ML20114C628
| ML20114C628 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/30/1992 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20114C627 | List: |
| References | |
| NUDOCS 9209030020 | |
| Download: ML20114C628 (28) | |
Text
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1 The Davis-Besse Nuclear Power Station Semiannual Radioactive Effluent and Waste Disposal Report Jan.1 - June 30,1992 L s
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EDISON ki Radio!oS i cal liEnvironmental- DMS BESSE MX1UR IMER STATK]N 9209030020 92082-9 PDR ADOCK 05000346 R PDR
SEMIANNUAL EFFLUENT AND UASTE DISPOSAL REPORT Davis-Besse Nuclear Power Station Unit No. 1 Jan. 1, 1992 through Jure 30, 1992 n
Docket Number 50-346 License Number NPF-3 Toledo Edison Company 300 Madiso Avenue Toledo, Ohfo 43652 August 1992 t_-__--__-____ __ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ - - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _ _ - _ -
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TABLE OF CONTENTS l
Title Page List of Tables 11 i
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- Summary 1
Supplemental Information 3 Effluent Data Tables 9 i l
Meteorological Data 24 l
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l DBNPS Semiannual Effluent Report i Jan. - June, 1992 y-
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LIST OF-TABLES Table Number Title Page 1 Gaseous Effluents - Summation of 9 All Releases
- 2. laseous 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 Liquid Effluents - Nuclides Released 15 7 Liquid Effluents - Abnormal Releases 17 8 Solid Vaste and Irradiated Fuel 18 Shipments 9- Semiannual Doses Due to Gaseous 19
-Releases 10 Semiannual Doses Due to Liquid 22 Releases 11 1992 Semiannual Dose to the Host- 23 Exposed Member of the Public DBNPS' Semiannual Effluent Report 11 Jan. - June, 1992
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, 1992 through June 30, 1992.
This report provides the folloving 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 (ODCH), but which was inoperable for more than 30 days.
Environmental samples were available from the normal collection locations during this reporting period. The locatione used for dose calculations and environmental monitoring vere those identified by the 1991 Land Use Consua.
During the period of January 1 through June 30, 1992, the t sximum individual offsite dose due to radioactivity released in effluents was approximately:
Liquid Effluents:
- 7.04E-02 mrem, whole body
- 9.34E-02 mrem, liver Gaseous Effluents:
Noble Gast ;
- 4.04E-03 mrem, whole body
- 1.09E-02 mrem, skin Iodine-131, Tritium, and Particulates with Half-lives Greater Than 8 Dayst
- 8.20E-03 mrem, whole body
- 1.52E-02 mrem, thyroid These doses are only a small fraction of the limits set by the NRC in the Davis-Lesse ODCH.
There exist several additional normal release pathways from the secondary system as a result of prior primary-to-secondary leakage. For gaseous effluents, these pathvays include the auxiliary feed pump turbine exhaust, the main steam safety valve system and the atmospheric vent valve system. For liquid effluents, the additional pathvays include the Turbine Building drains via the settling basins. Releases which occurred via these pathvays are included in the normal release tables in this report.
DBNPS Semiannual Effluent Report 1 Jan. - June, 1992
Slightly contaminated steam was released from safety valves on the Auxiliary Steam Headers on several occasions during this reporting
{ period. The resultant of fsite doses were 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 this report.
Two changes to the ODCM occurred during this reporting period. A copy of each of these changes is attached to this report. No changes to the Process Control Program (PCP) occurred during this reporting period, c
DBNPS Semiannual Effluent Report 2 Ja7. - June, 1992
SUPPLEHFRTAL 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 I site to areas at and beyond the site boundary shall be limited to the followings
- 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.
- b. Iodine-131, tritium, and all radionuclid-s 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 ca:+ndar 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 andbeyond the site boundary shall be limited to the followings
- 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 acco: dance 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 tot
- 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. - June, 1992
i 2 HAXIMUM '/ERMISSIBLE CONCENTRATION The maximum permissible concentrations (HPC) 'or 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 HPC being used in all cases. For dissolved and entrained gases the HPC of 2.0E-04 pCi/ml is applied. This HPC 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 FRERGY The Davis-Besse ODCM limits the dose equivalent rates due tn 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,
" Measuring, Evaluatir.g, and Reporting Radioactivity in Solid Vastes and Releases of Radioactive Materials in Liquid and Caseous Effluents from Light Vater-Cooled Nuclear Power Plants," is not applicable.
- 4. MEASURE *MNTS AND APPROKIMATIONS OF TOTAL ACTIVJTY 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 made by gamma spectroscopy.
C. Particulates sre collected on filter paper and counted on a germanium detector. Specific quantification of each radionuclide present on the filter paper is made by gamma spectroscopy.
Liquid Effluents are collected in a marinelli beaker and counted on a germanium detector. Specific quantification of each radionuclide present in liquid samples is made by gamma spectroscopy.
DBNPS Semiannual Effluent Report 4 Jan. - June, 1992
, 5. BATCH RELEASES A. Liquid from.1/1/92 to 6/30/92
- 1. Number of batch releases: 44 2.-Total time period for the batch releases: 6.72E+01 hours
- 3. Maximum time period for a batch release: 1.09E+02 minutes
- 4. Average time period fo' a batch telease 9.16E+01 minutes
- 5. Minimum time period for batch releases: 7.00E+01 minut2s B. Gaseous from 1/1/92 to 6/30/92
- 1. Number of batch releases: 1
- 2. Total time perk 1 for the batch releases: 3.62E+00 hours
- 3. Maximum time period for a batch release: 2.17E+02 minutes
- 4. Minimum time period for a batch release: 2.17E+02 minutes
- 5. Average time period for batch releases: 2.17E+02 minutes
- 6. ABNORMA1. RELEASES Several abnormal releases from the Auxiliary Steam System during this semiannual period due to system overpressurization and the subsequent lifting of safety valves. These releases occurred on 1/05/92, 1/12/92, 1/31/92, 2/08/92, 3/29/92, 5/18/92, 5/27/92, and 6/09/92. 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 (ODCH) release limits.
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l I-DBNPS Semiannual Effluent Report 5 Jan. - June, 1992
- 7. PERCENT 07 ODCM RELEASE LIMITS The following table presents the ODCH dose limits and the associated offsite dose to the public, in percent of limits, for Januarr through June 1992.
SPECIFICATI01; LIMIT PERCENT OF LIMITS A. First Ousrter, 1992: Gaseous Noble gases (gamma) 5.0 mrad 5.54E-02 Noble gases (beta) 10.0 mrad 7.48E-02
-I-131, tritium, and 7.5 mrem 1.01E 01 particulates with half-lives greater thai. 8 days B. Second Quarter, 1992: Gaseous Noble gases (gamma) 5.0 mrad 2.54E-02 Noble gases (beta) 10.0 mrad 3.44E-02 I-131, tritium, and 7.5 mrem 8.35E-03 particulates with half-lives greater than 8 days -
C. Calendar year, 1992: Gaseous Noble gases (gamma) 10.0 mrad 4.04E-02 Noble gases (beta) 20.0 mrad 5.45E-02 I-131,-tritium, and 15.0 mrem 5.47E-02 particulates with half-lives greater than 8 days D. First Quarter, 1992: Liquid Total body 1.5 mrem 3.35E+00 -
Any organ (liver) 5.0 mrem 1.37E+00 E. Second Quarter, 1992: Liquid Total body 1.5 mrem 1.35E+00 Any organ (liver) 5.0 mrem 5.02E-01 F. Calendar year, 1992: Liquid Total body: 3.0 mrem 2.35E+00 Any organ (liver) 10.0 mrem 9.34E-01 DBNPS Semiannual Effluent Report 6 Jan. - June, 1992
- 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 Pover Station."
l B. 0-50 mile meat, milk, vegetable production, and population i 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 l 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, "1991 Land Use Census," included in the 1991 Annual Environmental Operating Report for Davis-Besse.
- 9. DOSE TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY In accordance with ODCM Section 7.2, the Semiannual Effluent and 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 boundary.
In special instances, members of the public are permitted access to the radiologically controlled area vithin the Davis-Besse station.
Tours for the public are conducted with the assurance that no individual vill receive nn appreciable dose due to radioactivity released in gaseous or liacid 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 tc memberc 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 S=ction 7.2, the following exposure assumptions may be used:
DBNPS Semiannual Effluant Report 7 Jan. - Juney 1992
- Exposure tims 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 i
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 conservative estimate).
4 Annual average meteorological dispersion (conservative, default use of maximum site boundary disper. ion).
The equations in the CDCM 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 ODCH.
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 MONITORING EQUIPMPET 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 Flov Computer Point F-201 vas declared inoperable on March 25, 1992 due to probe alignment problems wi th FT3611, and a bad preamplifier on FT2799. The repairs vere not made within 30 days because Maintenance had difficulty obtaining the type of flow probe to use as a replacement. The computer point was declared operable on June 12, 1992.
- 11. CHANGES TO THE ODCM & PCP There have been two revisions to the ODCM during this reporting period. Entire copies of both revisions are submitted with this report. No changes to the PCP occurred during this reporting period.
t DBNPS Semiannual Effluent Report 8 Jan. - June, 1992
TABLE 1. GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES EST. TOTAL
! FIRST SECOND PERCENT TYPE UNIT OUARTER OUARTER ERROR A. Fission and Activation Gases
- 1. Total Release C1 1.73E+01 5.40E+00 2.50E+01
- 2. Average Release pCi/see 2.20E+00 6.87E-01 Rate for Period
- 1. Total Iodine C1 2.30E-04 1.77E-04 2.50E+01
- 2. Average Release pCi/sec 2.93E-05 2.25E-05 Rate for Period
- 3. Percent of % See Supplemental Information, ODCM Limits Section 7 C. Particulates
- 1. Particulates with C1 1.52E-06 9.71E-07 2.50E+01 half-lives greater than 8 days
- 2. Average Release pCi/sec 1.93E-07 1.23E-07 Rate for Period
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- 3. Percent of % See Supplemental Information, ODCM Limits Section 7
- 4. Gross Alpha ci 3.61E-07 2.14E-07 2.50E+01 Activity D. Tritium
- 1. Total Release Ci 7.23E+00 6.28E+00 2.50E+01
- 2. Average Release pCi/sec 9.20E-01 7.99E-01 Rate for Period
- 3. Percent of % See Supplemental Information, ODCM Limits Section 7 DBNPS Semiannual Effluent Report 9 Jan. - June, 1992
TABLE 2. CASEOUS EFFLtJENTS - GROUND-LEVEL RELEASES
- l COtmNUCrJS MODE' BA'ICH MODE"
+
FIRST SECOND FIRST SECOND NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER
- 1. Fission Gases Ci b
Kr-85 LLD 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 LLD 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 1.14E-06 2.52E-06 N/A N/A Sr-89 LLD LLD N/A N/A St-90 LLD LLD N/A N/A Cs-134 LLD LLD N/A N/A Cs-137 LLD 1.63E-07 N/A N/A Total for Period 1.14E-06 2.68E-06 N/A N/A Includes only Atmospheric Vent valve weepage and Auxiliary Feed Pump Turbine tests, both 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:
'Ar-41: <2.2E-08 Ci/ml Xe-133: <4.6E-08 Ci/ml Kr-85: <6.2E-06 pCi/ml Xe-133m: <1.6L-07 Ci/ml Kr-85m: <2.0E-08 Ci/ml Xe-135: <1.9E-08 vCi/ml Kr-87: <3.5E-08 pCi/ml Xe-135m: <9.9E-08 C1/ml Kr-88: <6.7E-08 C1/ml Xe-138: <2.5E-07 pCi/ml
.I-131: <1.0E-06 Ci/ml Cs-134: <2.1E-08 Ci/ml I-133: <2.1E-08 Ci/ml Cs-137: < 2 . 7 E--08 Ci/ml I-135: <6.8E-08 vCi/ml Sr-89: <5.0E-08 Ci/ml St-90: <6.0E-09 pC1/ml LLDs are applicable to both batch and continuous modes.
DBNPS Semiannual Effluent Report 10 Jan. - June, 1992 l
1
IABLE 3. GASEOUS EFTLUdiTS - MIXED-MODE PILEASES*
CONTINUOUS MODE BATCH MODE FIRST SECOND TIRST SECOND NUCLIDES UNIT QUARTER CUARTER QUARTER QUARTER
- 1. Fission Gases Ci Ar-41 - LIM LLD N/A IID Kr-85 LLD LLD N/A 3.84E-01 Kr-85m LLD LLD tyA LLD Kr-87 LLD LLD N/A LLD Kr-88 LLD LLD N/A LLD Xe-131m- LLD LLD N/A LLD Xe-133 1.39E+01 3.34E+00 N/A LLD Xe-133m LLD LLD N/A LLD Xe-135 3.44E+00 1.67E+00 N/A LLD Xe-135m LLD LLD N/A LLD Total for Period: 1.73E+01 5.01E+00 N/A 3.845-01
~
Total for Period: 2.30E-64 1.77E-04 N/A
- 3. Particulates Ci
.11 7.23E+00 6.28E+00 N/A 3.52E-04 Co-58 LLD LLD N/A LLD
[
! Er-89*'d LLD(1) LLD(2) H/A N/A Fr-90*** LLD(1) LLD(2) N/A N/A Pu-103 LLD LLD N/A LLD L Cs-134 4.30E-07 LLD N/A LLD
! Cs-137 1.09E-06 9.71E-07 N/A LLD Total for Period: 7.23E+00 6.28E+00 N/A 3.52E-04 ll DBNPS Semiannual Effluent Report 11 Jan. - June, 1992 h
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'IABLE 3. GASEOUS EFFLUENTS - MIXED-MODE RELEASES * (continued)
I Abnormal releases not included.
6 These radionuclides were not identified in concentrations above the lower
.imit of detection (LLD) listed below. The largest LLD value is listed.
Continuous Mode Batch Mode Ar-41: <2.9 E-08 vC1/ml Ar-41: <2.9 E-06 uci/ml Kr-85: <3.3 E-06 vCi/ml Kr-85m: <2.2 E-06 vCi/ml Kr-85m: <1.3 E-08 vCi/ml Kr-87: <4.5 E-06 vCi/ml Kr-87: <6.0 E-08 Ci/ml Kr-88: <6.6 E-06 vCi/ml Kr-88: <6.0 E-08 Ci/ml Xe-131m: <8.6 E-05 vCi/ml Xe-131m: <4.4 E-07 Ci/ml Xe-133: <3.9 E-06 Ci/ml Xe-133m <7.2 E-08 C1/ml Xe-133m: <1.8 E-05 Ci/ml Xe-135m: <5.9 E-06 vCiAnl Xe-135: <2.1 E-06 vCi/ml Xe-138: <2.0 E-05 vCi/ml Xe-135m: <1.4 E-05 pCi/ml 1-131: <2.6 E-14 Ci/ml I-131: <2.7 E-06 vCi/ml I-133: <3.1 E-13 vCiAnl 1-133: <3.0 E-06 C1/ml co-58: <1.6 E-14 vCi/ml Co-58: <3.0 E-06 vCi/ml Co-60: <2.5 E-14 vCi/ml co-60: <3.7 E-06 Ci/ml Sr-89(1): <1.3 E-15 vCi/ml Cs-134: <2.8 E-06 vCi/ml Sr-89(2): <1.4 E-15 Ci/ml Cs-137: <3.3 E-06 pCi/ml Sr-90(1): <2.9 E-16 Ci/ml Sr-90(2): <4.6 E-16 C1/ml Cs-134: <1.8 E-14 vCi/ml Cs-137: <2.4 E-14 vCi/ml Quarterly composite sample for continuous mode, d
Analysis not required for batch release.
DBNPS Semialmaal Effluent Report 12 Jan. - June, 1992
TABLE 4. CASEOUS EFTLUDCS - ABtOF2%L RELEASES FIRST SECCt1D NUCLIDES UNIT QUARTER (fJISTER
- 1. Fission Gases Ci Ar-41 LLD LLD*
Kr-85m LLD LLD Kr-87 LLD LLD Kr-88 LLD LLD Xe-133 LLD LLD Xe-133m LLD LLD Xe-135 LLD LLD Xe-135m LLD LLD Xe-138 LLD LLD Total for Period: N/A N/A
- 3. Particulates Ci H-3 2.56E-08 9.46E-08 Cs-134 LLD 1.20E-12 Cs-137 LLD 9.78E-09 Total For Period 2.56E-08 1.04E-07
- These radionuclides were not identified in concentrations above the lower h limit of detection (LID) listed in Table 2.
DBNPS Semiannual Effluent Report 13 Jan. - June, 1992 I
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'mBLE 5. LIQUID ErrLunns - Ste?%T8cN or ALL RELEASES EST. 'IOTAL FIRST SECOND PERCDU TYPE LNIT QUARTER QUARTER ERROR A. rission And Activation Products
- 1. Total Release (without Ci 6.45E-02 1.05E-02 1.00E+01 Tritium, Gases, Alpha)
- 2. Average Diluted Concen-
- Ci/ml 5.99E-09 1.04E-09 tration During Period
- 3. Percent of ODCM % See Supplemental information, Limit Section 7
- 4. Percent of 10CTR20 Limit % 2.12E-02 3.78E-03 B. Tritium
- 1. Total Release Ci 7.66E+01 1.20E+02 1.00E+01
- 2. /-arage Diluted concen-
- vCi/ml 7.12E-06 1.19E-05 tration During Period
- 3. Percent of 10CTR20 Limit % 2.37E-01 3.97E-01 C. Dissolved and Entrained Gases
- 1. Total Release Ci 1.37E-03 4.30E-04 1.00E+01
- 2. Average Diluted Concen-
- Ci/ml 1.28E-10 4.28E-ll tration During Period
- 3. Percent of Limit % 6.38E-05 2.14E-05 D. Gross Alpha b Total Release Ci LLD* 5.11E-06 1.00E+01 E. Volume of Waste Released liters 8.08E+07 9.31E+07 1.00E+01 (prior to dilution)
F. Volume of Dilution Water liters 1.06E+10 9.87E+9 1.00E+01 (used during releases)
G. Total Volume of Water liters 1.07E+10 9.91E+09 1.00E+01 Released (Outfall 001)
Based on volume of dilution water used during releases (Item F).
Alpha activity was not detected above the lower limit of detection, 2.tBE-08 Ci/ml.
DBNPS Semiannual Effluent Report 14 Jan. - June, 1992
n ,
1 TABLE 6. ' LIQUID EFTLUENTS - NUCLIDES RELEASED'- l COtTTINUCUS MODE -(Ci)d BAKH MODE (Ci)* ,
FIRST SECOND TIRST SECOND NUCLIDES QUARTER QUARTER QUARTER QUARTER
- 1. rission and Activation Products Cr-51 LtD* LLD 3.06E-04 LLD Mn-54 LLD LLD 6.24E-05 4.67E-05 re-55"- LLD(C1)- LLD(C2) 5.80E-03 4.05E-04 re-59 LLD LLD LLD LLD Co-57 LLD LLD 2.26E-05 2.03E-06 Co-58 LLD LLD 4.98E-03 6.10E-04 Co-60 'ID
. LLD 7.82E-03 1.84E-03 Zn-65 a LLD LLD LLD Sr-89* - LLD(C1) LLD(C2) LLD(B1) LLD(B2)
St-90' LLD(C1) LLD(C2) 3.57E-06 LLD(B2) 7r-95 LLD LLD 2.91E-04 1.11E-05 Zr-97 LLD LLD 9.75E-04 1.04E-04 Nb-95 LLD LLD 6.89E-05 LLD Nb-97 LLD LLD LLD 2.09E-Ce Mo-99 LLD LLD LLD LLD Te-99m LLD LLD LLD LLD Ru-103 LLD LLD 1.74E-04 LLD Ag-110m LLD LLD 4.19E-02 4.96E-03 Sb-125 LLD. LLD 1.51E-03 1.27E-03 Sn-113 LJ LLD 7.47E-04 6.75E-05 I-131 LLD LLD 2.02E-05 2.06E ,
Cs-134 LLD LLD 2.02E-03 6.82E Cs-136 LLD LLD LLD LLD Cs-137 LLD LLD 2.95E-03 9.31E-04 Ba-140 LLD LLD 4.13E-05 LLD Ce-141 LLD LLD LLD ~LLD
-Ce-144 LLD LID 6.36E-04 1.30E-05 Total for period: WA N/A 6.45E-02 1.05E-02
- 2. Tritium 2.10E-01 7.89E-01 7.66E+01 1.20E+02.
-3. Dissolved and' Entrained Gases Xe-133 LLD LLD 1.33E-03 3.89E-04 Te-133m LLD LLD 1.66E-05 LLD xe-135 LLD LLD 2.01E-05 4.10E-05 Total for Period: N/A N/A 1.37E-03 4.30E-04 DBNPS Semiannual Effluent Report 15 Jan. - June, 1992
TNBLE 6. LIQUID EFTLUENTS - NUCLIDES RELEASED * (continusd)
Abnormal releases not included.
These radionuclides were not identified in concentrations above the lower Jimit of detection (LLD) listed below. The largest LLD value is used tor each radionuclide.
Cr-51: <1.7 E-07 uci/ml Mn-54: <2.1 E-08 vCi/ml re-55(C1): <6.0 E-07 vC1/ml re-55(C2): <5.0 E-07 vCi/ml Fe-59: <4.2 E-08 Ci/ml Co-57: <1.6 E-08 vCi/nl Co-58: <1.9 E-08 pCi/ml co-60: <2.5 c-08 vC1/ml 2n-65: <5.2 E-08 pCi/ml Kr-85: -<6.2 E-06 pCi/ml Sr-89(B1): <4.0 E-08 vCi/ml Sr-89(B2): <2.1 E-05 vCi/ml Sr-89(C1): <3.0 E-08 Ci/ml Sr-89(C2): <7.0 E-08 vCi/ml St-90(B2): <3.7 E-06 pCi/ml Sr-90(C1): <6.0 E-09 vCi/ml Sr-90(C2): <1.0 E-08 vCi/ml Zr-95: <4.0 E-08 Ci/ml Nb-95: <2.1 E-08 vC1/ml tr-97: <2.5 E-08 vCi/ml Nb-97: <2.5 E-08 vCi/ml Mo-99: <1.6 E-07 vCi/ml Ru-103: <2.2 E-08 vCi/ml Tc-99m: <1.8 E-08 vCi/ml Ag-110m: <2.5 E-08 vC1/ml Sn-113: <2.8 E-08 vCi/ml Sb-125: <1.7 E-08 vCi/ml I-131: <2.5 E-08 pCi/nl I-133: . <2.1 E-08 pCi/ml Xe-133: <4.6 E-08 vCi/ml xe-133m: <1.6 E-07 vC1/ml xe-135: <1.9 E-08 vCi/ml Ce-141: <3.0 E-08 vCi/ml Ce-144: <1.7 E-07 pCi/ml -
Cs-134: <2.1 E-08 vCi/ml Cs-136: <2.8 E-08 Ci/ml Cs-137- <2.7 E-08 vCi/ml Ba-140: <7.0 E-08 vCi/ml Quarterly composite sample, d
- LLds are applicable to both batch and contint'ous modes due to j identical sample and analysis methods.
DBNPS Semiannual Effluent Report 16 Jan. - June, 1992
TABLE 7. LIQUID ErrLuntrS - ABIOPMAL RELEASES TIRST SECOND j
NUCLIDES-~ UNIT OUARTER QUARTER
- 1. rission and Activation Products N/A N/A
- 2. Tritium Ci N/A N/A
- 3. Dissolved and Entrained Gases N/A N/A
- There were no abnormal liquid relea3es during the first and second quarters of 1992.
DBNPS Semiannual Effluent Report 17 Jan. - June, 1992
TABLE 8. SOLID WASTE AND fRRADZATED FUEL SHfPMDRS A. Solid Waste Shipped offsite for Burial or Disposal (not irradiated fuel)
EST. M AL PERCENT
- 1. Type of Waste- UNIT QUAtCITY ERROR ;
- a. Spent resins, filter sludges, m' 5.8 E+00 evaporator bottoms, etc. Ci 3.2 E+00 2.5 E+01
- b. Dry compressible waste, m' O.0 E+00 contaminated equipment, etc. Ci 0.0 E+00 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' 4.5 E+00 System Cartridge Filters Ci 3.4 E+01 2.5 E+01
- 2. Estimate of Major IAlclide Composition (by type of waste) l l PERCENT ABUILANtf a re-55 21 Co-58 18 Co-60 15 Ni-63 10.
Cs-134 12 Cs-137 16 Ag-110m- 5
- d. re-55 29 i Co 12 Co-60' 42
- 3. Solid Waste Disposition Number of Shipments: 3
' Mode _of Transportation: Truck Destination: Barnwell, S.C.
_of Container 3 (Container Vclume)3)
), and'1 Filter HIC.(1.lm Solidification Agents: None
'B.. Tiradiated Fuel Shipments There were no snipments of irradiated fuel.
DBNPS Semiannual Effluent Report. 18 Jan. - June, 1992 i
'IABLE 9. SEMIANtRIAL DOSES DUE TO GASEOUS RELEASES A. . Maximum Individual Doses Due to 1-131, H-3, and Particulates with Half-lives Greater 'Ihan 8 Days'
- 1. Wnole 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
- 2. Significant organ Dose SECIOr DISTANCE (m) AGE ORGAN DOSE (mrem) ,
Quarter 1 W 1720 child 'Ihyroid 1.42E-02 Quarter 2 W 1720 child Thyroid 1.03E-03 Semiannual W 'MO Child Thyroid 1.52E-02 B. Maximum Individual Doses Due to Noble Gas"
- 1. Whole Body Dose SECIOR DISTANCE (m) AGE DOSE (mrem)
Quarter 1 W 980 NA 2.77E-03 -
Quarter 2 W 980 tm 1.27E-03 Semiannual W 980 tm 4.04E-03
- 2. Skin Dose SECIOR DISTANCE (m) AGE DOSE (mrem)
Quarter 1 W -980 tm 7.48E-03 Ouarter 2 W 980 NA 3.44E-03 Semiannual W 980 NA 1.09E-02 DBNPS Semiannual Effluent Report 19 Jan. - June, 1992
Tabla 9. SEMIAIUUAL DOSES DUE TO GASEOUS RELEASES (continusd) i l
l C. Population Doses due to I-131, H-3, and Particulates with j Half-lives Greater than 8 Days'
'IUTAL INTEGRATED AVERAGE DOSE 'IO '
POPULATIO4 DOSE INDIVIDUALS IN ORGAN (person rem) POPULATIOJ (mrem) ,
I Quarter 1 W/ body 5.70E-03 2.56E-06 l Quarter 2 _ W/ body 4.67E-04 2.10E-07 '
Semiannual W/ body 6.17E-03 2.77E-06 1
l l
D. Population Doses due to Noble Gas' !
'IOTAL ItTTEGRATED AVERAGE DOSE 'IO POPULATION DOSE INDIVIDUALS IN ORCWJ (person rem) POPULATIO4 (mrem)
Quarter 1 W/ body 2.77E-03 1.24E-06 Quarter 2 W/tody 1.21E-03 5.42E l Semiannual W/ body 3.97E-03 1.79E-06 l
-DBNPS Semiannual Effluent Report 20 Jan. - June, 1992
TABLE 9.-' SEMIANNUAL DOSES DUE TO GASEOUS RELEASES (continued)
E. - Abnormal Releases due to Overpressurization of the Auxiliary Steam Systen
-Half-lives Greater than 8 Days A. Vhole Body Dose SECTOR DISTANCE (m) AGE DOSE (mrem)
Quarter i NNE 870 Teen 5.33E-12 Quarter-2 SV 1340 Teen 1.34E-07 Semiannual SV 134f Teen 1.34E.V7
~
-B. Significant Organ Dose SECTOR DISTANCE (m) ACE ORGAN DOSE (mrem)
Quarter 1 NNE 870 Teen Liver 5.33E-12
-Quarter 2 SV 1340 Child Bone 2.36E-07 Semiannual SV 1340 Child Bone 2.36E-07
- 2. Maximum Individual Dose due to Noble Gas SECTOR DISTANCE (m) AGE ORGAN DOSE (mrem)
N/A N/A N/A N/A 0.00E+00 i=
Does not include abnormal releases.
DBNPS Semiannual Effluent Report 21 Jan. - June, 1992 l
1
-_ -__._. - -_.m_ _ _ _ - _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ - _ _-- __ ____
TABLE 10. SEMIAtNUAL DOSES DUE TO LIQUID PILEASES l A. Maxima Individual whole Body Dose SECTOR DISTANCE (mi) AGE DOSE (mrem)
Quarter 1 tM 0.6 Adult 5.02E-02 Quarter 2 tM 0.6 Adult 2.02E-02 Semiannual IM 0.6 Adult 7.04E-02 B. Maxim m Individual Significant Organ Dose SECTOR DISTANCE (mi) AGE ORGAN DOSE (mrem)
Quarter 1 IM 0.6 Teen Liver 6.83E-02 Quarter 2 iM 0.6 Teen Liver 2.51E-02 Semiannual IM 0.6 Teen Liver 9.34E-02 C. Population Dose 70TAL INTEGRATED AVERAGE DOSE TO POPULATION DOSE INDIVIDUALS IN ORGAN (perso_n rem) POPULATION (mrem)
Quarter 1 W/ body 7.99E-01 3.59E-04 Quarter 2 W/ body .L 9!>E-01 1.78E-04 Semiannual W/ body 1.195+00 5.37E-04 t
DBNPS Semiannual Effluent Report 22 Jan. - June, 1992
.thBLE 11. 1992 SEMIMa4UAL DOSE '10 THE MOST-EXPOSED MmBER OF THE PUBLIC 40 CTR 190 SEMIMR4UAL DOSE LIMITS PERCE?il' OT (mrem) (mrem) LIMITS Whole Body Dose
- tioble Gas 4.04E-03
- Iodine, Tritium, Particulates 8.20E-03
- Liquid 7.04E-02 heal Whole Body Dose 8.26E-02 25 3.31E-01 Thyroid Dose
-Iodine, Tritium, 1.52E-02 75 2.03E-02 Particulates Skin Dose
- tioble Gas 1.09E-02 25 4.36E-02 Liver Dose
- Liquid 9.34E-02 25 3.74E-01 DBNPS Semiannual Ef fluent Report 23 Jan. - June, 1992
!CTDROID3ICAL DATA Meteorological data on magnetic tape for January through June 1992 has been suinitted with this document to the U.S. !Melear Regulatory Comission Document Control Desk, Washington, D.C. 20555.
3 F
DBNPS Semiannual Effluent Report 24 Jan. - June, 1992
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