ML20236N428

Corrected Replacement Pages x,88 Through 90 & 108 Through 109 of Davis-Besse Nuclear Power Station 1997 Annual Radiological Environ Operating Rept, Including Radiological Effluent Release Rept

ML20236N428
Person / Time
Site:	Davis Besse
Issue date:	12/31/1997
From:	CENTERIOR ENERGY
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ML20236N410	List: ML20236N408 ML20236N428
References
NUDOCS 9807150125
Download: ML20236N428 (6)

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. Davis-Besse Nuclect Power Station 1997 Annual Radiologicci Environmental Operating Report Radiological Effluent Release Report The Radiological Emuent Release Report (RERR) is a detailed listing of radioactivity released from i the Davis-Besse Nuclear Power Station during the period, January 1,1997 through December 31, i 1997. The doses due to radioactivity released during this period were estimated to be:

Liquid Emuents:

Maximum Individual Whole Body Dose 5.03E-02 mrem (0.0503 mrem)

Maximum Individual Significant Organ Dose 5.25E-02 mrem (0.0525 mrem)

TotalIntegrated Population Dose 5.20E-01 person-rem (0.520 person-rem)

Average Dose to the Individual 2.39E-04 mrem (0.000239 mrem)

Gaseous Emuents:

Maximum Individual Whole Body Dose due to 8.31E-03 mrem I-131, H-3 and Particulate with half-lives (0.00831 mrem) greater than 8 days l

Maximum Significant Organ dose due to I-131, 1.54E-02 mrem H-3 and Particulate with half-lives greater than (0.0154 mrem) 8 days Total Integrated Population dose due to I-131, 5.75E-03 person-rem H-3 and Particulate with half-lives greater than (0.00575 person-rem)

' l 8 days Average dose to an Individual in the population 2.64E-06 mrem due to I-131, H-3 and Particulate with half-lives (0.00000264 mrem) greater than 8 days l

Maximum Individual Skin dose due to noble gases 2.36E-04 mrad (0.000236 mrad)

Maximum Individual Whole Body Dose due to 2.04E-04 mrad noble gases (0.000204 mrad)

. Total Integrated Population dose due to noble gases 6.42E-05 person-rem (0.0000642 person-rem)

Average dose to individual in population due to 2.95E-08 mrem noble gases (0.0000000295 mrem) 9907150125 990707 PDR ADOCK 05000346 R PDR. x

' Davis-B:sse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Regulatory Limits Gaseous Effluents In accordance with Offsite Dose Calculation Manual, 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:

Noble gases:

• Released at a sig equal to or less than 500 mrem TEDE per year. (Note: the total dose due to these releases is also limited to 50 mrem in any calendar year.)

e Released at a sig such that the total dose to the skin will be less than or equal to 3000 mrem in a year.

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

• Released at a rate such that the total dose to any organ will be less than or equal to 1500 mrem in a year.

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:

• 12ss than or equal to 10 mrad total for gamma radiation and less than or equal to 20 mrad total for beta radiation in any calendar year.

l - In accordance with 10CFR50, Appendix I, Sec. IIC, dose to a member of the public from lodine-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:

e less than or equal to 15 total mrem to any organ in any calendar year.

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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l iquid Effluents In accordance with 10CFR50, Appendix 1, Sec IIA, the dose or dose commitment to a member of the public from radioactivity in liquid emuents released to unrestricted areas shall be limited to accumulated doses of:

e~ 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.

Effluent Concentration Limits The Emuent Concentration Limits (ECs) for liquid and gaseous emuents 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 uCi/ml is applied. This EC is based on the Xe-135 DAC of IE-05 uCi/ml of air (submersion dose) converted to an equivalent concentration in water as discussed in the In-ternational Commission on Radiological Protection (ICRP), Publication 2.

Average Energy The Davis-Besse ODCM limits the dose equivalent rates due to the release of fission and activation products to less than or equal to 500 mrem per year to the total body and less than or equal to 3000 mrem per year to the skin. Therefore, the average beta and gamma energies (E) for gaseous emuents as described in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Emuents from Light-Water-Cooled Nuclear Power Plants" are not applicable.

Measurements of Total Activity

Fission and Activation Gases:

l These gases, excluding tritium, are collected in a marinelli beaker specially modified for gas sampling, steel l flasks, or glass vials and are counted on a germanium detector for principal gamma emitters. Radionuclides that are detected are quantified via gamma spectroscopy.  ;

Tritium gas is collected using a bubbler apparatus and counted by liquid scintillation.

Iodine Iodine are collected on a charcoal cartridge filter and counted on a germanium detector. Spec;fic quantification ,

of each iodine radionuclides is via gamma spectroscopy.

l Particulate Particulate are collected on filter paper and counted on a germanium detector. Specific quantification of each radionuclides present on the filter paper is via gamma spectroscopy.

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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report 2

Liquid Effluents Liquid' effluents are collected in a marinelli beaker and counted on a gennanium detector.

Quantification of each gamma-emitting radionuclides present in liquid samples is via gamma spectroscopy. Tritium in the liquid effluent is quantified by counting an aliquot of a composite sample in a liquid scintillation counting system.

Batch Releases Liquid from 1/1/97 through 12/31/97

1. Number of batch releases: 63 l 2. Total time period for the batch releases: 99.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />

3. Maximum time period for a batch release: 207 minutes

4. Minimum time period for a batch release: 67 minutes

5. Average time period for a batch release: 94 minutes Gaseous from 1/1/97 through 12/31/97

1. Number of batch releases: 9

2. Total time period for the batch releases: 137 hours0.00159 days <br />0.0381 hours <br />2.265212e-4 weeks <br />5.21285e-5 months <br />

3. Maximum time period for a batch release: 2530 minutes

4. Minimum time period for a batch release: 197 minutes

5. Average time period for batch release: 913 minutes Abnormal Releases

1. Reactor trip of 5-4-97. One OTSG relief valve did not reset.

2. Auxiliary steam 235 relief valve lifted twice for 4 seconds in June.

Percent of ODCM Release Limits The following table presents the ODCM annual dose limits and the associated offsite dose to the public, in percent oflimits, for January 1,1997 through December 31,1997.

PERCENT OF SPECIFICATION ANNUAL DOSE LIMIT LIMIT Report Period: January 1,1997 - December 31,1997 (gaseous)

Noble gases (gamma) 2.(ME-04 mrad 10 mrad 2.04E-03 Noble gases (beta) 2.36E-04 mrad 20 mrad 1.18E-03 I-131, tritium and particulate 8.31E-03 mrem 15 mrem 5.54E-02 Report Period: January 1,1997. December 31,1997 diquid)

Total body 5.03E-02 mrem 3 mrem 1.68E+00 Organ 5.25E-02 mrem 10 mrem 5.25E-01 i

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Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report l Table 24 Doses Due to Liquid Releases for January through December 1997 Maximum Individual Whole Body Dose 5.03E-02 mrem

~ Maximum Individual SigniGcant Organ Dose 5.25E-02 mrem Population Dose TotalIntegrated Population Dose 5.20E-01 person-rem Average Dose to Individual 2.39E-04 mrem I

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" Davis-Besse Nuclear Power Station 1997 Annual Radiological Environmental Operating Report Table 25 l A'nnual Dose to the Most Exposed Member of the Public 1997 ANNUAL DOSE 40CFR190 LIMIT - PERCENT OF (mrem) (mrem) LIMIT l Whole Body Dose l Noble Gas 2.04E-04

Iodine, Tritium, Particulate 8.31E-03 l Liquid 5.03E-02 Total Whole Body Dose 5.88E-02 25 2.35E-01 Thyroid Dose

- Iodine, Tritium, Particulate 1.54E-02 75 2.05E-02 Skin Dose Noble Gas 2.36E-04 25 9.44E-04 Significant Organ Dose (Liver) 5.25E-02 25 2.10E-01 Meteorological Data Meteorological data on 3'/ 2inch microdisk for January through December 31,1997, has been submitted with this document to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555.

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