ML20082M698

Semiannual Radioactive Effluent & Waste Disposal Rept.

ML20082M698
Person / Time
Site:	Davis Besse
Issue date:	06/30/1991
From:	Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
DSR-91-00492, DSR-91-492, NUDOCS 9109050333
Download: ML20082M698 (36)

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~ August 28,--1991-DSR-91--00492 Docket Number: 'iG-346 License Number: NPF-3 United States Nuclear Regulatory Commission Document Control Desk.

Vashington, D. C. 20555 .

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Subject:

. January 1 - June 30, 1991 Semiannual Effluent and Vaste Disposal Report-

~ Gentlement Enclosed are two copies of the January 1 - June 30, 1991 Semiannual Effluent ,

and Waste Disposal Panort for the. Davis-Besse Nuclear Power Station. -!

Gaseosa and liquid radioactivity released remained well within the limits of the Operating License Appendix A Technical Specifications. Changes were made E during this reporting period.to the Offsite Dose Calculation Manual and the Process Control Prograin to incorporate .the Radiological Ef fluent Technical Specifier.tiens (RETS) procedural details pursuant to the guidance of NRC Generic

-Letter 89-01 (, Implementation of Programcatic Controls for Radiological Effluent Technical Specifications.and the Relocation of Procedural Detalis of RETS t' the Offsite Dose Calculation Manual or the-Process Control Program). The RETS vill

'be. removed from-the Technical Specifications following approval of the License Amendment Application pending with the NRC. Should you have any questions please contact R. V. Schrauder, Manager'- Nuclear. Licensing, at (419) 249-2366.

Very truly'yours, JJ

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L. F.-Stor 1 Plant Manage .;

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Enclosure

-cc P. M. Byron, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, DB-1 NRC Senior Project Manager #j Utility Radiological Safety Board -

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DSR-91-00492 Page 2 For Information Only cc D.~ V. Briden (3185)

R. L. Dielman (3360)

B. L. Ceddes '(4060)

G. A. Gibbs (3387)

J. P. Greer E. Hammet M. E. Miles (3030)

Nuclear Records Management (3220)

R. Owen J. R. Polyak (1029)

R. V. Schrauder (3065)

D. C. Shelton (3080)

D. Sherman R. Stevenson

The Davis-Besse Nuclear Power Station Semiannual Radioactive Effluent and Waste Disposal Report January 1 - June 30,1991

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EDISON ki- RadioloS i cal IEnv i ronmental- DMS-MSSE NlY1 EAR KMER STAIKN l

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'l SEHIANNUAL EFFLUENT AND VASTE DISPOSAL REPORT Davis-Besse Nuclear Power Station Unit No. 1 January 1,-1991-through June 30, 1991 l

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1 Docket Number 50-346  !

License Number NPP-3 Toledo 8dison Company 300 Madison Avenue Toledo, Ohio 43652 August 1991 i

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4 TABLE OF CONTENTS l

Title Page 11 List of Tables 1

Summary Supplemental Information 3 14 Effluent Data Tables Meteorological Data 30 DBNPS Semiannual Effluent Report i Jcn. - June, 1991 l

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LIST OF TABLES-

. Table Number Title M 1 -Gaseous Effluents - Summation of 14  ;

All Releases 2 Gaseous Effluents - Ground Level Releases 15 3 Gaseous Effluents - Mixed Mode Releases 16 4 Gaseous Effluents - Abnormal Releases. 18 5 Liquid Effluents - Summation of 19 l All Releases )

l 6 Liquid Ef fluents - Nuclides Released 20 7 Liquid Effluents - Abnormal Releases 22 )

I 8 Solid Vaste and Irradiated Fuel 23 Shipments 9 Semiannual Doses Due to Gaseous 25 Releases 10 Semiannual Doses Due to Liquid 28 Releases 11 1990 Semiannual Dose to the Host- 29 Exposed Member of the Public DBNPS Semiannual Effluent Report 11 Jan. - June, 1991

SUMHARY l

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. 1991 through June 30, 1991.

T!.is report provides the following information:

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

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

- A listing of all radioactive effluent monitoring instrumentation required by Technical Specifications, but which was inoperable for more than 30 days.

Environmental samples vere available from the normal collection locations during this reporting period. The locations used for dose calculations and environmental monitoring vere those identified by the 1990 Land Use Census. No new sampling or dose assessment locations were identified in this Census.

During the petiod of January 1 through June 30, 1991, the maximum individual offsite dose due to radioactivity released in efflucnts was approximately:

Liquid Effluents:

- 1.06E-02 mrem, whole body

- 1.32E-02 mrem, liver Gaseous Effluents:

Noble Gas:

- 1.12E-02 mrem, whole body

- 4.08E-02 mrom, skin Iodine-131, Tritium, and Particulates with Half-lives Greater Than 8 Days

- 2.77E-03 mrem, whole body

- 1.44E-01 mrem, thyroid These doses are only a small fraction of the limits set by the NRC in the Davis-Besse Technical Specifications.

DBNPS Semiannual Effluent Report 1 Jan. - June, 1991

Prior to the 1990 outaga, a small primary-to-secondary leak existed in ons of the two steam generators. As a result, there exist several cdditional normal release pathways. For gaseous effluents, these pathways include the auxiliary feed pump turbine exhaust, tLe 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 p:thvays are included in the normal release tables in this report. In previous submittals, the total activity in these gaseous releases was included in the " Gaseous Effluents - Mixed-Hode Releases" table. Since these releases are calculated using a ground-level release model, the activity is nov being reported in a " Gaseous Effluents - Ground-Level heleases" table.

The gaseous release associated with the unplanned lift of the safety valves on the 235-psig Auxiliary Steam System Header on 3/6/91, and the unplanned release which occurred during testing of the containment crergency air lock door interlock on 5/2/91 vere both quantified and included in the abnormal release sections of this report.

In the Semiannual Report for June - Dec., 1990, a revised value for the station vent sampling efficiency was used on an interim bas.'s. This interim ef ficiency value of 0.72 has been specifically reevaluated and found appropriate. As a result, the calculations of the previous aubmittals need not be revised.

Analyses of the composite sample for continuous liquid releases from the fourth quarter of 1990 vere received and show no detectable Sr-89, Sr-90, or Fe-55 in the sample.

Changes to the Offsite Dose Calculation Manual (ODCM) and the Process Control Program (PCP) occurred during this reporting period. Section 11 of the supplemental Information contains an explanation of these changes.

DBNPS Semiannual Effluent Report 2 Jan. - June, 1991

SUPPLEMErfrAL INFORMATION

1. REGULATORY LIMITS A. Gaseous Effluents

1. In accordance with 10CFR20, Appendix B, Table II, dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following

a. Noble gases - Less than or equal to 500 mrem / year to the 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 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 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 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 or equal to 3 mrem to the total body and less than I

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

i DBNPS Semiannual Effluent Report 3 Jcn. - June, 1991 i

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2. MAXIMUM PERHISSIBLE CONCENTRATION i 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, 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 HPC 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 k 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 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 Radioactivc Materials in Liquid and Caseous Effluents from Light-Vater-Cooled Nuclear Power Plants," is not applicable.

4, hEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY A. Fission and Activation Gases:

1. These gases, excluding tritium, are ecllected in a marinelli beaker specially modified for gas sampling, steel bombs, or glass vials and are counted on a germar.ium 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.

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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 Semiannual Effluent Report 4 Jan. - June, 1991

5. BATCH RELEASES A. Liquid from 1/1/91 to 6/30/91

1. Number of batch releases: 42

2. Total time period for the batch releases: 6.60E+01 hours

3. Maximum time period for a batch release 1.82E+02 minutes

4. Average time period for a batch release: 9.43E+01 minutes

5. Minimum time period for batch releases: 6.60E+01 minutes B. Gaseous from 1/1/91 to 6/30/91

1. Number of batch releases: 6

2. Total time period for the batch releases: 6.77E+01 hours

3. Maximum time period for a batch release: 1.42E+03 minutes

4. Minimum time period for a batch release: 9.00E+00 minutes

5. Average time period for batch releases: 6.77E+02 minutes

6. ABNORMAL RELEASES An abnormal gaseous release occurred on 3/6/91 due to lift of safety s valves on the 235-psig Auxiliary Steam System lleader.

Another abnormal gaseous release occurred on 5/2/91 during the performance of DB-SP-03292, Semiannual Containment Emergency Air Lock Door Interlock Test.

Both releases produced very small offsite doses. Activity released and _

resultant doses are reported in Tables 4 and 9.

DBNPS Semiannual Effluent Report 5 Jan. - June, 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 January through June 1991.

SPECIFICATION LIMIT FERCENT OF LIMITS A. First Quarter, 1991: Gaseous $$

Noble gases (gamma)

• 5.0 mrad 4.22E-02 Noble gases (beta) 10.0 mrad 5.95E-02 I-131, tritium, and 7.5 mrem 3.28E-03 particulates with half-lives greater than 8 days B. Second Quarter, 1991: Caseous Noble gases (gamma) 5.0 mrad 1.32E-01 Noble gases (beta) 10.0 mrad 1.97E-01 I-131, tritium, and 7.5 mrem 6.08E-02 particulates with half-lives greater than 8 days C. Calendar year, 1991: Gaseous Noble gases (gamma) 10.6 mrad 8.69E-02 Noble gases (beta) 20.0 mrad 1.28E-01 1-131, tritium, and 15.0 mrem 3.20E-02 particulates with half-lives greater than 8 days D. First Quarter, 1991: Liquid Total body 1.5 mrem 5.25E-01 -

Any organ (liver) 5.0 mrem 1.97E-01 E. Second Quarter, 1991: Liquid Total body 1.5 mrem 1.82E-01 Any organ (liver) 5.0 mrem 6.70E-02 F. Calendar year, 1991: Liquid Total body: 3.0 mrem 3.53E-01 Any organ (liver) 10.0 mrem 1.32E-01 DBNPS Semiannual Effluent Report 6 Jan. - June, 1991 l

. 8. DOSE ASSESSMENT Sources of input data include:

A. Vater Usage: Aspendix 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, Agrieditural, Heat - Animal, and Milk Production Data Tables for 1982." This evaluation was based on the 1980 census; the Agricultural Ministry of Ontario 1980 report entitled, " Agricultural Statistics and Livestock Marketing Account, 1980"; the Agricultural Ministry of Ontario 1980 report entitled, " Agricultural Statistics for Ontario -

1980 Publication 21, 1980"; the Michigan Department of Agriculture, July, 1981 report entitled, " Michigan Agricultural Statistics, 1981") the Ohio Crop Reporting Service, 1981 report entitled, " Ohio Agricultural Statistics, 1981."

C. Gaseous and liquid source terms: Tables 1 through 7 of this report.

D. Location of the nearest individuals and pathways by sector out to 5 miles: Report entitled, "1990 Land Use Census," included in the 1993 Annual Environmental Operating Report 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 Disposal Report shall include an assessment of radiation doses from radioactivity released in liquid and gaceous 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 within the Davis-resse 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.

Considerin; the frequency and duration of the visits, the resultant dose would 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 Semiannual Effluent Report 7 Jan. - June, 1991

- Exposure time for maximum-exposed vis' tor 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 (ODCM) may be used for calculating the potential dose to a member of the public for activities inside the site boundary. Based on these assumptions, this dose vould be at least a factor of 400 less than the maximum site boundary air dose as calculated in the ODCM, There are no areas onsite accessible to the public where exposure to liquid effluents could occur. Therefore, the modeling of the ODCM conservatively estimates the maximum potential dose to members of the public.

10. INOPERABLE RADI0 ACTIVE EFFLUFXT MONITOllING EQUIPMENT The following radioactive effluent monitoring equipment, required to be operable by Davis-Besse Technical Specifications (TS) Sections 3.3.3.9 and 3.3.3.10, was iaoperable for more than 30 days during this reporting period.

- Total Dilution Flow Computer Point F-201 was declared inoperable on March 3, 1990 due to failure of flov transmitter FT-3611. It was declared operable on March 28,1991. The system could not be readily isolated while the plant was running, and Systems Engineering had to devise a method for doing so.

- The Vaste Gas Storage Tank (VGST) H2/02 monitor, AE5984 was declared inopera'.le on October 2, 1990 due to failure of a sensing element. It vas declared operable in May 1991.

Contributing to the down time were vendor problems with providing certified parts, and excess moisture in the system which required a plant modification to install coalescing filters.

11. CIIANGES TO THE ODCM AND PCP This section contains summaries of all previous revisions to the ODCH and PCP because the revious report submittals did not contain all the necessary informt u na.

ODCM Revision 1 Rationale: Tritium was included in the Tb 3.11.2.1.b requirements. Sections vere added on projecting personnel dose from gaseous effluents, on how TS relate to 40 CFR 190, and on how to perform calculations which demonstrate compliance to 40 CFR 190. A section was added indicating which TS dose vill be used to report the doses specified by Regulatory Guide 1.21 in the Semiannual Effluent and Vaste Disposal Report.

DBNPS Semiannua) Effluent Report 8 Jan. - June, 1991

Justification: These changes do not effect set point calculations,.because set points are not discussed in TS 3.11.2.1.b nor in 40_CFR 190. These changes do not decrease the accuracy and reliability of dose calculations.

CDCM Revision 2 Rationale Critical receptors were changed based on Land Use Census results.

Justification: This change does not affect set point calculations, as receptor data are not part of the  !

calculations. This change increases the accuracy and i reliability of dose calculations by accounting for changes in the critical receptors for each sector around the site.

ODCM Revision 3 l Rationale: The sections on liquid and gaseous releases were rewritten to clarify the concepts and makr aquations easier-to understand. The methodology of the equations themselves did not change.

Justification: This change greatly improved the readability and understandability of the ODCM and therefore did not j decrease the accuracy and reliability of set point or dose l calculations. I ODCM Revision 3.1 Rationales Critical receptors were changtd based on Land Use Census results. Table references were corrected. An erroneous equation for calculating Lover Limit of Petection (LLD) vas corrected.

Justification: This change does not affect set point calculations. Updating critical receptors increases the accuracy and reliability of dose calculations by accounting for changes in receptor locations. Correction of the table reference and of the erroneous equation for LLD increases the accuracy and reliability of dose calculations by insuring proper calculation of doses and proper reporting levels for radionuclides analyzed in effluent samples.

e ODCH Revision 4 Rationale: Changes were made to add the procedureal details of current Radiological Effluent Technical Specifications (RETS) to the ODCM or PCP pursuant to the guidance of NRC Generic Letter 89-01.

Justification: This change moves the RETS requirements from one document to another. This change does not adversely affect the accuracy or reliability of set point or offsite dose calculations because the requirements were not altered.

DBNPS Semiannual Effluent Report 9 Jan. - June, 1991

i SRB review and approval is documented by the signature of the SRB Chairman on the ODCM cover sheet. A copy of the ODCH cover sheet is included at the end of this section.

PCP Revision 1 Rationale A section vas added concerning exothermic reactions which may occur during spent resin solidification.

Justification: Since solidification is not done at Davis-Besse, this has no effect on overall conformance with existing criteria for radvaste devatering or solidification.

PCP Revision 2 Rationale: A section was added which specifies the frequency for verifying solidification or devatering of vet radioactive vaste, and actions to take should a radioactive vaste test not verify devatering or solidification criteria.

Justification: These changes concern testing whether radioactive vaste is properly devatered or solidified and follov-up actions They do not negatively affect conformance with existing criteria for radvaste devatering or solidification.

PCP Revision 3 Rationale A section was added stating that all radvaste processing is performed in accordance with the principles of ALARA. A description of Miscellaneous Vaste Monitor Tank (MVHT) influent processing was added. A diagram depicting the spent resin processing system was added.

Justification: The performance of radioactive vaste devatering or solidification in accordance with the principles of ALARA enhances worker safety. The addition of the description of the MVMT influent processing diagram depicting resin processing clarifies this process. None of these changes negatively affect overall conformance to existing criteria for radvaste devater ng or solidification.

DBNPS Semiannual Effluent Report 10 Jan. - June, 1991

PCP Revision 4 Rationales Definitions vere added for PCP, Devntering, and Solidification. A statement was added that shipments of radvaste vill be suspended if the PCP is not followed.

10 CFR 20,311 vas added to the manifest reporting requirements.

Reference to " vet decontamination mop heads" vss deleted from the examples of liquid vaste that are prohibited from inclusion in solid radvaste. The specific label, "RADI0 ACTIVE - LSA" vas deleted from the section stating that shipping containers are to be properly labeled. A section was added stating that the PCP may be modified as provided in TS 6.14. TS 6.16 vas added verbatim to comply with NRC Generic Letter 89-01.

Justification: Addition of definitions serves to clarify the Process Control Program. Suspension of shipments if the PCF is not followed strengthens adherence to the PCP. Addition o'f 10 CFR 20.311 to manifest reporting requirements further ensures control in accordance with applicable laws. Deletion of " vet decontamination mop heads" eliminates unnecessary examples. Deletion of "RADI0 ACTIVE - LSA" deletes the implied restriction that all radioactive vaste that is shipped is classified as LSA. Stating how the PCP may be modified further controls the PCP process. Addition of TS 6.16 clarifies reporting requirements for changes made to solid radvaste treatment systems. None of these changes negatively affect conformance to existing criteria for radvaste devatering er solidification.

SRB review and approval is documented by the signature of the SRB Chairman on the PCP cover sheet. A copy of the PCP covet sheet is included at the end of this section.

DBNPS Semiannual Effluent Report 11 Jan. - June, 1991

THE TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION OFF5ITE 0056 CALCULATIONS MANUAL P

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TABLE 1. GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES EST. TOTAL FIRST SECOND PERCENT TYPE UNIT OUARTER QUARTER ERROR A. Fission and Activation Gases

1. Total Release Ci 9.54E+01 3.27E+02 2.50E+01

2. Average Release uCi/see 1.23E+01 4.16E+01 Rate for Period

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

1. Total Iodine Ci 3.38E-04 8.31E-03 2.50E+01

2. Average Release uCi/sec 4.35E-05 1.06E-03 Rate for Period

3. Percent of  % See Supplemental Informationi Technical Section 7 Specifications Limits C. Parliculates

1. Particulates with C1 1.60E-06 4.16E-05 2.50E+01 half-lives greater than 8 days

2. Average Release pCi/see 2.065-07 5.29E-06 Rate for Period -

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

4. Gross Alpha Ci 3.17E-07 1.21E-07 2.50E+01 Activity D. Tritium

1. Total Release Ci 7.91E+00 4.12E+00 2.50E+01

2. Average Release pCi/see 1.02E+00 5.23E-01 Rate for Period

3. Percent of  % See Supplemental Information, Technical Section 7 Specifications Limits DBNPS Semiannual Efflueat Report 14 Jan. - June, 1991 l

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, TABLE 2. GASE0US EFFLUENTS - GROUND LEVEL RELEASES

• C0tfrINUOUS MODE BA'ICH MODE FIRST SECOND FIRST SECOND NUCLIDES UNIT CUARTER- QUARTER- QUARTER QUARTER

1. Fission Gases Ci Ar-41 1.43E-07 1.53E-07 N/A N/A Kr-85 LLD' LLD N/A N/A Kr-85m 3.02E-03 6.65E-03 WA N/A Kr-87 2.52E-03 6.12E-03 WA N/A Kr-88 4.55E-03 8.92E-03 N/A N/A Xe-133 8.97E-02 1.36E-01 N/A N/A Xe-133m 2.11E-03 4.38E-03 N/A N/A Xe-135 2.35E-02 5.33E-02 N/A N/A l Xe-135m 3.53E-03 8.00E-03 N/A N/A Xe-138 1.79E-03 5.01E-03 N/A N/A Total for Period: 1.31E-01 2.28E-01 N/A N/A

-2. Iodines Ci I-131 5.56E-08 3.26E-08 N/A N/A l I-133 8.67E-08 1.46E-07 N/A N/A i 1-135 LLD LLD N/A N/A Total for Period: 1.42E-07 1.78E-07 N/A N/A

3. Particulates Ci H-3 8.38E-03 1.29E-02 N/A N/A S r-89* N/A LLD WA N/A St-90* N/A LLD N/A N/A Cs-134 1.58E-08 LLD N/A N/A Cs-137 1.58E-06 6.78E-08 N/A N/A Total for Period: 8.38E-03 1.29E-02 N/A N/A Includes only Atmospheric Vent Valve weepage and Auxilliary Feed Pump Turbine tests, both are listed as continuous releases. All batch releases are mixed-mode.

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

Kr-85: <3.2E-06 vCi/ml Sr-89: <4.0E-10 pCi/ml Sr-90: <8,0E-11 Ci/ml Cs-134: <1.6E-08 vCi/ml I-135: <8.0E-08 C1/ml A composite sample for analysis of strontiums was only available for the second quarter.

DBNPS Semiannual Effluent Report 15 Jan. - June, 1991

TABLE 3. GASEOUS EFFLUDTrS - MIXED MODE RELEASES

• CONTINUOUS MODE BATCH NODE FIRST SECOND FIRST SEC0tO NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER

1. Fission Gases Ci Ar-41 lid LLD N/A' 6.63E-02 Kr-85 LLD LLD N/A 1.05E+01 Kr-85m LLD LLD N/A 5.20E-02 Kr-87 LLD LLD N/A 6.11E-03 Kr-88 LLD LLD N/A 3.50E-02 Xe-131m LLD LLD N/A 2.89E+00 Xe-133 9.36E+01 2.01E+02 N/A 1.05E+02 Xe-133m LLD LLD N/A 1.09E+00 Xe-135 1.76E+00 4.88E+00 N/A 9.86E-01 Xe-135m LLD LLD N/A 8.03E-04 Total for Period: 9.53E+01 2.06E+02 N/A 1.21E+02

2. Iodines Ci I-131 2.66E-04 1.37E-03 N/A 4.3BE-03 I-132 LLD LLD N/A 1.38E-04 I-133 7.18E-05 5.53E-04 N/A 1.43E-03 I-135 LLD LLD N/A 4.51E-04 Total for Period: 3.38E-04 1.92E-03 N/A 6.39E-03

3. Particulates Ci H-3 7.90E+00 3.93E+00 N/A 1. 7~ '-01 Co-58 LLD LLD N/A 6.94 t:-07 Co-60 LLD LLD N/A 1.26E-06 Sr-89 LLD(1) LLD(2) N/A LLD(2)

St-90 LLD(1) LLD(2) N/A LLD(2)

Ru-103 LLD LLD N/A 7.33E-07 Cs-134 LLD LLD N/A 1.81E-05 Cs-137 LLD 4.26E-07 N/A 2.03E-05 Total for Period: 7.90E+00 3.93E+00 N/A 1.75E-01 DBNPS Semiannual Effluent Report 16 Jan. - June, 1991 l

l

TABLE 3. GASEOUS EFFLUENTS - HIXED MODE RELEASES * (continued) t Abnormal releases not included

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

Continuous Release LLDs Batch Release LLDs Ar-41: <9.1 E-09 C1/ml Sr-89(2): <1.4 E-15 Ci/ml Kr-85: <2.8 E-06 C1/ml Sr-90(2): <2.9 E-16 Ci/ml Kr-85m: <2.6 E-09 vCi/ml Kr-87: <1.1 E-08 Ci/ml Kr-88: <2.8 E-08 pCi/ml Ru-103: <'.5 E-09 vCi/ml Xe-131m: <3.0 E-07 Ci/ml Xe-133m: <6.7 E-08 vCi/ml Xe-135m: <9.2 E-09 C1/ml Xe-138: <6.9 E-08 pCi/ml I-131: <l.6 E-14 Ci/ml I-132: <1.4-E-14 pCi/ml I-133: <1.2 E-14 Ci/ml I-135: <8.2 E-14 pC1/ml Co-58: <2.0 E-14 Ci/ml Co-60: <1.6 E-14 pC1/ml Sr-89(1): <1.2 E-15 vCi/ml Sr-89(2): <1.4 E-15 uCi/ml St-90(1): <1.5 E-16 Ci/ml Sr-90(2): <2.9 E-16 vCi/mi Cs-134: <1.2 E-14 vCi/ml Cs-137: <1.6 E-14 Ci/ml

• There were no batch releases during the first quarter of 1991.

DBNPS Semiannual Effluent Report 17 Jan. - June, 1991

TABIE 4. GASEOUS EFFLUEtTIS - ABtORMAL RELEASES i

FIRST SEOD NUCLIDES UNIT QUARTER QUARTER

1. Fission Gases Ci Ar-41 1.34E-08 LLD*

Kr-85m 1.45E-04 LLD Kr-87 1.35E-04 LLD Kr-89 2.30E-04 LLD xe-133 4.18E-03 7.37E-05 xe-133m 9.82E-05 LLD xe-135 1.14E-03 7.27E-07 xe-135m 2.23E-04 LLD xe-138 1.35E-04 LLD Total For Period: 6.29E-03 7.44E-05

2. Iodines Ci I-131 LLD 3.44E-11 I-133 LLD 1.03E-11 Total For Period: N/A 4.47E-11

3. Particulates Ci H-3 1.87E-07 9.38E-08 cs-137 4.62E-09 LLD Total For Period: 1.92E-07 9.38E-08 "These radionuclides were not identified in concentrations above the lower limit of detection (LLD) listed in Table 3.

DBNPS Semiannual Effluent Report 18 Jan. - June, 1991

{

I

. TABLE-5. LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES {

EST. TOTAL FIRST SECOND PERCENT  :

TYPE UNIT OUARTER QUARTER ERROR I'.

A. Fission And Activation Products -;

i

1. Total Release (without C1 2.03E-03 6.03E-03 1.00E+01  :

Tritium, Gases, Alpha) l i

2. Average Diluted Concen-

• pC1/ml 2.97E-10 5.18E-10  :

tration During Period I

3. Percent of Technical  % See Supplemental Information, i specifications Limit Section 7 l

4. Percent of 10CFR20 Limit  % 3.94E-03 1.86E-03  ;

t i

B. Tritium  ;

1. Total Release Ci 9.39E+01 5.26E+01 1.00E+01 )

2. Average Diluted concen- C1/ml 1.38E-05 4.52E-06 -

tration During Period i

3. Percent of 10CFR20 Limit t 4.59E-01 1.51E-01 ,

C. Dissolved and Entrained Gases h

1. Total Release Ci 7.91E-02 1.28E-01 1.00E+01 [

2. Average Diluted concen-

• vCi/ml 1.16E-08 1.11E-03 i tration During Period 7 l

3. Percent of Limit  % 5.80E-03 5.53E-03  :

I f

D. Gross Alpha

1. Total Release C1 2.56E-05 5.73E-05 1.00E+01 3 i

i E. Volume of Waste Released liters 1.10E+08 1.05E+08 1.00E+01 (prior to dilution)

F. Volure of Dilution Water liters 6.82E+09 3.05E+09 1.00E+01  ;

(used during releases) L i

g. Total Volune of Water liters 7.03E+09 3.15E+09 1.00E+01 j Released (Outfall 001)

• Based on volume of dilution water used during releases (Item F) [,

[

DBNPS Semiannual Effluent Report 19 Jan. - June, 1991 f

TABLE 6. LIQUID EFFLUENTS - NUCL7 DES RELEASED ,

l CCNTINUOUS PODE (Ci) BATCH FODE (Ci)

FIRST SECCND FIRST SECOto NUCLIDES QUARTER QUARTER CUARTER QUARTER

1. Fission and Activation Products Cr-51 Ltd LLD 9.65E-06 LLD Mn-54 LLD LLD LLD 4.67 -05 Fe-55* LLD(C1) LLD(C2) LLD(B1) 2.2 E-06 Fe-59 LLD LLD LLD LLD Co-57 LLD LLD 6.30E-06 LLD Co-58 LLD LID 6.47E-05 3.43E-04 Co-60 LLD LLD 3.09E-04 4.58E-03 Zn-65 LLD LLD LLD LLD St-89* LLD(C1) LLD(C2) LLD(B1) LLD(B2)

Sr-90* LLD(C1) LLD(C2) LLD(B1) LLD(B2)

Zr-95 LLD LLD LLD 2.58E-05 Nb-97 LLD LLD 4.49E-06 2-09E-06 Mo-99 LLD LLD LLD LLD Tc-99m LLD LLD LLD LLD Ag-110m LLD LLD 4.15E-05 5.66E-04 Sb-125 LLD LLD 1.13E-03 3.01E-04 Sn-113 LLD LLD 6.62E-07 1.96E-05 I-131 LLD LLD 6.60E-05 9.79E-06 I-133 LLD LLD LLD LLD Cs-134 LLD LLD 1.55E-04 1.88E-05 Cs-136 LLD LLD 1.60E-06 LLD Cs-137 LLD LLD 2.40E-04 5.23E-05 Ce-141 LLD LLD LLD LLD Ce-144 _LLD LLD LLD LLD Total for period: N/A N/A 2.03E-03 6.03E-03

2. Tritium 1.50E+00 7.89E-01 9.24E+01 5.18E+01

3. Dissolved and Entrained Gases Kr-85 LLD LLD 6.18E-03 4.88E-03 Xe-131m LLD LLD 4.66E-03 4.30E-03 Xe-133 LLD LLD 6.82E-02 1.10E- 01 Xe-133m LLD LLD 1.70E-05 2.87E-04 Xe-135 LLD LLD 6.74E-06 3.49E-05 Total for Period: N/A N/A 7.91E-02 1.28E-01 r

DENPS Semiannual Effluent Report 20 Jan. - June, 1991

s

'mBLE 6. LIQUID EFFLUDRS - NUCLIDES RELEASED * (continued) 1 Abnormal releases not included.

t

• These radionuclides were not identified in concentrations above the '

lower limit of detection (LLD) listed below:

Cr-51: <1.3 E-07 pCi/ml Mn-54: <2.1 E-08 vci/ml re-55(B1): <9.0 E P uCi/ml Fe-55(C1): <1.0 E-06 pCi/ml re-55(C2):' <1.0 E-M .Ci/ml Fe-59: <2.4 E-08 pCi/ml

<1.9 E-08 Ci/ml Co-57: <1.0 E-08 Ci/ml Co-58:

Co-60: <2.0 E-08 C1/ml zn-65: <4.2 E-08 pCi/ml  ;

Kr-85: <4.8 E-06 pCi/ml Sr-89(B1): <4.0 E-08 Ci/ml St-89(B2): <3.0 E-08 pCi/ml Sr-89(C1): <2.0 E-08 C1/ml  ;

Sr-89(C2): <4.0 E-08 pCi/ml Sr-90(B1): <5.0 E-09 Ci/ml ,

Sr-90(B2): <5.0 E-09 Ci/ml Sr-90(C1): <6.0 E-09 vCi/ml  !

Sr-90(C2): <1.0 E-08 Ci/ml Zr-95: <3.1 E-08 pCi/ml Nb-97: <1.7 E-08 pCi/ml Mo-99: <1.2 E-07 pCi/ml ,

Tc-99m: <1.2 E-08 Ci/ml Ag-110m: <1.3 E-08 C1/ml Sn-113: <1.5 E-08 pCi/ml Sb-125: <4.2 E-08 Ci/ml .

I-131: <1.2 E-08 pCi/ml I-133: <1.8 E-08 pCi/ml [

Xe-131m: <5.1 E-07 vCi/ml Xe-133: <3.0 E-08 Ci/ml  !

Xe-133m: <1.1 E-07 pCi/ml Xe-135: <1.4 E-08 pC1/ml  :

Ce-141: <1.9 E-08 Ci/ml Ce-144: <S.O E-08 vCi/ml l' Cs-134: <1.6 E-08 Ci/ml Cs-136: <1.4 E-08 Ci/ml Cs-137 <2.0 E-08 Ci/ml  ;

P Quarterly composite sample  ;

r p

I l

[

F h

L L

t DBNPS Semiannual Effluent Report 21 Jan. - June, 1991 ,

'IABLE 7. LIQUID EFFLUDfrS - ABtORMAL RELEASES

• FIRST SECOND NUCLIDES tNIT QUARTER QUARTER

1. Fission and Activation Products N/A N/A

2. Tritium Ci N/A N/A

3. Dissolved and Entrained Gases N/A N/A

'Ihere were no abnormal liquid releases during the first or second quarters of 1991.

DBNPS Semiannual Effluent Report 22 Jan. - June, 1991

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TABLE 8. SOLID UASTE AND 1RRADIATED FUEL SHIPMENTS f ,

A. Solid W ste Shipped Offsite for Burial or Disposal (r.ot irradiated fuel)

EST. TOTAL PERCENT

1. Type of Vaste UNIT 00ANTITY ERROR

a. Spent resins, filter sludges, m' 7.55E+01 evaporator bottoms, etc.* Ci 3.17E+00 2.5E401

b. Dry compressible waste, m' O.00E+00 contaminated equipent, etc, ci 0.00E+00 2.5E401

c. Irradiated components, control m' O.00r.+00 rods, etc. Ci 0.00E+00 2.5E401

d. Other:

1. Dewatered Primary m' 3.00E-01 System Cartridge rilters Ci 9.60E-01 2.5E+01

2. Estimte cf Major Nuclide Composition (by type of waste)

PERCDTI' ABUNDANCE

a. re-55 15 Co-60 19 N1-63 15 Cs-134 11 Cs-137 22

o. re-55 26 Co-58 16 Co-60 37

• T6 shipments of contaminated Powdex resin and one shipment of contaminated waste o a were sent to Scientific Ecology Group'for effect've volume reduction. Total volume shipped was 51.1 m . As of the end of this reporting period, none of the eterial has been buried.

l DBNPS Semiannual Effluent Report 23 Jan. - June, 1991 i

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

TABLI D. SOLID WASTE AND IRRADIATTD NEL SilIPMDTTS (continued) ,

A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) (continued)

3. Solid Waste Disposition Number of Shipoents: 2 Mode of Transportation: Truck Destination: Barnwell, SC TypeofContainer(Coptainervolume): 4 Resin Liners (5.83 m'),

1 Resin Liner (5.76 m )

Solidification Agents: None

.xmber of Shipnents: 3 Mode of Transportation: Truck Destination: ')ak Ridge, 'IN Type of, Container: 6 B25 Boxes (2.55 m : containing 23 55-gallon drums Solidification Agents: None B. Irradiated ruel Shipments

'Itere were no shipments o' irradiated fuel.

I i

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DBNPS Semiannual Effluent Report 24 Jan. - June, 1991 i

-w m p.-

• r-e-.i..-- -w-y.-- v- ---=r* r -- -

TABLE 9. SEMIAN!1UAL DOSES DUE TO GASEOUS RELEASES i A. Maximum Individual Doses Due to 1-131, 11-3, and Particulates with 11alf-lives Greater Than 8 Days'

1. Whole Body Dose SECIOR DISTRICE(m) AGE DOSE (mrem)

Ouarter 1 SSE 2900 Child 2.13E-03 Quarter 2 W 1050 Child 1.37E-03 Semiannual W 1050 Child 2.77E-03

2. Significant organ Doie SECIOR DISTNJCE(m) AGE ORGAN DOSE (mrem)

Quarter i SSE 2900 child '!hyroid 4.07E-03 Quarter 2 W 1050 Child 'Ihyroid 1.40E-01 Femiannual W 1050 Child Byroid 1.44E-01 B. Maximum Individual Doses fue to tbble Gas *

1. Whole Body Dose SECIOR DISTNJCE(m) AGE DOSElmrem)

Quarter i NE 900 la 1.46E-03 Quarter 2 !E 900 la 9.78E-03 Semiannual NE 900 NA 1.12E-02

2. Skin Dose SECIOR DISTM4CE(m) AGE DOSE (mrem)

Quarter 1 tE 900 ta 4.02E-03 Quarter 2 NE 900 la 3.67E-02 Semiannual tE 900 ta 4.08E-02 DBNPS Semiannual Effluent Report 25 Jan. - June, 1991

Tabla 9. SEMIAraAIAL tosES DUE 'IO GASEOUS RELEASES (continued)

C. Ig ulation Doses due to 1-131, 11-3, and Farticulates with Italf-lives Greater than 8 Days'

'IUIAL IITTEGRATED A"ERAGE DOSE 'IO POPULATIQ1 DOSE INDIVIDUALS 114 ORGAN (person rem) POPULATIQ1 (mrem)

Quarter 1 W/ body 1.74E-03 7.00E-07 Quarter 2 W/ body 1.39E-03 6.24E-07 S:miannual W/ body 3.12E-03 1.40E-06 D. W ation Doses due to Noble Gas *

'IUIAL INTEGRATED AVERAGE ICSE 'IO POPULATION COSE INDIVIDULLS IN ORGAN (person rem) POPULATI N (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 Does not include abnormal releases.

DnNPS Semiannual Effluent Report 26 Jan. - June, 1991

y

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TABLE 9. SEMI ANNUAL DOSES DUE TO GASEOUS RELEASES (continued) [

E. Abnormal Release due to over-pressuriention of the 235-psig :b Auxiliary Steam System Ileader on 3/6/91

1. Maximum Individual Dose due to 1-131, 11-3, and Particulates with llalf-lives Greater than 8 Days SECTOR DISTANCE (m) AGE ORGAN DOSE (prem)

N 800 Adult V/ body 4.05E-Oi N 880 child Bone 3.17E-07

2. Maximum Individual Dose due to Noble Gas SECTOR DISTANCE (m) AGE _ ORGAN __, DOSE (mrem)

N 880 NA V/ body 2.25E-02 N 880 NA Skin 4.12E-02 P. Abnormal Release from Containment Emergency Air Lock on 5/2/91

1. Maximum Individual Dose due to 1-131, 11-3, and Particulates vith flalf-lives Greater than 8 Days SECTOR DISTANCE (m) AGE ORGAN DOSE (mrem)

NE 900 Teen V/ body 3.25E-11 NE 900 Child Thyroid 1.62E-09

2. Maximum Individual Dose due to Noble Gas SECTOR DISTANCE (m) AGE ORGAN DOSE (mrem)

NE 990 NA V/ body 6.32E-09 NE 990 NA r '. 4 n 1.49E-08 DBNPS Semiannual Effluent Report 27 Jan. - June. 1991

s

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TABLE 10. SEMIANNUAL DOSES DUE TO LIQUID RELEASES A. Maximum Individual Whole Body Dose SECTOR DISTANCE (mi) AGE DOSE (mrem)

Quarter 1 IN 0.6 Adult 7.88E-03 Quarter 2 IN 0.6 Child 2.73E-03 S:aiannual IN 0.6 Adult 1.06E-02 B. Maximum Individual Significant organ Dose SECTOR DISTANCE (mi) AGE ORGAN DOSE (mrem)

Quarter 1 IN 0.6 Ci11d Liver 9.84E-03 Quarter 2 IN 0.6 Child Liver 3.35E-03 S:miannual NV 0.6 Child Liver 1.32E-02 C. Population Dose TOTAL INTEGRATED AVERAGE DOSE TO POPULATION DOSE INDIVIDUALS IN ORGAN (person rem) POPULATION (mrem)

Quarter i V/ body 2.57E-01 1.15E-04 Quarter 2 V/ body 2.72E-01 1.22E-04 S:miannual V/ body 5.28E-01 2.37E-04 DBNPS Semiannual Effluent Report 28 Jan. - June, 1991

l TABLP 11. 1991 SI:H1 ANNUAL DOSE TO Tile HOST-EXPOSED HEMIIER OF Tile PUBLIC 40 CFR 190 SEM1 ANNUAL DOSE LIMITS PERCENT OF (mrem) (mrem) LIMITS Vhole Body Dose

- Noble Gas 1.12E-02

- Iodine, Tritium, Particulates 2.77E-03

- Liquid 1.06E-02 Total Vhole Body Dose 2.46E-02 25 9.83E-02 Thyroid Dose

-lodine, Tritium, 1.44E-01 75 1.9?F J1 Particulates Skin Dose

- Noble Gas 4.08E-02 25 1.63E-01 Liver Dose

- Liquid 1.32E-02 25 5.28E-02 i

DBNPS Semiannut.1 Effluent Report 29 Jan. - June, 1991

METEOROLOGICAL DATA Mateorological data on magnetic tape for January through June 1991 has be:n submitted with this document to the U.S. Nuclear Regulatory C:: mission Document control Desk, Vashington, D.C. 20555.

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l DBNPS Semiannual Effluent Report 30 Jan. - June, 1991

__ - _ - -- .. ._ _