A.
Fission and Activation Gases 1.
Total Release C1 4.39E+02 4.63E+02 1.10E+02 2.
Average Release Rate for Period pCi/sec 5.58E+01 5.89E+01 3.
Percent of Technical Specification Limit 5.08E-01 9.08E-01 B.
Iodines l
1.
Total Iodine - 131 Ci 7.57E-06 7.33E-05 1.01E+02 2.
Average Release Rate for Period pCi/sec 9.63E-07 9.32E-06 l
3.
Percent of Technical Specification Limit 6.31E-01 9.08E-01 C.
Particulates 1.
Particulates with half-lives > 8 days C1 1.80E-05 4.87E-05 1.00E+02.
2.
Average Release Rate for Period nC1/sec 2.29E-06 6.19E-06 3.
Percent of Technical Specification Limit 6.31E-01 9.08E-06 4.
Gross Alpha Radioactivity Ci 6.18E-08 2.15E-08 D.
Tritium 1.
Total Release Ci 6.08E+00 2.58E+00 9.00E+01 2.
Average Release Rate for Period uCi/sec 7.73E-01 3.28E-01 3.
Percent of Technical Specification Limit 6.31E-01 9.08E-01 ga 8
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TABLE II-2 EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT - 7/1/84 - 12/31/84 GASE0US EFFLUENTS - GROUND-LEVEL RELEASES LOL CONTiNU0US M= E BATCH MNE Nuclides Released.
Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
-1.L Fission gases -
k rypton-85 '
C1 1.11E&00 3.94E+00 1.48E-01 1.90E+00 krypton-85m C1 4.95E-02 3.47E-02 k rypton-87 Ci
<5.12E+01 2.74E+00
<1.49E-02 6.37E-03 krypton-88 C1
<2.96E+01
<2.96E+01
<2.17E-02
<1.58E-01 xenon-133 C1 3.15E+02 2.18E+02 3.81E+01 1.47E+02 xenon-133m (4.76E+01
<4.76E+01 3.06E-01 1.26E+00 xenon-135 -
Ci 8.28E+01 7.99E+01 1.31E+00 1.35E+00 xenon-135m C1 3.78E+00 xenon-131m C1 7.22E-01 2.83E+00 xenon-138 Ci
<6.95E+02
<6.95E+02
<5.25E-02
<3.82E-01 Ci C1 Ci unidentified Ci Total for Period C1 3.98E+02 3.09E+02 4.07E+01 1.54E+02 Iodines 1(]).
iodine-l'31 Ci 7.57E-06 ~
-7.33E-05 iodine-133 C1 2.69E-06 Ci Total for. Period Ci 7.57E-06 7.60E-05 3.
Particulates manganese-54 Ci
<2.49E-05
<2.49E-05 1.24E-07 iron-59 Ci
<7.24E-05
<7.24E-05 cobalt-58 C1
<2.97E-04 1.57E-07 cobalt-60 Ci
<2.91E-05
<2.91E-05 zinc-65 Ci
<4.74E-05
<4.74E-05 nelybdenum-99
<l.71E <1.71E-04 cesium-134 Ci
<1.96E-05
<1.96E-05 cesium-137 Ci
<2.15E-05
<2.15E-05 cerium-141 Ci
<l.05E-04
<l.05E-04 i-cerium-144 Ci
<2.65E-05 9.07E-07 iodine-131 Ci (8.92E-06
<8.92E-06 strontium-89 C1
<5.79E-03 5.96E-07 strontium-90 Ci
<5.79E-03 3.17E-07 Ci l
Ci C1 Ci i
unidentified C1 1.79E-05 3.08E-05 4.16E-08 2.16E-07 Total C1 1.79E-05 3.28E-05 4.16E-08 3.4) E-07 l
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TABLE II-3 Doses to Individuals from Continuous Gaseous Effluent Releases THIRD QUARTER Beta Air Dose = N/A (4.0 miles,E)
Gama Air Dose = N/A (4.0 miles E)
Whole Body Dose Organ Dose Distance Distance (Mi.) and Dose (Mi.) and Dose Pathway Direction Age Group (mrem /yr)
Direction Age Group Organ (mrem /yr)
Plume Immersion N/A N/A N/A N/A N/A N/A N/A Ground Contamination N/A N/A N/A N/A N/A N/A N/A Inhalation N/A N/A N/A N/A N/A N/A N/A Vegetable Consumption N/A N/A N/A N/A N/A N/A N/A Cow Milk Consumption N/A N/A N/A N/A N/A N/A N/A Goat Hilk Consumption N/A N/A N/A N/A N/A N/A N/A Meat Consumption N/A.
N/A N/A N/A N/A N/A N/A E
Total N/A N/A N/A N/A N/A N/A N/A FOURTH QUARTER Beta Air Dose = NTA (4.0 miles,E)
Gama Air Dose = N/A (4.0 miles,E)
Whole Body Cose Organ Dose Distance Distance (Mi.) and Dose (Mi.) and Dose Pathway Direction Age Group (mrem /yr)
Direction Age Group Organ (mrem /yr)
Plume Immersion.
N/A N/A N/A N/A N/A N/A N/A Ground Contamination N/A N/A N/A N/A N/A N/A N/A Inhalation N/A N/A N/A N/A N/A N/A N/A Vegetable Consumption N/A N/A N/A N/A N/A N/A N/A Cow Milk Consumption N/A N/A N/A N/A N/A N/A N/A Goat Milk Consumption N/A N/A N/A N/A N/A N/A N/A Meat Consumption N/A N/A N/A N/A N/A N/A N/A Total N/A N/A N/A N/A N/A N/A N/A
i TABLE II-4 Doses to Individuals from Batch Gaseous Effluent Releases THIRD QUARTER Beta Air Dose = N/A (4.0 miles,E)
Gamma Air Dose = N/A (4.0 miles,E)
Whole Body Dose Organ Dose Distance Distance (Mi.) and Dose (Mt.) and Dose Pathway Direction Age Group (mres/yr)
Direction Age Group Organ (mres/yr) i Plume Immersion N/A N/A N/A N/A N/A N/A N/A Ground Contamination N/A N/A N/A N/A N/A N/A N/A Inhalation N/A N/A N/A N/A N/A N/A N/A Vegetable Consumption N/A N/A N/A N/A N/A N/A N/A I
Cow Milk Consumption N/A N/A N/A N/A N/A N/A N/A Goat Milk Consumption N/A N/A N/A N/A N/A N/A N/A Meat Consumption N/A N/A N/A N/A N/A N/A N/A C
Total N/A N/A N/A N/A N/A N/A N/A FOURTH QUARTER l
Beta Air Dose = N/A (4.0 miles,E) l Gamma Air Dose = N/A (4.0 miles,E)
Whole Body Dose Organ Dose i
Distance Distance (Mi.) and Dose (Mi.) and Dose Pathway Direction Age Group (arem/yr)
Direction Age Group Organ (mrem /yr)
I Plume Immersion N/A N/A N/A N/A N/A N/A N/A Ground Contamination N/A N/A N/A N/A N/A N/A N/A Inhalation N/A N/A N/A N/A N/A N/A N/A 4
Vegetable Consumption N/A N/A N/A N/A N/A N/A N/A Ccw Milk Consumption N/A N/A N/A N/A N/A N/A N/A i
Goat Milk Consumption N/A N/A N/A N/A N/A N/A N/A Meat Consumption N/A N/A N/A N/A N/A N/A N/A Total N/A N/A N/A N/A N/A N/A N/A i
s TABLE II-5 (d
Doses to the Population from Continuous Gaseous Effluent Releases THIRD QUARTER Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion N/A N/A N/A Ground Contamination N/A N/A N/A Inhalation N/A N/A N/A Vegetable Consumption N/A N/A N/A Milk Consumption N/A N/A N/A Meat Consumption N/A N/A N/A Total N/A N/A N/A F0URTH QUARTER Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion N/A N/A N/A
()
Ground Contamination N/A N/A N/A Inhalation N/A N/A N/A Vegetable Consumption N/A N/A N/A Milk Consumption N/A N/A N/A Heat Consumption N/A N/A N/A Total N/A N/A N/A-1 0
12
G TABLE II-6 V
Doses to the Population from Batch Gaseous Effluent Releases THIRD QUARTER Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Plume Immersion N/A N/A N/A Ground Contamination N/A N/A N/A Inhalation N/A N/A N/A Vegetable Consumption N/A N/A N/A Milk Consumption N/A N/A N/A Meat Consumption N/A N/A N/A Total N/A N/A N/A FOURTH QUARTER Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem) n Plume Immersion N/A N/A N/A L/
Ground Contamination N/A N/A N/A Inhalation N/A N/A N/A Vegetable Consumption N/A N/A N/A Milk Consumption N/A N/A N/A Meat Consumption N/A N/A N/A Total N/A N/A N/A O
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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 Condenser 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 effluent 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 noble gases, the concentration shall be less than or equal to 2 x 10-4 microcuries/ml. total activity.
Specification 3.11.1.2 O
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 mrem to any organ.
O U
14
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-m
2.
Radionuclide Concentrations 0-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 WC calculation performed before the release of the batch.
The concentration of each of the ganina emitting nuclides specifically noted in Figure III-1 is measured individually due to the requirements of the Technical Specification.
If any of the following radionuclides, mang-a nes e-54, iron-59, cesium-137, ceri um-141, or cerium 144 are less than their LLD value, an a-priori system LLD for each isotope is used to calcu-late the minimum detectable release activity.
Individual measurements are made on proportional composite liquid radwaste samples to determine the Fe-55, Sr-89, and Sr-090 concentration to be applied to individual release calculations.
A distillation and liquid scintillation counting technique is used to measure the tritium concentration on each batch release.
The measured and calc'ulated concentration values for each batch are used to calculate the dilution ratio, release rate, 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 O'
is used to assure that quarterly and annual release limits are not exceeded.
Bases used for the data of Table 111-1 are as follows:
A.
Fission and activation products The total release values (not including tritium, gases, gross alpha) are comprised of the sum of the individual radionuclide 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 then determined by dividing the calculated total body or organ dose by the applicable Technical Specification limit and then multiplying 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.
The average.dil.uted concentration. divided by the MPC limit, 3 x 10-3 luci/ml, is converted to give the percent of applicable limit.
O 15
f 1
limit, 3 x 10-3 pCi/ml, is converted to percent to give the percent of
[-
. applicable limit.
L C.
Dissolved and entrained gases - Concentrations' of dissolved and en-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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Iodine radionuclides in any form are detennined during the isotopic analysis for each release, therefore a separate analysis for possible gaseous forms is not per-formed.
The average diluted concentration of the dissolved and entrained gases is divided by the 19C limit, 2 x 10 4 uC1/ml, and converted to give the percent of applicable limit.
3.
Measurements and Approximations of Total Radioactivity 1
Details of the analytical procedures for liquid radwaste analysis are as follows:
4 I
Measurement Frecuency Method 1.
Gamma Isotopic Each Release Ge(L1) spectrometry with on-line computer 2.
Gross Beta Each Release Liquid scintillation
-(
i 3.
S r-89 Monthly Composite Chemical separation and beta scintillation counting 4.
Sr-90 Monthly Composite Chemical separation and beta scintillation counting 5.
Tritium Each Release Distillation and liquid
' scintillation counting 6.
Alpha Monthly Composite Alpha scintillation 7.
Dissolved Gases Each Release Ge(L1) spectrometry with on-line 3
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, t
sampling and mixing losses, and volume determinations.
l A.
Fission and Activation Products Total Release as calculated for each batch.
Statistical Error at m d 60%
L Waste Volume 10%
i-Counting Equipment Calibration 10%
Sampling and Mixing 20%
100%
f I
16 i
- u. n -.
m B.
Total Tritium Release as calculated from a ' monthly composite.
Waste Volume 10%
Counting Equipment Calibration 10%
Sampling and Mixing 20%
W C.
Dissolved and Entrained Gases Total Release as calculated from one batch per month.
Statistical Error at MDA 60%
Waste Volume 10%
Counting Equipment Calibration 10%
Sampling and Mixing 20%
T65f 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%
T665 4.
Batch and Unplanned Releases The batch liquid effluent releases may be summarized as follows:
7/1/84 - 12/31/84 Number of Batch Releases 3.45E+02 Total Time for all Releases (minutes) 3.14E+04 Maximum Time for any one Release (minutes) 3.00E+02 Average Time for all Releases (minutes) 9.11E+01 Minimum time for any one Release (minutes) 1.00E+00 Average dilution flow of Units 1, 2, and 3 during all Releases (liters / minutes) 2.74E+07 Number of Unplanned Releases 0.00E+00' Total Unplanned Activity Releases (Curie) 0.00E+00 The summation of liquid effluent releases is in Table 111-1 and the sunena-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 nuclear services water of Unit 3.
17
=_
1
.]-
The doses to individuals from liquid effluent releases are in Table III-3 and the doses to the population from liquid effluent releases are in Table III-4.
These doses are based on the dilution of the radioactive 4
liquid effluents by the condenser cooling water of Units 1, 2, and 3.
There were no unplanned releases for the third and fourth quarters of 1984.
i j.
i I.
t 1
i t
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f 1
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18
O
' ' S" " ' -
METH00S OF MEETING 10 CFR 20, APPENDIX B. TABLE II, COLUPN 2 WC LIMITS W C RANGE GAtNA-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) Gamma-Ray Fe-55 Spectroscopy)
(Separationand All Liquid Scintil-(Alpha lation Counting)
Counting Sengitivity 10-' uC1/ml as Pu-239)
Ba-La-140. Na-24. Cu-64 Tritium Co-60. Fe-59 Zn-6f1 (Distillation and Liquid Scintgilation g
}.,9 x 10-6 Ag-110m Mn-54. Co-58 Counting 10- uCi/ml) tj Zr-Nb-95. Cs-Ba-137 As-76. F-18. Cr-51 All others Np-239. Ce-141 (Liquid Scintillation Counting 10-b pCi/ml asCs-137)
Mo-Tc-99. Ce-Pr-144 (Ge(Li) Ganna-Ray Spectroscopy) b a
19
TABLE III-1
'~
EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT - 7/1/84 - 12/31/84 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 8.0EE-02 7.85E-02 1.00E+02 2.
Average diluted concentration during period uC1/ml 1.35E-07 7.60E-08 3.
Percent of applicable limit 4.46E+00 9.26E+00 B.
Tritium l
1.
Total Release Ci 7.96E+01 8.88E+01 4.00E+01 2.
Average diluted concentration during period uCi/mi 1.33E-04 8.59E-05 lll 3.
Percent of applicable limit 4.43E+00 2.86E+00 4.00E+01 C.
Dissolved and entrained gases 1.
Total release Ci 1.66E+00 3.38E+00 1.00E+02 2.
Average diluted concentration during period uCi/ml 2.78E-06
, 3.27E-06 3.
Percent of applicable limit 1.39E+00 1.64E+00 D.
Gross alpha radioactivity 1.
Total release Ci 4.18E-05 3.98E-05 1.00E+02 E.
Volume of Waste released (prior to dilution) 1.
Batch and Continuous Modes Gallons 2.65E+06 3.0SE+06 1.00E+01 F.
Volume of dilution water used during period 1.
Batch and Continuous Modes Gallons 1.55E+08 2.70E+08 1.00E+01 20
TABLE III-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/84 - 12/31/84
(~l LIQUID EFFLUENTS
(/
CONTINUOUS MODE BATCH MODE Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 chromium-51 Ci 1.92E-03 manganese-54 Ci
<l.14E-05
<l.08E-05 1.01E-04 5.53E-04 manganese-56 C1 2.55E-04 iron-55 Ci
<2.42E-04 3.91E-04 2.96E-03 7.09E-03 iron-59 Ci
<3.12E-05
<2.98E-05
<9.82E-04 1.43E-04 cobalt-58 C1
<l.36E-05
<l.30E-05 1.51E-03 2.39E-02 cobalt-60 C1
<l.52E-05
<l.46E-05 7.12E-03 4.28E-03 zinc-65 C1
<2.12E-05
<2.03E-05
<6.68E-04
<8.14E-04 strontium-89 C1
<l.21E-05
<l.16E-05 1.14E-05 1.05E-04 strontium-90 C1
<i.21E-05
<1.16E-05
<3.81E-04 2.48E-05 strontium-92 Ci 7.55E-03 1.09E-03 zirconium-95 C1 3.09E-04 zirconium-97 C1 6.63E-04 7.12E-05 molybdenum-99 C1
<8.03E-05
<7.67E-05
<2.53E-03
<3.08E-03 technetium-99m C1 2.08E-04 1.11E-04 ruthenium-106 C1 5.63E-04 silver-110m C1 1.77E-02 3.40E-03 todine-131 C1
<l.08E-05
<l.03E-05 6.91E-04 5.24E-04 todine-133 3.22E-04 9.05E-05
/~T cesium-134 C1
<l.66E-05
<l.59E-04 8.31E-05 3.74E-03
(_) cesium-137 Ci
<1.57E-05
<l.50E-05 4.04E-04 1.03E-02 barium-139 C1 1.01E-04 barium-140 C1 4.77E-05 lanthanum-140 Ci 3.08E-07 2.02E-04 cerium-141 Ci
<l.85E-05
<l.76E-05
<5.81E-04 (7.07E-04 cerium-144 C1
<3.40E-06
<8.02E-06
<2.46E-04 2.46E-06 niobium-95 C1 6.07E-05 5.06E-04
'a rgon-41 C1 7.30E-03 krypton-85 C1 9.88E-04 k rypton-85m C1 4.09E-05 1.43E-04 xenon-131m C1 2.56E-02 4.56E-02 xenon-133 C1 9.42E-05 1.61E+00 3.26E+00 xenon-133m C1 1.22E-02 3.09E-02 Xe-135 C1 4.78E-05 1.81E-02 3.90E-02 Unidentified C1 3.19E-05 4.08E-02 1.95E-02 Total for per.iod (above)
Ci 1.74E-04 3.91E-04 1.75E+ 00 3.46E+00
(~h V'
21 L
~
l-p TABLE III-3 y.
Doses to Individuals from. Liquid Effluent Releases THIRD QUARTER - CONTINU0US RELEASES Whole Body Dose Organ Dose Dose Dose x
Pathway Age Group (mrem /yr)
Age Group Organ
.(mrem /yr)
Fish Adult 7.10E-09 Adult GI-LLI 7.10E-09 Invertebrates Adul t.
1.75E-09 Adult GI-LLI 1.75E-09 Shoreline Use-0.00E+00 0.00E+00 Total
-Adult 8.84E-09 Adult GI-LLI 8.84E-09 FOURTH QUARTER - CONTINU0US RELEASES
- Whole Body Dose Organ Dose Dose Dose Pathway Age Group (mrem /yr)
Age Group Organ (mrem /yr)
Fish Adult 1.94E-05 Adult GI-LLI 4.77E-04 Invertebrates Adult 3.08E Adult GI-LLI 7.56E-04 Shoreline Use 0.00E+00 0.00E+00 h
Total Adult 5.02E-05 Adult GI-LLI 1.23E-03 THIRD QUARTER - BATCH RELEASES I'
Whole Body Dose Organ Dose i
(mrem /yr) -
Age Group Organ (mrem /yr)
. Dose Dose l
Pathway Age Group F1sh
-Adult 6.89E-03 Adult' GI-LLI 1.07E+00 Invertebrates Adult 5.40E-03 Adult' GI-LLI 3.15E-01 Shoreline Use
. Teen 1.30E-02 Teen Skin
-1.53E-02 l
Total Teen
,2.26E-02 Adult GI-LLI 1.38E+00 l.
FOURTH QUARTER - BATCH RELEASES l
Whole Body Dose Organ Dose Dose
.. Dose
~ Pathway
' Age Group
.(mrem /yr)-
Age Group Organ (mrem /yr),
r
[
Fish Adult 2.01E-02 Adult GI-LLI 3.94E-01 Invertebrates Adult 1.20E-02 Adult GI-LLI 2.08E-01 Shoreline Use Teen 1.53E-02 Teen Skin 1.79E-02 Total Teen 3.79E-02 Adult GI-LLI 6.04E-01' O
22 i
TABLE III-4 Doses to the Population from Liquid Effluent Releases Q-V THIRD QUARTER - CONTINU0US RELEASES Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Sport Fish 1.09E-06 GI-LLI 1.09E-06 Commercial Fish 1.12E-09 GI-LLI 1.12E-09 Sport Invertebrate 7.51E-08 GI-LLI 7.51E-0B Commercial Invertebrate 5.42E-10 GI-LLI 5.42E-10 Shoreline Use 0.00E+00 0.00E+00 Swimming 0.00E+00 Thyroid 0.00E+00 Boating 0.00E+00 Thyroid 0.00E+00 Total 1.17E-06 GI-LLI 1.17E-06 FOURTH QUARTER - CONTINU0US RELEASES Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Sport Fish 2.93E-03 GI-LLI 7.20E-02 Commercial Fish 3.02E-06 GI-LLI 7.41E-05 Sport Invertebrate 1.30E-03 GI-LLI 3.20E-02 Comercial Invertebrate 9.36E-M GI-LLI 2.30E-04 Shoreline Use 0.00E+00 0.00E+00 Swimming 1.33E-11 Thyroid 1.33E-11 Boating 1.33E-11 Thyroid 1.33E-11 Total 4.24E-03 GI-LLI 1.04E-01 THIRD QUARTER - BATCH RELEASES Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Sport Fish 1.07E+00 GI-LLI 1.59 E+02 Commercial Fish 1.11E-03 GI-LLI 1.62E-01 Sport Invertebrate 2.52E-01 GI-LLI 1.31E+01 Commercial Invertebrate 1.81E-03 GI-LLI 9.41E-02 Shoreline Use 5.83E-02 Skin 6.84E-02
,~
Swimming 5.97E-04 Thyroid 5.97E-04 Boating 5.97E-04 Thyroid 5.97E-04 Total 1.38E+00 GI-LLI 1.72E+02 FOURTH QUARTER - BATCH RELEASES Whole Body Dose Organ Dose Pathway (Man-Rem)
Organ Dose (Man-Rem)
Sport Fish 2.94E+00.
GI-LLI 5.67E+01
. Commercial Fish 3.02E-03 GI-LLI 5.74E-02 Sport Invertebrate 5.33E-01' GI-LLI 8.57E+00 Connercial Invertebrate 3.80E-03 GI-LLI 6.13E-02 Shoreline Use-6.86E-02 Skin 8.02E-02 Swimming 4.65E-04 Thyroid 4.65E-04 Boating 4.65E-04 Thyroid 4.65E-04 Total 3.55E+00 GI-LLI 6.54E+01
(]
23 L
r-IV. SOLID WASTE SHIPMENTS Solid waste shipments from the plant may include solidified liquid waste, dry compressed waste, spent resins, irradiated componen,i and spent fuel.
1.
Regulatory Limits The Technical Specification for solid waste shipment reporting is as foll ows:
Specification 6.9.1.5(d)
The radioactive effluent release report shall include the following information for each type of solid waste shipped offsite during the report period:
1.
container volume, 2.
total curie quantity (specify whether determined by measdrement or estimate),
3.
' principle radionuclides (specify whether determined by measure-ment or estimate),
4.
type of waste (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 summation of solid waste and irradiated fuel shipments is presented in Table IV-1 and Shipment Summaries in Table IV-2.
.g O
24 k
TABLE IV-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 7/1/84 - 12/31/84 m
C).
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Non irradiated fuel)
Second 1.
Type of waste Unit 6-month Est. Total period Error, %
a.
Spent resins, filter sludges, evaporator m3 1.68E+2 bottoms, etc.
C1 1.10E+3 2.00E+1 b.
Dry compressible waste, contaminated m3 1.78E+1 equip, etc.
C1 3.61E-1 5.00E+1 c.
Irradiated components, control m3 2.55E+0 rods, etc.
C1 7.70E+2 5.00E+1 d.
Other (describe) m3 E+
C1 E+
E+
2.
Estimate of major nuclide composition (by type of waste) a.
Cs-134 2.97E+1 Cs-137 3.23E+1 Co-58 2.40E+0
\\]-
/
Cs-134 9.94E+0 Cs-137 1.93E+1 Co-58 1.02E+1 Co-60 2.50E+1 1-131 1.65E+1 Ni-63 1.25E+1 c.
~~
3.20E+1 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 25 Transport Truck -
Chem-Nuclear Systems, Inc.
Exclusive Use Vehicle Barnwell, SC
' ~
0 8.'
I'RRADIATED FUEL SHIPMENTS-(D'isposition)
Number of Shipments Mode of Transportation Destination None NA NA o
25
- TABLE IV EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 7/1/84 - 12/31/84 SHIPMENT
SUMMARY
Page 1 of 2 DATE AND CONTAINER TOTAL WASTE CONTAINER SOLIDIF.
SHIPMENT NO.
TOLUME CURIES ISOTOPES TYPE TYPE ACENT 07/12/84 1.71 Co-60, I-131, Cs-134, 84-34 322 ft3 E-4 Cs-137, Trit t ure SC LSA N/A 07/19/84 7.35 84-36 322 ft3 E-4 Cs-134 Cs-137. Tritium SC LSA N/A 07/26/84 Mn-54, Co-60, co-58, Cs-137, 84-37 121 ft3 327.61 Cs-134, Ni-63 SR LSA N/A 08/14/84 4.96 84-39 322 ft3 E-4 Cs-134. Cs-137. Tritium SC f.R A N/A 08/23/84 Mn-54, Co-60, Co-58, I-131, 84-40 121 ft3 6.057 Cs-134. Cs-137. Ni-63 SR LSA N/A 08/30/84 1.60 Co-60, Sb-122, I-131, 84-41 322 ft3 E-4 Cs-134. Cs-137, Tritium SC LSA N/A 09/06/84 9.86 84-42 322 ft3 E-5 Sb-122. Cs-134 Cs-137. Tritium SC LSA N/A 09/13/84 84-44 121 f't3 214 Co-60, Cs-134 Cs-137, Ni-63 SR LSA N/A 09/24/84 84 x 3.62 Ag-110m, Co-58, co-60, Cs-134, 84-46 7.5 ft3 E-1 Cs-137, I-137, Mn-54, Ni-63 CW LSA N/A 09/25/84 1.19 Co-60, Sb-122, Cs-134, 84-47 322 ft3 E-4 Cs-137. Tritium SC LSA N/A' 09/27/84 84-48 121 ft3 214 Co-60, Cs-134, Cs-137, Ni-63 SR LSA N/A 10/04/84 7.37 84-49 322 ft3 E-5 Cs-134, Cs-137, Tritiun SC LSA N/A 10/11/84 84-50 121 ft3 214 Co-60, Cs-134, Cs-137, Ni-63 SR LSA N/A 10/15/84 7.37 84-51 322 ft3 E-5 Cs-134, Cs-137, Tritium SC LSA N/A 10/18/84 6.74 84-52 322 ft3 E-5 Cs-134, Cs-137, Tritium _
SC LSA N/A 10'/23/84- '
84-53 322 ft3.
6.13 E-5 Cs-134. Cs-137. Tritium SC LSA N/A 11/02/84 5.47 84-54 322 ft3 E-5 Cs-134, Cs-137. Tritium SC LSA N/A 11/05/84 5.06 85-55 322 ft3 E-5 Cs-134. Cs-137, Tritium SC LSA N/A WASTE TYPE: SR = Spent Resin CE = Contaminated Equipment SC = Secondary Resin IC = Irradiated Components CW = Compacted Waste F = Filters EB = Wvaporator Bottoms 26 t
J
Page 2 of 2 DATE AND CONTAINER TOTAL WASTE CONTAINER SOLIDIF.
O SHIPMENT NO.
TOLUME CURIES ISOTOPES TYPE TYPE ACENT 11/26/84 Cr-51, Mn-54, Co-60, co-58, 84-56 121 ft3 7.02 Ag-110m, Cs-134, Cs-137, Tritium SR LSA N/A 11/28/84 5.22 84-57 322 ft3 E-5 Cs-134 Cs-137. Tritium SC LSA N/A 12/10/84 Cr-51, Mn-54, Co-60, Co-58, 84-58 121 ft3 11.1 Nb-95, Cs-134, Cs-137. Ni-63 SR LSA N/A 12/11/84 4.32 84-59 322 ft3 E-5 Cs-134. Cs-137. Tritium SC LSA N/A 12/13/84 2.98 84-60 322 ft3 E-5 Cs-134, Cs-137, Tritium SC LSA N/A 12/18/84 Mn-54, Co-60, Sb-122, Cs-134, 84-61 121 ft3 67.08 Cs-137, Ni-63, Sr-89 SR LSA N/A Cr-51, Mn-54, Fe-59, 12/20/84 Co-60, co-58, Zr-95, Nb-95, 84-62 121 ft3 35.3 Cs-134. Cs-137. Ni-63 SR LSA N/A O
s
()
WASTE TYPE: SR = Spent Resin CE = Contaminated Equipment SC = Secondary Resin IC = Irradiated Conponents CW = Compacted Waste F = Filters EB = Evaporator Bottoms 27 L
C V METEOROLOGICAL DATA The historical meteorological data is being recovered manually and the summary tables will be submitted in a supplemental report as soon as the data is available.
O s
=
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28 k
-a
e
.O VI TECHNICAL SPECIFICATION REPORTS U-Technical Specification Sections 3.3.3.8, 3.3.3.9, and 3.12.1.2.b require reporting out of specification conditions in the Effluent and Waste Dispos-al Semiannual. Report.
There were no reports as required by the above specifications for the period of this report.
O y
b b
l l-O 29
. o N
e VII ODCM AND PCP CHANGES Technical Specifications Section 6.9.1.5.d requires ' reporting of changes to the Offsite Dose Calculation Manual (DDCM) and the Process Control Program (PCP) in the Semiannual Radioactive Effluent Release Report.
Revisions to the ODCM for the period of this, report are included in this section. The changes are marked for ease of review.
There were no revisions to the Process Control Program for the period of this report.
O t
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30
(
Seapointt.a, a aa= 1 A 5 Plant Discher ge Line Moniter (RM4.2)
SeediType Ralesses) 9 n j U smlODUCTION 3
h Following completion of the analyses regdred by'Section 1.2-4 and determination of 0
release rates and concentration ihnits in accordance with Section 1.5-2, the monitor i
seapoint regdres adjustinent to ensure that alarm and pathway isolation occur if the
- j nuclide concentration or release rate exceeds the Ihnits determined.
oj-l Evaporator Condensate Storage Tank or Laundry and Shower Sump Tank contents are circulated through radiation monitor RM-L2 and returned to the e-litary imilding sump to obtain the actual count rate at RM-L2 for the concentration contained in the tank for Ji release. The observed count rate is adjusted for release flow, background and statistical counting variations, particular to this release flow path. The resulting value is used as the j
alarm / trip setpoint and RM-L2 is adjusted to this value prior to initiating the relemee-
..l Cgr. a ATION
[ Net CPM x Admin. Facto) (I FR+PD
~ [
Monitor Setpoint
=
- k *
- NEE 3C /MPCI FR j E
(CPM)
(
i where c
O' Net CeM =
The oneerved monitor count rate. in counis,er minuie.
3 Admin. Factor = Administration Factor to account for error in setpoint j
determination. Admin. Factor = 0.8.
O l
3Cg/MPCI =
The ratio of the' actual gamma emi concentrations (e
dissolved and entrained of tank contents to be to the Maximum ermissible Concentration (MPC) as listed in 10 CFR 20, Table B, Column 2 for unrestricted areas.
f The release flow rate of waste to be discharged in gallons per
.i FRs
- j.*
minute. A maximum flow rate of 100 gym will be used for the Evaporator Condensate Storage Tanks and 40 gpm for the
- Laundry and Shower Sump Tanks, g;
}k.
I
- ,., ~ :.-. 3;:.
.-.2.a.. ;,. *:. %. -
L :.<
m
~ The 'dllution flow from the Nuclear Services Sea Yater
"~
- *'
- . F =
- t D
j system in gallons per minute.
BKG =
The background count rate at RM-L2 in counts per minute
- ]2 (cpm).
- i 3.3 STg =
A statistical spread on the background count rate which i
represents a 99.9.5% confidence level on monitor counting, This factor is ince%d to prevent inadvertent trip j
alarms due to randor a counts on the monitor.
the 1
,osim.) side.f u s, read is a,,iied.
REVISION 2
_o_
%e.*
f* Melan jM Turbine BulkBag Basement Discharge Line Monitor (RM-L7)
(Batch Type Releases)
O m oouenON Following completion of the analyses regdred by Section 1.2-4 and determination of release rates and concentration limits in accordance with Section 1.3-2, the monitor setpoint regdres adjustment to ensure that alarm and pathway isolation occur if the 4
i nuclide concentration or release rate exceeds the limits determined.
l METHODOt.OGY a
5tation Drain Twik (SDT-1) contents are ciradated through radiation monitor RM-L7 and returned to the sump to obtain the actual count rate at RM-L7 for the concentration i
contained in the tank for release. The observed count rate is adjusted for release flow, variations, particular to this release flow path. The background and statistical counting / trip setpoint and RM-L7 is adjusted to this value p resulting value is used as the alarm o
to initiating the release.
CALCULATION
[ Net CPM x Admin. Factor[
FR + FD Monitor Setpoint
=
(CPM) i 2C1/MPCI
/
(
FR
/
~
1 Net dPM =
The observed monitor count rate, in counts per minute.
l Admin. Factor = Administration Factor to account for error in setpoint determination. Admin. Factor = 0.3.
o, j
2CpMPCI =
The ratio of the actual gamma emi concentrations j
(excludin g dissolved and entrained gases) of tank contents to be reeased to the Maximum Permissible Concentration a
(MPC) as listed in 10 CFR 20, Table II, Column 2 for S
unrestricted areas.
The release flow rate of waste to be discharged in gallons per FR=
{
minute. A maximum flow rate of 600 gym will be used.
\\
The dilution flow from the Nuclear Services Sea Water FD=
system in gallons per minute.
t
-=.-.<:e---
BKG =
The background count rate at RM-L7 in counts per minute,
(cpm).
t.
3.3 (8Kg =
A statistical spread on the background count rate which spits a 99.93% confidence level on monitor counting.
[
This factor is included ts prevent inadvertent high/ trip alarms due to random counts on the monitor.
Only the positive (+) side of the spread is app!!ed.
}A NOTE:
If there are no gamma emitting nuclides identified, the
- U setpoint derived from 1.4-6 will be used.
t l
REVISION 2
, 2. -
t-j
=
e I
1 r"-
~
905E CALCIA.ATION 4.5-2 RADICIODINES & FARTICULATR9 The does to an Individual at or beyond the STE BOUNDARY due to Iodine-131. Trition and radioactive particulates with half Ilves of greater than 4 days is calculated as follows:
1 3.17 x 10-8 R (W Qg) 1 D
=
WlbefoS The radiation does to an Individual at or beyond the UNRESTRICTED D
=
AREA BOUNDARY,In mrom.
The does factor for each identified radionuc!!de,1, in m2 (mesm/ year)
RI
=
per uC1/sec or mrem / year per uC1/m3 (X/Q) for the inhalation pathway,2J x 10-6 sec/m3 T
=
(D/Q) for the food and ground plane pathway,1.9 x IN m-2, W
=
The releases of the radionuclides of concern in pC1, over the calendar l
(
Qg I
=
r quarter or calendar year, as appropriate.
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. W 65 j.:
.s. r.. '. :.,ei', V$i$j,
- :-;. Abyj. 9? t hh.,.';e,. F.?('.-
s......
c,
!I ei Ii iO
.afe,ence.
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NUREG 0133, Section 3.3.1 REVISION 3
"^* "'*"
((
..