ML20090C574

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Semiannual Radioactive Effluent & Waste Disposal Rept Jul-Dec 1991. W/Undated Ltr
ML20090C574
Person / Time
Site: Davis Besse 
Issue date: 12/31/1991
From: Storz L
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
DSR-92-00053, DSR-92-53, NUDOCS 9203050104
Download: ML20090C574 (62)
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Text

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TOL F DO EDISON A Ctateo n [ repr Ctmt.any i DtS,CO PL AZA 4

31) AAD6DN AVE Ntil 10Lf DD DHiO 4*J0!P(KX11 DSR-92-00053 Docket Number 50-346 License Number: HPF-3 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subjec t :

July 1 - December 31, 1991 Radioactive Effluent and Vaste Disposal Report Gentlemen:

i Enclosed are two copies of the July 1 - December 31, 1991 Radioactive Effluent and Vaste Disposal Report for the Davis-Besse Nuclear Power Station. This report meets the requirements of Regulatory Guide 1.21 and Davis-Besse Technical Specifications, Section 6.9.1.11.

Gaseous and liquid radioactivity released remained well within the limits of the Operating License Appendix A Technical Specifications. No changes were made to th9 Offsite Dose Calculation Manual or Process Control Program during this reporting period.

Should you have any questions please contact R. V. Schrauder, Manager - Nuclear Licensing, at (419) 249-2366.

Very truly yours,

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L. F. Storz Plant Manager IHB/ekg Enclosure cet V. Levis, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, DB-1 NRC Senior Project Manager Utility Radiological Safety Board f*3 or

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DSR-92-00053 Page 2 For Information Only cct D. V. Briden (3185)

R. L. Dielman (3360)

B. L. Geddes (4060)

G. A. Gibbs (3387)

J. P. Greer E.

llamme t H. E. Hiles (3030)

Nuclear Records Management (3220) j R._

Owen J. R. Polyak-(1029)

J R. V. Schrauder_

(3065)

D. C. Shelton (3080)

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Sherman R.

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i The Davis-Besse Nuclear Power Station l

l Semiannual Radioactive Effluent and Waste Disposal Report July 1 - December 31,1991 I

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RADIOACTIVE EFFLUENT AND VASTE DISPOSAL REPORT i

i Davis-Besse 14uclear Power Station i

Unit No. 1 July 1, 1991 through Dec. 31, 1991

!ocket Number 50 346 License Number NPF-3

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Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 1

March 1992 l-l l?

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TABLE OF CONTENTS Title g

l 1

i List of Tables 11 r

Summary 1

-Supplemental Information 3

Effluent Data Tables 9

Meteorological Data 25

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DBNPS Radioactive' Effluent Report'.

1

. July - Dec.

1991

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i LIST OF TABLES Table Number Title P_ age 1

Gaseous Effluents - Summation of 9

All Releases 2

Gaseous Effluents - Ground-Level Releases 10 3

Gaseous Eff ts - 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 20 Releases t

10 Semiannual Doses Due to Liquid 23 Releases 11 1991 Annual Dose to the Host-24 Exposed Member of the Public t

DBNPS Radioactive Effluent Report 11 July - Dec., 1991 n

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I

SUMMARY

The Radioactive Effluent and Vaste Disposal Report is a detailed listing of radioactivity released from the Davis-Desse Nuclear Power Station during the period from July 1, 1991 through December 31, 1991.

This report provides the following informations Summation of the quantities of radioactivity released in gaseous and liquid effluents, Summation of the quantities of to ioactivity contained in solid vaste packaged and shipped for offsite disposal at federally approved sites, and A listing of radioactive effluent monitoring instrumentation required by Technical Specifications which was inoperabic for 30 days or longer.

Environmental samples were available from the normal collection locations during this reporting period.

The locations used for dose calculations and environmental monitoring vere those identified by the 1991 ' and Use Census.

Some new sampling or dose assessment locations were identified in this Census, however, the critical receptor remained the same.

During the period of July 1 through December 31, 1991, the maximum individual offsite dose due to radioactivity released in effluents was approximately:

Liquid Effluents:

5.89E-02 mrem, whole body 9.91E-02 mrem, lover large intestine (CI-LLI)

Gaseous Effluents:

Noble Gas 8.18E-03 mrem, whole body 2.56E-02 mrem, skin Iodine-131, Tritium, and Particulates with flalf-lives Greater Than 8 Days:

2.71E-02 mrem, whole body 4.22E-02 mrem, thyroid These doses are only a small fraction of the limits set by the NRC in the Davis-Besse Technical Specifications.

DBNPS Radioactive Effluent Report 1

July - Dec., 1991

There cuist several additional normal release pathvays from the secondary system as a result of prior primary-to-secondary leakage. For gaseous effluents, these pathways include the auxiliary feed pump turbine exhaust, the main steam safety valve system and the atmospheric vent valve system.

Por liquid effluents, the additional pathways 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.

Several small gaseous releases associated with overpressurization of the Auxiliary Steam System occurred in the second half of 1991. These releases were quantified and included in the abnormal release sections of this report.

On October 15, 1991, 910 gallons of slightly contaminated water vere disa.harged to the onsite Training Center Pond due to overfilling a steam generator. The discharge contained a total of 81 901 of tritium, cesium-134 and cesium-137. The water discharged to the Training Center Pond has not yet been released from the site. Therefore, this does not constitute an offsite release and no resulting dose to the public vill be reported for this semiannual period. Vater samples are collected veekly from the Training Center Pond to track activity.

The third quarter composite samples from gaseous ground-level releases and 11guld continuous releases vere not analyzed due to loss of control of the samples. Therefore, Tables 2 and 6 use the term " unavailable" for the affected radionuclides. Based on past analyses, these radionuclides should not have been detectable in the third quarter samples.

No changes to the Offsite Dose Calculation Manual (ODCM) or the Process Control Program (PCP) occurred during this reporting period, i

-DBNPS Radioactive. Effluent Report 2

July - Dec., 1991-p

_-.--,.__.O

StJPPLEMENTAL INFORMATION 1.

RECllLATORY LIMITS A.

Caseous 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 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 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 1, 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 followings 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 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 equal to 3 mrem to the total body and less than s

or equal to 10 mrem to any organ during any calendar year.

DBNPS Radioactive Effluent Report 3

July Dec., 1991

2.

MAXIMllM PERMISSIBLE CONCFETRATION The maximum permissible concentrations (HPC) for liquid and gaseous effluents at and beyond the site boundary are listed in 10 CFR 20, Appendix B, Table II, Column 2. vith the most restrictive HPC being used in all cases.

For dissolved and entrained gases the HPC of 2.OE-04 pCi/ml is applied. This HPC is based on the Xe-135 MPC in air (submersion dose) converted to an equivalent concentration in vater as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.

3.

AVERAGE ENERGY The Davis-Desse Technical Specifications limit the dose equivalent rates due to the release of fission and activation products to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin.

Therefore, the average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21, "Heasuring, Evaluating, and Reporting Radioactivity in Solid Vastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Vater-Cooled Noelcar Power Plants," is not applicable.

4.

HEASilREMENTS AND APPROXIMGONS OF TOTAL 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 made by 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 made by 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 made by gamma spectroscopy, i

l DBNPS Radioactive Effluent Report 4

July - Dec., 1991 D

5.

HATCil RELEASES A.

Liquid from 7/1/91 to 12/31/91

1. Number of batch releases:

62

2. Total time period for the batch releasest 1.08E402 hours i
3. Maximum time period for a batch release:

2.44E+02 minutes

4. Average time period for a batch release:

1.05E.02 minutes

5. Minimum time period for batch releases:

6.30E+01 minutes

~

B.

Gaseous from 7/1/91 to 12/31/91

1. Number of batr's releases:

11

2. Total time period for the batch releases: 9.29E+01 hours
3. Maximum time period for a batch release:

1.340403 minutes

4. Hinimum time period for a batch release:

1.80E402 minutes

5. Average time period for batch releases:

5.07E402 minutes 6.

ABNORMA1.-RElfASES Several unplanned Easeous releases occurred during this reporting period from lifts of safety valves on the 235-psig and 50-psig Auxiliary Steam System 11eaders due to system overpressurization. These releases occurred on 8/10/91, 10/08/91, 10/15/91, 10/21/91, 11/08/91, 11/17/91, 11/25/91, and 12/23/91 and produced very small offsite doses. Activity released and resultant doses are reported in Tables 4 and 9.

-DBNPS Radioactive Effluent Report 5

July - Dec., 1991

7.

PERCENT OF TECHNICAL SPECIFICATIONS LIMITS The following table presents the Technical Specifications dose limits and the associated offsite dose to the public, in percent of limits, for July through December 1991.

SPECIFICATION LIMIT PERCENT OF LIMITS A. Third Quarter, 1991: Gaseous Noble gases (gamma) 5.0 mrad 3.02E-01 Noble gases (beta) 10.0 mrad 4.63E-01 I-131, tritium, and 7.5 mrem 7.47E-01 particulates with half-lives greater than 8 days B. Fourth Quarter, 1991:

Gaseous Noble gases (gamma) 5.0 mrad 4.74E-03 Noble gases (beta) 10.0 mrad 9.96E-03 I-131, tritium, and 7.5 mrem 4.82E-02 particulates with half-lives greater than 8 days C. Calendar year, 1991:

Gaseous Noble gases (gamma) 10.0 mrad 1.53E-01 Noble gases (beta) 20.0 mrad 2.36E-01 l

I-131, tritium, and 15.0 mrem 3.98E-01 particulates with half-lives greater than 8 days l

l D. Third Quarter, 1991:

Liquid Total body 1.5 mrem 1.30E400 Any organ (liver) 5.0 mrem 5.02E-01 E. Fourth Quarter, 1991:

Liquid Total body 1.5 mrem 1.26E400 Any organ (GI-LLI)'

5.0 mrem 2.50E400 F. Calendar year, 1991:

Liquid Total body 3.0 mrem 1.28E400 Any organ (GI-LLI) 10.0 mrem 1.30E+00 DBNPS Radioactive Effluent Report 6.

July - Dec., 1991

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 $0, 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 Hilk Production Data Tables for 1982." This evaluation vas based on the 1980 census:

the Agricultural Ministry of Ontario 1980 report entitled,

" Agricultural Statistics and Livestock Harketing 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 pathvays 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 Tile SITE BOUNDARY In accordance with Technical Specification 6.9.1.11, 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 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 Technical Specification 6.9.1.11, the following exposure assumptions may be used:

,3NPS Radioactive Effluent Report 7

July - Dec., 1991 E

a

Exposure time for maximum-exposed visitor of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> (4 visits, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per visit is a maximum conservative estimate).

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

The equations in the Offsite Dose Calculation Manual (ODCH) 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 ODCH conservatively estimates the maximum potential dose to members of the public.

10.

INOPERAllLE RAD 10ACr1VE EFFLUENT MONITORING F/)UIPMlWf No radicartive effluent monitoring equipment requited to be operable by Davis-Besse Technical Specifications Sections 3.3.3.9 and 3.3.3.10 was inoperable for 30 days or longer during this reporting period.

11.

CilANCES TO Tile 1.AND USE CENSUS The following are the results of the 1991 Land Use Census. Changes from the 1990 Land Use Census are denoted with asterisks.

Distance X/0 D/

Sector (metersl Pathways Age Group (sec/m8)

(m'g)

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 through SE are located over norsh areas and Lake Erie, no inhalation or ingestion pathways are present.

SSE 2900 vegetation child 6.80E-08 7.90E-10 S

1450 vegetation child 1.21E-07 2.46E-09 SSW 1560*

vegetation child 1.03E-07*

2.20E-09*

SW 1050*

vegetation child 2.92E-07*

5.33E-09*

WSW 4270 cow / milk infant-5.71E-08 5.31E-10 W

1720*

vegetation child 2.47E-07*

3.81E-09*

Pasi 1750*

vegetation child 1.46E-07*

1.72E-09*

NW 2630*

vegetation child 5.96E-08*

4.50E-10*

ta44 1210 vegetation child 2.70E-07 1.92E-09 DBNPS Radioactive Effluent Report 8

July - Dec., 1991

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TABLE 1.

GASEOUS EFPLUDJTS - SUMMATIO24 OF ALI RELEASES EST. 'IUTAL THIRD TOURTil PERCD4T TYPE UNIT CUARTER OUARTER ERROR A.

Fission and Activation Gases 1.

Total Release C1 7.21E+02 1.22E+01 2.50E+01 2.

Average Release sic 1/sec 9.08E+01 1.53E+00 Rate for Period 3.

Percent of See Supplemental Information, Technical Section 7 Specifications Limits B.

Iodines 1.

Total Iodine ci 2.87E-03 2.88E-04 2.50E+01 2.

Average Release tic 1/t;ec 3.61E-04 3.63E-05 Rate for Period 3.

Percent of See Supplemental Information, Technical Section 7 Specifications Limits C.

Particulates 1.

Particulates with Ci 5.81E-06 7.57E-06 2.50E+01 half-lives greater than 8 days 2.

Average Release sici/sec 7.31E-07 9.540-07 Rate for Period 3.

Percent of See Supplemental Information, Technical Section 7 Specifications Limits 4.

Gross Alpha Ci 3.47E-07 3.10E-07 2.50E+01 Activity D.

Tritium 1.

Total Release Ci 4.72E+01 5.41E+00 2.50E+01 2.

Average Release siCi/sec 5.95E+00 6.83E-01 Rate for Period 3.- Percent of See Supplemental Information, Technical Section 7 Specifications Limits DDNPS Radioactive Elfluent Report 9

July - Dec., 1991

'!ABLE 2.

GASEOUS ErrLUENTS - GROUND-LETEL RELEASES' CONTINUOUS MODE

!%TCil NODE

'IllIRD IVUR'I11

'IllIRD ftVR'111 NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER 1.

Fission Gases Ci Ar-41 1.66E-07 LLD' N/A N/A Kr-85 LLD LLD N/A N/A Kr-85m 3.02E-03 LLD N/A N/A Kr-87 2.64E-03 LLD N/A N/A

-Kr-88 3.39E-03 LLD N/A N/A Xe-133 7.29E-02 LLD N/A N/A Xe-133m 1.98E-03 LLD N/A N/A Xe-135 7.86E-03 LLD N/A N/A Xe-135m 3.71E-03 LLD N/A N/A Xe-138 2.24E-03 LLD N/A N/A l

Total for Period:

9.77E-02 N/A N/A WA 2.

Iodines Ci I-131 5.31E-08 LLD N/A N/A I-133 2.55E-07 LLD N/A N/A I-135 LLD LLD N/A Nl4%

Total for Period:

3.08E-07 N/A N/A N/A 3.

Particulates Ci H-3 2.55E-02 8.94E-04 N/A N/A Sr-89*

unavailable LLD(2)

N/A N/A St-90*

unavailable LLD(2)

N/A N/A Cs-134 LLD 4.11E-08 N/A N/A Cs-137 2.59E-07 1.15E-07 N/A N/A Total for Period:

2.55E-02 8.94E-04 N/A N/A Includes Atmcspheric Vent Valve weepage and Auxilliaty reed Pump Turbine tests, both are listed as continuous releases.

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

-Ar-41:

<1.4E-08 vCi/ml Xe-135m:

<9.2E-09 pC1/ml Kr-85:

<3.2E-06 vCi/ml Xe-138:

<6.9E-08 vCi/ml Kr-85m:

<2.6E-06 vCi/ml I-131:

<1.2E-08 Ci/ml Kr <1.1E-08 vC1/ml I-133:

<1.8E-08 Ci/ml Kr-88:

<2.8E-08 Ci/ml I-135:

<8.0E-08 vC1/ml Xe-133:

<3.4E-08 Ci/ml Cs-134:

<1.6E-08. Ci/ml Xe-133m:

' 6.7E-08 vCi/ml Sr-89(2):

<1.0E-08 Ci/ml Xe-135:

<8.0E-09 Ci/ml Sr-90(2):

<2.0E-09 vCi/ml Quarterly composite sample DBNPS Radioactive Effluent Report 10 July - Dec., 1991 r

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TABLE 3.

CASDOUS ErrLUENTS - MIXED-MODE RELEASES C0ffrI!UOUS MODE laTCl! MODE 7111RD FOUR111 THIRD FOURTil NUCLIDES UNIT OUARTER QUARTER QUARTER QUARTER 1.

rission Gases Cl Ar-41 Ltd LLD LLD 1.73E-02 Kr-85 LLD LLD 2.82E+01 3.88E+00 Kr-85m LLD LLD LLD 2.99E-04 Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD LLD LLD Xe-131m LLD LLD 4.68E+00 1.67E-01 Xe-133 1.54E+02 6.65E+00 5.24E+02 8.09E-01 Xe-133m LLD LLD 7.72E-01 1.07E-02 Xe-135 1.01E+01 6.15E-01 7.28E-02 7.38E-03 Xe-138 LLD Lin LLD LLD Total for Period:

1.64E+02 7.26E+00 5.58E+02 4.89E+00 2.

Iodines Ci 1-131 2.48E-03 1.44E-04 LLD 4.71E-06 I-132 LLD LLD LLD 6.36E-06 1-133 3.94E-04 4.90E-05 LLD 5.35E-05 I-135 LLD LLD LLD 3.07E-05 Total for Period:

2.87E-03 1.93E-04 LLD 9.52E-05 3.

Particulates Ci H-3 5.39E+00 5.40E+00 4.18E+01 2.32E-02 Co-58 LLD LLD LLD 1.81E-07 St-89 LLD(1)

LLD(2)

LLD(1)

LLD(2)

Sr-90 LLD(1)

LLD(2)

LLD(1)

LLD(2)

Cs-134 2.45E-06 LLD LLD

2. 85E- 06 Cs-137 3.10E-06 QD LLD 4.54E-06 7btal for Period:

5.39E+00 5.40E+00 4.18E+01 2.32E-02 L

DBNPS Radioactive Effluent Report 11 July - Dec., 1991 L

TM LE 3.

GASIX)US EITLUDITS - MIXED-MODE RELEASES (continued) l Abnormal releases not included b

'Ihese radionuclides were not identified in concentrations above the lower I

limit of detection (LLD) listed below:

Ar-41:

<9.1 E-09 vCi/ml Kr-85:

<2.8 E-06 vci/ml Kr-85ti:

<2.6 E-09 vC1/ml Kr-87:

<1.1 E-08 vCi/ml Kr-88:

<2.8 E-08 vCi/ml Xe-131m:

<3.0 E-07 vCi/ml Xe-133m:

<6.7 E-08 vC1/ml Xe-138:

<6.9 E-08 Ci/ml I-131:

<1.6 E-14 vC1/ml I-132:

<1.4 E-14 Ci/ml I-133:

<1.2 E-14 vCi/ml I-135:

<8.2 E-14 Ci/mi co-58:-

<2.0 E-14 vCi/ini Sr-89(1):

<1.0 E-14 pCi/mi Sr-89(2):

<1.5 E-15 vCi/ml Sr-90(1):

<2.0 E-15 Ci/ml Sr-90(2):

<3.0'E-16

. Ci/ml Cs-134:

<1.2 E-14 vci/ml Cs-137:

<1.6 E-14 C1/ml 1

DBNPS Radioactive Effluent Report 12 July - Dec., 1991 l

. _.. _.. _,. _. = _, _. _. _ _. _. - _.... _ _... _ _ _. _ _ _ _

TABLE 4.

CASCOUS ErrLUErfrS - AB!JOR?nL RELEASES 1111RD FOUR111 NUCLIDES UNIT QUARTER QUARTER 1.

rission Gases ci LLD' LLD Total For Period N/A N/A 2.

Iodines Ci LLD LLD Total For Period N/A N/A 3.

Particulates ci 11-3 6.91E401 2.81E+01 Cs-134 LLD 1.66E-01 Cs-137 2.14E-04 5.32E-01 Total For Period:

6.91E401 2.88E+01

These radionuclides were not identified in concentrations-above the lower l

limit of detection (LLD) listed in Table 3.

l l

.DBNPS Radioactive Effluent Report 13-July - Dec., 1991

TABLE 5.

LIQUID ErrLUErfrS - SUMtmTION or ALL RELEASES EST. 'IOrAL

'IllIRD IVURUI PERCE!Tr TYPE UNIT QUARTER QUAR 1TR EPROR A.

rission And Activation Products 1.

Total Release (without Ci 4.18E-02 1.13E-01 1.00E+01 Tritium, Gases, Alpha) 2.

Average Diluted Concen-fiC1/ml 4.29E-09 1.05E-08 tration During Period 3.

Percent of Technical See Supplemental Information, Specifications Limit Section 7 4.

Percent of 10CrR20 Limit t

1.20E-01 2.86E-02 B.

Tritium 1.

Total Release ci 8.01E+01 9.90E+01 1.00E+01 2.

Average Diluted Concen-s/Ci/ml 7.18E-06 9.18E-06 tration During Period 3.

Percent of 10CTR20 Limit t

2.39E-01 3.06E-01 C.

Dissolved and Entrained Gases 1.

Total Release C1 1.29E+00 8.56E-02 1.00E+01 2.

Average Diluted Concen-

//Ci/ml 1.16E-07 7.68E-09 tration During Period 3.

Percent of Limit t

4.83E-02 3.20E-03 D.

Gross Alpha 1.

Total Release Ci LLif 2.17E-05 1.00E+01 E.

Volume of Waste Released liters 1.55E+08 1.28E408 1.00E+01 (prior to dilution) t F.

Volume of Dilution Water liters 1.11c+10 1.08E+10 1.00Es01

'(used during releases) g.

Total Volume of Water liters 1.13E+10 1.09E+10 1.00E+01 Released (Outfall 001)

Based on volume of dilution water used during releases (Item F) b Alpha' activity was not detected above the lower limit of detection, 2.8E-07 tiCi/cc DBNPS Radioactive Effluent Report 14 July - Dec., 1991 upr-y r

f.

v-w c

-9 9

w.--.---mre-g g

m.'y3

-w-, --mngw

-v--

'mBLE 6.

L20UID CrrLUE2&S - IUCLIDES RELEASED

  • C0tRI!UOUS MODE (Ci)

BMCil MODE (Ci)

TilIRD IWRTil Ti!IRD IWRTti 10CLIDES QUARTER QUARTER QUARTER QUARTER 1.

rission and Activation Products Cr-51 Ltd LLD 3.19E-04 8.08E-03 Mn-54 LLD LLD 7.26E-06 3.32E-04 re-55' unavailable LLD(C2)

LLD(B1) 1.61E-02 re-59 LLD LLD 2.01E-05 2.25E-04 Co-57 LLD LLD 2.23E-06 2.55E-06 Co-58 1.09E-03 LLD 3.74E-02 1.70E 02 Co-60 LLD LLD 1.21E-03 2.83E-02 Cu-64 LLD LLD LLD 4.49E-03 Zn-65 LLD LLD LLD LLD Sr-89' unavailable LLD(C2)

LLD(B1) 6.21E-05 Sr-9C*

unavailable LLD(C2)

LLD(B1)

LLD(B2)

Zr-95 LLD LLD LLD 2.64E-03 Zr-97 LLD LLD 2.79E-05 5.53E-05 14>-95 LLD LLD LLD 4.38E-03 Nb-97 LLD LLD 4.49E-06 2.09E-06 Mo-99 LLD LLD LLD LLD Tc-99m LLD LLD 8.65E-06 LLD Ru-103 LLD LLD 3.38E-06 1.37E-03 Ru-106 LLD LLD LLD 1.82E-04 Ag-110m LLD LLD 6.11E-04 3.36E-02 5b-125 LLD LLD 5.86E-05 9.51E-04 Sn-113 LLD LLD 1.03E-05 8.69E-04 Te-132 LLD LLD 1.09E-04 LLD I-131 3.61E-03 LLD 2.57E-04 1.36E-05 I-132 LLD LLD 9.69E-05 LLD I-133 LLD LLD LLD 5.04E-06 Cs-134 LLD LLD 7.54E-04 5.98E Cs-136 LLD LLD 3.55E-05 LLD Cs-137 1.31E-03 7.61E-03 8.92E-04 8.31E-04 Ba-140 LLD LLD 3.59E-06 LLD La-140 LLD LLD 1.41E-06 LLD Ce-141 LLD LLD LLD 1.37E-04 Ce-144 LLD LLD LLD 1.53E-04 Total for period: 6.01E-03 7.61E-03 4.18E-02 1.06E-01 2.

Tritium 1.22F+00 5.72E-01 7.88E+01 9.84E+01 3.

Dissolved and Entrained Gases Kr-85 LLD LLD 3.46E-02 5.05E-02 Kr-85m LLD LLn 1.26E-06 LLD Xe-131m LLD LLD 3.63E-02 9.97E-03 Xe-133 LLD LLD 1.20E+00 2.52E-02 Xe-133m

.LLD LLD-1.44E-02 LLD.

Xe-135' LLD LLD 1.62E-03 LLD Total for Period: tyA tyA 1.29E+00 8.56E-02 l

j; DBNPS Radioactive. Effluent-Report 15 July - Dec., 1991 l

-~

TABLE 6.

LIQUID ErrLULYrS - NUCLIDES RELEASED * (continued)

Abnormal releases not included.

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

Cr-512

<3.3 E-07 vC1/ml Mn-54:

<2.1 E-08 pCi/ml re-55(B1):

<2.0 E-06 pCI Anl re-55(C2):

<1Ji E-06 vCi/ml Fe-59:

<2.4 E-08 vCi/ml Co-57:

<l.J E-08 C1/ml Co-58:

<1.9 E-08 vC1/ml co-60:

<2.0 E-08 vCi/ml Cu-64

<3.5 E-06 vCi/ini Zn-65:

<4.2 E-08 vCi/ml Kr-85:

<4.8 E-06 pCi/ml Kr-85m:

<1.1 E-08 vCi/ml Sr-89(B1):

<3.0 E-08 vCIA.1 Sr-89(B2):

<3.0 E-08 vCi/ml St-89(C2):

<3.0 E-08 vCi/ml Sr-90(B1):

(7.0 E-09 vCi/ml Sr-90(B2):

<9.0 E-09 Ci/ml Sr-90(C2):

16.0 E-09 vCi/ml Zr-95:

<3.1 E-08 vCi/ml Zr-97:

<1.5 E-08 vCi/ml Nb-95:

<1.4 E-08 Ci/ml Nb-97:

<l 7 E-08 vC1/ml Mo-99:

<1.2 E-07 vCi/ml Tc-99m:

<1.2 E-08 Ci/ml Ru-103:

<1.6 E-08 pCi/ml Ru-106:

<1.2 E-07 vC1/ml Ag-110m:

<1.3 E-08 vCi/ml Sn-113:

<1.5 E-08 vCi/ml Sb-125:

<4.2 E-08 pCi/ml Te-132:

<1.2 E-08 vC1/ml I-131:

<1.2 E-Da,::"L/ml I-132.

<1.6 E-08 vCi/ml I-133:

<1.8 E />8 vCi/mi Xe-131m:

<5.1 E-07 Ci/ml Xe-133:

<3.0 E-18 vCi/ml Xe-133m:

<1.1 E-07 vCi/ml

.Xe-135:

<1.4 E-LB Ci/ml Ba-140:

<6.1 E-08 Ci/ml La-140:

<2.1 E-08 vC1/ml Ce-141:

<1.fe E-08 vCi/ml Ce-144:

s9.0 E-08 C1/ml Cs-134:

<1.6 E-08 vC1/ml Cs-136:.

<1.4'E-08 vCi/ml Quarterly composite sample DBNPS Radioactive Effluent Report 16 July - Dec., 1991

'IABLE 7.

LIQUID EFFLUENTS - ABtJORt%L RELEASES' TiiIRD FOURTil NUCLIDES UNIT QUARTER QUARTER

1. Fission and Activation Products N/A N/A
2. Tritiura Ci N/A N/A
3. Dissolved and Entrained Gases N/A N/A There were no abnorrnal liquid releases during the third or fourth IDBNPSRadioactive quarters of 1991.

17 July - Dec., 1991

TABLE 8.

SOLID WASTE AND IRRADIATED FUEL SHIPMD1TS A.

Solid Waste Shipped offsite for Burial or Disposal (not irradiated fuel)

EST. 701'AL PFRCDTT 1.

Type of Waste UNIT QUN1TITY ERROR a.

Spent resins, filtet sludges, m'

6. 20E4 01 evapotator bottoms, etc.

Ci 5.42E+02 2.5E+01 b.

Dry compressible waste, m'

9.60E+01 contaminated equipment, etc.

Ci 1.26E+00 2.5E+01 c.

Irradiated components, control m'

O.00E+ 0 rods, etc.

Ci 0.00E430 N/A d.

Other:

~

1.

Contaminated oil m'

4.47E+00 Ci 2.86E-04 2.5E+01 2.

Estimate of Major Nuclide Composition (by type of waste)

PERCD4T COMPOSITION a.

Fe-55 5.3 Ni-63 12.7 Cs-134 18.6 Cs-137 56.1 b.

Fe-55 20.5 Co-5R 12.6 Co-60 25.9 Cs-134 6.0 Cs-137 16.2 Mn-54 7.7 Cr-51 5.5 Ni-63 5.3 d.

Fe-55 8.3 Co-60 18.0 Ni-63 31.0 Cs-137 41.0 DBNPS Radioactive Effluent Report 18 July - Dec., 1991

iu.

misw=

TABLE 8.

SOLID WASTE AND IRRADIATED FUEL SHIPME!TI'S (continued)

A.

Solid waste shipped Offsite for Burial or Disposal (not irradiated fuel) (continued) 3.

Solid Waste Disposition thimber of Shipments:

6 Mode of Transportation: Truck Destination: Barnwell, SC Type of Container (Container Volume): 30 B25 Boxes (2.7 m'), 1 Resin Liner (5.80 m'), 3 Resin Liners (3.36 m'), 1 Resin Liner (5.1 m')

Solidification Agents: None Number of Shipments:

4 Mode of Transportation: Truck Destination: Oak Ridge, 'IN Type of Container: 6 B25 Boxes (2.7 m') containing 20 55-gallon drums, 6 B25 Boxes (2.7 m'), 7 Resin Liners (5.84 m')

Solidification Agents: None B.

Irradiated ruel Shipments There were no shipments of irradiated fuel.

]

DBNPS Radioactive Effluent Report 19 July - Dec., 1991

3 TABLE 9.

SEtiIANNUAL DOSES DUE TO GASEOUS RELEASES A.

Maxinum Individual Doses Due to I-131,11-3, and Particulates with Italf-lives Greater 'Ihan 8 Days *

1. Whole Body Dose SEC'IOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 SSE 2900 Child 2.13E-03 Quarter 2 W

1050 child 1.37E-03 Semiannual W

1050 Child 2.77E-03 Quacter 3 WSW 2640 child 2.71E-02 Quarter 4 SSE 2900 child 1.34E-03 Semiannual WSW 2640 Child 2.71E-02 1991 Annual WSW 2640 child 2.76E-02

2. Significant Organ Dose SEC'IOR DISTANCE (m) AGE ORGAN DOSE (mrem)

Quarter 1 SSE 2900 Child Thyroid 4.07E-03 Quarter 2 W

1050 child Thyroid 1.40E-01 Semiannual W

1050 Child Thyroid 1.446-01 Quarter 3 WSW 2640 Child Thyroid 4.20E-02 Quarter 4 SSE 2900 child Thyroid 2.91E-03 Semiannual wsw 2640 Child Thyroid 4.22E-02 1991 Annual W

1050 child Thyroid 1.44E-01 B.

Maximum Individual Doses Due to Noble Gas"

1. Whole Body Dose SEC"IOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 NE 900 NA 1.46E-03 Quarter 2 NE 900 NA 9.78E-03 Semiannual NE 900 NA 1.12E-02 Quarter 3 5

1070 NA 8.17E-03 Quarter 4 N

800 NA 1.00E-04 Semiannual S

1070 NA 8.18E-03 1991 Annual NE 900 NA 1.48E-02 Doesfnot include abnormal releases DBNPS Radioactive Effluent Report 20 July - Dec., 1991

Tabic 9.

SEMIANNUAL DOSES DUE 'IO GASEOUS RELEASES (continued)

2. Skin Dose SECTOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 NE 900 tm 4.02E-03 Quarter 2 NE 900 tm 3.67E-02 Semiannual NE 900 la 4.08E-02 Quarter 3 S

1070 im 2.56E-02 Quarter 4 N

800 ta 1.75E-03 Semiannual S

1070 NA 2.56E-02 1991 Annual-NE 900 la 5.10E-02 C.

Population Doses due to I-131,11-3, arx1 Particulates with Half-lives Greater than 8 Days T0frAL INTEGRATED AVERAGE DOSE 'IO POPULATION DOSE INDIVIDUALS IN ORGAN (person rem)

POPULATION (mrem)

Quarter 1 W/ body 1.74E-03 7.80E-07 Quarter 2 W/ body 1.39E-03 6.24E-07 Semiannual W/ body 3.12E-03 1.40E-06 Quarter 3 W/ body 7.48E-03 3.36E Quarter 4 W/ body 1.49E-03 6.69E-07 Semiannual W/ body 8.97E-03 4.03E-06 1991 Annual W/ body 1.21E-02 5.43E-06 LD.

P N ation Doses due to Noble Gas

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

POPULATION (mrem)

Quarter 1 W/ body 1.29E 5.82E-07 Quarter 2 W/ body 1.33E-02 5.97E-06 Semiannual-W/ body-1.46E-02

-6.55E-06 Quarter 3 W/ body

-1.84E-03 8.26E-06 i

Quarter 4 W/ body 8.96E-05 4.03E-08 l

Semiannual _

W/ body 1.85E-02 8.30E-06

-1991 Annual W/ body 3.31E-02 1.49E-05 l

l DBNPS Radioactive Effluent Report 21 July - Dec., 1991

l TABLE 9.

SEMIANNUAL DOSES DUE 70 CASEOUS RELEASES (continued)

E.

Almormal Releases due to Overpressurization of the Auxiliary Steam System

1. Maximum Individual Dose due to I-131, H-3, and Particulates with Half-lives Greater than 8 Days SEC'IOR DISTANCE (m) AGE ORCAN DOSE (mrem)

SSE 2900 Adult W/ body 9.83E-06 SSE 2900 child Liver 1.65E-05

2. Maximum Individual Dose due to Noble Gas
  • SEC'IOR DISTANCE (m) AGE ORGAN DOSE (mrem) im NA tm W/ body 0.00E+00 NA NA NA Skin 0.00E+00

" Noble gases were not detected above the lower level of detectability in samples from the Auxilliary Steam System. Refer to Table 6 for LLD values.

DBNPS Radioactive Effluent Report 22 July - Dec., 1991

TABLE 10. SEMIN@UAL DOSES DUE TO LIQUID RELEASES A.

Maximum Individual Whole Body Dose SECTOR, DISTANCE (mi) AGE DOSE (mrem)

Quarter 1 tM 0.6 Adult 7.88E-03 Quarter 2 iM 0.6 Child 2.73C-03 Semiannual tM 0.6 Adult 1.06E-02 Quarter 3 iM 0.6 Adult 3.) 2-02 Quarter 4 iM 0.6 Adult 2.71E-02 Semiannual IM 0.6 Adult 5.89E-02 1991 Annual IM 0.6 Adult 6.95E-02 B.

Maxinaua Individual Significant organ Dose SEC'IOR DISTN4CE(mi) AGE ORGAN DOSE (mrem)

Quarter 1 IM 0.6 Child Liver 9.84E-03 Quarter 2 tM 0.6 Child Liver 3.35E-03 Semiannual IM 0.6 child Liver 1.32E-02 Quarter 3 FM 0.6 Teen Liver 4.44E-02 Quarter 4 IM 0.6 Teen GI-LLI 9.50E-02 Semiannual tM 0.6 Teen GI-LLI 9.91E-02 1991 Annual IM 0.6 Teen GI-LLI 1.12E-01 C.

Population Dose

'IOTAL INTEGRA'IT.D AVERAGE DOSE 'IO POPULATION DOSE INDIVIDUALS IN ORGAN (person rem)

POPULATION (mrem)

Quarter 1 W/ body 2.57E-01 1.15E-04 Quarter 2 N/ body 2.72E-01 1.22E-04 Semiannual W/ body 5.28E-01 2.37E-04 Quarter 3 W/ body 3.31E-01

1. 49E -04 Quarter 4 W/ body 1.36E+00 6.10E-04 Semiannual W/ body 1.69E+00 7.59E-04 1991 Annual W/txxty 2.22E+00 9.96E-04 DBNPS Radioactive Effluent Report 23 July - Dec., 1991

'IABLE 11.

1991 MWJAL DOSE TO THE MOST-EXPOSED MEMBER OF THE PtSLIC 40 CFR 190 M MIAL DOSE LIMITS PERCENT OF (mrem)

(mrem)

LIMITS Whole Body Dose 4

- Noble Gas 1.48E-02

- Iodine, Tritium, Particulates 2.76E-02

- Liquid 6.95E-02 Total Whole Body Dose 1.12E-01 25 2.44E-01 Thyroid Dose

-Iodine, Tritium, 1.44E-01 75 1.92E-01 Particulates Skin Dose

- Noble Gas 5.10E-02 25 2.04E-01 GI-LLI Do_se

- Liqui 6 1.12E-01 25 4.48E-01 l

DBNPS Radioactive Effluent Report 24 July - Dec., 1991 l

l l

METEOROLOG2 CAL DATA Meteorological data on magnetic tape for July through December 1901 has been submitted with this document to the U.S. Nuclear Regulatory Commission Document contro'. Desk, Washington, D.C. 20555.

s

(.

DBNPS Radioactive Effluent Report 25_

July - Dec., 1991

The Davis-Besse Nuclear Power Station Semiannual Radioactive Effluent and i

Waste Disposal Report July 1 - December 31,1991

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EDISON E+ nv ronmental-i CAVIS-BESSE NUCLEAR POWER stall 0N

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RADI0 ACTIVE EFFLUENT AND VASTE DISPOSAL REPORT Davis-Besse Nuclear Power Station Unit No. 1 July 1, 1991 through Dec. 31, 1991 Docket Number 50-346 License Number NPF-3 s

Toledo Edison _ Company 300 Madison Avenue Toledo, Ohio 43652 March.1992-t

TABLE OF CONTENTS Title Page

~ List of Tables 11

-Summary 1

Supplemental Information 3

Effluent Data Tables 9

-Heteorological Data 25 t

i b

DBNPS Radioactive Effluent Report i-July - Dec., 1991

. ~. ~. -

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-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 20 Releases 10 Semiannual Doses Due to Liquid 23 Releases 11 1991 Annual Dose to the Most-24 Exposed Member of the Public DBNPS Radioactive Effluent Report 11 July - D(

, 1991

SUMMARY

The Radioactive Eftluent and Vaste Disposal Report is a detailed listing of radioactivity released from the Davis-Besse Nuclear Power Station during the period from July 1, 1991 through December 31, 1991.

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 radioactive effluent monitoring instrumentation required by Technical Specifications which was inoperable for 30 days or longer.

Environmental samples were available from the normal collection locations during this reporting period. The locations used for dose calculations and environmental monitoring vere those identified by the 1991 Land Use Census.

Some new sampling or dose assessment locations were identified in this Census, however, the critical receptor remained the same.

During the period of July 1 through December 31, 1991, the maximum individual offsite dose due to radioactivity released in effluents was approximately:

' Liquid Effluents:

5.89E-02 mrem, whole body 9.91E-02 mrem, lover large intestine (GI-LLI)

Gaseous Effluents:

Noble Gas:

8.18E-03 mrem, whole body 2.56E-02 mrem, skin Iodine-131, Tritium, and Particulates with flalf-lives Greater Than 8 Days:

2.71E-02 mrem, whole body-4.22E-02 mrem,-thyroid These doses are only a small fraction of the limits set by the NRC in the Davis-Besse Technical Specifications.

DBNPS-Radioactive Effluent Report 1

July - Dec., 1991

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 pathways include the Turbine Building drains via the settling basins.

Releases which occurred via these pathways are included in the normal release tables in-this report.

Several small gaseous releases associated with overpressurization of the Auxiliary Steam System occurred in the second half of 1991. These releases were quantified and included in the abnormal release sections of this report.

on October 15, 1991, 910 gallons of slightly contaminated water vere discharged-to the onsite Training-Center Pond due to overfilling a steam generator. The discharge contained a total of 81 901 of tritium, cesium-134 and cesium-137. The water discharged to the Training Center Pond has not yet been released from the site. Therefoce, this does not constitute an offsite release and no resulting dose to the public vill be reported for this semiannual period. Vater samples are collected weekly from the Training Center Pond to track activity.

The third quarter composite samples from gaseous ground-level releases and liquid continuous releases were not analyzed due to loss of control of the samples. Therefore, Tables 2 and 6 use the term " unavailable" for the affected radionuclides. Based on past analyses, these radionuclides should not have been detectable in the third quarter samples.

No changes to the Offsite Dose Calculation Manual (0DCM) or the Process Control Program (PCP) occurrtd during this reporting period.

'I L

L DBNPS Radioacti'e' Effluent Report 2

July - Dec., 1991

SUPPLEMENTAL INFORMATION 1.

RF4ULATORY 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 total body.

- 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-li/es 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 eqt_1 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.

D3NPS Radioactive Effluent Report 3

July - Dec., 1991

2.

MAXIMUM PERMISSIBLE CONCFETRATION The maximum periaissible concentrations (MPC) for liquid and gaseous effluents at and beyond the site boundary are listed in 10 CFR 20, Appendix B, Table II, Column 2, with the most restrictive MPC being used in all cases. For dissolved and entrained gases the MPC of 2.0E-04 pCi/ml is applied.

This MPC is based on the Xe-135 MPC in air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP), Publication 2.

3.

AVERAGE ENERGY The Davis-Besse Technical Specifications limit the dose equivalent rates due to the release of fission and activation products to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year tc 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 not applicable.

4.

MEASURENFNTS AND APPROXIMATIONS OF TOTAL ACTIVITY A.

Fission and Activation Cases:

1. These gases, excluding tritium, are collected in a narinelli 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 are 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.

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 made by gamma spectroscopy.

DBNPS Radioactive Effluent Report 4

July - Dec., 1991

5. -BATCH RELEASES A.

Liquid from 7/1/91,a 12/31/91

1. Number of batch releases:

62

2. Total time period for the batch releases: 1.08E+02 hours
3. Maximum time period for a batch release:

2.44E402 minutes

4. Average time period for a batch release:

1.05E+02 minutes

5. Minimum time period for batch releases:

6.30E+01 minutes B.

Gaseous from 7/1/91 to 12/31/91

1. Number of batch releases:

11

2. Total time period for the batch releases: 9.29E401 hours
3. Maximum time period for a batch release:

1.34E+03 minutes

4. Minimum time period for a batch release:

1.80E+02 minutes

5. Average _ time period for batch releases:

5.07E+02 minutes 6.

ABNORMAL RELEASES Several unplanned gaseous releases occurred during this reporting period from lifts of safety valves on the 135-psig and 50-psig Auxiliary Steam System Headers due to system overpressurization. These releases occurred on 8/10/91, 10/08/91, 10/15/91, 10/21/91, 11/08/91, 11/17/91, 11/25/91, and 12/23/91 and produced very small offsite doses. Activity teleased and_ resultant doses are reported in Tables 4 and 9.

DENPS Radioactive Effluent Report 5

July - Dec., 1991 a

I

7.

FERCENT OF TFCHNICAL SPECIFICATIONS LIMITS The following table presents the Technical Specifications dose limits and the associated offsite dose to the public, in percent of limits, for July _through December 1991.

SPECIFICATION LIMIT PERCENT OF LIMITS A. Third Quarter, 1991:

Gaseous Noble gases (gamma) 5.0 mrad 3.02E-01 Noblo gases (beta) 10.0 mrad 4.63E-01 1-131, tri tium, atid 7.5 mrem 7.47E-01 particulates with half-lives greater than 8 days B. Fourth Quarter, 1991:

Gaseous Noble gases (gamma) 5.0 mrad 4.74E-03 Noble gases (beta) 10.0 mrad 9.96E-03 I-131, tritium, and 7.5 mrem 4.82E-02 particulates with half-lives greater than 8 days C. Calendar year, 1991:

Gaseous Noble gases (gamma) 10.0 mrad 1.53E-01 Noble gases (beta) 20.0 mrad 2.36E-01 I-131, tritium, and 15.0 mrem 3.98E-01 particulates with half-lives greater than 8 days D. Third Quarter, 1991:

Liquid Total body 1.5 mrem 1.30E+00 Any organ (liver)

-5.0 mrem-5.02E-01

-E Fourth Quarter, 1991:

Liquid Total body 1.5 mrem 1.26E+00 Any organ (GI-LLI) 5.0 mrem 2.50E+00 F. Calendar year, 1991:

Liquid Total body:

3.0 mrem 1.28E+00 Any organ (GI-LLI) 10.0 mrem 1.30E+00 DBNPS Radioactive Effluent Report 6

July - Dec., 1991

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 Prcduction 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 Hichigan Depnrtment of Agriculture, July, 1981 report entitled, " Michigan Agricultural Statistics, 1981"; the Ohio Crop Reporting Service, 1981 report entitled, "0hio Agricultural Statistics, 1981."

C.

Gaseous ano liquid source terms:

Tables 1 through 7 of '.his 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 Repoct for Davis-Besse.

9.

DOSE TO PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY In accordance with Technical Specification 6.9.1.11, the Semiannual Effluent and Vaste Disposa) Report shall include an assessment of rndiation 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 if the public are permitted access to the radiologically controlled area within the Davis-Besse siation.

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 Technical Specification 6.9.1.11, the following exposure assumptions may be-used:

DBNPS Radioactive Effluent Report 7

July - Dec., 1991

Exposure time for maximum-exposed visitor of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> (4 visits, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per visit is a maximum conservative estimate).

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

The equations in the Offsite Dose Calculation Manual (ODCH) 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 ODCH conservatively estimates the maximum potential dose to members of the public.

10.

INOPERABLE RADIOACTIVE bFFLUF;rf MONITORING EQUIPHFRf No radioactive effluent monitoring equipment required to be operable by Davis-Besse Technical Specifications Sections 3.3.3.9 and 3.3.3.'10 was inoperable for 30 days or longer during this reporting period.

11.

CilANCES TO THE LAND USE CENSUS The following are the results of the 1991 Land Use Census. Changes from the 1990 Land Use Census are denoted with asterisks.

Distance X/0 D/f Sector (meters)

Pathways Age Group (sec/m')

'm-))

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 through SE are located over marsh areas and Lake Erie, no inhalation or ingestion pathways are present.

SSE 2900 vegetation child 6.80E-08 7.90E-10 S

1450 vegetation child 1.21E-07 2.46E-09 SSW

.1560*

-vegetation child 1.03E-07*

2.28E-09*

SW 1050*

vegetation child 2.92E-07*

5.33E-09*

WSW 4270 cow / milk infant 5.71E-08 5.31E-10 W

1720*

vegetation child 2.47E-07*

3.81E-09*

WNW 1750*

vegetation child 1.46E-07*

1.72E-09*

NW 2630*

vegetation child 5.96E-08*

4.50E-10*

ta44 1210 vegetation child 2.70E-07 1.92E-09 l

DBNPS Radioactive Effluent Report 8

July - Dec., 1991

TABLE 1.

GASEOUS EFFLUD4TS - SUMMATION OF ALL RELEASES EST. 'IOTAL THIRD FOURTH PERCD4T TYPE LR4IT CUARTER QUARTER ERROR A.

Fission and Activation Gases 1.

Total Release Ci 7.21E+02 1.22E+01 2.50E+01 2.

Average Release Ci/sec 9.08E+01 1.53E+00 Rate for Period 3.

Percent of See Supplemental Information, Technical Section 7 Specifications Limits B.

Iodines 1.

Total Iodine ci 2.87E-03 2.88E-04 2.50E+01 2.

Average Release pC1/sec 3.61E-04 3.63E-05 Rate for Period 3.

Percent of See Supplemental Information, Technical section 7 Specifications Limits C.

Particulates 1.

Particulates with Ci 5.81E-06 7.57E-06 2.50E+01 half-lives greater than 8 days 2.

Average Release vCi/sec 7.31E-07 9.54E-07 Rate for Period 3.

Percent of-See Supplemental Information, Technical Section 7 Specifications Limits 4.

Gross Alpha Ci --

3.47E-07 3.10E-07 2.50E+01 Activity D.

Tritium l'

Total Release Ci 4.72E+01 5.41E+00 2.50E+01' 2.

Average Release Ci/sec. 5.95E+00 6.83E-01 Rate for Period 3.

Percent of See Supplemental Information, Technical section 7 Specifications Limits DBNPS Radioactive Effluent Report 9

July - Dec., 1991

TABLE 2.

GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

  • CONTINUOUS MODE BATCll MODE 7111RD FOURTli TliIRD FOURTl!

NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER 1.

Fission Gases Ci Ar-41 1.66E-07 LLD" N/A N/A Kr-85 LLD LLD N/A N/A Kr-85m 3.02E-03 LLD N/A N/A Kr-87 2.64E-03 LLD N/A N/A Kr-88 3.39E-03 LLD N/A N/A Xe-133 7.29E-02 LLD N/A N/A Xe-133m 1.98E-03 LLD N/A N/A Xe-135 7.86E-03 LLD N/A N/A Xe-135m 3.71E-03 LLD N/A N/A Xe-138 2.24E-03 LLD N/A N/A Total for Period:

9.77E-02 N/A N/A N/A 2.

Iodines Ci I-131 5.31E-08 LLD N/A N/A I-133 2.55E-07 LLD N/A N/A I-135 LLD LLD N/A N/A Total for Period:

3.08E-07 N/A N/A N/A 3.

Particulates C1 11 - 3 2.55E-02 8.94E-04 N/A N/A Sr-89*

unavailable LLD(2)

N/A N/A Sr-90*

unavailable LLD(2)

N/A N/A Cs-134 LLD 4.llE-08 N/A N/A

Cs-137 2.59E-07 1.15E-07 N/A N/A Total-for Period:

'2.55E-02 8.94E-04 N/A N/A Includes Atmospheric Vent Valve weepage and Auxilliary Feed Ptmp Turbine tests, both are listed as continuous reler.es.

These radionuclides were not identified in concentrations above the

. lower limit of detertion (LLD) listed below:

Ar-41:

<l.4E-08 vCi/ml Xe-135m:

<9.2E-09 pC1/ml Kr-85:

<3.2E-06 C1/ml Xe-138:

<6.9E-08 vCi/ml Kr-85m:

<2.6E-06 Ci/ml I-131:

<1.2E-08 vCi/ml Kr-87:

<1.1E-08 vCi/ml I-133:

<1.8E-08 pCi/ml

~Kr-88:

<2.8E-08 pCi/ml.

1-135:

<8.0E-08 Ci/ml Xe-133:

<3.4E-08 C1/ml Cs-134:

<1.6E-08 Ci/ml Xe-133m:

<6.7E-08 vCi/ml Sr-89(2):

<1.0E vCi/ml Xe-135:

<8.0E-09 vC1/ml Sr-90(2):

<2.0E-09 Ci/ml C

Ouarterly composite sample DBNPS Radioactive Effluent Report 10 July - Dec., 1991

'IABLE 3.

GASEOUS EFFLUENTS - MIXED-MODE RELEASES

  • CCNTINUOUS MODE BATCH MODE THIRD FOURTH THIRD FOUR'H1 NUCLIDES-UNIT QUARTER QUARTER QUARTER QUARTER 1.

Fission Gases Ci Ar LLD' LLD LLD 1.73E-02 Kr-85 LLD LLD 2.82E+01 3.88E+00 Kr-85m LLD LLD LLD 2.99E-04 Kr-87 LLD LLD LLD LLD Kr-88 LLD LLD-LLD LLD Xe-131m LLD LID 4.68E+00 1.67E-01 Xe-133 1.54E+02 6.65E+00 5.24E+02 8.09E-01 Xe-133m LLD LLD 7.72E-01 1.07E-02 Xe-135 1.01E+01 6.15E-01 7.28E-02 7.38E-03 Xe-138 LLD LLD LLD LLD Total for Period:

1.64E+02 7.26E+00 5.58E+02 4.89E+00 2.

Iodines Ci I-131 2.48E-03 1.44E-04 LLD 4.71E-06 I-132 LLD LLD LLD 6.36E-06 I-133 3.94E-04 4.90E-05 LLD 5.35E-05 I-135 LLD

-LLD LLD 3.07E-05

'Ibtal for Period:

2.87E-03 1.93E-04 LLD 9.52E-05

3. : Particulates Ci H-3.

5.39E+00 5.40E+00 4.18E+01 2.32E-02 Co-58 LLD LLD LLD 1.81E-07 Sr-89

.LLD(1)

LLD(2)

_LLD(1)

LLD(2)

Sr-90.

LLD(1)

LLD(2)

LLD(1)

LLD(2)

Cs-134 2.45E-06 LLD LLD 2.85E-06 Cs-137 3.10E-06 LLD LLD 4.54E-06 Total for Period:

5.39E400 -5.40E+00 4.18E+01 2.32E-02 e

i DBNPS Radioactive Effluent Report 11 July - Dec., 1991

U TABLE 3.

CASEOUS EFFLUErfI'S - MIXED-MODE RELEASES (continued)

Abnormal releanes not included 6

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

Ar-41:

<9.1 E-09 pCi/h1 Kr-85:

<2.8 E-06 vCi/ml Kr-85m:

<2.6 E-09 uCi/td Kr-87:

<1.1 E-08 vCi/nd Kr-88:

<2.8 E-08 C1/td Xe-131m:

<3.0 E-07 vCi/hd Xe-133m:

<6.7 E-08 Ci/td Xe-138:

<6.9 E-08 vC1/hd I-131:

<1.6 E-14 Ci/hd I-132:-

<1.4 E-14 Ci/hd I-133:

<1.2 E Ci/hd I-135:

<8.2 E-14 pCi/bl Co-58:

<2.0 E-14 Ci/hd Sr-89(1):

<1.0 E-14 vCi/ml Sr-89(2):

<1.5 E-15 C1/mi Sr-90(1):. <2.0 E-15

. Ci/hd Sr-90(2):

<3.0 E-16 pCi/nd Cs-134:

<1.2 E-14 pCi/ml Cs-137:

<1.6 E-14 Ci/hd DBNPS Radioactive Effluent Report 12 July - Dec., 1991

O TABLE 4.

GASEOUS EFTLUEtTIS - ABNORMAL RELEASES

-THIRD FOURTH NUCLIDES UNIT QUARTER QUARTER 1.

Fission Gases Ci-LLD*

LLD Total For Period N/A N/A 2.

Iodines Ci LLD LLD Total For Period:

N/A N/A 3.

Particulates Ci H-3 6.91E+01 2.81E+01 Cs-134 LLD 1.66E-01 Cs-137 2.14E-04 5.32E-01 Total For Period:

6.91E+01 2.88E+01 0

'These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed.in Table 3.

I DBNPS Radioactive Effluent Report 13 July - Dec., 1991

e w

a.

4 M -

A a

J-a 4:

r-.

2 m

TABLE 5.

LIQUID EFFLUENTS - SUMMAT20N OF ALL RELEASES EST. 'IOTAL THIRD FOURTH PERCENT TYPE UNIT QUARTER QUARTER ERROR A.

Fission And Activation Products 1.

'Ibtal Release (without Ci 4.78E-02 1.13E-01 1.00E+01 Tritium, Gases, Alpha) 2.

Average Diluted Concen-C1/ml 4.29E-09 1.05E-08 tration During Period 3.

Percent of Technical See Supplemental Information, Specifications Limit Section 7 4.

Percent of 10CFR20 Limit 1.20E-01 2.86E-02 B.

Tritium 1.

Total Release ci 8.01E+01 9.90E+01 1.00E+01 2.

Average Diluted Concen-Ci/ml 7.18E-06 9.18E-06 tration During Period 3.

Percent of 10CFR20 Limit 2.39E-01 3.06E-01 C.

Dissolved and Entrained Gases 1.

Total Relenae C1 1.29E+00 8.56E-02 1.00E+01 2.

Average Diluted Concen-Ci/ml 1.16E-07 7.68E-09 tration During Period 3.

Percent of Limit 4.83E-02 3.20E-03 D.

Gross Alpha b

1.

Total Release Ci LLD 2,17E-05 1.00E+01 E.

Volume of Waste Released liters 1.55E+08 1.28E+08 1.00E+01 (prior to dilution)

F.

Volume of Dilution Water liters 1.11E+10

- 1.08E+10 1.00E+01 (used during releases) 9 Total Volume of Water liters 1.13E+10 1.09E+10 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,

-2.8E-07 Ci/cc

'DBNPS Radioactive Effluent Report 14.

July - Dec., 1991

TABLE 6.

LIQUID ErrLUDUS - IUCLIDES RELFJGED*

COtRI!UOUS MODE (C1)

BATCil MODE (Cl)

TilIRD IUJRTil Ti!IRD TOURTil iUCLIDES QUARTER GIARTER OUARTER GIARTER 1.

rission and_ Activation Products Cr-El Ltd LLD 3.19E-04 8.08E-03 Mn-54 LLD LLD 7.2cE-06 3.32E-04 re-55' unavailable LLD(C2)

LLD(B1) 1.61E-02 re-59 LLD LLD 2.01E-05 2.25E-04 Co-57 LLD LLD 2.23E-06 2.55E-06 Co-58 1.09E-03 LLD 3.74E-02 1.70E-02 Co-60 LLD LLD 1.21E-03 2.83E-02 Cu-64 LLD LLD LLD 4.49E-03 Zn-65 LLD LLD LLD LLD S r-89*

unavailable LLD(CE)

LLD(B1) 6.21E-05

$ r-90' unavailable LLD(C2)

LLD(B1)

LLD( D2-)

Zr-95 LLD LLD LLD 2.64E-03 Zr-97 LLD LLD 2.79E-05 5.53E-05 tA>-95 LLD LLD LLD 4.38E-03 IJb-97 LLD LLD s.49E-06 2.09E-06 Mo-99 LLD LLD

'.LD LLD Tc-99m LLD LLD b. 6:i3-06 LLD Ru-103 LLD LLD 3.38E-06 1.37E-03 Ru-106 LLD LLD LLD 1.82E-04 Ag-110m LLD LLD 6.11E-04 3.36E-02 Sb-125 LLD LLD 5.86E-05

').51E-04 Sn-113 LLD LLD 1.03E-05 S.69E-04 Te-132 LLD LLD 1.09E-04 LLD I-131 3.61E-03 LLD 2.57E-04 1.35E-05 I-132 LLD LLD 9.69E-05 LLD I-133 LLD LLD LLD 5.04E-06 Cs-134 LLD LLD 7.54E-04 5.98E-04 Cs-136 LLD LLD 3.55E-05 LLD

-Cs-137 1.31E-03 7.61E-03 8.92E-04 8.31E-04 Ba-140 LLD LLD 3.59E-06 LLD La-140 LLD LLD 1.41E-06 LLD Ce-141 LLD LLD LLD 1.37E-04 Ce-144 LLD LLD LLD 1.53E-04 Total for period:

6.01E-03 7.61E-03 4.18E-C

1.06E-01 2.

Tritium 1.23E+00 5.72E-Ci 7.88E+01 9.84E+01 3.

Dissolved and Entrained Gases Kr-85 LLD LLD 3.46E-02 5.00E-02 Kr-85m LLD LLD 1.26E-06 LLD Xe-131m LLD LLD 3.63E-02 9.97E-03 Xe-133 LLD LLD 1.20E+00 2.52E-02 Xe-133m LLD LLD 1.44E-02 LLD xe-135 LLD LLD 1.62E-03 LLD Total for Period:

N/A 14/A 1.29E+00 8.56E-02 DBNPS Radioactive Effluent Report 15 July - Dec., 1991

TABIZ 6.

LICOID EFFLUINTS - NUCLIDES RELTJGED' (continued)

Abnormal releases not included.

These radionuclides were not identified in concentrations above the lower limit of detection (LLD) 'isted below Cr-51:

<1.3 E-07 pci/ml Mn-54:

<2.1 E-08 uti/ml re-55(B1):

<2.0 E-06 vCi/ml re-55(C2):

<1.0 E-06 vC1/ml re-59:

<2.4 E-08 vCi/ml Co-57:

<1.0 E-08 vC1/ml Co-SB:

<1.9 E-09 vCi/ml Co-60:

<2.0 E-08 vC1/ml Cu-64

<3.5 E-06 vCi/ml In-65:

<4.2 E-08 vC1/ml Kr-85:

<4.8 E-M vC1/ml Fr-85m:

<1.1 E-09 vCi/ml i

Sr-89(B1):

<3.0 E-08 vCi/ir?

Sr-89(B2):

<3.0 E-08 vCi/ml St-89(C2):

<3.0 E-08 vCi/ml Sr-90(B1):

<7.0 E-09 vC1/ml Sr-90(B2):

<9.0 E-09 vCi/mi Sr-90(C2):

<6.0 E-09 vC1/ml Zr-95:

08 vCi/ml Zr-97:

<1.5 E-08 vCi/ml Nb-95:

.-08 vC1/ml Nb-97:

<1.7 E-08 vCi/ml Mo-99:

G.

E-07 vC1/ml Tc-99m

<1.2 E-08 vCi/ml Ru-103:

<1.6 E-08 vCi/ml Ru-10C,

<1.2 E-07 vCi/ml Ag-110m:

<1.3 E-08 Ci/mi Sn-113:

<1.5 E-08 vCi/ml Sb-125 :

<4.2 E-08 pC1/ml Te-132:

<1.2 E-08 vCi/ml 1-131:

<1.2 E-08 vCi/mi I-132:

<1.6 E-08 vCi/mi I-133:

<1.8 E-08 vCi/mi Xe-131m:

<5.1 E-07 vCi/ml Xe-133:

<3.0 E-08 vCi/ml Xe-133m:

<1.1 E-07 vC1/ml Xe-135:

<1.4 E-08 vCi/ml Ba-140:

<6.1 E-08 vCi/ml La-140:

<2.1 E-tB vCi/ml Ce-141:

<1.9 E-08 vCi/ml Ce-144:

<9.0 E-08 vC1/ml Cc-134:

<1.6 E-08 vCi/ml Cc-136:

<1.4 E-08 vCi/ml Quarterly composite cample DBNPS Radioactive Effluent Report 16 July - Dec.,1991

TABLE 7.

LIQUID ErrLUINTS - AB!ORf%L RELEASES *

f. '

T11110 TOUR 111 tJUCLIDES L: NIT GitaTER OLIARTER

1. rission and Activation Prcducts IUA 14/A l
2. Tritium Ci 11/A 11/A
3. Dissolved and Entrained Gases

!J/A N/A i

L hherewerenoabnormalliquidreleasesduringthethirdorfourth quarters of 1991.

DBNPS Radioactive Effluent Report 17 July - Dec., 1991

TABLE 8.

SOLID WASTE AND IRRADIATED TUEL S!!!PMf2RS A.

Solid Waste Shi;Ted Offsite for Burial or Disposal (not irradiated fuel)

EST. 'IUTAL PERCDU 1.

'Iype of Waste th!T QUAfCITY ERROR a.

Spent resins, filter sludges, m'

6.20E+01 i

evaporator bottoms, etc.

Ci

5. 42 E+ 02 2.5E+01 b.

Dry compressible waste, m'

9.60E+01 contaminated equipnent, etc.

C1 1.26E+00

2. 5E+ ')1 I

c.

Irradiated components, control m'

O.00E+00 rods, etc.

C1 0.00E+00 N/A d.

Other 1.

Contaminated Oil m'

4.47t+00 C1 2.86E-04 2.5E+01 2.

Estimate of Major Nuclide Composition (by type of waste) l PERCD4T COMPOSITION a.

re-55 5.3 Ni-63 12.7 Cs-134 10.6 Cs-137 56.1 b.

Pc 20.5 Co-58 12.6 Co-60 25.9 Cs-134 6.0 Cs-137 16.2 Mn-54 7.7 cr-51 5.5 Ni-63 5.3 d.

Fe-55 8.3 Co-60 18.0 N1-63 31.0 -

i Cs-137 41.0 t

I t

DBNPS Radioactive Effluent' Report 18 July - Dec., 1991

....,....--_.w.

TNuz 8.

SOLID WASTE N,'D IRRADIATED FUEL SillPMDirs (continued)

A.

Solid Waste Shipped Offsite for Burial ot Disposal (not irradiated fuel) (continued) 3.

Solid Waste Disposition

! Amber of Shipnents:

6 Mode of Transportation:

Truck Destination:

'3arnwell, SC TypeofContainer(pontainerVolume): 30B25 poxes (2.7m'),

1 Resinpiner(5.80m), 3 Rosin Liners (3.36 m ), 1 Resin Liner (5.1 m )

Solidification Agents: 14one 14 umber of Shipments:

4 Mode of Transportation: Truck Dentination: Oak Ridge,114 Type of Container: 6 B25 Boxes (2.7 m') containing 20 55-gallon drums, 6 B25 Boxes (2.7 m' ), 7 Resin Liners (5.84 m' )

Solidification Agents: None B.

Irradiated ruel Shipments There were no shipments of irradiate 1 fuel.

P 7

DBNPS Radioactive Effluent Report 19 July - Dec., 1991

i TABLE 9.

S!241NJrJUAL DOSES DUE 'Io GASDOUS RELTASES A.

tuxin a Individual Dones Due tes I-131, 11-3, and Particulater, with Italf-lives Greater 'Ihan 8 IMys*

1. Whole Body Dose SEC'IOR DISTANCE (m) AGE DOSE (mrem)

Quarter 1 SSE 2900 Child 2.13E-03 Quarter 2 W

1050 Child 1.37E-03 Semiannual W

1050 Child 2.77E-03 Quarter 3 WSW 2640 Child 2.71E-02 Ouarter 4 SSE 2900 Child 1.34E-03 Semiannual WSW 2640 Child 2.710-02 1991 Annual WSW 2640 Child 2.76E-02

2. Significant organ Dose SEC'IOR DISTA!JCE(m) AGE ORCA!J DOSE (mrem)

Quarter 1 SSE 2900 Child Thyroid 4.07E-03 Quarter 2 W

1050 Child Thyroid 1.40E-01 Semiannual W

1050 Child Thyroid 1.44E-01 Quarter 3 WSW 2640 child Thyroid 4.20E-02 Quarter 4 SSE 2900 child Thyroid 2.91E-03 Semlannual WSW 2640 child Thyroid 4.22E-02 1991 Annual W

1050 Child Thyroid 1.44E-01 B.

tiaximum Individual Doces Due to Noble Cas*

1. Whole Body Dose SEC'IUR DISTNJCE(m) AGE DOSE (mrem)

Quarter 1 NE 900

!m 1.46E-03 Quarter 2 NE 900 tm 9.78E-03 Semiannual NE 900 la 1.12E-02 Quarter 3 S

1070 NA 8.17E-03 Quarter 4 N

800 la

1. 00E- 04 Semiannual 5

1070 NA 8.18E-03 1991 Annual NE 900 tm 1.48E-02 Does not include abnormal releases DBNPS Radioactive Effluent Report 20 July - Dec., 1991 i

l Tablo 9.

SEMINCJUAL DOSES DUE 70 GASEOUS RELEASES (continued) j

2. Skin Dose SECTOR DISTNJCE(m) AGE DOSE (rarem)

Quarter 1 tit 900 tm 4.02E-03 Quarter 2 NE 900 tm 3.67E-02 Semiannual IIE 900 tm 4.00E-02 Quarter 3 S

1070 ta 2.56E-02 Quarter 4 N

880 im 1.75E-03 Semiannual S

1070 tm 2.56E-02 1991 Annual NE 900 ta 5.10E-02 C.

Population Dones due to 1-131,11-3, arxl Particulates with llalf-lives Greater than 6 Days

'IDTAL INTEGPATED AVEPAGE DOSE 70 POPUL*. TION [OSE INDIVIDUALS IN ORGtd4 (Jetson rem)

POPUIATION (mremj Ouarter 1 W/ body 1.74E-03 7.80E-07 Quarter 2 W/ body 1.39E-03 6.24E-07 Semiannual W/ body 3.12E-03 1.40E-06 Quarter 3 W/ body 7.48E-03 3.36E-06 Quarter 4 W body 1.49E-03 6.69E-07

/

Semiannual W/ body 8.97E-03 4.03E-06 1991 Annual W/ body 1.210-02 5.43E-06 D.

Population Doces due to Noble Gas TOTAL INTEGRATED AVEPAGE DOSE '10 POPULATION DOSE INDTVIDUALS IN ORGAN (person rem)

POPULATION (mrem)

Quarter 1 W/ body 1.29E-03 5.82E-07 Quarter 2 W/ body 1.33E-02 5.97E-06 Semiannual W/ body 1.46E-02 6.55E-06 Quarter 3 W/ body 1.84E-03 8.26E-06 Quarter 4 W/ body 8.96E-05 4.03r-08 Semiannual W/ body 1.85E-02 8.30E-06 1991 Annual W/ body 3.31E-02 1.49E-05 DBNPS Radioactive Effluent Report 21 July - Dec., 1991

TABLE 9.

SEMIN M RL DOSTS DUE 'IO GASEOUS RELEASES (continued)

E.

Abnornal Releases due to (Nerpressurization of the Auxiliary Steam System

1. fiaximum Individu.sl Dose due to I-131,11-3, and Particulates with llalf-lives Greater than 8 Days SEC103 DISTNJCE(m) AGE ORGN4 DOSE (mrem)

SSE 2900 Adult W/ body 9.83E-06 SSE 2900 Child Liver 1.65E-05 2 !bximum Individual Dose due to 14cble Gas' SEC70R DISTA!JCE(m) AGE ORGNJ DOSE (mrem) ta la tm WAxxiy 0.00E400 IM im im Skin 0.00E400

  • tioble gases were not detected above the lower level of detectability in samples from the Auxilliary Steam System. Refer to Table 6 for LLD values.

dbl 4PS Radioactive Effluent Report 22 July - Dec., 1991

TABLE 10. SEMINauAL DOSES ICE 10 LIQUID RELEASES A.

tuxinum Individual khole ikxty Done SECTOR DISTNiCE(mi) AGE DOSE (mrem)

Quarter I

!M 0.6 Adult 7.80E-03 Quarter 2

!M 0.6 Child 2.73E-03 Semiannual IM 0.6 Adult 1.06E-02 Quarter 3

!M 0.6 Adult 3.18E-02 Quarter 4

!M 0.6 Adult 2.71E-02 Semiannual IM 0.6 Adult 5.89E-02 1991 Annual tM 0.6 Adult 6.95E-02 D.

twlmum Irrlividual Significent Organ Done SEC'IOR DISTNJCC(mi ) AGE ORGN1 LOSE (mrem)

Quarter 1 IM 0.6 Child Liver 9.84E-03 Quarter 2

!M 0.6 Child Liver 3.35E-03 Semiannual IM 0.6 Child Liver 1.32E-02 Quarter 3 IM 0.6 Teen Liver 4.44E-02 Quarter 4

!M 0.6 Teen GI-LLI 9.50E-02 Semiannual

!M 0.6 Teen GI-LLI 9.91E-02 1991 Annual IM 0.6 Teen GI-LLI 1.12E-01 C.

Population Done

'ICIAL INTEGRATED AVERAGE DOSE TO POPULATION DOSE INDIVIDUALS IN ORGAN Ip rson rem)

POPULATION (mrem)

Quarter 1 W/ body 2.57E-01 1.15E-04 Quarter 2 W/ body 2.72E-01 1.2eE-04 semiannual W/ body 5.28E-01 2.37E-04 Quarter 3 W/ body 3.31E-01 1.49E-04 Quarter 4 W/ body 1.36E+00 6.10E-04 Semiannual W body 1.69E+00 7.59E-04

/

1991 Annual W tody 2.22E+00 9.96E-04 DBNPS Radioactive Effluent Report 23 July - Dec., 1991 s

7AnLE 11, 1991 namAL DOSE 10 'ntE MOST-rJ. POSED MEMBER OF 111E PUBLIC 40 CrR 190 NamAL DOSE LIMITS PERCDir Or (mrem)

(mrem)

LIMITS Whole Dody Do_se

- Noble Gas 1.40E-02

- Iodine, Tritium, Particulates 2.76E-02

- Liquid 6.95E-02 Total Whole Body Dose 1.12E-01 25 2.44E-01

'lhyroid Dose

-Iodine, Tritium, 1.44E-01 75

1. 9'd,-01 Particulates Skin Dose

- Noble Gas 5.10E-02 25 2.04E-01 GI-LLI Dose

- Liquid 1.12E-01 25 4.40E-01 9

DBNPS Radioactive Effluent Report 24 July - Dec., 1991

... -. -... _ -.. - - - - ~ _ - - - -

- - - -.. - _.. =. -. - -.

METDOROLOGICAL DATA Meteorological data on regnetic tape for July through DecemMr 1991 has been submitted with this docament to the U.S. Nuclear Re'f.ilatory connission Document control Desk, Washington, D.C. 20555.

i J

1 1

?

t DBNPS Radioactive Effluent Report 25 July - Dec., 1991

_ _ -. -. _... _ _ _,. _,.,. _ _ _....-_.. _._. _.2._

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