ML20044B698
| ML20044B698 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/31/1992 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20044B697 | List: |
| References | |
| NUDOCS 9303030133 | |
| Download: ML20044B698 (29) | |
Text
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The Davis-Besse Nuclear Power Station Semiannual Radioactive Effluent and Waste Disposal Report July 1 - December 31,1992 i
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r SEMIA!MUAL EFFLUENT AND VASTE DISPOSAL REPORT ;
i Davis-Besse Nuclear Power Station !
t Unit No. 1 l t
e July 1, 1992 through December 31, 1992 'i!
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Docket Number 50-346 :
License Number NPF-3 ;
i Toledo Edison Company ;
300 Madison Avenue '
Toledo, Ohio 43652 February 1993 i
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I TABLE OF CONTE!US l i
Title Pg l
List of Tables ii J Summary 1 Supplemental Information 3 Effluent Data Tables 10 Meteorological Data 26 2
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DBNPS Semiannual Effluent Report i July - Dec., 1992
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LIST OF TABLES Table Number Title Page 1 Gaseous Effluents - Summation of 10 All Releases 2 Gaseous Effluents - Ground-Level Releases 11 j 3 Gaseous Effluents - Mixed-Hode Releases 12 4 Gaseous Effluents - Abnormal Releases 14 s
5 Liquid Effluents - Summation of 15 All Releases ;
6 Liquid Effluents - Nuclides Released 16 i
7 Liquid Effluents - Abnormal Releases 18 8 Solid Vaste and Irradiated Fuel 19 Shipments 9 Semiannual Doses Due to Gaseous 21 Releases 10 Semiannual Doses Due to Liquid 24 Releases i
11 1992 Semiannual Dose to the Most- 25 I
Exposed Member of the Public DBNPS Semiannual Effluent Report 11 July - Dec., 1992
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SUMMARY
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The Semiannual Effluent and Vaste Disposal Report is a detailed listing of !
radioactivity released'from the Davis-Besse Nuclear Power Station during the period from July.1, 1992 through December 31, 1992. ;
This report provides the following information: l i
Summation of the quantities of radioactivity released in '
gaseous and liquid effluents, l Summation of the quantities of radioactivity contained in solid i vaste packaged and shipped for offsite disposal at federally approved sites, and j A listing of all radioactive effluent monitoring '
instrumentation required by the Offsite Dose Calculation .
Manual (ODCH), but which was inoperable for more than 30 days. l Environmental samples were available from the normal collection locations i during this reporting period. The locations used for dose calculations :
and environmental monitoring vere those identified by the 1992 Land Use !
Census.
During the period of July 1 through December 31, 1992, the maximum-individual offsite dose due to radioactivity released in effluents was '
approximately:
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!- 1 Liquid Effluents- 'i 6.23E-02 mrem, whole body 8.32E-02 mrem, liver Gaseous Effluents: ;
Noble Gas: ,
i 1.81E-03 mrem, whole body l 4.95E-03 mrem, skin l
Iodine-131 Tritium, and Particulates with Half-lives :
Greater Than 8 Days: j 1.10E-02 mrem, whole body l 1.29E-01 mrem, thyroid l These doses are only a small fraction of the limits set by the NRC in the Davis-Besse ODCM. !
There exist several adaitional normal release pathways from the :
secondary system as a result of prior primary-to-secondary leakage. For !
gaseous effluents, these pathways include the auxiliary feed pump ,
turbine exhaust, the main steam safety valve system and the atmospheric j vent valve system. For liquid effluents, the additional pathways l include the Turbine Building drains via the settling basins. Releases i which occurred via these pathvays are included in the normal release J tables in this report. !
I DBNPS Semiannual Effluent Report 1 July - Dec., 1992 3
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t On August 16, 1992 a small volume of radioactive gasses escaped to the atmosphere during the performance of an emergency escape hatch surveillance test. In addition, on December 7, 1992 a failed regulator resulted in the overpressurization of the gland seal steam header. The overpressurization caused two relief valves to open, releasing slightly contaminated steam. The resultant offsite doses vere a small fraction of the limits. Additional information on these releases is contained in Section 6 of the Supplemental Information and in Tables 4 and 9 of the abnormal release sections of the report.
Total Dilution Flow Computer Point F201 required to be operable by Davis-Besse Offsite Dose Calculation Manual Section 2.1 was inoperable for more than 30 days during this reporting period. Additional information is contained in Section 10 of the Supplemental Information.
There vere no changes to the ODCM during this reporting period. No changes to the Process Control Program (PCP) occurred during this reporting period.
i DBNPS Semiannual Effluent Report 2 July - Dec., 1992 t
6 SUPPLEMENTAL INFORMATION }
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- 1. REGULATORT LIMITS A. Gaseous Effluents :
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- 1. In accordance with 10CFR20, Appendix B, Table II, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited :
to the following: f
- a. Noble gases:- Less than or equal to 500 mrem / year to the -
total body.
- Less than or equal to 3000 mrem / year to the skin.
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- b. Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
- Less than or equal to 1500 mrem / year to any organ.
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- 2. In accordance with 10CFR50, Appendix I, Sec. IB, air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- a. Less than or equal to 5 mrad for gamma radiation and less ;
1 than or equal to 10 mrad for beta radiation during any ,
calendar quarter. l
- b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.
- 3. In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a meaber of the public from Iodine-131, Tritium, and all ,
radionuclides in particulate form vith half-lives greater than :
8 days in gaseous effluents released to areas at and beyond !
the site boundary shall be limited to the following: l 1
! a. Less than or equal to 7.5 mrem to any organ during any !
calendar quarter. ,
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- b. Less than or equal to 15 mrem to any organ during any j calendar year. l B. Liquid Effluents {
In accordance with 10CFR50, Appendix I, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to: ;
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- 1. Less than or equal to 1.5 mrem to the total body and less j than or equal to 5 mrem to any organ during any calendar quarter. l Less than or equal to 3 mrem to the total body and less than 2.
or equal to 10 mrem to any organ during any calendar year. l t
L DBNPS Semiannual Effluent Report 3 July - Dec., 1992 l
- 2. MAXIMUM PERMISSIBLE CONCENTRATION The maximum permissible concentrations (MPC) for liquid and gaseous effluents at and beyond the site boundary are listed in 10 CFR 20, Appendix B, Table II, Column 2, with the most restrictive MPC being used in all cases. For dissolved and entrained gases the MPC of 2.0E-04 pCi/ml is applied. This MPC is based on the Xe-135 MPC in air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection .
(ICRP), Publication 2.
- 3. AVERAGE ENERGY i
i The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activation products to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 .
mrem / year to the skin. Therefore, the average beta and gamma energies .
(E) for gaseous effluents as described in Regulatory Guide 1.21, l I
" Measuring, Evaluating, and Reporting Radioactivity in Solid Vastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Vater-Cooled Nuclear Power Plants," is not applicable.
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- 4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL A m v m A. Fission and Activation Gases:
- 1. These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel bombs, or glass vials and are counted on a germanium detector for principal gamma e emitters. Detected radionuclides are quantified via gamma spectroscopy.
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- 2. Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation.
B. Iodines are collected on a charcoal cartridge filter, and counted ,
on a germanium detector. Specific quantification of each iodine radionuclide is made by gamma spectroscopy.
C. Particulates are collected on filter paper and counted on a germanium detector. Specific quantification of each radionuclide l present on the filter paper is made by gamma spectroscopy. i D. Liquid Effluents are collected in a marinelli beaker and counted l on a germanium detector. Specific quantification of each :
radionuclide present in liquid samples is made by gamma spectroscopy.
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! l DBNPS Semiannual Effluent Report 4 July - Dec., 1992
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- 5. BATCP RELEASES A. Liquid from 7/1/92 to 12/31/92 l t
- 1. Number of batch releases: 38 l
- 2. Total time period for the batch releases: 5.80E+01 hours !
- 3. Maximum time period for a batch release: 1.05E+02 minutes
- 4. Average time period for a batch release: 9.17E+01 minutes !
- 5. Minimum time period for batch releases: 7.20E+01 minutes ;
B. Gaseous from 7/1/92 to 12/31/92
- 1. Number of batch releases: 1 j
- 2. Total time period for the batch releases: 3.50E+00 hours
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- 3. Maximum time period for a batch release: 2.10E+02 minutes t
- 4. Minimum time period for a batch release: 2.10E+02 minutes
- 5. Average time period for batch releases: 2.10E+02 minutes
- 6. ABNORMAL RELEASES ,
i On August 16, 1992 a small volume of radioactive gasses escaped to the atmosphere during the performance of an emergency escape hatch surveillance test. In addition, on December 7, 1992 a failed regulator resulted in the overpressurization of the gland seal steam header.
The overpressurization caused two relief valves to open, releasing ,
slightly contaminated steam. The activity released from these events !
is listed in Table 4. The resultant offsite dose is listed in Table 9 and represents a small fraction of the Davis-Besse Offsite Dose Calculation Manual (ODCM) release limits. ,
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h DBNPS Semiannual Effluent Report 5 July - Dec., 1992 i.
- 7. PERCENT OF ODCM RELEASE LIMITS The following table presents the ODCH dose limits and the associated offsite dose to the public, in percent of limits, for July through December 1992.
SPECIFICATION LIMIT PERCENT OF LIMITS A. Third Quarter, 1992: Gaseous Noble gases (gamma) 3.0 mrad 3.86E-03 Noble gases (beta) 10.0 mrad 3.86E-03 l I-131, tritium, and 7.5 mrem 4.36E-03 particulates with half-lives greater than 8 days B. Fourth Quarter, 1992: Gaseous l
5.0 mrad Noble gases (gamma) 7.02E-03 Noble gases (beta) 10.0 mrad 1.05E-02 I-131, tritium, and 7.5 mrem 2.01E-03 particulates with half-lives greater than 8 days C. Calendar year, 1992: Gaseous Noble gases (gamma) 10.0 mrad 1.46E-02 Noble gases (beta) 20.0 mrad 1.64E-02 l I-131, tritium, and 15.0 mrem 9.80E-03 particulates with half-lives greater than 8 days D. Third Quarter, 1992: Liquid l
Total body 1.5 mrem 2.84E+00 Any organ (liver) 5.0 mrem 1.13E+00 E. Fourth Quarter, 1992: Liquid Total body 1.5 mrem 1.32E+00 Any organ (liver) 5.0 mrem 5.24E-01 F. Calendar year, 1992: Liquid ;
Total body: 3.0 mrem 4.40E+00 Any organ (liver) 10.0 mrem 1.77E+00 DBNPS Semiannual Effluent Report 6 July - Dec., 1992
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- 8. DOSE ASSESSMENT f
Sources of input data include:
A. Vater Usage: Appendix I analysis, NRC Docket 50-346,
" Evaluation of Compliance with Appendix I to 10 CFR 50, June 4, 1976, Davis-Besse Nuclear Power Station."
0-50 mile meat, milk, vegetable production, and population
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data: 1982 Annual Environmental Operating Report, report entitled, " Evaluation of Compliance with Appendix I to 10 CFR 50: Updated Population, Agricultural, Heat - Animal, and Milk !
Production Data Tables for 1982." This evaluation was based i on the 1980 census; the Agricultural Ministry of Onterio 1980 !
report entitled, " Agricultural Statistics and Livestock Marketing Account, 1980"; the Agricultural Ministry of Ontario ,
1980 report entitled, " Agricultural Statistics for Ontario - i j
1980 Publication 21, 1980"; the Michigan Department of Agriculture, July, 1981 report entitled, " Michigan ,
Agricultural Statistics, 1981"; the Ohio Crop Reporting Service, 1981 report entitled, " Ohio Agricultural Statistics, '
- 1981."
C. Gaseous and liquid source terms: Tables 1 through 7 of this report. .
D. Location of the nearest individuals and pathvays by sector out to 5 miles: Report entitled, "1992 Land Use Census," included in the 1992 Annual Environmental Operating Report for Davis-Besse. j s ,
- 9. DOSE TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY j In accordance with ODCM Section 7.2, the Semiannual Effluent and j
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Vaste Disposal Report shall include an assessment of radiation doses ;
from radioactivity released in liquid and gaseous effluents to ;
members of the public due to their activities inside the site !
j boundary. ;
l In special instances, members of the public are permitted access to the radiologically restricted area within the Davis-Besse station.
Tours for the public are conducted with the assurance that no !
individual vill receive an appreciable dose due to radioactivity released in gaseous or liquid effluents (i.e., not more than a small fraction of the 40 CFR 190 dose standards).
The Visitor Center located inside the Davis-Besse Administration Building (DBAB) is also accessible to members of the public.
1 Considering the frequency and duration of the visits, the resultant dose vould be a small fraction of the calculated maximum site boundary dose. The dose from gaseous effluents as modeled for the DBAB Visitor Center is considered the controlling factor when evaluating doses to members of the public from activities inside the site boundary. For purposes of assessing the dose to members of the i public in accordance with ODCM Section 7.2, the following exposure assumptions may be used:
DBNPS Semiannual Effluent Report 7 July - Dec., 1992 1
Exposure time for maximum-exposed visitor of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> (4 visits, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per visit is a conservative estimate).
Annual average meteorological dispersion. ,
The equations in the ODCM may be used for calculating the potential dose to a member of the public for activities inside the site '
boundary. Based on these assumptions, this dose would be at least a factor of 400 less than the maximum site boundary air dose as calculated in the ODCM. ;
There are no areas onsite accessible to the public where exposure to liquid effluents could occur. Therefore, the modeling of the ODCH conservatively estimates the maximum potential dose to members of the public.
- 10. INOPERABLE RADIOACTIVE EFFLUENT MONITORING EQUIPMENT Computer point F201, dilution flov to the collection box, required to be operable by ODCM Sections 2.1 was inoperable for more than 30.
days during this reporting period. This point is a summation value of four computer points, which may go out of service for different reasons. These systems are not readily isolated while the plant is operating. If any of these points fail, F201 vill be out of service. Dilution flow is then approximated using the remaining in service points that are available and pump curves.
A Potential Condition Adverse to Quality Report was written to document that incorrect dilution pump flow curves had been used.
These curves had been used to estimate dilution flov when F201 vas inoperable. Based on 1992 data, dilution flov from the pump vas overestimated by approximately 18%. This non-conservative value resulted in underestimating the dose to the public from liquid estimates by 1.02%, vell within the 20% total error.
- 11. CHANGES TO THE ODCM & PCP There vere no revisions to the ODCM during this reporting period. No changes to the PCP occurred during this reporting period.
DENPS Semiannual Effluent Report 8 July - Dec., 1992
- 12. CHANGES TO THE LAND USE Pathway Locations and Corresponding Atmosphere !
r Dispersion (X/0) and Deposition (D/0) Parameters .
SECTOR METERS CRITICAL AGE X/0 D/ ,
PATHVAY GROUP (SEC/M1 ) (Pfg) .
N 880 INHALATIOi CHILD 9.15E-07 8.4E-09 INE 870 INHAIATIOi CHILD 1.27E-06 1.47E-08 i
NE 900 INHAIATIQi CHILD 1.26E-06 1.58E-08 .,
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ESE" SE^
SSE 2880 VEGELTIQi CHILD 6.85E-08 8.01E-10 S 1440 VEGETATION GILD 1.22E-07 2.48E-09 SS# 1560 VEGETATI m GILD 1.03E-07 2.28E-09 SW" 1050 VEGETATIQi CHILD 2.92E-07 5.33E-09 t WSW 4270 CCW/ MILK INFANT 5.71E-08 5.31E-10 l W" 6530 GOAT / MILK INFANT 4.54E-08 2.79E-10 {
W:7# 1750 VEGETATIOi CHILD 1.46E-07 1.72E-09 !
N# 2450 VEGEIATION GILD 6.47E-08 5.15E-10 l INA 1490 VEGEIATIQi CHILD 1.64E-07 1.26E-09 i i
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Since these sectors are located over marsh areas and Lake Erie,no ingestion pathways exist. ,
j Changes since 1991. f i.
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DBNPS Semiannual Effluent Report 9 July - Dec., 1992 T
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'IABLE 1. GASEC7JS EFFLUE2CS - SUMMATICN OF ALL PILF.ASES EST. 'IOTAL '
THIRD FOURTH PERCE2C TYPE UNIT OUARTER QUARTER EPROR A. Fission and Activation Gases ;
- 1. Total Release Ci 4.96E+00 8.50E+00 2.50E+01
- 2. Average Release Ci/sec 6.24E-01 1.07E+00 Rate for Period
- 1. Total Iodine Ci 3.99E-04 2.69E-04 2.50E+01
- 2. Average Release pCi/sec 7.36E-05 3.0E-05 ,
, Rate for Period !
- 3. Percent of % See Supplemental Information, l ODCM Limits Section 7 !
i C. Particulates ,
- 1. Particulates with Ci 6.55E-04 1.43E-06 2.50E+01
- half-lives greater :
than 8 days
- 2. Average Release pCi/sec 8.24E-05 1.80E-07 .l Rate for Period i i
- 3. Percent of % See Supplemental Information, '
ODCM Limits Section 7
- 4. Gross Alpha Ci 3.57E-07 4.15E-07 2.50E+01 Activity ;
D. Tritium
- 1. Total Release Ci 4.47E+00 3.64E+00 2.50E+01 )1
- 2. Average Release pCi/sec 5.62E-01 4.58E-01 ;
Rate for Period j
- 3. Percent of % See Supplemental Information, ODCM Limits Section 7 ;
i DBNPS Semiannual Effluent Report 10 July - Dec., 1992 l
i TABLE 2. GASEXXJS EFFLUENTS - GRCKRD-LEVEL RELEASES
- CCICINUOUS MODE
- BATCH MODE
- THIRD FOURTH THIRD IVURTH l NUCLIDES UNIT QUARTER 7JARTER 7JARTER QUARTER ,
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- 1. Fission Gases Ci Kr-85 lid LLD LLD LLD Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-133 LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Xe-135m LLD LLD LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A t
- 2. Iodines Ci -
I-133 LLD LLD LLD LLD i I-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A !
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- 3. Particulates Ci H-3 7.36E-07 1.69E-06 6.81E-05 6.11E-06 St-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD 6.50E-04 LLD Co-58 5.93E-07 LLD 2.25E-06 LLD i
Total for Period: 1.33E-06 1.69E-06 7.20E-04 6.11E-06 r
Includes Atmospheric Vent Valve weepage, Auxiliary Feed Pump Turbine tests, a planned auxiliary steam relief valve test, and a planned auxiliary boiler reief valve test.
These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below:
Ar-41: <2.2E-08 Ci/ml Xe-133: <4.6E-08 pCi/ml Kr-85: <6.2E-06 pCi/ml Xe-133m: <1.6E-07 pCi/ml Kr-85m: <2.0E-08 Ci/ml Xe-135: <1.9E-08 Ci/ml Kr-87: <3.5E-08 Ci/ml Xe-135m: <9.9E-08 pCi/ml Kr-88: <6.7E-08 vCi/ml Xe-138: <2.5E-07 pCi/ml ,
I-131: <1.0E-06 pCi/ml Cs-134: <2.1E-08 Ci/ml l I-133: <2.1E-08 pCi/ml Cs-137: <2.7E-08 pCi/ml I-135: <6.8E-08 Ci/ml Sr-89: <5.0E-08 vCi/ml Co-58: <1.9E-08 pCi/ml Sr-90: <6.0E-09 pCi/ml LLDs are applicable to both batch and continuous modes.
DBNPS Semiannual Effluent Report 11 July - Dec., 1992
B BLE 3. CASE 00S EFFLUENTS - MIXED-MODE RELEASES
- CQJTINUOUS MODE BATCH MODE THIRD FOURTH THIRD FOURTH NUCLIDES G4IT QUARTER QUARTER QUARTER QUARTER
- 1. Fission Gases Ci ,
Kr-85 LLD LLD N/A LLD Kr-85m LLD LLD N/A LLD '
Kr-87 LLD LLD N/A LLD r Kr-88 LLD LLD N/A LLD Xe-131m LLD LLD N/A LLD Xe-133 3.96E+00 8.50E+00 N/A LLD ;
Xe-133m LLD LLD N/A LLD Xe-135 9.98E-01 LLD N/A LLD Xe-135m LLD LLD N/A LLD .
Total for Period: 4.96E+00 8.50E+00 N/A N/A l
Total for Period: 3.99E-04 2.69E-04 N/A N/A i
- 3. Particulates Ci H-3 4.47E+00 3.64E+00 N/A 1.34E-03 Co-58 LLD LLD N/A LLD Co-60 LLD LLD N/A LLD i Sr-89**' LLD LLD N/A LLD .
Cs-137 2.36E-06 1.43E-06 N/A LLD {
1 Total for Period: 4.47E+00 3.64E+00 N/A 1.34E-03 !
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DBNPS Semiannual Effluent Report 12 July - Dec., 1992 i i
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TABLE 3. GASECUS EFFLUENTS - MIXED-MODE RELEASES * (continued) ;
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i Abnormal releases not included. ;
These radionuclides were not identified in concentrations above the lower I limit of detection (LLD) listed below. The largest LLD value is listed.
Continuous Mode Batch Mode Ar-41: <2.9 E-08 pCi/ml Ar-41: <2.9 E-06 Ci/ml Kr-85: <3.3 E-06 pCi/ml Kr-85: <3.1 E-04 pCi/ml ;
Kr-85m: <1.3 E-08 Ci/ml Kr-85m: <2.2 E-06 pCi/ml Kr-87: <6.0 E-08 Ci/ml Kr-87: <4.5 E-06 Ci/ml ;
Kr-88: <6.0 E-08 pCi/ml Kr-88: <6.6 E-06 pCi/ml Xe-131m: <4.4 E-07 pCi/ml Xe-131m: <8.6 E-05 pCi/ml -
Xe-133m: <7.2 E-08 vCi/ml Xe-133 <3.9 E-06 pCi/ml '
Xe-135 <1.1 E-08 pCi/ml Xe-133m: <1.8 E-05 pCi/ml r Xe-135m: <5.9 E-06 Ci/ml Xe-135: <2.1 E-06 Ci/ml Xe-138: <2.0 E-05 Ci/ml Xe-135m: <1.4 E-05 pCi/ml :
I-131: <2.6 E-14 Ci/ml I-131: <2.7 E-06 Ci/ml '
I-133: <3.1 E-13 pCi/ml I-133: <3.0 E-06 pCi/ml Co-58: <1.6 E-14 pCi/ml Co-58: <3.0 E-06 pCi/ml >
Co-60: <2.5 E-14 Ci/ml Co-60: <3.7 E-06 pCi/ml i Sr-89(3): <7.2 E-16 yCi/ml Cs-134: <2.8 E-06 Ci/ml i Sr-89(4): <9.3 E-16 Ci/ml Cs-137: <3.3 E-06 pCi/ml ,
Sr-90(3): <2.9 E-16 Ci/ml ;
Sr-90(4): <3.1 E-16 pCi/ml '
Cs-134: <1.8 E-14 pCi/ml Cs-137: <2.4 E-14 Ci/ml
, Ru-103: <1.5 E-14 Ci/ml !
Quarterly composite sample for continuous mode. ;
Analysis not required for batch release.
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DBNPS Semiannual Effluent Report 13 July - Dec., 1992
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TABLE 4. CASEOUS EFFLUEtES - AB!ORFAL RELEASES ,
THIRD FOURTH ,
IUCLIDES UNIT QUARTER QUARTER
Xe-133m LLD LLD Xe-135 LLD LLD Xe-135m LLD LLD .
Xe-138 LLD LLD l Total For Period: N/A N/A
I-133 LLD LLD Total For Period: N/A N/A
- 3. Particulates Ci '
i H-3 1.15E-07 2.12E-08 Cs-134 LLD LLD Cs-137 LLD LLD :
Total For Period: 1.15E-07 2.12E-08 :
- These radionuclides were not identified in concentrations above the 1craer limit of detection (LLD) listed in Table 2. ,
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DENPS Semiannual Effluent Report 14 July - Dec.,=1992 j
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'IABLE 5. LICUID EFFLUENTS - SUMMATION OF ALL RELEASES EST. TOTAL THIRD ftXJRTH PERCDIT IMIT QUARTER QUARTER ERROR 7YPE A. Fission And Activation Products Ci 2.61E-02 2.98E-03 2.00E+01
- 1. Total Release (without Tritium, Gases, Alpha)
Average Diluted Concen-* Ci/ml 1.79E-07 1.89E-08 2.
tration During Period
- 3. Percent of ODCM % See Supplemental Information, Limit Section 7 -
8.10E-01 2.68E-01
- 4. Percent of 10CFR20 Iimit %
B. Tritium Ci 1.11E+02 7.19E+01 2.00E+01
- 1. Total Release Average Diluted Concen-
- Ci/ml 1.08E-05 6.20E-06 2.
tration During Period Percent of 10CFR20 Limit % 3.60E-01 2.06E-01 3.
C. Dissolved and Entrained Gases Ci 8.01E-04 1.46E-03 2.00E+01
- 1. Total Release
- 2. Average Diluted Concen-
- Ci/ml 5.48E-09 9.27E-09 tration During Period 2.74E-43 4.63E-03
- 3. Percent of Limit %
D. Gross Alpha 5.11E-03 3.06E-03 2.00E+01
- 1. Total Release ci liters 5.23E+07 7.85E+07 2.00E+01 E. Volume of Waste Released (prior to dilution) liters 1.03E+10 1.15E+10 2.00E+01 F. Volume of Dilution Water (used during releases) liters 1.04E+10 1.16E+10 2.00E+01 G. Total Volume of Water Released (Outfall 001)
- Based on volume of dilution water used during releases (Item F).
DBNPS Semiannual Effluent Report 15 July - Dec., 1992
I
. TABLE 6. LIQUID EFFLUENTS - NUCLIDES RELEASED
- CONTIl0005 MODE (Ci)* BATCH MODE (Ci)#
THIRD FOURTH THIRD IVURTH NUCLIDES QUARTER QUARTER QUARTER QUARTER
Mn-54 LLD LLD 1.78E-05 LLD Fe-55' LLD(C3) LLD(C4) 3.16E-03 LLD Fe-59 LLD LLD 3.90E-05 LLD j Co-57 LLD LLD 2.11E-05 LLD Co-58 LLD LLD 1.20E-02 4.57E-04 Co-60 LLD LLD 2.41E-03 1.56E-04 ,
Sr-89* LLD(C3) LLD(C4) LLD LLD S r-90* LLD(C3) LLD(C4) LLD LLD Zr-95 LLD LLD 1.31E-04 LLD ,
Zr-97 LLD LLD 9.49E-05 1.98E-06 Nb-95 LLD LLD 1.70E-04 LLD Nb-97 LLD LLD LLD 3.64E-06 Mo-99 LLD LLD LLD LLD Tc-99m LLD LLD 4.80E-06 LLD Ru-103 LLD LLD 4.26E-05 LLD ,
Ag-110m LLD LLD 2.22E-03 1.41E-04 Sb-124 LLD LLD 1.35E-04 LLD j Sb-125 LLD LLD 6.13E-04 4.44E-05 i Sn-113 LLD LLD 9.47E-05 3.81E-06 I-131 LLD LLD 1.68E-04 7.40E-05 ;
I-133 LLD LLD 4.11E-06 9.71E-06 Cs-134 LLD LLD 1.74E-03 7.78E-04 Cs-136 LLD LLD LLD LLD ,
Cs-137 LLD LLD 2.61E-03 1.31E-03 ,
Ba-140 LLD LLD 2.28E-06 LLD Ce-141 LLD LLD LLD LLD !
Total for period: N/A N/A 2.61E-02 2.98E-03 i
- 2. Tritium 2.36E-01 7.60E-01 1.11E+02 7.11E+01 i
- 3. Dissolved and Entrained Gases !
l Xe-133 LLD LLD 7.23E-04 1.39E-03 r Xe-133m LLD LLD LLD 4.04E-06 Xe-135 LLD LLD 7.81E-05 6.79E-05 I
Total for Period: N/A N/A 8.01E-04 1.46E-03 t
DBNPS Semiannual Effluent Report 16 July - Dec., 1992 i
TABLE 6. LIQUID EFFLUENTS - IUCLIDES RELEASED * (continued)
" Abnormal releases not included.
These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below.
Na-24: <1.2 E-08 Ci/ml Mn-54: <2.1 E-08 pCi/ml Cr-51: <1.7 E-07 pCi/ml Fe-55(B4C): <7.0 E-07 pCi/ml Fe-55(B3C): <9.0 E-07 Ci/ml co-57: <1.6 E-08 Ci/ml Fe-59: <4.2 E-08 pCi/ml Co-60: <2.5 E-08 pCi/ml co-58: <1.9 E-08 pCi/ml Kr-85: <6.2 E-06 pCi/ml In-65: <5.2 E-08 pCi/ml Sr-89(B4C): <2.0 E-08 pCi/ml Sr-89(B3C): <2.0 E-08 vCi/ml Sr-90(B4C): <7.0 E-09 Ci/ml Sr-90(B3C): <5.0 E-09 pCi/ml Zr-95: <4.0 E-08 pCi/ml Nb-95: <2.1 E-08 Ci/ml Zr-97: <2.5 E-08 pCi/ml Nb-97: <2.5 E-08 Ci/ml Mo-99: <1.6 E-07 Ci/ml Ru-103: <2.2 E-08 pCi/ml Tc-99m: <1.8 E-08 Ci/ml Ag-110m: <2.5 E-08 Ci/ml Sn-113: <2.8 E-08 pCi/ml Sb-125: <1.7 E-08 pCi/ml I-131: <2.5 E-08 pCi/ml I-133: <2.1 E-08 Ci/ml Xe-133: <4.6 E-08 Ci/ml Xe-133m: <1.6 E-07 Ci/ml Xe-135: <1.9 E-08 pCi/ml Ce-141: <3.0 E-08 Ci/ml Ce-144: <1.7 E-07 pCi/ml Cs-134: <2.1 E-08 Ci/ml Cs-136: <2.8 E-08 pCi/ml Cs-137: <2.7 E-08 pCi/ml Ba-140: <7.0 E-08 pCi/ml Cs-138: <6.7 E-08 pCi/ml Ce-141: <1.9 E-08 pCi/ml .
Sb-124: <1.7 E-08 pCi/ml I-133: C.8 E-08 pCi/ml ;
Quarterly cor.posite sample.
t
- LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.
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3 DBNPS Semiannual Effluent Report 17 July - Dec., 1992 ,
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TABLE 7. LIQUID EFFLUESTTS - ABtOTfAL RELEASES
- THIRD FOURTH NUCLIDES INIT QUARTER QUARTER
- 1. Fission and Activation Products N/A N/A !
- 2. Tritium Ci N/A N/A
- 3. Dissolved and Entrained Gases N/A N/A j 1
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- There were no abnormal liquid releases during the third and fourth quarters of 1992. ;
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DBNPS Semiannual Effluent Report 18 July - Dec., 1992 1
l TABLE 8. SOLID HASTE AND IRRADIATED FUEL SHIPMD CS A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) i EST. 'IDIAL i PERCE2R I
- 1. Type of Waste LNIT QUAV. IITY ERROR ,
I
- a. Spent resins, filter sludges, m' 2.33 E+01 evaporator bottoms, etc. Ci 3.4 E+00 2.5 E+01 l
- b. Dry compressible waste, m' 3.5 E+00 l contaminated equipment, etc. Ci 3.6 E-01 2.5 E+01 l
- c. Irradiated components, control m' O.0 E+00 rods, etc. Ci 0.0 E+00 2.5 E+01 !
- d. Other:
- 1. Dewatered Primary m'- 0.0 E+00 System Cartridge Filters Ci 0.0 E+00 2.5 E+01 :
- 2. Estimate of Major Nuclide Composition (by type of waste)
PERCD1T ABUNDANCE
Ag-110m 0.3
- 3. Solid Waste Disposition Number of Shipments: 1 e Mode of Transportation: Truck Destination: Barnwell, S.C.
Type of Container (Container Volume): 1 Resin HIC (5.8m') :
i Solidification Agents: None Nunber of Shipments: 1 Mode of Transportation: Truck ;
Destination: Scientific Ecology Group, Oak Ridge, 'IN. f Type of Container (Container Volume): 2 20 foot sealands of dry activated waste and contaminated metal (35m') :
Solidification Agents: None DBNPS Semiannual Effluent Report 19 July - Dec., 1992 {
i Table 8. SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (continued)
- 3. Solid Waste Disposition (con't.)
Number of Shipments: 1 Mode of Transportation: Truck Destination: Quadrex Recycle Center, Oak Ridge, TN.
Type of Container (Container Volume): 3 resin liner containers (6.2m') ;
and 4 dry activated waste boxes (2.7m')
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B. Irradiated Fuel Shipments t There were no shipments of irradiated fuel. ;
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DBNPS Semiannual Effluent Report 20 July - Dec., 1992
I TABLE 9. SEMIAtmAL DOSES DUE TO GASEOUS RELEASES j A. Maxinum Individual Doses Due to I-131, B-3, and Particulates with l Balf-lives Greater man 8 Days
- j
- 1. Whole Body Dose SECIOR DISTANCE (m) AGE DOSE (mrem)
Quarter 1 W 1720 child 7.58E-03 Quarter 2 W 1720 child 6.26E-04 Semiannual W 1720 child 8.20E-03 Quarter 3 W 1750 Child 6.34E-03 Quarter 4 W 1750 child 4.61E-03 .
Semiannual W 1750 child 1.10E-02 l Annual W 1750 Child 1.92E-02
- 2. Significant Organ Dose SECTOR DISTANCE (m) AGE ORGAN DOSE (mrem)
Quarter 1 W 1720 child myroid 1.42E-02 Quarter 2 W 1720 child Thyroid ~ 1.03E-03 Semiannual W 1720 child Thyroid 1.52E-02 Quarter 3 W 6530 Infant Thyroid 7.78E-02 Ouarter 4 W 6530 Infant tyroid 5.09E-02 Semiannual W 6530 Infant Thyroid 1.29E-01 Annual W 6530 Infant Thyroid 1.44E-01 B. Maxinum Individual Doses Due to Noble Gas' f
- 1. Whole Body Dose SECIOR DISTANCE (m) AGE DOSE (mrem)
Quarter 1 W 980 !a 2.77E-03 Quarter 2 W 980 la 1.27E-03 Semiannual W 980 la 4.04E-03 Quarter 3 W 980 la 1.16E-03 Quarter 4 W 980 la 6.53E-04 Semiannual W 980 la 1.81E-03 ;
i' Annual W 980 ta 5.85E-03 i
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DBNPS Semiannual Effluent Report 21 July - Dec., 1992 l
Table 9. SEMIANNUAL DOSES DUE 'IO GASEOUS RELEASES (continued)
- 2. Skin Dose SECIOR DISTANCE (m) AGE DOSE (mrem) ,
Quarter 1 W 980 !a 7.48E-03 !
Quarter 2 W 980 !a 3.44E-03 Semiannual W 980 NA 1.09E-02 Quarter 3 W 980 !a 3.12E-03 Quarter 4 W 980 NA 1.83E-03 !
Semiannual W 980 NA 4.95E-03 ,
Annual W 980 NA 1.58E-02 >
C. Population Doses due to I-131, B-3, and Particulates with .
Half-lives Greater than 8 Days *
'IOTAL IhTEGRATED AVERAGE DOSE 'IO POPULATIOi DOSE INDIVIDUALS IN ORGAN (person rem) POPULATIO4 (mrem)
Quarter 1 W/ body 5.70E-03 2.56E-06 Quarter 2 W/ body 4.67E-04 2.10E-07 Semiannual W/ body 6.17E-03 2.77E-06 Quarter 3 W/ body 3.90E-03 1.75E-06 Ouarter 4 W/ body 2.62E-03 1.18E-06 Semiannual W/ body 6.52E-03 2.93E-06 ,
Annual W/ body 1.27E-02 5.70E-06 D. Population Doses due to Noble Gas'
'IOTAL INTEGRATED AVERAGE DOSE 'IO POPULATIQ4 DOSE INDIVIDUALS IN ORGAN (person rem) POPULATIQi (mrem)
Quarter 1 W/ body 2.77E-03 1.24E-06 Quarter 2 W/ body 1.21E-03 5.42E-07 ,
Semiannual W/ body 3.98E-03 1.78E-06 ,
Quarter 3 W/ body 8.56E-04 3.85E-07 Quarter 4 W/ body 5.85E-04 2.63E-07 Semiannual W/ body 1.44E-03 6.48E-07 ;
Annual W/ body 5.42E-03 2.43E-06 j I
DBNPS Semiannual Effluent Report 22 July - Dec., 1992 l
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l BBLE 9. SEMIAINUAL DOSES DUE 'IO GASDOUS RELEASES (continued)
E. Abnonnal Releases due to the Emergency Escape Batch surveillance -
Test and Gland Seal Steam Regulator Failure
Half-lives Greater than 8 Days :
A. hhole Body Dose SECIOR DISTANCE (m) AGE DOSE (mrem)
Quarter 3 N 880 Teen 9.79E-11 '
Ouarter 4 N 880 Teen 6.69E-12 '
Semiannual N 880 Teen 1.04E-10 B. Significant Organ Dose SECIOR DISTANCE (m) AGE ORGAN DOSE (mrem) i i
Quarter 3 N 880 Child 'Ihyroid 2.27E-11 ;
Quarter 4 N 880 Teen T-body 6.69E-12 Semiannual N 880 child Thyroid 2.27E-11 ,
- 2. Maximum Individual Dose due to Noble Gas SECIOR DISTANCE (m) AGE ORGAN DOSE (mrem) t Quarter 3 N/A N/A N/A 0.00E+00 !
Quarter 4 N/A N/A N/A 0.00E+00 Semiannual N/A N/A N/A 0.00E+00 l
Does not include abnormal releases.
DBNFS Semiannual Effluent Report 23 July - Dec., 1992
'IABLE 10. S911A!NUAL DOSES DUE 'IO LIQUID RELEASES A. Maxi == Individual Whole Body Dose SECIOR DISTM1CE(mi) AGE DOSE (mrem)
Quarter 1 IM 0.6 Adult 5.02E-02 Quarter 2 IM 0.6 Adult 2.02E-02 ,
Semiannual IM 0.6 Adult 7.04E-02 Quarter 3 IM 0.6 Adult 4.26E-02 Quarter 4 IM 0.6 Adult 1.97E-02 Semiannual !M 0.6 Adult 6.23E-02 Annual IM 0.6 Adult 1.23E-01 t
B. Mri = = Irdividual Significant Organ Dose ,
SEC'IOR DISTANCE (mi) AGE ORGAN DOSE (mrem)
Quarter 1 IM 0.6 Teen Liver 6.83E-02 Quarter 2 ru 0.6 Teen Liver 2.51E-02 Semiannual ru 0.6 Teen Liver 9.34E-02 !
f Quarter 3 ru 0.6 Teen Liver 5.70E-02 {
Ouarter 4 IM 0.6 Teen Liver 2.62E-02 Semiannual is 0.6 Teen Liver 8.32E-02 Annual IM 0.6 Teen Liver 1.77E-01 !
C. Population Dose
'IDIAL IITIEGRATED AVERAGE DOSE TO !
POPUIATIG4 DOSE INDIVIDUALS IN !
ORGAN (person rem) POPUIATIO4 (mrem) !
Quarter 1 W/ body 7.99E-01 3.59E-04 :
Quarter 2 W/ body 3.95E-01 1.78E-04 :
Semiannual W/ body 1.19E+00 5.37E-04 ;
i Quarter 3 W/ body 4.35E-01 1.96E-04 ,
Quarter 4 W/ body 1.90E-01 8.54E-05 ;
Semiannual w/ body 6.25E-01 2.81E-04 j.
Annual W/ body 1.81E+00 8.18E-04 l l
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DBNPS Semiannual Effluent Report 24 July - Dec., 1992
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TABLE 11. 1992 RNAL DOSE TO THE MOST-EKPOSED MEMBER OF THE PUBLIC .
40 CPR 190 SEMIN NUAL DOSE LIMITS PERCDC OF ,
(mrem) (mrem) LIMITS Whole Body Dose
- Noble Gas 5.85E-03
Particulates 1.92E-02 .
- Liquid 1.33E-01 Total Whole Body Dose 1.58E-01 25 6.32E-01 :
Thvroid Dose
-Iodine, Tritium, 1.44E-01 75 1.92E-01 Particulates ;
Skin Dose
- Noble Gas 1.59E-02 25 6.34E-02 [
Liver Dose l r
- Liquid 1.77E-01 25 7.08E-01 j l
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DBNPS Semiannual Effluent Report 25 July - Dec., 1992
iu.AwiOIMICAL DNIA !
o Meteorological data on magnetic tape for January through June 1992 has been submitted with this document to the U.S. Nuclear Regulatory Commission Document Control Desk, Washington, D.C. 20555. i i
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i DBNPS Semiannual Effluent Report 26 July - Dec., 1992 i
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