ML20056F210

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Semiannual Radioactive Effluent & Waste Disposal Rept for Jan-June 1993.
ML20056F210
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/30/1993
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20056F209 List:
References
NUDOCS 9308260184
Download: ML20056F210 (28)
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Text

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The Davis-Besse Nuclear Power Station Semiannual Radioactive Effluent and Waste Disposal Report January 1 - June 30,1993 1

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SEMIANNUAL EFFLUENT AND VASTE DISPOSAL REPORT Davis-Besse Nuclear Power Station j Unit No. 1 January 1, 1993 through June 30, 1993 Docket Number 50-346 License Number NPF-3 Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 August 1993 L _ __ _ _ _ _ _

TABLE OF CONTDJTS Title Page List of Tables 11 Summary 1 Supplemental Information 3 Effluent Data Tables 9 Heteorological Data 24 i

i DBNPS Semiannual Effluent Report i Jan. - Jun., 1993

LIST OF TABLES Table Number Title Page 1 Gaseous Effluents - Summation of 9 All Releases 2 Gaseous Effluents - Ground-Level Releases 10 3 Gaseous Effluents - Mixed-Hode Releases 11 4 Gaseous Effluents - Abnormal Releases 13 5 Liquid Effluents - Summation of 14 All Releases 6 Licuid Effluents - Nuclides Released 15 7 Liquid Effluents - Abnormal Releases 17 8 Solid Vaste and Irradiated Fuel 18 Shipments 9 Semiannual Doses Due to Gaseous 20 Releases 10 Semiannual Doses Due to Liquid 22 Releases 11 1993 Semiannual Dose to the Most- 23 Exposed Member of the Public DBNPS Semiannual Effluent Report 11 Jan. - Jun., 1993

SUMMARY

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 January 1, 1993 through June 30, 1993.

This report provides the following information:

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

- 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 (ODCM), but which was inoperable for more than 30 days.

Environmental samples were available from the normal collection locations during this reporting period. The locations used for dose calculations and environmental monitoring care thos" identified by the 1992 Land Use Census.

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

Liquid Effluents:

5.77E-02 mrem, whole body 7.85E-02 mrem, liver Caseous Effluents:

Noble Gas:

3.04E-03 mrem, whole body 1.66E-02 mrem, skin Iodine-131, Tritium, and Particulates with Half-lives Greater Than 8 Days:

. 2.05E-02 mrem, whole body 2.13E-01 mrem, thyroid These doses represent an extremely small fraction of the limits set by the NRC in the Davis-Besse ODCM.

DBNPS Semiannual Effluent Report 1 Jan. - Jun., 1993

Additional normal release pathways from the secondary system exist. For gaseous effluents, these pathvays 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. There vere no abnormal gaseous nor abnormal liquid releases this reporting period.

No changes to the ODCM nor to the Process Control Program (PCP) occurred during this reporting period.

l l

l DBNPS Semiannual Effluent Report 2 Jan. - Jun., 1993

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:
a. Noble gases:

- Less than or equal to 500 mrem / year to the whole body.

(Davis-Besse ODCM limit is 50 mrem / year)

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

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.

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 than or equal to 10 mrad for beta radiation during 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 during any calendar year.
3. In accordance with 10CFR50, 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 during any calendar quarter.
b. Less than or equal to 15 mrem to any organ during 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 during 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 during any calendar year.

DBNPS Semiannual Effluent Report 3 Jan. - Jun., 1993 L _ _ _ _ _ _ _ _ _ _

2. EFFLUENT CONCENTRATION LIMITS The Effluent Concentration Limits (ECs) 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 EC being used in all cases. For dissolved and entrained gases the EC of 2.0E-04 UCi/ml is applied. This EC 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 ENERGT f-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 50 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, ,

" 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 na* eoplicable.

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITI 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 Semiannual Effluent Report 4 Jan. - Jun., 1993

5. BATCH RELEASES A. Liquid from 1/1/93 to 6/30/93
1. Number of batch releases: 49
2. Total time period for the batch releases: 7.98E+01 hours
3. Maximum time period for a batch release: 2.12E+02 minutes
4. Minimum time period for ' batch releases: 6.10E+01 minutes
5. Average time period for a batch release: 9.77E+01 minutes B. Gaseous from 1/1/93 to 6/30/93
1. Number of batch releases: 12
2. Total time period for the batch releases: 1.37E+02 hours
3. Maximum time perind for a batch release: 1.43E+03 minutes
4. Minimum time period for a batch release: 2.14E+02 minutes
5. Average time period for batch releases: 6.86E+02 minutes
6. ABNORMAL RELEASES There were no abnormal releases during this reporting period.

DBNPS Semiannual Effluent Report 5 Jan. - Jun., 1993

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 January through June, 1993.

SPECIFICATION LIMIT PERCENT OF LIMITS A. First Quarter, 1993: Gaseous Noble gases (gamma) 5.0 mrad 2.20E-02 Noble gases (beta) 10.0 mrad 5.66E-02 I-131, tritium, and 7.5 mrem 7.57E-02 particulates with half-lives greater than 8 days B. Second Quarter, 1993: Gaseous Noble gases (gamma) 5.0 mrad 3.44E-04 Noble gases (beta) 10.0 mrad 2.51E-03 I-131, tritium, and 7.5 mrem 2.15E-03 particulates with half-lives greater than 8 days C. Calendar year, 1993: Gaseous Noble gases (gamma) 10.0 mrad 1.12E-02 Noble gases (beta) 20.0 mrad 2.96E-02 I-131, tritium, and 15.0 mrem 3.89E-02 particulates with half-lives greater than 8 days l

D. First Quarter, 1993: Liquid l Total body 1.5 mrem 2.40E+00 Any organ (liver) 5.0 mrem 9.66E-01 E. Second Quarter, 1993: Liquid Total body 1.5 mrem 1.44E+00 ,

Any organ (liver) 5.0 mrem 6.04E-01 l F. Calendar year, 1993: Liquid Total body: 3.0 mrem 1.92E+00 Any organ (liver) 10.0 mrem 7.85E-01 1

DBNPS Semiannual Effluent Report 6 Jan. - Jun., 1993

8. DOSE ASSESSMENT 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."

B. 0-50 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, Heat - Animal, and Milk Production Data Tables for 1982." This evaluation was based on the 1980 census; the Agricultural Ministry of Ontario 1980 report entitled, " Agricultural Statistics and Livestock Marketing Account, 1980"; the Agricultural Ministry of Ontario 1980 report entitled, " Agricultural Statistics for Ontario -

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 pathways by sector out to 5 miles: Report entitled, "1992 Land Use Census," included in the 1992 Annual Environmental Operating Report for Davis-Besse.

9. DOSE TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDART l

In accordance with ODCM Section 7.2, the Semiannual Effluent and Vaste Disposal Report includes an assessment of radiation doses from I radioactivity released in liquid and gaseous effluents to members of the public due to activities inside the site boundary.

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.

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 public in accordance with ODCM Section 7.2, the following exposure assumptions are used:

DBNPS Semiannual Effluent Report 7 Jan. - Jun., 1993

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 dispersion (conservative, default use of maximum site boundary 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 vould 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.

1 I

10. INOPERABLE RADIOACTIVE EFFLUE!G MONITORING EQUIPMENT The following radioactive effluent monitoring equipment, required to be operable by ODCM Sections 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 planned service water system maintenance. The scheduled repairs were not made within 30 days because of the large amount of the service water piping which was replaced. Upon completion of the service water system modification, the computer point was returned to service.

During the time period that the computer point was out of service, total dilution flov was estimsfed using other means.

11. CHANGES TO THE ODCM & PCP There vere no revisions to the ODCM nor to the PCP during this reporting period.

DBNPS Semiannual Effluent Report 8 Jan. - Jun., 1993

t TABLE 1. GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES  :

EST. TOTAL

  • FIRST SECOND PERCENT TYPE UNIT GUARTER OUARTER ERROR t I

A. Fission and Activation Gases

1. Total Release Ci 3.24E+02 4.03E+00 2.50E+01 a
2. Average Release pCi/sec 4.16E+01 5.12E-01 Rate for Period ,

d i 3. Percent of  % See Supplemental Information, 1 ODCM Limits Section 7 s

B. Iodines i

1. Total Iodine Ci 8.06E-03 3.16E-04 2.50E+01
2. Average Release pCi/sec 1.04E-03 4.01E-05 '

Rate for Period

3. Percent of  % See Supplemental Information, ODCM Limits Section 7- l I

C. Particulates

1. Particulates with Ci 2.59E-04 1.72E-04 2.50E+01 half-lives greater than 8 days
2. 4verage Release pCi/sec 3.33E-05 2.18E-05 Rate for Period l
3. Parcent of  % See Supplemental Information, ODCM Limits Section 7
4. Gross Alpha Ci 5.68E-07 3.49E-07 2.50E+01 Activity D. Tritium
1. Total Release Ci 4.72E+00 5.60E+00 2.50E+01
2. Average Release pCi/sec 6.08E-01 7.12E-01 Rate for Period
3. Percent of  % See Supplemental Information, ODCM Limits Section 7 DBNPS Semiannual Effluent Report 9 Jan. - Jun., 1993

TABLE 2. GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

  • CONTINUCUS MODE" BATCH MODE
  • FIRST SECOND FIRST SECOND NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER
1. Fission Gases Ci l Kr-85 LI8 LLD N/A N/A Kr-85m LLD LLD N/A N/A Kr-87 LLD LLD N/A N/A Kr-88 LLD LLD N/A N/A xe-133 LLD LLD N/A N/A xe-135 LLD LLD N/A N/A xe-135m LLD LLD N/A N/A Xe-138 LLD LLD N/A N/A Total for Period: N/A N/A N/A N/A
2. Iodines Ci I-131 LLD LLL N/A N/A I-133 LLD LLD N/A N/A I-135 LLD LLD N/A N/A Total for Period: N/A N/A N/A N/A
3. Particulates Ci H-3 3.40E-06 1.08E-06 N/A N/A Sr-89 LLD LLD N/A N/A Sr-90 LLD LLD N/A N/A Cs-134 LLD LLD N/A N/A Cs-137 6.38E-07 9.65E-06 N/A N/A Total for Period: 4.04E-06 1.07E-05 N/A N/A Includes Atmospheric Vent Valve weepage, Auxiliary Feed Pump Turbine tests, and Main Steam safety valve testing which are listed as continuous releases. All batch releases are mixed-mode.

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

H-3: <3.6E-06 vCi/ml Ar-41: <2.2E-08 vCi/ml Xe-133: <4.6E-08 Ci/ml Kr-85: <6.2E-06 pCi/ml Xe-133m: <1.6E-07 Ci/ml Kr-85m: <2.0E-08 pCi/ml Xe-135: <1.9E-08 Ci/ml Kr-87: <3.5E-08 pCi/ml Xe-135m: <9.9E-08 uti/ml Kr-88: <6.7E-08 pCi/ml Xe-138: <2.5E-07 Ci/ml I-131: <1.0E-06 vCi/ml Cs-134: <2.lE-08 vCi/ml I-133: <2.1E-08 pCi/ml I-135: <6.8E-08 pCi/ml Sr-89: <5.0E-08 vCi/ml Sr-90: <6.0E-09 uti/ml LLDs are applicable to both batch and continuous modes.

DBNPS Semiannual Effluent Report 10 Jan. - Jun., 1093

'IABLE 3. GASEOUS EFFLUENIS - MIXED-FODE RELEASES

  • CONTI!UOUS MODE BATCH MODE FIRST SECOND FIRST SECOIO

!UCLIDES UNIT QUARTER QUARTER QUARTER QUARTER

1. Fission Gases Ci Ar-41 lid LLD LLD 1.28E-01 Kr-85 LLD LLD 2.65E+02 2.61E+00 Kr-85m LLD LLD LLD LLD Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-131m LLD LLD 9.12E+00 1.25E-02 Xe-133 1.22E+01 LLD 3.50E+01 1.24E+00 Xe-133m LLD LLD 2.21E+00 LLD Xe-135 LLD LLD 6.48E-02 4.27E-02 Xe-135m LLD LLD LLD LLD Total for Period: 1.22E+01 N/A 3.11E+02 4.03E+00
2. Iodines Ci I-131 8.00E-04 7.33E-05 6.09E-03 7.01E-05 I-132 N/A N/A 3.60E-05 1.24E-05 I-133 1.44E-04 3.36E-05 9.95E-04 7.73E-05 I-135 LLD LLD LLD 4.91E-05 Total for Period: 9.44E-04 1.07E-04 7.12E-03 2.09E-04
3. Particulates Ci H-3 4.63E+00 5.17E+00 9.10E-02 4.34E-01 Mn-54 LLD LLD 2.51E-06 LLD Co-58 LLD LLD 6.89E-05 1.14E-05 Co-60 LLD LLD 6.64F-06 LLD Sr-89d LLD(Cl) LLD(C2) im im Sr-90*** LLD(C1) LLD(C2) In in Ru-103 2.26E-06 LLD LLD LLD Cs-134 1.11E-06 LLD 7.50E-05 5.69E-05 Cs-137 3.15E-06 1.95E-06 8.51E-05 9.12E-05 Ba-140 LLD LLD 1.24E-05 LLD Ce-144 LLD 9.87E-07 LLD LLD Total for Period: 4.63E+00 5.17E+00 9.12E-02 4.34E-01 i

DBNPS Semiannual Effluent Report 11 Jan. - Jun., 1993 l 1

'IABLE 3. GASEOUS EFFLUINTS - MIXED-10DE RELEASES" (continued)

Abnormal releases not included.

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 pCi/ml Kr-85: <3.3 E-06 Ci/ml Kr-85m: <2.2 E-06 Ci/ml Kr-85m: <1.3 E-68 vCi/ml Kr-87: <4.5 E-06 Ci/ml Kr-87: <6.0 E-08 vCi/ml Kr-88: <6.6 E-06 vCi/ml Kr-88: <6.0 E-08 pCi/ml Xe-133m: <1.8 E-05 vCi/ml Xe-131m: <4.4 E-07 vCi/ml Xe-135m: <1.4 E-05 vCi/ml Xe-133m: <7.2 E-08 pCi/ml I-135: <1.0 E-US vCi/ml Xe-133: <2.0 E-08 pCi/ml Co-60: <3.7 E-06 pCi/ml Xe-135m: <5.9 E-06 pCi/ml Ru-103: <2.8 E-06 pCi/ml Xe-135: <1.1 E-08 vCi/ml Ba-140: <1.1 E-05 vCi/ml I-135: <3.9 E-10 Ci/ml Ce-144: <1.4 E-05 vCi/ml Mn-54: <2.6 E-14 Ci/ml Mn-54: <2.6 E-14 Ci/ml Co-58: <1.6 E-14 vCi/ml Co-60: <2.5 E-14 Ci/ml Sr-89(Cl): (9.3 E-16 Ci/ml Sr-89(C2): <8.0 E-16 Ci/ml Sr-90(C1): <3.1 E-16 Ci/ml

, Sr-90(C2): <3.0 E-16 pCi/ml Cs-134: <1.8 E-14 Ci/ml Ba-140: <8.4 E-14 pCi/ml Ce-144: <1.2 E-13 vCi/ml Ru-103:

<2.4 E-14 Ci/ml Ouarterly composite sample for continuous mode.

Analysis not required for batch release.

Note: numbers in parenthesis are for the quarter of occurence DBNPS Semiannual Effluent Report 12 Jan. - Jun., 1993

\

'IABLE 4. GASEDUS EFFLUENTS - ABt0RMAL RELEASES FIRST SECOND IUCLIDES UNIT QUARTER QUARTER

1. Fission Gases Ci Total fcr Period: N/A N/A
2. Iodines Ci Total for Period: N/A N/A
3. Particulates Ci Total for Period: N/A N/A a

There were no abnormal gaseous releases during the first and second quarters of 1993.

i l

DBNPS Semiannual Effluent Report 13 Jan. - Jun., 1993 i

'IABLE 5. LICUID EFFLUERTS - SUMMATION OF ALL RELFASES j EST. 'IOTAL FIRST SECOND PERCENT TYPE UNIT QUARTER QUARTER ERROR A. Fission And Activation Products

1. Total Release (without Ci 1.52E-02 2.45E-02 2.00E+01 Tritium, Gases, Alpha)
2. Average Diluted Concen-
  • Ci/ml 2.17E-09 3.65E-09 tration During Period
3. Percent of ODCM  % See Supplemental Information, Limit Section 7
4. Percent of 10CFR20 Limit  % 2.41E-01 4.06E-01 ,

B. Tritium

1. Total Release Ci 1.11E+02 7.81E+00 2.00E+01
2. Average Diluted Concen-* Ci/ml 1.57E-05 1.16E-06 tration During Period
3. Percent of 10CFR20 Limit  % 1.57E+00 1.16E-01 C. Dissolved and Entrained Gases
1. Total Release Ci 2.57E-01 5.53E-06 2.00E401
2. Average Diluted Concen-* Ci/ml 3.65E-08 8.24E-13 tration During Period
3. Percent of Limit  % 1.82E-02 4.12E-07 D. Gross Alpha
1. Total Release Ci 1.61E-02 2.76E-03 2.00E+01 E. Volume of Waste Released liters 1.10E+08 6.27E+07 2.00E+01 (prior to dilution)

F. Volume of Dilution Water liters 7.04E+09 6.71E+09 2.00E+01  ;

(used during releases) l G. Total Volume of Water liters 7.15E+09 6.77E+09 2.00E401 Released j

Based on volume of dilution water used during releases (Item F).

l l DBNPS Semiannual Effluent Report 14 Jan. - Jun., 1993 1

TABLE 6. LIQUID EFFLUENTS - NUCLIDES RELEASED

  • CONTINUOUS MODE (Ci)d BATCH MODE (Ci)#

FIRST SECOND FIRST SECOtO NUCLIDES OUARTER QUARTER QUARTER OUARTER

1. Fission and Activation Products i

Na-24 LLD(b) LLD 1.46E-05 LLD CR-51 LLD LLD 1.20E-04 1.14E-04 Mn-54 LLD LLD 3.71E-06 5.07E-05 Fe-55' LLD(C1) LLD(C2) LLD(C1) 3.92E-03(C2)

Fe-59 LLD LLD LLD 3.74E-05 .

Co-57 LLD LLD 2.84E-06 5.00E-05 Co-58 LLD LLD 2.98E-03 1.23E-02  :

Co-60 LLD LLD 8.96E-04 1.50E-03 Zn-65 LLD LLD LLD LLD Sr-89c LLD(Cl) LLD(C2) LLD(C1) LLD(C2)

Sr-90c LLD(C1) LLD(C2) LLD(Cl) LLD(C2) 2r-95 LLD LLD LLD 2.65E-04 Zr-97 LLD LLD 1.11E-05 8.54E-05 "

Nb-95 LLD LLD LLD 4.79E-04 Nb-97 LLD LLD 5.28E-06 1.21E-05 Mo-99 LLD LLD LLD LLD Tc-99m LLD LLD 1.70E-06 LLD Ru-103 LLD LLD 2.50E-05 1.70E-04 Ru-106 LLD LLD 9.08E-05 LLD Ag-110m LLD LLD 3.38E-04 1.81E-03 Sb-124 LLD LLD 7.61E-04 5.07E-06 Sb-125 LLD LLD 4.32E-03 4.28E-04 Sn-113 LLD LLD 5.05E-05 5.18E-04 I-131 LLD LLD 1.29E-04 1.97E-06 I-132 LLD LLD 5.21E-04 LLD-I-133 LLD LLD LLD 2.47E-06 Te-132 LLD LLD 5.22E-04 7.33E-07 Cs-134 LLD LLD 1.76E-03 1.03E-03 Cs-137 LLD LLD 2.61E-03 1.65E-03 Ba-140 LLD LLD LLD LLD Ce-141 LLD LLD LLD LLD Ce-144 LLD LLD LLD 5.24E-05 Np-239 LLD LLD 7.94E-05 LLD Total for period: N/A N/A 1.52E-02 2.45E-02 l 2. Tritium 1.54E+00 1.55E-01 1.09E+02 7.65E+00

3. Dissolved and Entrained Gases Kr-85 LLD LLD 2.81E-02 LLD Xe-131m LLD LLD 2.36E-03 LLD l Xe-133 LLD LLD 2.25E-01 5.53E-06 l

Xe-133m LLD LLD 1.01E-03 LLD Xe-135 LLD LLD 9.19E-05 LLD t

l Total for Period: N/A N/A 2.57E-01 5.53E-06 l

l DBNPS Semiannual Effluent Report 15 Jan. - Jun., 1993 l

TABLE 6. LIQUID EFFRE:NTS - NOCLIDES RELEASE [f (continued)

Abnormal releases not included.

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

Na-24: <2.0 E-08 Ci/ml I-131: <2.5 E-08 Ci/ml Cr-51: <1.7 E-07 vCi/ml I-132: <2.2 E-08 Ci/ml Mn-54: <2.1 E-08 vCi/ml I-133: <2.1 E-08 gCi/ml Fe-55(C1)- <7.0 E-07 Ci/ml Kr-85: <6.2 E-06 Ci/ml Fe-55(C2): <5.0 E-07 Ci/ml Xe-131m: <7.7 E-07 vCi/ml Fe-59: <4.2 E-08 Ci/ml Xe-133: <4.6 E-08 vCi/ml Co-57: <1.6 E-08 Ci/ml Xe-133m: <1.6 E-07 vCi/ml co-58: <1.9 E-08 vCi/ml Xe-135: <1.9 E-08 vCi/ml co-60: <2.5 E-08 Ci/ml Zn-65: <5.2 E-08 Ci/ml Sr-89(C1): <3.0 E-08 Ci/ml Sr-89(C2): <2.0 E-08 Ci/ml Sr-90(C1): <6.0 E-09 Ci/ml Sr-90(C2): <8.0 E-09 vCi/ml Zr-95: <4.0 E-08 vCi/ml Zr-97: <2.5 E-08 Ci/ml Nb-95: <2.1 E-08 vCi/ml Nb-97: <2.5 E-08 Ci/ml Mo-99: <1.6 E-07 pCi/ml Tc-99m: <1.8 E-08 C1/ml Ru-103: <2.2 E-08 Ci/ml Ru-106: <2.1 E-07 pCi/ml Ag-110m: <2.5 E-08 vCi/ml Sn-113: <2.8 E-08 Ci/ml Sb-124: <1.7 E-08 C1/ml Sb-125: <1.7 E-08 vCi/ml Te-132: <1.8 E-08 vCi/ml Ce-141: <3.0 E-08 Ci/ml Ce-144: <1.7 E-07 vCi/tal Cs-134: <2.1 E-08 Ci/ml Cs-136: <2.8 E-08 vCi/ml Cs-137: <2.7 E-08 Ci/ml Ba-140: <7.0 E-08 Ci/ml Np-239: <l.2 E-07 Ci/ml Ouarterly composite sample.

LLDs are applicable to both batch and continuous modes due to identical sample and analysis methods.

Note: numbers in parenthesis are for the quarter of occurence l

l l DBNPS Semiannual Effluent Report 16 Jan. - Jun., 1993

TABLE 7. LIQUID EFFLUENfS - AIMORfmL RELEASES" FIRST SECOO NUCLIDES UNIT OUARTER QUARTER

1. Fission and Activation Products Total for Period: Ci N/A N/A
2. Tritium Total for Period: Ci N/A N/A
3. Dissolved and Entrained Gases Total for Period: Ci N/A N/A a  ;

There were no abnormal liquid releases during the first and second quarters of 1993.

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DBNPS Semiannual Effluent Report 17 Jan. - Jun., 1993 l

l TABLE 8. SOLID HASTE AND IRRADIATED FUEL SHIPMDirS A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fue]) 3 EST.'IOTAL PERCDTI

1. Type of Waste RilT OUANTITY ERROR
a. Spent resins, filter sludges, m' 5.%'E+00 evaporator bottoms, etc. Ci 4.16E-01 2.5 E+01
b. Dry compressible waste, m' 8.90E+00 contaminated equipment, etc. Ci 2.94E-01 2.5 E+01
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' O.0 E+00 System Cartridge Filters Ci 0.0 E+00 2.5 E+01
2. Estimate of Major Ivuclide Composition (by type of waste)

PERCDJT ABUNDANCE Type a. Fe-55 6.40E+00 Co-58 6.67E+01 Co-60 7.10E+00 Ni-63 3.30E+00 Cs-134 4.90E+00 Cs-137 8.00E+00 Ag-110m 1.60E+00 Type b. Fe-55 7.00E+00 Co-58 7.00E+01 Co-60 2.30E+01

3. Solid Waste Disposition Number of Shipments: 1 Mode of Transportation: Truck Destination: Barnwell, S.C.

Type of Container (Container Volume): 1 Resin HIC (5.8m')

Solidification Agents: None Number of Shipments: 4 Mode of Transportation: Truck Destination: Scientific Ecology Group, Oak Ridge, TN.

Type of Container (Container volume): 8-20 foot sealands of dry activated waste and contaminated metal (8.9m3) buried Solidification Agents: None DBNPS Semiannual Effluent Report 18 Jan. - Jun., 1993

BBLE 8. SOLID WMTIE AND IRRADIATED FUEL SHIPMENTS (continued)

Number of Shipments: 2 Mode of Transportation: Truck Destination: Quadrex Recycle Center, Oak Ridge, TN.

Type of Container: 1 shipment of contaminated metal for decontamination and processing (0 m3) buried Solidification Agents: None B. Irradiated Fuel Shipments There were no shipments of irradiated fuel.

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i DBNPS Semiannual Effluent Report 19 Jan. - Jun., 1993 i

7 TABLE 9. SD11ANNLRL DOSES DUE TO GASEDUS RELEASES A. Maximum Individual Doses Due to I-131, H-3, and Particulates with Half-lives Greater Than 8 Days"

1. Whole Body Dose SECTOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 W 980 TEEN 5.16E-03 Quarter 2 W 1750 ADULT 1.59E-02 Semiannual W 1750 CHILD 2.05E-02

2. Significant Organ Dose SECIOR DISTANCE (m) AGE ORGAN DOSE (mrem)

Quarter 1 W 6530 INFANT Thyroid 1.46E-01 i Quarter 2 W 6530 INFANT Thyroid 6.68E-02 Semiannual W 6530 INFANT Thyroid 2.13E-01 B. Maximum Individual Doses Due to Noble Gas * ]

1. Whole Body Dose SECTOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 W 980 NA 2.87E-03 Quarter 2 W 980 Im 1.75E-04 Semiannual W 980 NA 3.04E-03 g 2. Skin Dose l SECTOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 W 980 im 1.56E-02 Quarter 2 W 980 im 1.03E-03 Semiannual W 980 NA 1.66E-02 C. Population Doses due to I-131, H-3, and Particulates with Half-lives Greater than 8 Days' TUTAL INTEGRATED AVERAGE DOSE 70 POPUIATION DOSE INDIVIDUALS IN ORGAN (person rem) POPULATION (mrem)

Quarter 1 W/ body 3.42E-03 1.54E-06 Quarter 2 W/ body 6.17E-04 2.77E-06 Semiannual W/ body 4.03E-03 4.31E-06 DBNPS Semiannual Effluent Report 20 Jan. - Jun., 1993

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l 'IABLE 9. SEMIAlfilRL DOSES DUE 'ID GASDOUS RELEASES (continued) l D. Population Doses due to Noble Gas

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'IDTAL INTEGRATED AVERAGE DOSE 'IO POPULATION DOSE INDIVIDUALS IN ORGAN (person rem) POPULATION (mrem)

Quarter 1 W/ body 5.42E-03 2.44E-06 Quarter 2 W/ body 1.76E-05 7.92E-08 Semiannual W/body 5.44E-03 2.52E-06 l

E. Abnonnal Releases due to *1bsting of the Main Steam System

1. Maximum Individual Dose due to I-131, H-3, and Particulates with Half-lives Greater than 8 Days A. Whole Body Dose SECTOR DISTANCE (m) AGE DOSE (mrem) l l Quarter 1 NE 900 TEEN 1.92E-13 l Quarter 2 N/A N/A N/A N/A Semiannual NE 900 TEEN 1.92E-13 l

1 B. Significant Organ Dose SECIOR DISTANCE (m) AGE ORGAN DOSE (mrem)

Quarter 1 NE 900 TEEN LIVER 1.92E-13 Quarter 2 N/A N/A N/A N/A N/A Semiannual NE 900 TEEN LIVER 1.92E-13

2. Maximum Individual Dose due to Noble Gas l

l SECIOR DISTANCE (m) AGE ORGAN DOSE (mrem)

N/A N/A N/A N/A N/A i

l Does not include abnormal releases.

l DBNPS Semiannual Effluent Report 21 Jan. - Jun., 1993 i

'IABLE 10. SEMIA!MPd. DOSES DUE TO LIQUID RELEASES A. Maximum Individual Whole Body Dose SECIOR DISTANCE (mi) AGE DOSE (mrem)

Quarter 1 Nd 0.6 Adult 3.61E-02 Quarter 2 Nd 0.6 Adult 2.16E-02 Semiannual IM 0.6 Adult 5.77E-02 B. Maximum Individual Significant Organ Dose SECIOR DISTANCE (mi) AGE ORGAN DOSE (mrem)

Quarter 1 !M 0.6 Teen Liver 4.83E-02 Quarter 2 Nd 0.6 Teen Liver 3.02E-02 Semiannual IM 0.6 Teen Liver 7.85E-02 C. Population Dose YUTAL INTEGRATED AVERAGE DOSE 'IO POPUIATION DOSE INDIVIDUALS IN ORGAN (person rem) POPULATION (mrem)

Quarter 1 W/ body 3.18E-01 1.43E-04 Quarter 2 W/ body 1.27E-01 5.71E-05 Semiannual WAxydy 4.45E-01 2.00E-04 l

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! DBNPS Semiannual Effluent Report 22 Jan. - Jun., 1993 l

TABLE 11. 1993 SEMIM@UAL DOSE TO THE MOST-EXPOSED MEMBER OF THE PUBLIC 40 CFR 190 SEMIM2UAL DOSE LIMITS PERCENT OF (mrem) (mrem) LIMITS Whole Body Dose

- Noble Gas 3.04E-03

- Iodine, Tritium, Particulates 2.05E-02

- Liquid 5.77E-02 Total htole Body Dose 8.12E-02 25 3.25E-01 Thyroid Dose

-Iodine, Tritium, 2.13E-01 75 2.84E-01 Particulates Skin Dose

- Noble Gas 1.66E-02 25 6.64E-02 Liver Dose

- Liquid 7.85E-02 25 3.14E-01 l

I DENPS Semiannual Effluent Report 23 Jan. - Jun., 1993

T METEOROLOGICAL DATA Meteorol.ogical data on magnetic tape for January through June,1993 has been subnitted with this document to the U.S. Nuclear' Regulatory i Commission, Document Control Desk, Washington, D.C. 20555.

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l DBNPS Semiannual Effluent Report 24 Jan. - Jun., 1993 i

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