ML20072S832

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Radioactive Effluent Release Rept Jul 1993 - June 1994
ML20072S832
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/30/1994
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20072S827 List:
References
NUDOCS 9409140260
Download: ML20072S832 (30)
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The Davis-Besse Nuclear Power Station l Radioactive Effluent Release Report l .

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Radiation Protection Section  !

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9409140260 DR 940826 ADOCK 05000346 PDR J

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RADIOACTIVE EFFLUENT RELEASE REPORT Davis-Besse Nuclear Power Station Unit No. 1 July 1, 1993 through June 30, 1994 Docket Number 50-346 License Number NPF-3 l

Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 August 1994 l

i

TABLE OF CONTENTS

  • Title Page List of Tables 11 Summary 1 Supplemental Information 3 Effluent Data Tables 10 Meteorological Data 26 0

DBNPS Radioactive Effluent -i- July 1. 1993 - June 30, 1994 Release Report

LIST OF TABLES Table Number Title Page 1 Gaseous Effluents - Summation of 10 All Releases 2 Gaseous Effluents - Ground Level Releases 12

a. Batch

. b. Continuous 3 Gaseous Effluents - Mixed Mode Releases 14

a. Batch
b. Continuous 4 Liquid Effluents - Summation of 17 all Releases 5 Liquid Effluents - Nuclides Released 19
a. Batch
b. Continuous 6 Solid Vaste and Irradiated Fuel 22 Shipments 7 Annual Doses Due to Gaseous 24 Releases 8 Annual Doses Due to Liquid 24 Releases 9 Annual Dose to the Most 25 Exposed Member of the Public DBNPS Radioactive Effluent -ii- July 1, 1993 - June 30, 1994 Release Report

SUMMARY

The Radioactive Effluent Release Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period from July 1, 1993 through June 30, 1994.

This report provides the following information:

. Summation of the quantities of radioactivity released in gaseous and g liquid effluents, g

. Summation of the quantities of radioactivity contained in solid vaste packaged and shipped for offsite disposal at federally approved sites, and

. A listing of all radioactive effluent monitoring instrumentation (_

required by the Offsite Dose Calculation Manual (0DCM), but which (r

vere inoperable for more than 30 days.  %

Environmental samples were available from the locations specified in Table 6-1 of the Offsite Dose Calculation Manual (0DCM) during this reporting period.

Sampling of milk at location T-8 vas discontinued in December, 1993. The ,

individual at that location ceased his dairy operation; there is no other dairy animal within 8 km (5 miles) of the plant. Broad Leaf Vegetation sampling was ( _._--

substituted for milk sampling according to paragraph 4.c of the ODCM, Table 6-1.

The locations used for dose calculations and environmental monitoring vere those identified by the 1993 Land Use Census.

During the period of July 1, 1993 through June 30, 1994, the estimated maximum individual offsite dose due to radioactivity released in effluents vas:

Liquid Effluents:

. 6.05E-02 mrem, whole body

. 7.87E-02 mrem, liver Gaseous Effluents:

Noble Gas:

. 1.06E-03 mrad, whole body

. 3.87E-03 mrad, skin DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

Iodine - 131, Tritium, and Particulates with Half-lives greater than 8 Days:

. 5.54E-04 mrem, whole body

. 7.92E-03 mrem, thyroid These doses represent an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCH.

Additional normal release pathways from the secondary system exist. For gaseous ~

n effluents, these pathways include the auxiliary feed pump turbine exhausts, the main steam safety valve system and the atmospheric vent valve system. For <^

liquid effluents, the additional pathways include the Turbine Building drains via the settling basins. Releases via these pathways are included in the normal release tables in this report.

c There were no abnormal liquid releases this reporting period. Three abnormal gaseous releases occurred during this reporting period.

No changes to the Process Control Program (PCP) occurred during this time period. Revision 6 to the Offsite Dose Calculation Manual was written during this reporting period and accompanies this report. Additionally, ODCM Rev 5.2 and PCP Rev 5.0 accompany this report in compliance with Technical _-_----

Specification requirements. ..

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

L' SUPPLEMENTAL INFORMATION

1. Regulatory Limits A. Gaseous Effluents
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:

~ _z

a. Nob a gases: .

1_

- Less than or equal to 500 mrem / year to the whole body. b (Davis Besse ODCM limit is 50 mrem in a year)

- Less than or equal to 3000 mrem / year to the skin.

b. Iodine - 131, tritium, and all radionuclides in particulate form z with half-lives greater than 8 days:

- Less than or equal to 1500 mrem / year to any organ.

2. In accordance with 10CFR50, Appendix I, Sec. IIB.1, air dose due to radioactivity 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 than or equal to 10 mrad for beta radiation in any calendar quarter.
b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation in any calendar year.

In accordance with 10 CFR 50, Appendix I, Sec. IIC, dose to a member of the public from Iodine-131, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

a. Less than or equal to 7.5 mrem to any organ in any calendar quarter.
b. Less than or equal to 15 mrem to any organ in any calendar year.

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:

1. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ in any calendar quarter.
2. Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ in any calendar year.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

2. EFFLUENT CONCENTRATION LIMITS The Effluent Concentration Limits (ECs) for liquid and gaseous effluents at and beyond the site boundary are listed in 10CFR20, Appendix B, Table II, Column 2, with the most restrictive EC being used in all cases. For dissolved and entrained gases the EC of 2.0E-04 pCi/ml is applied. This EC is based on the Xe-135 DAC of 1x10" Ci/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.
3. AVERAGE DERGY The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activation products to less than or equal to 50 mrem in a year to the total body and less than or equal to 3000 mrenVyear to the. skin.

Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,"

are not applicable.

4. MEASUREMENIS AND APPROKIME"ICNS OF 'IOTAL ACTIVITY 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 emitters.

Detected radionuclides are quantified via gamma spectroscopy.

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 via gamma spectroscopy.
c. Particulates are collected on filter paper and counted on a germanium detector. Specific quantification of each radionuclide present on the filter paper is via gamma spectroscopy.
d. Liquid effluents are collected in a marinelli beaker and counted on a germanium detector. Specific quantification of each radionuclide present in liquid samples is via gamma spectroscopy.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

5. BAIG RELEASES A. Liquid from 7/1/93 to 6/30/94
1. Number of batch releases: 32
2. Total time period for the batch releases: 50.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />
3. Maximum time period for a batch release: 197 minutes
4. Minimum time period for batch releases: 58 minutes p i
5. Average time period for a batch release: 95.4 minutes B. Gaseous from 7/1/93 to 6/30/94
1. Number of batch releases: 7
2. Total time period for the batch releases: 70.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
3. Maximum time period for a batch release: 1389 minutes
4. Minimum time period for a batch release: 198 minutes
5. Average time period for batch releases: 601 minutes ,
6. ABNORMAL RELEASES On October 8, 1993 a small amount of radioactive steam was released from the Main Steam Safety Valves and Atmospheric Vent Valve due to a Reactor Trip.

There were 9.30E-6 curies of tritium released which resulted in no quantifiable gamma and beta gas air dose. A dose of 3.07E-9 mrem resulted from iodine and particulates which is 2.05 E-08 percent of the annual limit.

(PCAQ 93-0455)

On December 21, 1993, while purging the Makeup Tank gas space to the Reactor Coolant Drain Tank (RCDT) in preparation for taking a Makeup Tank Gas Sample, a release of noble gas occurred. The noble gas leak occurred due to multiple causes. The release was vented through the station vent.

A total of 16.5 curies of noble gas was released. The resulting gamma air dose at the site boundary was 8.8E-4 mrad and beta air dose was 1.3E-3 mrad.

The percent of limit was 8.8E-03 percent and 6.5E-03 percent for gamma and beta air dose, respectively. (LER 93-008 and PCAQ 93-0603)

On January 28, 1994, while venting RC160 to a poly bottle from the RCDT a small amount of radioactive gas was released. The release was vented through the station vent to the atmosphere. A total of 6.77E-1 curies of Xe-133 was released. The resulting gamma air dose was 1.39E-5 mrad and beta air dose was 4.12E-5 mrad. The percent of limit for this release was 1.4E-4 percent and 2.1E-4 percent for gamma and beta air dose, respectively.

(PCAQ 94-0107)

The resultant dose from these releases represent a small fraction of the Davis-Besse Offsite Dose Calculation manual (ODCM) release limits.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 j Release Report

7. PERCENT OF ODCM RELEASE LIMITS The following table presents the ODCM dose limits and the associated offsite dose to the public, in percent of limits, for July 1, 1993 through June 30, 1994.

Specification Limit Percent of Limit A. Report Period July 1, 1993 - June 30, 1994 (Gaseous)

Noble gases (gamma) 10 mrad 1.06E-02 i Noble gases (beta) 20 mrad 1.94E-02 I-131, tritium, and 15 mrem 5.20E-02 particulates with half-lives greater than 8 days.

B. Reporting Period July 1, 1993 June 30, 1994 (liquid)

Total body 3 mrem 2.02E+00 Organ 10 mrem 7.87E-01 l DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

8. DOSE ASSESSMENT Sources of input data include:

A. Water 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."

B. O-50 mile meat, milk, vegetable production, and population data: 1982 Annual Environmental Operating Report, report entitled, " Evaluation of =

Compliance with Appendix I to 10 CFR 50: Updated Population, Agricultural, Meat - Animal, and Milk Production Data Tables for 1982."

This evaluation was based on the 1980 census; the Agricultural Ministry of Ontario 1980 Marketing Account, 1980"; the Agricultural Ministry or Ontario 1980 report entitled " Agricultural Statistics for Ontario - 1980 Publication 21, 1980"; the Michigan Department of Agriculture, July, 1981"; the Ohio Crop Reporting Service, 1981 report entitled, " Ohio Agricultural Statistics, 1981."

C. Gaseous and liquid source terms: Tables 1 through 5 of this report.

D. Location of the nearest individuals and pattrsays by sector out to 5 miles: Report entitled, "1993 Land Use Census," included in the 1993 Annual Radiological Environmental Operating Report for Davis-Besse.

t

9. DOSE TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE DOUNDARY In accordance with ODCM Section 7.2, the Radioactive Effluent Release Report includes an assessment of radiation doses from radioactivity released in liquid and gaseous effluents to members of the public due to activities inside the site boundary.

In special instance, 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 will receive any 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. Considering the frequency and duration of the visits, the resultant dose would be a small fraction of the calculated maximum site boundary dose. For purposes of assessing the dose to members of the public in accordance with ODCM Section 7.2, the following exposure assumptions are used:

Exposure time for maximumally-exposed visitors is 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 maximum).

Annual average meteorological disperaion (conservative, default use of maximum site boundary dispersion).

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

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 ODCM conservatively estimates the maximum potential dose to members of the public.

10. INOPERABLE RADIOACTIVE EFFLUENT MONI'IORING EQUIPMENT The following radioactive effluent monitoring equipment required to be operable by ODCM Section 2.1 and 3.1 was inoperable for more than 30 days during this reporting period.

. Total Dilution Flow, Computer Point F-201, was unavailable for greater than thirty days due to FE-3611 dilution flow element probe .

malfunctioning. Upon completion of maintenance activity, the computer point was returned to service. During the time period that the computer point was out of service, total dilution flow was estimated using other methods.

(PCAQ 93-0514)

. The following radioactive effluent monitors were unavailable for more than thirty days due to modification (Mod 92-0046) which replaced the detectors and Control Room readouts. The logarithmic meter readouts were }q replaced with digital readouts. The detectors were replaced with new (

detectors. Effected monitors were:

- RE 1770 A Clean Radwaste System Outlet

- RE 1770 B Clean Radwaste System Outlet

- RE 1878 A Miscellaneous Radwaste System Outlet Upon completion of maintenance activities, the RE's were returned to service. During the time period that the instruments were out of service, releases were conducted in accordance with ODCM requirements.

11. CHANGE 'ID 'IHE ODCM AND PCP There were no changes to the PCP and one revision (6.0) to the ODCM.

The previous revisions, ODCM 5.2 and PCP 5.0, are accompanying this report in accordance with Technical Specifications.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 ,

Release Report

12. CHANGES 'IO 'IHE LAND USE Pathway Location and Corresponding Atmospheric Dispersion (X/Q) and Deposition (D/Q) Parameters SEC'IOR METERS CRITICAL AGE X/Q PATKdAY GROUP (SEC/M') D/g)

(M~

4.

N 880 INHALATION CHILD 9.15E-07 8.40E-09 NNE 870 INHALATION CHILD 1.27E-06 1.47E-08 NE 900 INHALATION CHILD 1.26E-06 1.58E-08 ENE* - - - - -

E* - - - - -

ESE* - - - - -

SE* - - - - -

~

SSE 2880 VEGETATION CHILD 6.85E-08 8.02E-10 S 1440 VEGETATION CHILD 1.22E-07 2.48E-09 SSW 1560 VEGETATION CHILD 1.03E-07 2.28E-09 SW 1050 VEGETATION CHILD 2.92E-07 5.33E-09 WSW 4270 CON / MILK INFANT 5.71E-08 5.31E-10 W 6530 GOAT / MILK INFANT 4.54E-08 2.79E-10 WNd 1750 VEGETATION CHILD 1.46E-07 1.72E-09 Nd** 2660 VEGETATION CHILD 5.89E-08 4.41E-10 NNW 1490 VEGETATION CHILD 1.64E-07 1.26E-09 Since these sectors are located over marsh areas and Lake Erie, no ingestion '

pathways are present.

    • Changes since 1992.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

1 4

nBLE 1. GASEOUS EFFLUI2frS - SUMMATION OF ALL RELEASES THIRD FOURTH EST. 'IOTAL TYPE UNIT QUARTER QUARTER (PERCENT 1993 1993 ERROR)

A. Fission and Activation Gases

1. Total Release Ci 1.48E+00 1.91E+01 2.50E+01 a1
2. Average Release Ci/sec 1.86E-01 2.43E+00 Rate for period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 B. Iodines
1. Total Iodine ci 9.75E-05 3.68E-04 2.50E+01
2. Average Release Ci/sec 1.23E-05 4.63E-05 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 C. Particulates
1. Particulates with Ci 2.14E-06 N/A 2.50E+01 Half-lives greater than 8 days
2. Average Release vCi/sec 2.69E-07 N/A Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7
4. Gross Alpha Ci 4.45E-07 1.80E-07 2.50E+01 Activity D. Tritium
1. Total Release ci 7.53E+00 4.55E+00 2.50E+01
2. Average Release Ci/sec 9.47E-01 5.72E-01 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

TABLE 1. GASEOUS EFFLUENTS - SUMMATIO4 OF ALL RELEASES (continued)

FIRST SECOND EST. TOTAL TYPE UNIT QUARTER QUARTER (PERCENT 1994 1994 ERROR)

A. Fission and Activation Gases

1. Total Release ci 5.04E+00 3.97E+01 2.50E+01
2. Average Release Ci/sec 5.48E-01 2.38E+00 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 B. Iodines ,

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1. Total Iodine Ci 1.32E-04 6.50E-04 2.50E+01
2. Average Release Ci/sec 1.70E-05 8.27E-05 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 C. Particulates
1. Particulates with Ci 4.55E-07 2.79E-05 2.50E+01 Half-lives greater than 8 days
2. Average Release Ci/sec 5.85E-08 3.55E-06 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7
4. Gross Alpha Ci 3.94E-07 6.23E-08 2.50E+01 Activity D. Tritium
1. Total Release Ci 4.09E+00 4.02E+00 2.50E+01
2. Average Release Ci/sec 5.26E-01 5.11E-01 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

BBLE 2. GASEUS EFFIUDTr5 - GROWD-ILVEL RELEASES' BATCH MODE THIRD FOURTH FIRST SECOND NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER 1993 1993 1994 1994 l

1. Fission Gases Ci Kr-85 N/A N/A N/A N/A s Kr-85m N/A N/A N/A N/A 1 Kr-87 N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Xe-135M N/A N/A N/A N/A -

.=

Xe-138 N/A N/A N/A N/A _

Total for Period: N/A N/A N/A N/A

2. Iodines Ci
  • I-131 N/A N/A N/A N/A I-133 N/A N/A N/A N/A [

I-135 N/A N/A N/A N/A i Total for Period: N/A N/A N/A N/A

3. Particulates Ci H-3 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Ba-140 N/A N/A N/A N/A Total for Period: N/A N/A N/A N/A DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

TABLE 2. GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES" CONTINUOUS MODE THIRD FOURTH FIRST SECOND NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER 1993 1993 1994 1994

1. Fission Gases Ci b

Kr-85 LLD 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

2. Iodines Ci I-131 LLD LLD LLD LLD I-133 LLD LLD LLD LLD I-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A
3. Particulates Ci H-3 7.36E-06 9.96E-06 1.74E-06 7.42E-06 Sr-89 LLD LLD LLD LLD Sr-90 LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD LLD Ba-140 LLD LLD LLD LLD Total for Period: 7.36E-06 9.96E-06 1.74E-06 7.42E-06 Includes Atmospheric Vent Valve weepage, Auxiliary Feed Pump Turbine -

tests, and Main Steam Safety valve testing and Reactor Trip which are listed as continuous releases. All batch releases are mixed-mode.

b These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below:

H-3: <3.6E-06 Ci/ml Ar-41: <2.2E-08 Ci/ml Xe-133: <4.6E-08 Ci/ml Kr-85: <6.2E-06 Ci/ml Xe-133m: <1.6E-07 Ci/ml Kr-85m: <2.0E-08 Ci/ml Xe-135: <1.9E-08 Ci/ml Kr-87: <3.5E-08 Ci/ml Xe-138: <2.5E-07 Ci/ml I-131: <1.0E-06 vCi/ml Cs-134: <2.1E-08 Ci/ml I-133: <2.1E-08 vCi/ml I-135: <2.1E-08 Ci/ml Sr-89: <5.0E-08 pCi/ml Sr-90: <6.0E-09 vC1/ml Kr-88: <4.0E-08 Ci/ml Cs-137: <3.0E-08 pCi/ml Xe-135m: <4.0E-07 Ci/ml Ba-140: <7.0E-08 Ci/ml DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

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4

TABLE 3. CASEOUS EFFLUENTS - MIXED-MODE RELEASES"

);

BATCH MODE THIRD FOURTH FIRST SECOND )

NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTERi )

1993 1993 1994 1994 i f- 1. Fission Gases Ci Ar-41 LLIf LLD LLD 3.59E-02 j Kr-85 2.05E-01 1.24E+00 LLD 2.81E+00 i

Kr-85m LLD -LLD _LLD 2.19E-03

! Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD i Xe-131m LLD LLD LLD 3.00E-01 i Xe-133 9.91E-04 3.12E-02 LLD 1.31E+01

Xe-133m LLD LLD LLD 6.62E-02  ;

. Xe-135 LLD LLD LLD 4.48E-02

} Xe-135m LLD LLD LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: 2.06E-01 1.27E+00 N/A 1.64E+01  ;

i

2. Iodines Ci I-131 LLD LLD LLD 1.59E-04 i
- I-132 LLD LLD LLD 1.91E-05  !

I-133 LLD LLD LLD 1.18E-04  :

I-135 LLD LLD LLD 6.84E-05 I i

Total for Period: N/A N/A N/A 3.65E-4 1 I

, 3. Particulates Ci j

j H-3 4.87E-03 3.93E-03 LLD 2.17E-01 Na-24 LLD LLD LLD 1.19E-06

) Co-58 LLD LLD LLD 3.10E-06 Co-60 LLD LLD LLD 2.97E-07 i Ru-106 LLD LLD LLD 1.07E-06 j Cs-134 LLD LLD LLD 8.45E-06 Cs-137 LLD LLD LLD 1.22E-05 Ba-140 LLD LLD LLD LLD 5 Total for Period: 4.87E-03 3.93E-03 N/A 2.17E j e

1 4

1 1

DBNPS Radioactive Effluent July 1, 1993 - June 30,_1994

Release Report j

)

' j

nBLE 3. GASBOUS EFFLUENTS - MIXED-MODE RELEhSES" (continued)

CONTNUOUS MODE THIRD FOURTH

  • FIRST SECOND NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER 1993 1993 1994 1994
1. Fission Gases Ci Ar-41 LLD 1.36E-02 LLD LLD Kr-85 LLD LLD LLD LLD Kr-85m LLD 2.67E-01 LLD LLD Kr-87 LLD 9.67E-02 LLD LLD Kr-88 LLD 3.07E-01 LLD LLD Xe-131m LLD LLD LLD LLD Xe-133 1.27E+00 1.44E+01 4.70E+00 2.33E+01 Xe-133m LLD 2.59E-01 LLD LLD Xe-135 LLD 2.44E+00 3.36E-01 LLD Xe-135m LLD 3.51E-02 LLD LLD Xe-138 LLD LLD LLD LLD Total for Period: 1.27E+00 1.78E+01 5.04E+00 2.33E+01
2. Iodines Ci I-131 4.99E-05 2.77E-04 7.55E-05 1.32E-04 I-132 LLD LLD LLD' 1.91E-05 I-133 4.76E-05 9.12E-05 5.60E-05 1.34E-04 I-135 LLD LLD LLD' LLD Total for Period: 9.75E-05 3.68E-04 1.32E-04 2.85E-04
3. Particulates Ci H- 3 7.53E+00 4.55E+00 4.09E+00 3.80E+00 Sr-89*** LLD LLD LLD LLD Sr-90*** LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 2.14E-06 LLD 4.55E-07 1.62E-06 Ba-140 LLD LLD LLD LLD Total for Period: 7.53E+00 4.55E+00 4.09E+00 3.80E+00 i

i DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994

Release Report

nBLE 3. GASEOUS EFFLUENIS - MIXED-MODE RELEASES" (continued)

Ahtormal releases included.

b These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below. The largest LLD value is listed.

Continuous Mode Batch Mode Ar-41: <2.9 E-08 Ci/ml Ar-41: <2.9 E-06 Ci/ml Kr-85: <3.3 E-06 Ci/ml Kr-85m: <2.2 E-06 pCi/ml Kr-85m: <1.3 E-08 Ci/ml Kr-87: <4.5 E-06 pCi/ml Kr-87: <6.0 E-08 pCi/ml Kr-88: <6.6 E-06 Ci/ml Kr-88: <6.0 E-08 Ci/ml Xe-133m <1.8 E-05 Ci/ml Xe-131m: <4.4 E-07 vCi/ml Xe-135m <1.4 E-05 pCi/ml Xe-133m: <7.2 E-08 pCi/ml I-135: <1.0 E-05 vCi/ml Xe-133: <2.0 E-08 pCi/ml Co-60: <3.7 E-06 Ci/ml Xe-135m: <5.9 E-06 Ci/ml Ru-103: <2.8 E-06 pCi/ml Xe-135: <1.1 E-08 Ci/ml Ba-140: <1.1 E-05 vCi/ml I-135: <3.9 E-10 pCi/ml Ce-144: <1.4 E-05 Ci/ml Mn-54: <2.6 E-14 Ci/ml Mn-54: <9.5 E-07 Ci/ml Co-58: <1.6 E-14 Ci/ml Na-24: <9.8 E-07 pCi/ml Co-60: <2.5 E-14 Ci/ml H-3 <1.6 E-09 C1/ml Sr-89: <9.3 E-16 pCi/ml Co-58 <3.0 E-06 Ci/ml Sr-90: <3.1 E-16 Ci/ml Kr-85 <3.1 E-04 Ci/ml Cs-134: <1.8 E-14 Ci/ml Xe-131m <3.2 E-05 vCi/mi Ba-140: <8.4 E-15 vCi/ml Xe-133 <3.9 E-06 vCi/ml Ce-144: <1.2 E-13 pCi/ml Xe-135 <2.1 E-06 pCi/ml Ru-103: <2.4 E-14 Ci/ml Xe-138 <2.8 E-05 pCi/ml Xe-138 <2.0 E-05 Ci/ml I-131 <2.7 E-06 vCi/ml Cs-137 <2.4 E-14 Ci/ml I-132 <1.1 E-06 vCi/ml I-133 <3.0 E-06 Ci/ml Ru-106 <1.2 E-05 Ci/ml Cs-134 <2.8 E-06 pCi/ml Cs-137 <3.3 E-06 vCi/ml Quarterly composite sample for continuous mode.

Analysis not required for batch release.

Fourth Quarter Fission Gases curies include the Make-up Tank release. The tritium curies for fourth quarter includes the Reactor Trip.

First Quarter Fission Gases curies include RCDT release.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

TABLE 4. LIQUID LN - SIR 9%TICN OF ALL RELEASES THIRD FOURTH EST. 'IOTAL TYPE UNIT QUARTER QUARTER PERCENT 1993 1993 ERROR A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (without Ci 1.07E-02 1.66E-03 2.00E+01 Tritium, Gases, Alpha)
2. Average Diluted Concen- Ci/ml 1.69E-07 2.84E-08 tration during Period'
3. Percent of ODCM  % See Supplemental Information, Limit Section 7
4. Percent of 10CFR20 Limit  % 3.55E+00 7.81E-01 B. Tritium
1. Total Release Ci 2.22E+01 3.98E+01 2.00E+01
2. Average Diluted Concen- Ci/ml 2.37E-06 3.83E-06 tration During Period *
3. Percent of 10CFR20 Limit  % 2.37E-01 3.83E-01 C. Dissolved and Entrained Gases
1. Total Release Ci N/A 2.39E-05 2.00E+01
2. Average Diluted Concen- Ci/ml N/A 4.09E-10 tration During Period'
3. Percent of 10CFR20 Limit  % N/A 2.05E-04 D. Gross Alpha
1. Total Release Ci 2.72E-06 N/A 2.00E+01 E. Volume of Waste Released (prior to dilutions)
1. Batch liters 2.30E+05 2.12E+05 2.00E+01
2. Continuous 4.60E+07 5.19E+07 F. Volume of Dilution Water (used during releases)
1. Batch liters 6.34E+07 5.85E+07 2.00E+01
2. Continuous 9.30E+09 1.03E+10 G. Total Volume of Water liters 9.36E+09 1.04E+10 2.00E+01 Released Tritium is found in both continuous and batch releases. Fission & Activation products and Dissolved and Entrained Gases are only found in batch releases.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

TABLE 4. LIQUID EFFLUDfrS - SUMMATICN OF ALL RELEASES (continued)

FIRST SECOND EST. 'IOTAL TYPE UNIT QUARTER QUARTER ( PERCD4T 1994 1994 ERROR)

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (without Ci 2.16E-03 7.80E-03 2.00E+01 Tritium, Gases, Alpha)
2. Average Diluted Concen- Ci/ml 5.12E-09 7.03E-08 tation during Period *
3. Percent of ODCM  % See Supplemental Information, Limit Section 7
4. Percent of 10CFR20 Limit  % 2.16E-01 1.85E+00 B. Tritium
1. Total Release Ci 3.25E+01 1.41E+02 2.00E+01
2. Average Diluted Concen- pCi/ml 3.55E-06 1.31E-05 tration During Period *
3. Percent of 10CFR20 Limit  % 3.55E-01 1.31E+00 C. Dissolved and Entrained Gases
1. Total Release Ci N/A 1.61E-01 2.00E+01
2. Average Diluted Concen- Ci/ml N/A 1.45E-06 tration During Period *
3. Percent of 10CFR20 Limit  % N/A 7.25E-01 D. Gross Alpha
1. Total Release Ci N/A 3.96E-06 2.00E+01 E. Volume of Waste Released (prior to dilutions)
1. Batch liters 1.68E+05 3.77E+05 2.00E+01
2. Continuous 1.06E+08 8.20E+07 F. Volume of Diluted Water (used during releases)
1. Batch liters 4.22E+08 1.11E+08 2.00E+01
2. Continuous 8.74E+09 1.07E+10 G. Total Volume of Water liters 9.16E+09 1.08E+10 2.00E+01 Released Tritium is found in both continuous & batch releases. Fission and Activation products & Dissolved and Entrained Gases are only found in batch releases.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Felease Report

TABLE 5. LIQUID EFFLUENTS - NUCLIDES RELEASED BATCH RELEASES

  • THIRD FOURTH FIRST SECOND Nuclides Unit Quarter Quarter Quarter Quarter 1993 1993 1994 1994
1. Fission and Activation Products Cr-51 Ci LLD LLD LLD LLD Mn-54 2.59E-05 3.72E-06 2.22E-06 7.71E-06 Fe-55 1.81E-03 7.00E-04 5.88E-04 2.00E-03 Co-57 2.18E-05 9.33E-07 4.00E-06 2.46E-05 Co-58 4.22E-03 1.85E-04 1.34E-04 3.73E-04 Co-60 1.12E-03 1.83E-04 2.24E-04 1.35E-03 Zn-65 LLD LLD LLD LLD Se-75 9.08E-05 LLD 2.24E-06 LLD Sr-89 LLD LLD LLD LLD Sr-90**' LLD LLD LLD LLD Nb-95 7.56E-05 LLD LLD LLD Nb-97 9.62E-06 4.05E-06 LLD LLD Zr-95 5.15E-05 1.18E-06 LLD LLD Zr-97 7.62E-05 2.49E-06 1.87E-05 7.19E-05 Mo-99 LLD LLD LLD LLD Tc-99m LLD LLD LLD LLD Ru-103 1.00E-05 LLD LLD LLD Ru-106 LLD LLD LLD 1.71E-06 Ag-110m 1.42E-03 1.28E-04 3.33E-04 1.84E-03 Sn-113 1.87E-04 6.76E-05 9.26E-05 4.59E-05 Sb-125 2.57E-04 4.86E-05 2.23E-05 8.84E-04 I-131 LLD LLD LLD LLD Cs-134 5.08E-04 1.20E-04 2.47E-04 3.86E-04 Cs-137 8.47E-04 2.20E-04 4.87E-04 8.08E-04 Cs-138 LLD LLD LLD 2.45E-06 Ce-141 LLD LLD LLD LLD Ce-144 LLD LLD LLD 7.52E-06 Total for Period: 1.07E-02 1.66E-03 2.16E-03 7.80E-03
2. Tritium Ci 2.19E+01 3.90E+01 3.16E+01 1.40E+02
3. Dissolved and Entrained Gases Kr-85 Ci LLD LLD LLD 1.02E-02 Xe-131m LLD LLD LLD 4.69E-03 Xe-133 LLD 2.39E-05 LLD 1.46E-01 Xe-133m LLD LLD LLD 4.36E-04 Xe-135 LLD LLD LLD 2.14E-05 Total for Period: N/A 2.39E-05 N/A 1.61E-01 DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

TABLE 5. LIQUID EFFLUENTS - NUCLIDES RELEASED (continued)

CONTINUOUS RELEASES

  • THIRD FOURTH FIRST SECOND NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER 1993 1993 1994 1994
1. Fission and Activation Products cr-51 Ci LLD LLD LLD LLD Mn-54 LLD -LLD LLD LLD Fe-59 LLD LLD LLD LLD Co-58 LLD LLD LLD LLD Co-60 LLD LLD LLD LLD Zn-65 LLD LLD LLD LLD Sr-89**b LLD LLD LLD LLD Sr-90*'b LLD LLD LLD LLD Zr-95 LLD LLD LLD LLD Nb-95 LLD LLD LLD. LLD Mo-99 LLD LLD LLD LLD Tc-99m LLD LLD LLD LLD I-131- 'LLD LLD LLD LLD Cs-134 LLD LLD LLD LLD Cs-137 LLD LLD LLD 'LLD Ba-140 LLD LLD LLD LLD Ce-141 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A
2. Tritium Ci 2.84E-01 7.94E-01 ~ 9.03E-01 8.88E-01
3. Dissolved and Entrained Gases Xe-133 Ci LLD LLD LLD LLD Xe-135 LLD LLD LLD LLD Total for Period: N/A N/A N/A N/A DBNPS Radioactive Effluent July 1,'1993 - June 30, 1994 Release Report

TABLE 5.

LIQUID EFFWENTS - NUCLIDES RELEASED (continued)

These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed below. The largest LLD value is used for eact radionuclide.

Na-24: <2.0 E-08 pCi/ml I-131: <2.5 E-08 Ci/ml cr-51: <1.7 E-07 Ci/ml I-132: <2.2 E-08 pCi/ml Mn-54: <2.1 E-08 pCi/ml I-133: <2.1 E-08 Ci/ml Fe-55: <7.0 E-07 pCi/ml Kr-85: <6.2 E-06 vCi/ml Fe-59: <4.2 E-08 pCi/ml Xe-131m: <7.7 E-07 pCi/ml Co-57: <1.6 E-08 Ci/ml Xe-133: <4.6 E-08 Ci/ml co-58: <1.9 E-08 Ci/ml Xe-133m: <1.6 E-07 vCi/ml Co-60: <2.5 E-08 Ci/ml Xe-135: <1.9 E-08 Ci/ml Zn-65: <5.2 E-08 Ci/ml Se-75: <2.4 E-08 Ci/ml Sr-89: <3.0 E-08 Ci/ml Sr-90: <8.0 E-09 Ci/ml Zr-95: <4.0 E-08 Ci/ml Zr-97: <2.5 E-08 Ci/ml Nb-95: <2.1 E-08 pCi/ml Nb-97 <2.5 E-08 Ci/ml Mo-99: <1.6 E-07 Ci/ml Tc-99m: <1.8 E-08 Ci/ml Ru-103: <2.2 E-08 Ci/ml Ru-106: <2.1 E-07 Ci/ml Ag-110m: <2.5 E-08 Ci/ml Sn-113: <2.8 E-08 Ci/ml Sb-124: <1.7 E-08 Ci/ml Sb-125: <1.7 E-08 Ci/ml Te-132: <1.8 E-08 Ci/ml Ce-141: <3.0 E-08 Ci/ml Ce-144: <1.7 E-07 Ci/ml Cs-134: <2.1 E-08 Ci/ml Cs-136: <2.8 E-08 Ci/ml Cs-137: <2.7 E-08 pCi/ml Cs-138: <6.7 E-08 ci/ml Ba-140: <7.0 E-08 Ci/ml Np-239: <1.2 E-07 vCi/ml Quarterly composite sample LLDs are applicable to both batch and continuous r: odes due to identical sample and analysis methods.

There were no abnormal liquid releases during the reporting period.

DBtES Radioactive Effluent July 1. 1993 - June 30, 1994 Release Report

I

'mBLE 6. SOLID MASTE AND IRRADIA'IED FUEL SHIPfG!NTS A. Solid Waste Shipped offsite for Burial or Disposal (not irradiated fuel)

EST. 'IOTAL PERCENT

1. TYPE OF NASTE UNIT QUANTITY ERROR
a. Spent resins, filter sludges, m' 3.62E+01 evaporator bottoms, etc. Ci 7.68E+02 2.5 E+01
b. Dry compressible waste, m' 2.93E+01 contaminated equipment, etc. Ci 2.35E+00 2.5 E+01
c. Irradiated components, control m' O.00E+00 rods,-etc. Ci 0.00E+00 2.5 E+01
d. Other:
1. Dewatered Primary m' 1.74E+00 System Cartridge Filters Ci 9.79E+00 2.5 E+01
2. Estimate of Major Nuclide Composition (by type of waste)

Percent Abundance Type a. Fe-55 4.30E+00 Co-58 1.46E+00 Co-60 9.19E+00 8

Ni-63 1.70E+01 Cs-134 2.10E+01 Cs-137 4.71E+01 Type b. Fe-55 3.92E+00 Co-58 6.90E-01 Co-60 4.13E+00 Sn-113 3.12E+00 Ni-63 1.44E+00 Cs-134 6.84E+00 Cs-137 1.29E+01 Ba/La-140 6.64E+01 Type c. N/A Type d. Fe-55 2.27E+00 Co-58 7.01E+01 Co-60 1.36E+00 Cr-51 2.70E+00 Mn-54 1.34E+00 Ni-63 1.60E+00 Zr-95 1.20E+00 Nb-95 1.46E+00 Ba/La-140 1.46E+01 DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

l

, l TABLE 6. SOLID NASTE AND IRPADIATED FUEL SHIPMENTS (continued)

3. Solid Waste Disposition Number of Shipments: 3 Mode of Transportation: Truck Destination: Barnwell, S.C.

Type of Container (Container Volume): 2 Resin HIC (3.75m3 each) Buried.

1 Resin HIC (5.73m') Buried.

Solidification Agents: None Number of Shipments: 2 Mode of Transportation: Trt.ck Destination: Scientific Ecology Group, Oak Ridge, TN.

Type of Container (Container volume): 3 - 20 foot Sealands of dry activated waste and contaminated metal (5.0 m') buried Solidification Agents: None Nunber of Shipments: 1 Mode of Transportation: Truck Destination: American Ecology, Oak Ridge, 'IN.

Type of Container (Container volume): 4 steel liners of (5.67m') each of dewatered powdered resin for use as waste package filler. (22.68m')

buried.

Solidification Agents: None Number of Shipments: 1 Mode of Transportation: Truck Destination: Scientific Ecclogy Group, Oak Ridge, 'IN.

Type of Container (Container Volume): 1 filter HIC Sent for additional processing, (1.73 m') Buried.

Solidification Agents: None Number of Shipments: 2 Mode of Transportation: Truck Destination: Barnwell, S.C.

Type of Container (Container Volume):

7SteelBoxes(18.88m*})

5- 55 gal drums (1.06m Buried Buried Solidification Agents: None Number of 3hipments: 3 Mode of Transportation: Truck Destination: Scientific Ecology Group, Oak Ridge, TN.

Type of Contair.er (Container Volume): 13 Steel Boxes 10 Wood Boxes 1 - 55 gal drum sent for additional processing, (1.73m') Buried.

Solidification agents: None B. Irradiated Fuel Shipments There were no shipments of irradiated fuel.

DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

'mBLE 7. AfMAL DOSES DUE 'ID GASEQUS RELEASES A. Maximum Individual doses due to I-131, H-3 and Particulates with Half-Lives Greater than 8 Days.

1. Whole Body Dose 5.54E-04 mrem
2. Significant Organ Dose 7.92E-03 mrem B. Maximum Individual Dose Due to Noble Gas
1. Whole Body Dose 1.06E-03 mrad
2. Skin Dose 3.87E-03 mrad C. Population Doses due to I-131, H-3, and Particulates with Half-Lives Greater than 8 Days.
1. Total Integrated Population 8.60E-03 rem Dose
2. Average Dose to Individual in 4.52E-06 mrem Population D. Population Dose due to Noble Gas
1. Total Integrated Population 1.74E-03 rem Dose
2. Average Dose to Individual 9.15E-07 mrem in Population

'mBLE 8. AMUAL DOSES DUE '10 LIQUID RELEASES A. Maximum Individual Whole Body Dose 6.05E-02 mrem B. Maximum Individual Significant Organ Dcse 7.87E-02 mrem C. Population Dose

1. Total Integrated Population Dose 7.21E-01 rem
2. Average Dose to Individual 3.79E-04 mrem DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

i

'mBLE 9. AleRRL DOSE 'IO 'IEE POST-EKPOSED MEMBER OF 'IEE PUBLIC l

40 CFR 190 ANNUAL DOSE LIMITS PERCENT OF l (mrem) (mrem) ' LIMITS Whole Body Dose

- Noble Gas 1.06E-03

- Iodine, Tritium, 5.54E-04 Particulates

- Liquid 6.05E-02 Total Whole Body Dose 6.21E-02 25 2.48E-01 Thyroid Dose

- Iodine, Tritium, 7.92E-03 75 1.06E-02 Particulates Skin Dose

- Noble Gas 3.87E-03 25 1.55E-02 Significant Organ Liver Dose

- Liquid 7.87E-02 25 3.15E-01 1

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l DBNPS Radioactive Effluent . July 1, 1993 - June 30, 1994 )

Release Report i

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l METEOROLOGICAL DATA Meteorological data on 3 1/2 inch microdisk for July 1, 1993 through June 30, 1994 has been submitted with this document to the U. S. Nuclear Regulatory i Commission, Document Control Desk, Washington, D. C. 20555.

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DBNPS Radioactive Effluent July 1, 1993 - June 30, 1994 Release Report

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