Text

Ei Hatch Unit 1 & 2 Annual Rept of Plant Radioactive Effluent Releases for 1998. with
	ML20206E045
Person / Time
Site:	Hatch
Issue date:	12/31/1998
From:	Sumner H; SOUTHERN NUCLEAR OPERATING CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HL-5780, NUDOCS 9905040317
	Download: ML20206E045 (105)
	v • d • e

Lawls Sumner Southern Nuclear l~ * '

Vice. President' Operating Canpany,Inc.

ilatch Project Support 40 Invemess Parkway Post Office Box 1295

(

Birmingham, Alabama 35201 Tel 205.992.7U9 fax 205.992.0341 SOUTHERN h*

COMPANY Energy to Serve YourWorld" April 28, 1999 Docket Nos. 50-321 HL-5780 50-366 U.S. Nuclear Regulatory Commission ATrN: Document Control Desk l' Washington, D.C 20555 Edwin I. Hatch Nuclear Plant Annual Radioactive Emuent Release Report Ladies and Gentlemen:

In accordance with the provisions of Plant Hatch Technical Specifications, Southern Nuclear Operating Company is providing the Plant Hatch Units I and 2 Annual Radioactive Effluent Release Report. This report covers the period of January 1,1998 through December 31,1998.

Should you have any questions in this regard, please contact this office.

Respectfully submitted,

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ewio i1. L. Sumner, Jr.

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Enclosure:

Annual Radioactive Effluent Release Report cc: (See next page.)

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U. S. Nuclear Regulatory Commission Page 2 April 28, 1999

'cc: Southern Nuclear Oocratina Company Mr. P. H. Wells, Nuclear Plant General Manager SNC Document Management (R-Type A02.001)

U.S. Nuclear Reaulatory Commission. Washington. D.C.

Mr. L. N. Olshan, Project Manager - Hatch U.S. Nuclear Regulatory Commission. Reaion II Mr. L. A. Reyes, Regional Administrator Mr. J. T. Munday, Senior Resident Inspector - Hatch State of Geornia J. L. Setser, Department of Natural Resources 1

American Nuclear Insurers l Mr. R. A. Oliveira 1

HL-5780

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT l UNITS NO.1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1,1998 THROUGH DECEMBER 31,1998 SECTION TITLE PAGE {

1.0 Liquid Effluents - 1 1.1 Regulatory Limits / Technical Specifications 1 1.1.1 Concentration Limits l 1

1.1.2 Dose Limits 1 O 1.2 Effluent Concentration Limit 1 1.3 Measurements and Approximations of Total 2 Radioactivity 1.4 Liquid Effluent Release Data 4 1.5 Radiological impact on Man Due to Liquid Release 5 1.6 Abnormal Releases 5 1.7 Batch Releases 5 2.0 Gaseous Effluents 32 2.1 ODCM Specifications 32 2.1.1 Dose Rate Limit 32 2.1.2 Air Dose Due to Noble Gas 32 2.1.3 Dose to Any Organ 32 i

i O SECTION TITLE PAGE 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 33 2.2 Release Points of Gaseous Effluents 33 2.3 Total Quantitles of Radioactivity, Dose Rates 34 and Cumulative Doses 2.3.1 Fiss!on and Activation Gas 34 2.3.2 Radlolodine, Tritium and Particulate Releases 34 2.3.3 Gross Alpha Release 35 2.4 Gaseous Effluent Release Data 36 2.4.1 Methodology 36 2.5 Radiological Impact Due to Gaseous Releases 38 2.6 Abnormal Releases 38 3.0 Solid Waste 66 3.1 Regulatory Limits / Technical Specifications 66 3.1.1 Solid Radioactive Waste System 66 3.1.2 Reporting Requirements 66 3.1.3 Process Control Program (PCP) 66 3.2 Solid Waste Data 67 4.0 Changes to the Plant Hatch ODCM 72 5.0 Doses to Members of the Pubilc inside The 72 Site Boundary 6.0 Major Changes to the Liquid, Gaseous and 81 O

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Solid Radwaste Treatment Systems SECTION TITLE PAGE 7.0 Meteorological Data 81 8.0 Inoperable Liquid or Gaseous Effluent 81 Monitoring Instrumentation

- 9.0 Tanks Exceeding Curie Content Limits 83 O

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SOUTHERN COMPANY E. L HATCH NUCLEAR PLANT UNITS NO.1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-1 A Liquid Effluents - Summation of All Releases 6 Unit 1 (Quarters 1,2,3 and 4) '

1-1 B Liquid Effluents - Summation of All Releases 8 Unit 2 (Quarters 1,2,2 and 4)

' 1-1 C Liquid Effluents - Summation of All Releases 10 Site (Quarters 1,2,3 and 4) 0 1-2A Liquid Effluents - Unit 1 (Quarters 1,2,3 and 4) 12 1-2B Liquid Effluents - Unit 2 (Quarters 1,2,3 and 4) 15 i 1-2C Liquid Effluents - Site (Quarters 1,2,3 and 4) 19 1-3A Doses to a Member of The Public Due to Liquid 23 Releases Unit 1 (Quarters 1,2,3 and 4) 1-3B Doses to a Member of The Public Due to Liquid 25 Releases Unit 2 (Quarters 1,2,3 and 4) 1-4A Liquid Effluents - Batch Release Summary 27 Unit 1 1-4B Liquid Effluents - Batch Release Summary 29 Unit 2 1-5 Minimum Detectable Concentration - 31 Liquid Sample Analysis O

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TABLE LIST OF TABLES PAGE 21A ' Gaseous Effluents - Summation of All 39 Releases Unit 1 (Quarters 1,2,3 and 4) 2-1 B Gaseous Effluents - Summation of All 41 '

Releases -Unit 2 (Quarters 1, 2, 3 and 4) 2-1 C Gaseous Effluents - Summation of All 43 Releases - Site (Quarters 1,2,3 and 4) 2-2A Gaseous Effluents - Elevated Releases 45 Unit 1 (Quarters 1,2,3 and 4) 2-2B Gaseous Effluents - Elevated Releases 47 Unit 2 (Quarters 1,2,3 and 4) i 2-2C Gaseous Effluents - Elevated Releases 49 I Site (Quarters 1,2,3 and 4) 2-3A Gaseous Effluents - Ground Level Release 51 Unit 1 (Quarters 1,2,3 and 4) i 2-3B Gaseous Effluents - Ground Level Release 53 Unit 2 (Quarters 1,2,3 and 4) 2-3C Gaseous Effluents - Ground Level Release 55 Site (Quarters 1,2,3 and 4) i 2-4A Air Doses Due to Gaseous Releases - 57 I Unit 1 (Quarters 1,2,3 and 4) 2-4B Air Doses Due to Gaseous Releases- 59 i Unit 2 (Quarters 1,2,3 and 4) l 2-5A Doses to a Member of the Public Due to 61 !

Radiolodine, Tritium, and Particulates in Gaseous Releases - Unit 1 (Quarters 1,2,3 and 4) 2-5B Doses to a Member of the Public Due to 63 Radiolodine, Tritium, and Particulates in ;

Gaseous Releases - Unit 2 (Quarters 1, 2, 3 and 4) 2-7 Minimum Detectable Concentration - 65 Gaseous Sample Analyses V

TABLE LIST OF TABLES PAGE 3-1 A,B Solid Waste and irradiated Fuel Shipments 68,70 4-1 Dose to A Member of the Public Due to Activities 73 !

Inside The Site Boundary I

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1.0 Liquid Effluents 1.1 Regulatory Limits / Technical Specifications 1.1.1 Concentration Limits The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table ll, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-4 microcuries/ml total activity.

1.1.2 Dose Limits The dose or dose commitment, to a MEMBER OF THE PUBLIC from l radioactive materials in liquid effluents released from each unit to I UNRESTRICTED AREAS, shall be limited:

a. During any calendar quarter, to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year, to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

1.2 Effluent Concentration Limit (ECL)

ECL values used in determining allowable liquid radwaste release rates and concentrations, for principal gamma emitters,1-131, tritium, Sr-89, Sr-90 and Fe-55, are taken from 10 CFR Part 20, Appendix B, Table ll, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table ll, Column 2.

For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 uCl/mi total activity.

For gross alpha in liquid radwaste, the ECL is 2.0E-09 uCi/ml.

Furthermore, for all the above radionuclides, or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.

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p The method utilizing the ECL fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.

1.3 Measurements and Approximations of Total Radioactivity Prior to the release of any tank containing liquid radwaste, following the required recirculations, samples are collected and analyzed in accordance with the Edwin I. Hatch Nuclear Plant Offsite Dose Calculation Manual (ODCM) Table 2-3. A sample from each tank planned for release is analyzed for principal gamma emitters,1 131, and dissolved and entrained noble gases, by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks released. Liquid radwaste sample analyses are performed as follows:

MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.

2. Dissolved or entrained Each Batch Gamma Spectroscopy n noble gases with computerized data reduction

3. Tritium Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

5. Sr-89 & Sr 90 Quarterly Chemical separation Composite and gas flow proportionalor scintillation counting

6. Fe-55 Quarterly Chemicalseparation Composite and liquid scintillation counting O

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Gamma Isotopic measurements are performed in-house using germanium O detectors with a resolution of 2.0 kev or lower. The detectors are shielded by four inches of lead. A liquid radwaste sample is typically counted for 3000 seconds and a peak search of the resulting gamma ray spectrum is performed. ;

Energy and net count data for all significant peaks are determined and a '

quantitative reduction or MDC calculation is performed to ensure that the MDC's are met for the nuclides specified in the ODCM Ch 10 (i.e., Mn-54, Fe-59, l Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present.

The maximum error associated with volume and flow measurements, based upon plant calibration practice, is estimated to be + or - 10%. The average error associated with counting is estimated to be less than + or - 15%. i Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.

The radionuclide concentrations determined by gamma spectroscopic analysis of samples taken from tanks planned for release, in addition to the most current sample analysis results available for tritium, gross alpha, Sr-89, O Sr-90 and Fe-55, are used along with the corresponding ECL values to determine the ECL fraction for these tanks. This ECL fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the ODCM are not exceeded.

i A monitor reading in excess of the calculated setpoint will result in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.

Radionucikte concentrations, safety factors, dilution stream flow rate, and the liquid effluent radiation monitor calibration factor, are entered into the computer and a pre-release printout is generated. If the release is not permissible, appropriate warnings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Foreman on duty. The pertinent information is transferred manually from the prerelease printout to a one-page release permit, which is forwarded to Radwaste Operations. When the release is completed, the release permit is retumed from Radwaste Operations to Chemistry with the actual release 3

data provided. These data are input into the computer and a post-release printout O is generated. The post release printout contains the actual release rates, the actual release concentrations and quantitiec, the actual dilution flow, and the calculated doses to an individual.

1.4 Liquid Effluent Release Data Regulatory Guide 1.21, Tables 2A and 2B are found in this report as Table 1-1 A, for Unit 1, Table 1-18, for Unit 2 and Table I-10, for the site; and Table 1-P.A, for Unit 1,1-28, for Unit 2, and Table 120, for the site. Typical liquid minimum detectable concentrations (MDC's) used for analyses are found in Table 1-5.

The evaluation for the release of Unit One RHR Service Water from 1996:

Release of Contaminated Water can be found in Appendix A of this report.

The values for the four categories of Tables 1-1 A, and 1-1 B, and 1-1C, are calculated and the Tables completed as follows:

1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of tho sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective quarter.

2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period.

3. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy using a one liter sample from each liquid radwaste batch. The measured concentrations are used to calculate the total release and the average diluted concentration during the period. Radioisotopes of iodine in any form are also determined during the isotopic analysis for each batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not provide additional information.

4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity.

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l 1.5 Radiological impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated l In accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-3A for Unit 1, and 1-3B for Unit 2, for all four quarters.

1.6 Abnormal Releases There were no abnormal liquid releases for this reporting period.

1.7 Batch Releases I Batch Release information for Units 1 and 2 is summarized in the following tables:

Unit 1 Liquid Batch Releases: Table 1-4A l Unit 2 Liquid Batch Releases: Table 1-4B l

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TABLE 1-1A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Sununation of All Releases Unit: 1 i h Starting : 1-Jan-1998 Ending : 30-Jun-1998

' d l TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.81E-02 1.12E-02 4.70E+01.

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uC1/ML 4.03E-08 2.10E-08

3. PERCENT OF APPLICABLE LIMIT % *

B. TRITIUM

1. TOTAL RELEASE CURIES 2.04E+00 1.98E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.53E-06 3.72E-06

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3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 3.47E-03 2.17E-03 1.00E+02 i

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2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.72E-09 4.08E-09

3. PERCENT OF' APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE' CURIES 1.43E-06 2.55E-07

......................................................................... 20E+02 1 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 2.16E+06 2.43E+06 F. VOLUME OF DILUTION WATER USED LITERS 00E+01 1

4.49E+08 5.32E+08

......................................................................... 60E+02 1

Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report, i

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l TABLE 1 1A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I Liquid Effluents - Summation of All Releases

,O Unit: 1 ,

Starting 1.Jul-1998 Ending : 31-Dec-1998 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR % ,

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................................................................................ l A. FISSION si ACTIVATION PRODUCTS I 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 2.93E.02 2.00E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.09E-08 4.50E-08

3. PERCENT OF APPLICABLE LIMIT % *

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................................................................................ 1 B. TRITIUM

1. 'IOTAL RELEASE CURIES 3.45E+00 2.34E+00 3.70E+31

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2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.82E-06 5.26E-06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 4.462 03 1.63E-03 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.22E.09 3.67E-09

3. PERCENT OF APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.07E-06 4.35E.06 1.20E+

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E. WASTE VOL RELEASED (PRE. DILUTION) LITERS 3.17E+06 1.93E+06 1.00E+

F. VOLUME OF DILUTION WATER USED LITERS 7.17E+08 01..

4.45E+08

....................................................................... 1.60E+02 ........

Applicable limits are expressed in terms of dose. See Tables 1 3A and 1-3B of this report, k

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TABLE 1-1B E. I. NATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Sunnation of All Releases j

O Starting 1.Jan.1998 Unit: 2 Ending : 30-Jun-1998 a ,

TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

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1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 5.67E-03 5.13E-03 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.89E-08 1.59E-08

3. PERCENT OF APPLICABLE LIMIT t *

B. TRITIUM

1. TOTAL RELEASE CURIES 1.41E+00 1.82E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.69E-06 5.62E-06

3. PERCENT OF APPLICABLE LIMIT t *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 5.42E-04 6.14E-04 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.81E-09 1.90E-09

3. PERCENT OF APPLICABLE LIMIT t *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 5.478-08 5.48E-07 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 1.28E+06 1.37E+06 1.00E+

F. VOLUME OF DILUTION WATER USED LITERS 01 ..

3.00E+08 3.23E+08

.......................................................................... 0E+02 1.6

. Applicable limits are expressed in terms of dose. See Tables 1-3A and.1 3B of this report.

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TABLE l-1B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents . Summation of All Releases Unit: 2

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1 Starting : 1-Jul-1998 Ending 31-Dec-1998 s.

TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 2.49E-02 3.90E-02 4.70B+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.86E-08 6.90E-08

3. PERCENT OF APPLICABLE LIMIT % *

M B. TRITIUM

1. TOTAL RELEASE CURIES 3.05E+00 3.22E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.95E-06 5.69E-06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES m 1. TOTAL RELEASE CURIES 3.64E-04 5.55E-04 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.09E-10 9.80E-10

3. PERCENT OF APPLICABLE LIMIT % *

1 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 9.21E-07 1.68E-06 1.20B+02 ,

................................................................................ i E. WASTE VOL RELEASED (PRE. DILUTION) LITERS 2.775+06 2.75E+06 1.00E+

F. VOLUME OF DILUTION MATER USED LITERS 5.14E+08 01 ..

5.66E+08

............................................................................E+02 1.60 Applicable limits are expressed in terms of dose. See Tables !

1-3A and 1-3B of this report. l t

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TABLE 1-1C E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Sunnation of All Releases Unit Site O Starting : 1-Jan 1998 Ending : 30-Jun-1998'

. V TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 2.38E-02 1.63E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.17E-08 1.91E-08

3. PERCENT OF APPLICABLE LIMIT % * * '

B. TRITIUM

1. TOTAL RELEASE CURIES 3.44E+00 3.79E+00 3.70E+01

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2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.59E.06 4.44E-06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE O CURIES 4.01E-03 2.79E-03 1.00E+02

\ 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.35E-09 3.26E-09

3. PERCENT OF APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 1.49E-06 8.03E-07 1.20B+02 E. WASTE VOL RELEASED (PRE DILUTION) LITERS 3.45E+06 3.80E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 7.49E+08 8.55E+08

......................................................................... 60E+021 Applicable limits are expressed in terms of dose. See Tables 1 3A and 1-3B of this report.

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1 TABLE 1-1C E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Summation of All Releases Unit: Site Starting : 1 Jul.1998 Ending : 31.Dec.1998 v

TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION 8 ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 5.43E-02 5.91E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.41E-08 5.84E-08

3. PERCENT OF APPLICABLE LIMIT % *

B. TRITIUM

1. TOTAL RELEASE CURIES 6.51E+00 5.56E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.29E.06 5.50E-06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 4.82E-03 2.19E-03 1.00B+

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2. AVERAGE DILUTED CONCENTRATION 02 DURING PERIOD uCi/ML 3.92E.09 2.16E.09

3. PERCENT OF APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOAC*.IIVITY

1. TOTAL RELEASE CURIES 6.03E-

................................................................. 06 2.995 06 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 5.95E+06 4.68E+

F. VOLUME OF DILUTION WATER USED LITERS 06 1.00E+01 1.23E+09

.............................................................. 1E+09 1.0 1.60E+02 Applicable limits are expressed in terms of dose. See Tables 1-3A and 1 3B of this report.

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j TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

' Liquid Effluents Unit: 1

('"\ Starting : 1-Jan-1998 Ending : 30-Jun.1998 ix_,)

l CONTINUOUS MODE ** BATCH

..........................................................l......................l NUCLIDE l UNIT MODE l QUARTER 1 l QUARTER 2 l QUARTER 1 2

.....................................................................lQ.UARTER ..........

l H.3

.......................................................,..l...........l...........l CURIES l 0.00E+00 l 0.00E+00 l 2.04E+00 1.98E+00 FISSION & ACTIVATION PRODUCTS CO-58 CURIES 0.00E+00 0.00E+00 CO.60 1.66E-04 2.30E-05 CURIES 0.00E+00 0.00E+00 8.41E-03 4.21E-03 CR-51 CURIES 0.00E+00 0.00E+00 CS.134 5.33E-05 0.00E+00 CURIES 0.00E+00 0.00E+00 7.74E-05 1.03E-04 CS-137 CURIES 0.00E+00 0.00E+00 1.21E-03 FE-55 2.01E 03 CURIES 0.00E+00 0.00E+00 1.36E-03 4.22E-04 I-131 CURIES 0.00E+00 0.00E+00 I-133 3.97E-04 2.60B.04 CURIES 0.00E+00 0.00B+00 7.46E 04 5.49E-04 MN-54 CURIES 0.00E+00 0.00E+00 NA.24 1.89E-03 1.11E-03 CURIES 0.00E+00 0.00E+00 3.93B 06 3.39E-05 NB 97 CURIES 0.00E+00 0.00E+00 SR.89 3.34E 06 0.00E+00 CURIES 0.00E+00 0.00E+00 1.48E-04 7.01E 05 SR-90 CURIES 0.00E+00 0.00E+00 ZN-65 1.79E.07 4.83E-13 CURIES 0.00E+00 0.00E+00 3.62E-03 2

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TOTALS CURIES 38E-03 ........

l l 0.00E+00 l 0.00E+00 1.81E 02

\,,)

..........................................................l...........l.. 1 12E-02 l l

l DISSOLVED AND ENTRAINED GASES KR 85 CURIES 0.00E+00 0.00E+00 XE-133 6.93E-04 0.00E+00 CURIES 0.00E+00 0.00E+00 7.43E-04 5.82E.04 XE 135 CURIES 0.00E+00 0.00E+00 XE 135M 1.76E-03 1.59E.03 '

CURIES 0.00E+00 0.00E+00 2.72E-04 TOTALS CURIES 0.00E+00 ..........

l l 0.00E+00 0.00B+00 3.47E-

...............................................l...........l......03............... l 2.17E-03 l G-ALPHA l CURIES l 0.00E+00 0.00E+00

...............................................l...........l.....E-06 1.43 l 2.55E-07 l Zeroes at in thislevels.

detectable table indicate that no radioactivity was present See Table 1-5 for typical minimwm j detectable concentrations. '

There are no continuous mode radioactive liquid release pathways at Plant Match.

l l l

(~' \

h

\

N.

12

TABLE 1-2A*

E. I. EATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUElfr RELEASE REPORT Liquid Effluents Unit 1

[V Starting : 1-Jul.1998 Ending : 31-Dec-1998 l CONTINUOUS MODE ** BATCH

..........................................................l......................l NUCLIDE l UNIT MODE l QUARTER 3 l QUARTER 4 3 l QUARTER 4 l

..........................................................lQ.UARTER .....................

H-3 CURIES l l 0.00E+00 l 0.00E+00 3.45E+00 2.34E+

..........................................................l...........l......00 ....

l FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0.00E+00 0.00E+00 BA-140 1.32E-05 2.12E-05 CURIES 0.00E+00 0.00E+00 1.77E.05 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 CO-60 1.17E-04 3.18E-04 CURIES 0.00E+00 0.00E+00 1.21E 4.62E.03 CR-51 CURIES 0.00E+00 0.00E+00 CS-134 3.20E-05 3.818 04 CURIES 0.00E+00 0.00E+00 2.46E-04 8.09E-05 CS-137 CURIES 0.00E+00 0.00E+00 FE-55 5.38E.03 2.06E.03 CURIES 0.00E+00 0.00E+00 1.168 03 4.26E-03 FE-59 CURIES 0.00E+00 0.003+00 0.00E+00 I-131 7.05E-06 CURIES 0.00E+00 0.00E+00 6.218 04 2.68E.04 I 133 CURIES 0.00E+00 0.00E+00 1.525-03 I-135 5.30E-04 CURIES 0.00E+00 0.00E+00 1.52E-04 0.00E+00 LA-140 CURIES 0.00B+00 0.00E+00 MN-54 1.27E-05 0.00E+00 CURIES 0.00B+00 0.00E+00 2.31E-03 1.99E.03

% MN.56 CURIES 0.00E+00 0.00E+00 6.26E-06 0.00E+00

) NA-24 NB.95 C.URIES CURIES 0.00E+00 0.00E+00 0.00E+00 1.91E-04 5.78E-05 SR-89 0.00E+00 1.88E-06 0.00E+00 CURIES 0.00E+00 0.00E+00 1.58E.04 9.44E-05 SR-90 CURIES 0.00E+00 0.00E+00 SR-91 1.12E-05 0.00E+00 CURIES 0.00E+00 0.00E+00 4.05E.05 0.00E+00 '

SR-92 CURIES 0.00E+00 0.00E+00 TC-99M 1.04E.05 0.00E+00 CURIES 0.00E+00 0.00E+00 1.71E.05 2.12E-06 Y-91M CURIES 0.00E+00 0.00E+00 ZN.65 7.93E.05 5.79E-06 CURIES 0.00E+00 0.00E+00 5.16E-03 5.34E 03 ZN-69M CURIES 0.00E+00 0.00E+00 TOTALS CURIES 1.12E.

05 0.00E+00 l l 0.00E+00 0.00E+00

...............................................l...........l......02 2.93E. l 2.00E-02 l DISSOLVED AND ENTRAI*iED GASES XE 133 CURIES 0.00E+00 0.00E+00 KE.135 1.13E-03 5.19E-04 i CURIES 0.00E+00 0.00E+00 3.30E-03 1.06E.03 O

13

' TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELIASE REPORT Liquid Effluents

.[

Starting : 1.Jul-1998 Unit: 1 Ending : 31-Dec-1998 l CONTINUOUS MODE **

..........................................................l..............

NUCLIDE l UNIT l QUARTER 3 jQUARTER 4 BATCH NODE l

..........................................................lQ.UARTER 3 l QUARTER 4l DISSOLVED AND ENTRAINED GASES XE.135M CURIES l l 0.00E+00 l 0.00E+00 2.67E-05

..........................................................l...........l.5.79E-05l TOTALS CURIES l l 0.00E+00 0.00E+00 4.46E-03

...............................................l...........l...........l.1.63E-03 ..........

l G-ALPHA CURIES l 0.00E+00 0.00E+00 l 2.07E-06

...............................................l...........l...........l.4.35E-06 ..........

l Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum detectable concentrations.

There are no continuous mode radioactive liquid release pathways at Plant Hatch.

O r

k 14

, TABLE 1-20*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents Unit: 2

. Starting : 1-Jan-1998 Ending : 30-Jun-1998 l~ CONTINUOUS MODE ** BATCH

.................................................................................l NUCLIDE l- UNIT l MODE l QUARTER 1 l QUARTER 2 1 l QUARTER 2 l

..........................................................lQ.UARTER .....................

H.3 CURIES l l 0.00E+00 l 0.00E+00 1.41E+00 1.82E+00

..........................................................l...........l...........{

FISSION & ACTIVATION PRODUC"PS AS 76 CURIES 0.00E+00 0.00E+00 4.11E.05 BA 140 1.55E-03 CURIES 0.00E+00 0.00E+00 0.00E+00 CE-141 1.19E-05 CURIES 0.00E+00 0.00E+00 2.66E 06 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 CO.60' 5.94E-05 4.38E-05 CURIES 0.00E+00 0.00E+00 1.17E-03 5.20E-04 CR 51 CURIES 0.00E+00 0.00E+00 CS.134 0.00E+00 2.90E-05 CURIES 0.00E+00 0.00E+00 2.175 05 4.87E-06 CS.137 CURIES 0.00E+00 0.00B+00 PE.55 8.69E-04 4.72E-04 CURIES 0.00E+00 0.00E+00 3.82E-04 I.131 CURIES 2.075 05 0.00E+00 0.00E+00 1.01E-05 2.41E-05 I.132 CURIES 0.00E+00 I.133 0.00E+00 0.00E+00 2.67E-05 CURIES 0.00E+00 0.00E+00 3.03E-05

'MN 54 CURIES 1.85E-04 0.00E+00 0.00E+00 8.55E-04 2.47E-04

-NA.24 CURIES 0.00E+00 0.00E+00 5.57E-04 O NB 97 CURIES 0.00E+00 0.00E+00 0.00E+00 1.39E-03 (j 88 122 SR-89 CURIES 0.00E+00 0.00E+00 0.00E+00 1.22E-04 1.71E 05 CURIES 0.00E+00 .0.00B+00 1.52E-04 SR-90 CURIES 4.23E-05 0.00E+00 0.00E+00 6.78E-08 4.19B 13 SR-91 CURIES 0.00B+00 TC-99M 0.00E+00 0.00E+00 2.52E-05 CURIES 0.00E+00 0.00E+00 5.63E-06 Y-91M CURIES 8.60E-05 0.00E+00 0.00E+00 0.00E+00 5.72E-05 ZN-65 CURIES 0.00E+00 EN-69M 0.00E+00 1.51E-03 2.40E-04 CURIES 0.00E+00 0.00E+0 2.85E-06

.......................................................0 TOTALS CURIES 1.45E-05 l 0.00B+00 0.00E+ 00 l 5.67E-03 l 5.13E-03 l

....................................l...........l...... ..........................

DISSOLVED AND ENTRAINED GASES ER-85' CURIES 0.00E+00 l 0.00E+00 1.80E-04 XE-133 0.00E+00 XE-135.

CURIES 0.00E+00 ' O.00E+00 2.17E-04 5.36E-05 CURIES 0.00E+00 0.00E+00 1.455-04 XE-135M -CURIES 4.24E-04 0.00E+00 0.00E+00 0.00E+00 1.36E-04 15

r'

. TABLE l-2B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents

' v-h ~ Starting : 1-Jan-1998 Unit: 2 Ending : 30.Jun-1998 l

l CONTINUOUS MODE ** BATCH

................................................................................l NUCLIDE l UNIT l MODE l QUARTER 1 l QUARTER 2 l QUARTER 1 2

.....................................................................lQ.UARTER ..........

l DISSOLVED AND ENTRAINED GASES TOTALS CURIES l l 0.00B+00 l 0.00E+00 5.42E-04 6.14E-04

..........................................................l...........l...........l G-ALPHA CURIES 5.47E-08 l l 0.00E+00 l 0.00E+00 5.48E-07

..........................................................l...........l...........l l l

l Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical min 4= =

detectable concentrations.

There are no continuous mode radioactive liquid release pathways at Plant Hatch. ,

i I

\

l i

e i

m 16

~

l TABLE 1-2B*

E. I. HATCH NUCLEAR PLANT I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !

Liquid Effluents Unit: 2 Starting : 1-Jul-1998 Ending : 31-Dec-1998 f l) l CONTINUOUS MODE ** l BATCH

................................................................................l NUCLIDE UNIT MODE l l QUARTER 3 l QUARTER 4 l QUARTER 3 4

.....................................................................lQ.UARTER ..........

l H.3 CURIES l l 0.00E+00 l 0.00E+00 l 3.05E+00 3.22E+00

.....................................................................l...........l FISSION is ACTIVATION PRODUCTS AS 76 CURIES 0.00E+00 0.00E+00 4.06E-05 ]

CE-141 2.12E-04 -

CURIES 0.00B+00 0.00E+00 3.82E-06 1.64E-05 CO-58 CURIES 'O.00E+00 0.00E+00 CO.60 1.43E-03 1.59E-03 CURIES 0.00E+00 0.00E+00 4.93E-03 7.06E-03 CR-51 CURIES 0.00E+00 0.00E+00 4.53E-03 CS-134 1.92E-03 CURIES 0.00E+00 0.00E+00 3.47E-05 3.37E.05 CS.137 CURIES 0.00E+00 0.00E+00 1.69E-03 FE 55 2.23E-03 CURIES 0.00E+00 0.00E+00 3.83E-04 4.73E.04 FE-59 CURIES 0.00E+00 0.00E+00 I-131 1.80E-04 9.85E-05 CURIES 0.00E+00 0.00E+00 2.50E-05 1.31E-06 I-133 CURIES 0.00E+00 0.00E+00 4.88E-05 2.72E-05 MN-54 CURIES 0.00E+00 0.00E+00 NA-24 4.09E-03 5.45E-03 l CURIES 0.00E+00 0.00E+00 0.00E+00 5.43E-04 NB-95 CURIES 0.00E+00 0.00E+00 1.88E-05

]

NB-97 1.72E-05 '

fg CURIES 0.00E+00 0.00E+00 7.07E-06 3.23E-05 5

SR-89 CURIES 0.00E+00 0.00E+00 9.12E-05 SR-90 5.75E-05 CURIES 0.00E+00 0.00E+00 4.26E-14 0.00E+00 TC.99M CURIES 0.00E+00 0.00E+00 2.78E.06 Y-91M 1.94E-05 CURIES 0.00E+00 0.00E+00 2.13E.06 0.00E+00 ZN-65 CURIES 0.00E+00 0.00E+00 ZN-69M 7.44E-03 1.93E-02 CURIES 0.00E+00 0.00E+00 0.00E+00 2.72E-06 ,

..................................................................... .......... l TOTALS CURIES l l 0.00E+00 0.00E+0C

...............................................l...........l...... 2.49E- 02 l 3.90E-02 l DISSOLVED AND ENTRAINED GASES AR.41 CURIES 0.00H+00 0.00E+00 XE-133 9.87B-07 0.00E+00 CURIES 0.00E+00 0.00E+00 8.90E-05 9.15E-05 XE-135 CURIES 0.00E+00 0.00E+00 TOTALS CURIES 2.74E-0 4 4.64E-04 l

l l 0.00E+00 0.00E+00

...............................................l...........l..64E-04 3.

l 5.55E-04 l

................... {

I

(<

s

j. >

l

\~s/ ' 1 17 1

J

TABLE 1-2B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents c Unit: 2 )

}

Starting : 1-Jul-1998 Ending : 31-Dec-1998 l CONTINUOUS BODE **

..........................................................l................E NUCLIDE l UNIT 4 BATCH MOD l

l QUARTER 3

...............................................lQ.UARTER l QUARTER 3 l QUARTER 4 l G-ALPHA CURIES l 0.00B+00 0.00B+00 l 9.21E.07

...............................................l...........l...........l..68E-06 1 l

Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical mininnum detectable concentrations. i i

There are no continuous mode radioactive liquid release pathways at Plant Hatch.

O

'V 18

1 TABLE 1-2C* l E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT {

Liquid Effluents l

Unit: Site i Starting : 1-Jan-1998 Ending : 30-Jun-1998 l CONTINUOUS MODE ** BATCH MODE

..........................................................l......................l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 1 l QUARTER 2 l

..........................................................lQ.UARTER .....................

H3 CURIES l l 0.00E+00 l 0.00E+00 3.44E+00 3.79

..........................................................l...........l.....E+00 ......

l FISSION is ACTIVATION PRODUCTS AS-76 CURIES 0.00E+00 0.00E+00 BA.140 4.11E.05 1.55E-03 CURIES 0.00E+00 0.00E+00 0.00E+00 1.19E-05 CE-141 CURIES 0.00E+00 0.00E+00 CO-58 2.66E-06 0.00E+00 CURIES 0.00E+00 0.00E+00 2.25E-04 6.68E-05 CO-60 CURIES 0.00E+00 0.00E+00 CR-51 9.58E-03 4.73E-03 CURIES 0.00E+00 0.00E+00 5.33E-05 2.90E-05 CS-134 CURIES 0.00B+00 0.00E+00 CS 137 9.91E-05 1.08E-04 CURIES 0.00E+00 0.00E+00 2.088-03 2.49E-03 FE-55 CURIES 0.00E+00 0.00E+00 I-131 1.75E-03 4.43E-04 CURIES 0.00E+00 0.00E+00 4.07E-04 2.85E-04 I-132 CURIES 0.00E+00 0.00E+00 I.133 0.00E+00 2.67E-05 CURIES 0.00E+00 0.00E+00 7.77E-04 7.34E-04 MN-54 CURIES 0.00E+00 0.00E+00 NA-24 2.74E.03 1.36E-03 CURIES 0.00E+00 0.00E+00 5.61E-04 1.42E-03 NB 97 CURIES 0.00E+00 0.00E+00 i

SB 122 3.34E-06 1.22E-04 CURIES 0.00E+00 0.00E+00 0.00E+00 1.71E-05 SR-89 CURIES 0.00E+00 0.00E+00 SR 90 3.00E-04 1.12E-04 CURIES 0.00E+00 0.00E+00 2.47E.07 9.02E-13 SR-91 CURIES 0.00E+00 0.00E+'00 TC-99M 0.00E+00 2.52E-05 CURIES 0.008+00 0.00E+00 5.63E-06 8.60E-05 Y-91M CURIES 0.00E+00 0.00E+00 ZN-65 0.00E+00 5.72E-05 CURIES 0.00E+00 0.00E+00 5.13E-03 2.62E-03 ZN-69M CURIES 0.00E+00 0.00E+00 TOTALS CURIES 858-06 2 1.45E 05 l 0.00E+00

...............................................l. .........l...." 02 l 1.63E-02 l l 0.00E+00 2.3 DISSOLVED AND ENTRAINED GASES KR-85 CURIES 0.00E+00 0.00E+00 XE-133 8.73E-04 0.00E+00

' CURIES 0.00E+00 0.00E+00 9.60E-04 XE-135 CURIES 6.35E 04 0.00E+00 0.00E+00 1.91E-03 2.01E 03 XE-135M CURIES 0.00E+00 0.00E+00 2.72E-04 1.36E.04

[ '

19

TABLE 1 2C8 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents n Unit: Site

~l Starting : 1-Jan-1998 Ending : 30.Jun.1998 l CONTINUOUS MODE ** l BATCH

................................................................................l NUCLIDE l UNIT MODE l QUARTER 1 l QUARTER 2 l QUARTER 1 2

.....................................................................lQ.UARTER..........

l DISSOLVED AND ENTRAINED GASES TOTALS CURIES l l 0.00E+00 l 0.00E+00 4.01E-03 2.79E-03

..........................................................l...........l...........l G-ALPHA CURIES 1.49E-06 l l 0.00E+00 l 0.00E+00 8.03E-07

..........................................................l...........l...........l Zeroes in this. table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum detectable concentrations.

There are no continuous mode radioactive liquid release pathways at Plant Hatch.

O i

N 20

TABLE 1-2C*'

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents

~

Unit: Site

, Starting : 1-Jul-1998 Ending : 31-Dec-1998

................................................................................j l CONTINUOUS MODE ** l BATCH MODE NUCLIDE UNIT l l QUARTER 3 l QUARTER 4 l QUARTER 3

-.....................................................................lQ.UARTER ..........

4l 1

i H-3 CURIES l l 0.00E+00 l 0.00E+00 l 6.51E+00 5.56E+00

.....................................................................l...........l I FISSION 8: ACTIVATION PRODUCTS AS-76 CURIES 0.00E+00 0.00E+00 5.38E-05 2.33E-04 BA 140 CURIES 0.00E+00 0.00E+00 1.77E.05 0.00E+00 CE-141 CURIES 0.00B+00 0.00E+00 3.82E-06 1.648 05 CO 58 CURIES 0.00B+00 0.00E+00 CO-60 1.55E.03 1.91E-03 CURIES 0.00E+00 0.00E+00 1.70E-02 1.17E-02 CR-51 CURIES 0.00E+00 0.00E+00 CS-134 4.56E.03 2.30E-03 l CURIES 0.00E+00 0.00E+00 2.81E.04 1.15E-04 CS-137 CURIES 0.00B+00 0.00E+00 7.07E-03 i

FE-55 4.29E-03 CURIES 0.00E+00 0.00E+00 1.54E-03 4.73E-03 FE-59 CURIES 0.00E+00 0.00E+00 1.80E.04 1.06E.04 I-131 CURIES 0.00B+00 0.00E+00 I 133 6.478 04 2.70E-04 CURIES 0.00E+00 0.00B+00 1.57E-03 5.57E I-135 CURIES 0.00E+00 0.00B+00 LA 140 1.52E.04 0.00E+00 l CURIES 0.00E+00 0.00E+00 1.27E-05 0.00E+00 MN 54 CURIES 0.00E+00 0.00E+00 6.40E 03 MN 56 7.44E-03 CURIES 0.00E+00 0.00B+00 6.26E-06 NA-24 0.00E+00 CURIES 0.00E+00 0.00E+00 1.91E.04 6.00E 04 NB-95 CURIES 0.00E>00 0.00E+00 NB-97 2.06E 05 1.72E-05 CURIES 0.00E+00 0.00E+00 7.07E-06 3.23E-05 SR-89 CURIES 0.00E+00 0.00E+00 BR 90 2.49E-04 1.52E-04 CURIES 0.00E+00 0.00E+00 1.12E-05 0.00E+00 SR-91 CURIES 0.00E+00 0.00E+00 4.05E-05 SR-92 0.00E+00 CURIES 0.00E+00 0.00E+00 1.04E.05 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 1.99E-05 Y-91M 2.15E-05 CURIES 0.00E+00 0.00E+00 8.15E-05 5.798-06 ZN 65 CURIES 0.00E+00 0.00E+00

~ZN-69M 1.26E.02 2.46E-02 CURIES 0.00E+00 0.00E+00 1.12E-05 TOTALS CURIES 2.72E-06 ....

l l 0.00E+00 l 0.00E+00 5.43E-02

..........................................................l...........l..91E-02 5 l

DISSOLVED AND ENTRAINED GASES AR-41 l ' CURIES l 0.00E+00 l 0.00E+00 l 9.87E.07 l.0.00E+00 l w.) -

21

)

TABLE 1-2C8 )

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents Unit: Site Starting : 1-Jul-1998 Ending : 31-Dec-1998 l CONTINUOUS MODE **

................................................................................l NUCLIDE UNIT l BATCH MODE l

l l QUARTER 3 l QUARTER 4 l QUARTER 3 4

.....................................................................lQ.UARTER..........

l DISSOLVED AND ENTRAINED GASES l XE.133 CURIES 0.00E+00 0.00E+00 1.22E-03 6.10E-04 XE-135 CURIES 0.00E+00 0.00E+00 3.58E-03 XE-135M 1.52E-03 CURIES 0.00E+00 0.00E+00 2.67E-05 5.79E-05 TOTALS CURIES l l 0.00E+00 l 0.00E+00 4.82E-03 2.19E-03

..........................................................l...........l...........l G-ALPHA CURIES l l 0.00E+00 l 0.00E+00 l 2.99E-06 6.03E-06

.....................................................................l...........l Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum detectable concentrations.

There are no continuous mode radioactive liquid release pathways at Plant Hatch.

v\

I t

\

22

TABLE 1-3A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT . 1998 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES

(' Starting: 01-Jan-1998 Unit: 1 Ending: 30-Jun-1998 Cumulative Domes per Quarter Organ Tech Unite Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mram 4.86E.03 9.72E-02 8.09B-03 1.62E.01 Liver 5.0 mram 7.84E-03 1.57E-01 1.20E.02 2.40E-01 TBody 1.5 mram 5.30E.03 3.54E-01 8.00E-03 5.33E-01 Thyroid 5.0 mram 2.73E-03 5.46E.02 Kidney 1.91E.03 3.81E 02 5.0 mrom 3.00E-03 5.99E-02 4.32E-03 8.64E 02 Lung 5.0 mram 7.25E-04 1.45E-02 1.25E-03 2.51E 02 GILLI 5.0 mram 5.39E-03 1.08E.01 3.14E-03 6.28E.02 Cumulative Doses per Year Organ Tech Unite Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mram 1.30E-02 1.30E.01 Liver 10.0 mrem 1.99E-02 1.99E-01 TBody 3.0 mram 1.33E.02 4.43E-01 Thyroid 10.0 mram 4.64E.03 4.64E.02

, Kidney 10.0 mram 7.32E-03 7.32E-02 Lung 10.0 mram 1.98E.03 1.98E.02 GILLI 10.0 mram 8.52E.03 8.52E-02 e

23

TABLE 1-3A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES

-/-~ Unit 1 Starting: 01-Jul.1998 Ending: 31-Dec-1998 k

l Cumulative Doses per Quarter Organ Tech Units Quarter t of Quarter t of Spec 3 Tech 4 TecL Limit Spec Spec Limit Limit Bone 5.0 mram 1.838-02 3.66E-01 7.36E-03 1.47E-01 Liver 5.0 mram 2.69E.02 5.378 01 1.14E-02 2.27E-01 TBody 1.5 mram 1.80E.02 1.20E+00 7.36E-03 4.91E-01 Thyroid 5.0 mram 4.20E-03 8.40E-02 1.77E-03 3.54E-02 Kidney 5.0 mram 9.54E-03 1.91E 01 4.36E-03 8.72E-02 Lung 5.0 mram 2.82E-03 5.65E-02 1.09E-03 2.19E-02 GILLI 5.0 mram 7.33E-03 1.47E-01 3.67E-03 7.35E.02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 zxem 3.86E-02 3.86E-01 Liver 10.0 mram 5.81E-02 5 81E-01

,_s TBody 3.0 mram- 3.86E-02 1.29E+00

/ ) Thyroid 10.0 mrem 1.06E-02 1.06E-01

(,,/ Kidney 10.0 mram 2.12E-02 2.12E-01 Lung 10.0 mram 5.89E-03 5.89E.02 GILLI 10.0 mram 1.95E-02 1.95E-01 O

24

TABLE 1-33 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2

( Starting: 01-Jan-1998 Ending: 30-Jun-1998 Cumulative Dosee per Quarter Organ Tech Units Quarter t of Quarter t of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrom 3.65E-03 7.30E.02 1.73D-03 3.46E-02 Liver 5.0 mram 5.44E-03 1.09E-01 2.46E-03 4.92E-02 TBody 1.5 mrom 3.52E 03 2.35E-01 1.62E-03 1.08E-01 l Thyroid 5.0 mram 9.98E-05 2.00E-03 2.89E-04 5.79E-03 Kidney 5.0 mrom 2.03E 03 4.06E-02 8.68E-04 1.74E-02 Lung 5.0 mram 5.52E-04 1.10E-02 2,. 81E - 04 5.61E-03 GILLI 5.0 mram 1.24E-03. 2.49E-02 4.22E 04 8.44E 03 l Cumulative Domes per Year Organ. Tech Units Year to t of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mram 5.38E 03 5.38E.02 Liver 10.0 mram 7.90E-03 7.90E-02 TBody 3.0 mram ~ 5.15E-03 1.72E-01

[h

( ,/

Thyroid Kidney 10.0 10.0 mrem mram 3.89E-04 2.90E-03 3.89E-03 2.90E-02 Lung 10.0 mrom 8.33E-04 8.33E-03 GILLI 10.0 mram 1.67E-03 1.67E-02 k

Q' 25

TABLE 1-3B E. I. HATCH NUCLEAR PLAffr ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit 2 Starting: 01.Jul-1998 Ending: 31-Dec-1998 Cumulative Domes per Quarter Organ Tech Units Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mram 7.61E-03 1.52E-01 9.60E.03 1.92E-01 Liver 5.0 mram 1.24E-02 2.48E-01 1.72E-02 3.44E-01 73ody 1.5 mram 7.82E 03 5.21E.01 1.03E-02 6.83E-01 Thyroid 5.0 mram 2.208 04 4.40E-03 4.76E-05 9.52E.04 Kidney 5.0 mram 5.08E 03 1.02E.01 7.84E-03 1.57E-01 ]

Lung 5.0 mrom 1.07E-03 2.15E-02 1 21E-03 2.42E-02 i

I GILLI 5.0 mram 5.61E-03 1.12E.01 8.42E-03 1.68E-01 l Cumulative Doses per Year Organ Tech Units Year to % of i

Spec Ending Tech Limit Date Spec Limit l Bone 10.0 mram 2.26E.02 2.26E.01 Liver 10.0 mram- 3.75E-02 3.75E 01 TBody 3.0 mram 2.32E.02 7.74E.01

(~'

\

Thyroid Kidney 10.0 10.0 mram mrem 6.57E-04 1.58E-02 6.57E-03 1.58E-01 Lung 10.0 mrom 3.12E.03 3.12E.02 GILLI 10.0 mrem 1.57E-02 1.57E-01 1

l l

l 8

26

f 1 l

TABLE 1-4A IO/ E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RETRASE REPORT - 1999 Liquid Effluents - Batch Release Summary Unit 1 Starting 1-Jan-1998 Ending 30-Jun-1998 l

LIQUID RELEASES NUMBER OF BATCH RELEASES : 172 TOTAL TIME PERIOD FOR BATCH RELEASES : 18650.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 175.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 108.43 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 82.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 9.54E+03 CFS j

[ l i

~

O)

\.

l 27 i 4

7 0

TABLE 1 4A

. \[ E. I. HATG NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1999 Liquid Effluents - Batch Release Summary Unit 1 Starting i 1.Jul-1998 Ending 31-Dec-1998 LIQUID RELEASES NUMBER OF BATG RELEASES : 150 TOTAL TIME PERIOD FOR BATG RELEASES : 20083.00 MINUTES MAXIMUM TIME PERIOD FOR A BATG RELEASE : 173.00 MINUTES AVERAGE TIME PERIOD FOR BATG RELEASES : 133.89 MINUTES MINIMUM TIME PERIOD FOR A BATG RETRASE : 10.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 9.54E+03 CFS l

l

\

s 28 L

TABLE 1-4B E. I. HATCH NUCLEAR PLANT C ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT . 1999

( Liquid Effluents - Batch Release Summary Unit 2 Starting : 1-Jan.1998 Ending 30-Jun-1998 LIQUID RELEASES NUMBER OF BATCH RELEASES : 117 TOTAL TIME PERIOD FOR BATCH RELEASES : 11829.00 MINUTES ]

MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 128.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 101.10 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 84.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF I RELEASE (l( LIQUID EFFLUENT INTO A FLOWING STREAM : 9.54E+03 CFS !

I

_..............___-_........... ................_................._ .,_.. _.--_. j l

1 4

i Q h .

D-v 29 W

I l

f TABLE 1-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1999 Liquid Effluents . Batch Release Sunmary Unit 2 Starting : 1.Jul-1998 Ending a 31-Dec-1998 LIQUID RELEASES NUMBER OF BATCH RELEASES : 201 TOTAL TIME PERIOD FOR BATCH RELEASES : 20979.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 137.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 104.37 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 42.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 9.54E+03 CFS O'

U 30

/ TABLE 1-5 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SA A*PLE ANAL YSES E. I. HATCH NUCLEAR PLANT JANUARY,1998 - DECEMBER,1998 The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 1.97E-08 uCi/mi Fe-59 3.94E-08 uCi/ml Co-58 1.59E-08 uCi/ml Co-60 1.72E-08 uCi/ml .

2n-65 2.92E-08 uCl/mi i

Mo 99 1.20E-07 uCi/ml

/ Cs 134 1.75E-08 uCi/ml Cs-137 1.62E-08 uCi/ml Ce-141 1.92E-08 uCi/mi Ce-144 8.83E-08 uCi/mi '

l131 1.43E-08 uCl/mi Xe-135 1.03E-08 uCl/ml Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml 4 Sr-90 8.50E-09 uCi/ml {

H3 6.00E-07 uCl/mi !

i l

U 31 i

1 2.0 Gaseous Effluents 2.1 ODCMSpecifications

. The ODCM Specifications presented in this section are for Unit 1 and Unit 2.

2.1.1 Dose Rate Limit The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and, ,

l

b. For lodine-131, lodine-133, tritium and for all radionuclides in l particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.

2.1.2 Air Dose Due To Noble Gas l The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following:

O a. During any calendar quarter: Less than or soual to 5 mrads ;

i for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any caiendar year: Less than or equal to 10 mrads for gamma !

radiation and less than or equal to 20 mrads for beta radiation.

2.1.3 Dose To Any Organ The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released from each unit, to areas at and beyond the SITE BOUNDARY, shall be limited to the following.

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ.

b. During any calendar year: Less than or equal to 15 mrems to any organ.

32

2.1.4 TotalFuelCycle Dose Commitment (40CFR190)

The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

2.2 Release Points of Gsseous Effluents Waste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit 1 reactor building vent; Unit 2 reactor building i

vent, and the recombiner building vent. Each of these four paths is continuously monitored for gaseous radioactivity. Each is equipped with an integrating-type sample collection device for collecting particulates and lodines. Unless required more frequently under certain circumstances, samples are collected as follows:

1. Noble gas samples are collected by grab sampling monthly.

2. Tritium samples are collected by grab sampling monthly.

. 3. Radiolodine samples are collected by pulling the sample stream through l r a charcoal cartridge over a 7-day period.

4. Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period.

5. The 7-day particulate filters above are annlyzed for gross alpha activity.

-6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the samples are analyzed for Sr-89 and Sr-90.

Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, the dose rates associated with gaseous releases, and the cumulative doses for the current quarter and year. This task is normally performed with computer assistance.

The noP W grab sample analysis r:Sts are used along with maxinRm 9;w;ted release flow rates from each of the four vents to calculate moniior setpoints for the gaseous effluent monitors serving the four release points. Calculation of monitor setpoints is described in the ODCM.

O 33 1

For each release period, released radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated b' along with the percent of the ODCM limit for each release, for the current quarter and year.

2.3 Total Quantitles of Radianctivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:

2.3.1 Fission and Activation Gas The released radioactivity is determined using sample analyses results collected as described above and the average release flow rates over the period represented by the collected sample.

Instantaneous dose rates due to noble gases, radioiodines, tritium, and i particulates are calculated (with computer assistance). The calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, !

radiolodine, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.

O Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure I due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and :

year. Cumulative air doses are compared to the dose limits specified in ;

ODCM 3.1.3. The current percent of the ODCM limits are shown on the printout for each release period. Air dose calculation methodology is presented in the ODCM.

2.3.2 Radiolodine, Tritium and Particulate Releases Released quantities of radioiodines are determined using the weekly samples and release flow rates for the four release points. Radioiodine concentrations are determined by gamma spectroscopy.

Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the four release points. Gamma spectroscopy is used to quantify concentrations of principal gamma emitters.

D t/

.34

After each quarter, the particulate filters from each vent are combined, fused, and i a strontium separation is performed. Since sample flows and vent flows are !

almost constant over each quarterly period the filters from each vent can be I dissolved together. Decay corrections are performed back to the middle of the quarterly collection period. If Sr-89 or Sr-90 is not detected, MDC's are calculated. Strontium concentrations are input into the composite file of the computer and used for release dose rate and individual dose calculations.

Tritium samples are obtained monthly from each vent by passing the sample stream through a cold trap. The grams of water vapor / cubic foot is measured upstream of the cold trap in order to alleviate the difficulties in j determining water vapor collection efficiencies. The tritium samples are analyzed l by an independent laboratory and the results are furnished in uCi/ml of water. The tritium concentration in water is converted to the tritium concentration in air and this value is input into the composite file of the computer and used in release, dose rate, and individual dose calculations. j Dose rates due to radiolodine, tritium and particulates are calculated for a hypothetical child exposed to the inhalation pathway at the location in the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated, for each release point for each l release period, and the total dose rates from both release points are I compared to the dose rate limits specified in ODCM 3.1.2 Individual doses due to radiolodine, tritium and particulates are calculated for the controlling receptor, which is described in the ODCM.

Individual doses are calculated for each release period, and cumulative totals are kept for each unit, for the current calendar quarter and year. Cumulative individuti doses are compared to the dose limits specified in ODCM 3.1.4. ,

The current percent of ODCM limits are shown on the printout for each release period.

2.3.3 Gross Alphe Release 1

The gross alpha release is computed each month by counting the particulate '

filters, for each week for gross alpha activity in a proportional counter. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed ,

at the end of the month. The summed activity is then divided by the total monthly j volume to determine the concentration. This concentration is input into the i composite file of the computer and used for release calculations. l I

35

2.4 Geseous Effluent Release Dets 2.4.1 hiethodology Regulatory Guide 1.21 Tables 1 A,1 B, and 1C are found in this report as Tables 2-1 A,2-18,2-10,2-2A, ,2-2B,2-20,2-3A,2-38,2-30, and data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all quarters.

To complete table 2-1 A,2-1 B, and 2-10, total release for each of the four categories (fission and activation gases, lodine's, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCl/second for each category for each quarter. However, the percent of the ODCM limits are not applicable because we have no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are !

limited as specified in ODCM 3.1.2. The other three categories (tritium, l radiolodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases, and due to radioiodine, tritium, and !

particulates were calculated as part of the pre-release and post-release I permits on individual permits. No limits were exceeded for this reporting period. 1 Gross alpha radioactivity is reported in Table 2-1 A,2-18, and 2-10, as curies released in each quarter.

Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-4A and 2-48, along with percent of ODCM limits.

Limits for cumulative individual doses due to radiolodine, tritium and particulates, are specified in ODCM 3.1.4. Cumulative individual doses are presented in Table 2-5A, and 2-5B, along with percent of ODCM limits. 1 The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total process of sampling and measurement. Due to the difficulty with assigning error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective is to obtain an overall estimate

- of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.

Esiimated errors are associated with counting equipment calibration, counting stW :s, vent-flow rates, vent sample flow rates, non steady release ratt chemical yield factors and sample losses for such items as charcoal cartridges.

h 36

=

Fission and activation total release was calculated from sample analysis results and release point flow rates.

Statistical error - 60%

Counting equipment calibration 10%

Vent flow rates 10%

Non-steady release rates 20%

TOTAL ERROR 100 %

l-131 releases were calculated from each weekly sample:

Statistical error 60 %

Counting equipment calibration 10%

Vent flow rates 10%

Vent sample flow rates 10%

Non steady release rates 10%

Losses from charcoal cartridges 10%

TOTAL ERROR 110 %

Particulates with half lives greater than 8 days releases were calculated from sample analysis results and release point flow rates.

Statistical error 60 %

Counting equipment calibration 10%

O' Vent flow rates 10% '

Vent sample flow rates 10%

Non steady release rates 10%

TOTAL ERROR 100 %

Total tritium releases were calculated from sample analysis results and release point flow rates.

Water vapor in sample stream determination 20%

Vent flow rates 10%

Counting calibration and statistics 10%

Non-steady release rates 50 %

TOTAL ERROR 90 %

O 37

l l

f)

V Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.

l Statistical error 60%

Counting equipment calibration 10%

Vent flow rates 10% '

Vent sample flow rates 10% l

. Non Steady release rates 10%

TOTAL ERROR 100 %

2.5 RadiologicalImpact Due to Gaseous Releases Dose rates due to noble gas release were calculated for the site in accordance with ODCM 3.1.2. Dose rates due to radioiodine, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.1.2.

i These dose rates were calculated as part of the pre-release and post release on individual release permits. No limits were exceeded for this reporting period.

Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.1.4. These results are presented in Tables 2-6A ,and 2-6B.

Dose rates and doses were calculated using the methodology presented in the ODCM.

2.6 Abnormal Releases There were no unplanned or uncontrolled releases during this reporting period.

~h (J

38

TABLE 2-1A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !

Gaseous Effluents - Summation of All Releases j

Unit 1

. d Starting : 1-Jan-1998 Ending : 30-Jun-1998 l

TYPE OF EFFLUENT UNITS QUARTER 1 1

QUARTER 2 EST. TOT ERROR %

l A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.97E+02 9.96E+01 1.00E+02 j

2.-AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.53E+01 1.27E+01 I

................................................................................ j

3. PERCENT OF APPLICABLE LIMIT % *

1 1

.................................................................................. j 1

B. RADIOIODINES l

1. TOTAL IODINE-131 CURIES 1.08E 03 1.53E-03

......................................................................... 10E+02 1

...... i

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.38E.04 1.95E-04 {

................................................................................ j

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES 1 j

................................................................................ 1

1. PARTICULATES (HALF-LIVES >8 DAYS) CURIES 6.59E-04 5.03E-04

....................................................................... 1.00E+02 n 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.47E-05 6.40E-05

3. PERCENT OF APPLICABLE LIMIT % * *

................................................................................ {

4. GROSS ALPHA RADIOACTIVITY CURIES 3.85E-07 6.15E-07 D. TRITIUM 1 1

1. TOTAL RELEASE CURIES 1.14E+00 1.81E,00

....................................................................... 9.00E+01 ........ 1

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.47E-01 2.30E-01

3. PERCENT OF APPLICABLE LIMIT % *

1 1

Applicable limits are expressed in terms of dose. See Tables 2 4A, 2 4B, 2-5A, and 2-5B of this report.

s 1

I r

(

V) I 4

39

o 1

TABLE 2-1A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Q

Gaseous Effluents - Sununation of All Releases Unit: 1 Starting : 1-Jul.1998 Ending : 31-Dec-1998 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.77E+02 1.52E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.23E+01 1.91E+01

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES g g gg g g;g . ....

gg ....

ggg

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.17E-04 1.02E-04

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES (HALF-LIVES >8 DAYS) CURIES 3.50E-04 4.31E-04 1.00E+02

,F 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.40E-05 5.42E-05 t ................................................................................

V

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 5.23E-07 6.74E-08 D. TRITIUM

1. TOTAL RELEASE CURIES 4.14E+00 2.33E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 5.21E-01 2.94E-01

3. PERCENT OF APPLICABLE LIMIT % *

1 1

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

f%

.( ~

40 1

TABLE 2-1B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

,q Gaseous Ef fluents - Sunnatio.7 of All Releases 8

Unit: 2 (d Starting : 1-Jan-1998 Ending : 30-Jun-1998

' TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

................................................................................ I

1. TOTAL RELEASE CURIES 1.97E+02 9.96E+01 1.00E+02 I

................................................................................ l l

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.53E+01 1.27E+01 I

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 4.03E-03 6.03E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.18E-04 7.67E-04

3. PERCENT OF APPLICABLE LIMIT % *

1 C. PARTICULATES

1. PARTIGULATES(HALF-LIVES >8 DAYS) CURIES 1.84E-03 7. 89E-03 1.00E+02 N 2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 2.36E.04 2.402-04

3. PERCENT OF APPLICABLE LIMIT % *

4 GROSS ALPHA RADIOACTIVITY CURIES 7.20E.07 6.62E-07 D. TRITIUM

1. TOTAL RELEASE CURIES 4.01E+00 5.90E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.15E-01 7.50E-01

3. PERCENT OF APPLICABLE LIMIT- % *

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

,A, t }*

%)

41

1 l

W M 2-1B E. I. 444 <. P OLEAR PLANT ANNUAL RADIOACT N 1 U.UENT RELEASE REPORT D Gaseous Effluer v $.7.ation of All Releases p

,k... . 2

\

Starting : 1-JL 1PF Ending : 31-Dec-1998 TYPE OF EFFLUENT N ffS QUARTER 3 QUARTER 4 EST. TOT ERROR t A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.52B+02 5.84E+01 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.91E+01 7.35E+00

3. PERCENT OF APPLICABLE LIMIT % *

B. RADICIODINES

................................................................................ l

1. TOTAL IODINE-131 CURIES 6.07E-03 4.10E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.64E-04 5.15E-04

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES (HALF-LIVES >8 DAYS) CURIES 1.49E-03 1.05E-03 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.88E-04 1.3 E-04 (A}

V ................................................................................

3. PERCENT OF APPLICABLE LIMIT t * *

4. GROSS ALPHA RADIOACTIVITY CURIES 3.19E-07 2.96E-08 D. TRITIUM

1. TOTAL RELEASE CURIES 6.46E+00 5.09E+00 9.00E+

2. AVERAGE RELEASE PJL.*;s FOR PERIOD uCi/Sec 8.12E-01 01 ..

6.40E-01

3. PERCENT OF APPLICABLE LIMIT t *

Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

I 4

I 42

f l

TABLE 2 1C E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

/^ Gr.seous Effluents - Sunanation of All Releases I l

i Unit Site

\

Starting : 1-Jan.1998 Ending : 30-Jun-1998 l

TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 3.94E+02 1.99E+02 1.00E+02

)

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.06E+01 2.53E+01

3. PERCENT OF APPLICABLE LIMIT % *

i B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 5.10E-03 # 7.56E-03 1.10E+02 l

2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 6.56E-04 9.62E-04

................................................................................ l

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES (HALF. LIVES >8 DAYS) CURIES 2.50E-03 2.39E-03 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.21E-04 3.04E-04

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 1.10E-06 1.28E-06 D. TRITIUM

1. TOTAL RELEASE CURIES 5.15E+00 7.71E+00

............................................................................E+01 9.00

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.62E-01 9.20E-01

3. PERCENT OF APPLICABLE LIMIT % *

Applicable limits are expressed in terms of dose. See Tables 2 4A, 2-4B, 2-5A, and 2-5B of this report.

6

.g.

G 43

TABLE 2-1C E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents - Summation of All Releases Unit: Site j C Starting : 1.Jul-1998 Ending : 31-Dec-1998 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT

! i ERROR % !

A FISSION in ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 3.29E+02 2.10E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.14E+01 2.65E+01

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 7.79E-03 4.91E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.81E-04 6.18E-04

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES (HALF-LIVES >8 DAYS) CURIES 1.85E-03 1.48E-03 1.00E+02 p 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.328-04 1.86E-04

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 8.41E-07 9.69E-08 D. TRITIUM

1. TOTAL RELEASE CURIES 1.06E+01 7.42E+00

......................................................................... 00E+01 9

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.33E+00 9.34E 01

3. PERCENT OF APPLICABLE LIMIT % * *

................................................................................ l i

e Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2 -5A, and 2-5B of this report.

% l

O i

TABLE 2-2A* 1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Elevated Level Releases i Unit: 1 Starting : 1.JAn-1998 Ending : 30-Jun-1998 l CONTINUOUS MODE l BATCH MODE ** l E05Es5ESEEEEA$E$"'"."i"~5E$i"ibEAENETib6AENATi6EAENATI6E

]

I FISSION GASES I

................................................................................ l XE.137 CURIES 1.38E+02 6.69E+01 0.00E+00 0.00E+00 l XE.138 CURIES 3.64E+01 1.70E+01 0.00E+00 0.00E+00 XE-135M CURIES 1.69E+01 8.15E+00 0.00E+00 0.00E+00 KR-87 CURIES 1.20E+00 6.59E-01 0.00E+00 0.00E+00 l AR-41 CURIES 1.08E.01 0.00E+00 0.00E+00 0.00E400 i KR-85M CURIES 5.22E-02 7.34E-01 0.00E+00 0.00E+00 XE-135 l CURIES 3.28E+00 1.94E+00 0.00B+00 0.00E+00 !

XE-133 CURIES 1.09E+00 4.22E+00 0.00E+00 0.00E+00 l

................................................................................ 1 TOTAL POR PERIOD CURIES l l 1.97E+02 l 9.96E+01 l 0.00E+00 0.00E+00

.....................................................................l...........l IODINES I-133 CURIES 1.29E-02 2.69E-02 0.00E+00 I-131 0.00E+00 I CURIES 9.04E-04 1.31E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.385-02 l 2.82E-02 0.00E+00 0.00E+00 O ..........................................................l...........l...........l PARTICULATES I.131 CURIES 7.37E.06 4.48E-06 0.00E+00 BA-140 0.00E+00 CURIES 5.14E-04 3.88E 04 0.00E+00 0.00E+00 CE-141 CURIES 1.15E.08 1.14E-07 0.00E+00 SR-89 0.00E+00 CURIES 1.27E-04 1.03E-04 0.00E+00 0.00E+00 CE-144 CURIES 1.168 06 0.00E+00 0.00E+00 SR-90 0.00E+00 CURIES 1.04E-06 1.57E-06 0.00E+00 0.00E+00 CS-137 CURIES 2.99E-06 1.96E-06 0.00E+00 0.00E+00 TOTAL POR PERIOD l CURIES l 6.54E-04 l 4.98E-04 0.00E+00 0.00E+0 0 l

..........................................................l...........l....... ...

................................................................................ }

G ALPHA CURIES 2.04E-08 3.57E-08 H-3 0.00E+00 0.00E+00 CURIES 3.968-01 6.49E-01 0.00B+00 0.00E+0

__............................................................................ 0...

Zeroes at in thislevels.

detectable table indicate that no radioactivity was present See Table 2-7 for typical minimum detectable concentrations.

There at Plant are no batch mode radioactive gaseous release pathways Match.

O)

\~, ;

i l

45 l

l TABLE 2-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Elevated Level Releases

[%

Unit 1

' V) Starting : 1-Jul-1998 Ending : 31-Dec-1998 l CONTINUOUS MODE

..........................................................l......................l NUCLIDES RELEASED l UNIT BATCH MODE **

l l QUARTER 3 l QUARTER 4

..........................................................lQ.UARTER 3 l QUARTER 4 l FISSION GASES XE.137 CURIES 6.57E+01 1.20E+02 0.00E+00 XE-138 0.00E+00 CURIES 1.68E+01 0.00E+00 0.00h+00 0.00E+00 XE-135M CURIES 7.67E+01 1.38E+01 0.00E+00 KR-87 0.00E+00 CURIES 1.65E+00 0.00B+00 0.00E+00 0.00E+00 AR-41 CURIES 0.00E+00 3.67B+00 0.00E+00 KR-85M 0.00E+00 CURIES 6.87E-01 2.33E+00 0.00E+00 0.00E+00 XE-135 CURIES 3.22E+00 2.36E+00 0.00E+00 XE-133 0.00E+00 CURIES 9.18E+00 1.00B+01 0.00E+00 0.00E+

TOTAL FOR PERIOD CURIES 00 ....

l l 1.74E+02 l 1.52E+02 0.00E+00 0.00E+ 00 l

..........................................................l...........[...... ....

IODINES I-133 CURIES 3.23E-02 1.22E-02 I-131 0.02h+00 0.00E+00 CURIES 1.55E-03 6.55E-04 0.00f+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.38E-02 l 1.28E-02 0.00E+00 0.00E+

...........................................................l...........l...... 00 l PARTICULATES-I-131 CURIES 5.83E.06 BA-140 4.93E-06 0.00E+00 0.00E+00 CURIES 2.60E-04 3.14E-04 0.00E+00 0.00E+00 CE-141 CURIES 4.13E-07 SR-89 4.30E-07 0.00E+00 0.00E+00 CURIES 7.91E 05 9.05E-05 0.00E+00 0.00E+00 ZN-65 CURIES 1.87E-07 5.92B-07 CE-144 0.00E+00 0.00E+00 CURIES 9.36E-08 1.09E-06 0.00E+00 0.00E+00 CO-60 CURIES 1.76E-07 5.56E-07 SR-90 0.00E+00 0.00E+00 CURIES 1.12E-06 5.24E-08 0.00E+00 0.00E+00 CS-137 CURIES 6.31E-07 1.10E-06 0.00E+00

..................................................................... 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.48E.04 4.13E-04 0.00E+

...............................................l...........l......00 l 0.00E+00 l H.3 CURIES 1.05E+00 7.19E.01

.............................. 0.00E+00 0.00E+00 Eeroes at in thislevels.

detectable tabTe indicate that no radioactivity was present See Table 2-7 for typical minimum detectable concentrations. {

j **

i There at Plantare no batch mode radioactive gaseous release pathways Match.

l l O).

t v

46

~

TABLE 2-2B*

E. I. MATCH NUCLEAR PLANT ANNUAL RADIOACTIVE kiTLUENT RELEASE REPORT Gaseous Effluents Elevated Level Releases

(

' Unit: 2 Starting : 1-Jan.1998 Ending : 30-Jun-1998 CONTINUOUS MODE

................................................................................l NUCLIDES RELEASED l UNIT l l BATCH MODE **

l QUARTER 1 l QUARTER 2 l QUARTER 1 2

.....................................................................lQ.UARTER ..........

l FISSION GASES XE-137 CURIES 1.38E+02 6.69E+01 0.00E+00 0.00E+00 XE-138 CURIES 3.64E+01 1.70E+01 0.00E+00 XB-135M 0.00E+00 CURIES 1.69E+01 8.15E+00 0.00E+00 0.00E+00 KR-87 CURIES 1.20E+00 6.59E-01 0.00E+00 AR-41 0.00E+00 CURIES 1.08E-01 0.00E+00 0.003+00 0.00E+00 KR-85M CURIES 5.22E-02 7.348-01 0.00E+00 XE-135 0.00E+00 CURIES 3.28E+00 1.94E+00 0.00E+00 0.00E+00 XE-133 CURIES 1.09E+00 4.22E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.978+02 l 9.96E+01 0.00E+00 0.00E+00

..........................................................l...........l...........l

. IODINES 1-133 CURIES 1.29E-02 2.69E-02 0.00E+00 0.00E+00 I-131 CURIES 9.04E-04 1.31E-03 0.00B+00 0.00E+00

-(

g TOTAL FOR PERIOD l CURIES l 1.38E-02 l 2.82E-02 0.00E+00 0.00E+00

..........................................................l...........l...........l N

PARTICULATES I-131 CURIES 7.37E-06 4.48E-06 0.00E+00 RA-140 0.00E+00 CURIES 5.14E-04 3.88E-04 0.00E+00 0.00E+00 CE-141 CURIES 1.15E-08 1.14E-07 0.00E+00 SR-89 0.00E+00 CURIES 1.27E-04 1.038-04 0.00E+00 0.00E+00

-CE.144 CURIES 1.16E-06 0.00E+00 0.00E+00 SR-90 0.00E+00 CURIES 1.04E-06 1.575-06 0.00E+00 0.00E+00 CS-137 CURIES 2.99E-06 1.96E-06 0.00E+00 0.00E+

........................................................................... 00 TOTAL FOR PERIOD l CURIES l 6.54E-04 l 4.98E-04 0.00E+00 0.00E+0 0 l

..........................................................l...........l....... ...

G-ALPHA CURIES 2.04E-08 3.57E-08 H3 0.00E+00 0.00E+00 CURIES 3.96E.01 6.49E-01 0.00E+00 0.

........................................................................ 00E+00

~

Zeroes at in thislevels.

detectable table indicate that no radioactivity was present See Table 2 7 for typical minimum detectable concentrations.

There at are Plant no batch mode radioactive gaseous release pathways Hatch.

47

TABLE 2-2B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

' "/'~' Gaseous Effluents-Elevated Level Releases Unit 2 Starting 1-Jul-1998 Ending : 31.Dec-1998 CONTINUOUS MODE. BATCH MODE **

................................................................................l NUCLIDES RELEASED l UVIT l l l QUARTER 3 l QUARTER 4 3 l QUARTER 4 l

..........................................................lQ.UARTER .....................

FISSION GASES XE-137 CURIES 3.43E+01 3.94E+01 0.00E+00 0.00E+00 XE-138 CURIES 1.68E+01 0.00E+00 0.00E+00 0.00E+00 XE-135M CURIES 7.365+01 7.75E+00 0.00E+00 0.00E+00 KR-87 CURIES 1.65E+00 0.00E+00 0.00E+00 i AR-41 0.00E+00 l CURIES 0.00E+00 3.67E+00 0.00E+00 0.00E+00

-KR-85M CURIES 6.87E-01 1.60E+00 0.00E+00 0.00E+00 XE-135 CURIES 2.40E+00 1.188+00 0.00E+00 0.00E+00 XE-133 CURIES 6.14E+00 4.85E+00 0.00E+00 .0.00E+00 TOTAL FOR PERIOD CURIES l l 1.36E+02 l 5.84E+01 0.00E+00 0.00B+00

..........................................................l...........l...........l IODINES I-133 CURIES 2.82E-02 6.28E-03 0.00E+00 I-131 0.00E+00 CURIES 1.18E-03 3.35E-04 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES .l 2.94E-02 l 6.61E-03 0.00E+00 0.00E+00

( ..........................................................l...........l...........l PARTICULATES I-131 CURIES 3.70E-06 BA-140 1.95E-06 0.00E+00 0.00E+00 CURIES 1.86E-04 1.52E.04 0.00E+00 0.00E+00 CE-141 CURIES 1.66E-07 0.00E+00 0.00B+00 SR-89 0.00E+00 CURIES 5.30E-05 4.83E-05 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 7.90E.07 0.00E+00 SR-90 0.00E+00 CURIES 8.19E-07 0.00B+00 0.00E+00 0.00E+00 CS-137 CURIES 6.31E-07 8.035-07 0.00E+00 0.00E+

TOTAL FOR PERIOD CURIES 00 ....

j l l 2.44E-04 l 2.04E.04 0.00E+00 0.00E+

..........................................................l...........l......00l ....

................................................................................ 1 G-ALPHA CURIES 2.29E-08 H3 1.23E.08 0.00E+00 0.00E+00 CURIES 9.68E-01 5.57E-01 0.00E+00

..........................................................................E+00 0.00 Zeroes at in thislevels.

detectable table indicato that no radioactivity was present 1 See Table 2-7 for typical minimum detectable concentrations.

There at areHatch.

Plant no batch mode radioactive gaseous release pathways

\

48

TABLE 2-2C*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Elevated Level Releases

[T Unit: Site

\ ,) Starting : 1-Jan.1998 Ending : 30-Jun-1998 l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l FISSION GASES XE 137 CURIES 2.76B+02 1.34E+02 0.00E+00 0.00E+00 XE-138 CURIES 7.28E+01 3.40E+01 0.00E+00 0.00E+00 XE 135M CURIES 3.37E+01 1.63E+01 0.00E+00 0.00E+00 KR-87 CURIES 2.39E+00 1.32E+00 0.00E+00 0.00E+00 AR.41 CURIES 2.16E-01 0.00E+00 0.00E+00 0.00E+00 KR-85M CURIES 1.04E-01 1.47E+00 0.00E+00 0.00E+00 XE-135 CURIES 6.57E+00 3.88E+00 0.00E+00 0.00E+00 XE 133 CURIES 2.19E+00 8.43E+00 0.00E+00 0.00E+00 i

................................................................................ 1 TOTAL FOR PERIOD CURIES l 3.94E+02 l 1.99E+02 l 0.00E+00 l 0.00E+00

................................................................................l l

IODINES I 133 CURIES 2.58E-02 1 5.38E-02 0.00E+00 0.00E+00 <

I-131 CURIES 1.81E-03 1 2.62E-03 0.00E+00 0.00E+00 I f" ' TOTAL FOR PERIOD l CURIES l 2.76E-02 l 5.65E-02 l 0.00E+00 0.00E+00 5 .....................................................................l...........l PARTICULATES I I-131 CURIES 1.47E-05 8.96E-06 0.00E+00 0.00E+00 BA-140 CURIES 1.03E-03 7.75E-04 0.00E+00 0.00E+00 CE 141 CURIES 2.30E-08 2.27E-07 0.00E+00 0.00E+00

-SR-89 CURIES 2.54E-04 2.062-04 0.00E+00 0.00E+00 CE-144 CURIES 2.31E-06 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 2.08E-06 3.13E-06 0.00E+00 0.00E+00 CS-137 CURIES -5.99E 06 3.92E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD. l CURIES l 1.31E-03 l 9.97E-04 0.00E+00 ~0.00E+00

..........................................................l...........l...........l G-ALPHA CURIES 4.08E-08 7.14E 08 0.00E+00 H-3 0.00E+00 CURIES 7.93E 01 1.30E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present j at detectable levels. See Table 2-7 for typical minimwm detectable concentrations. 1 There are no batch mode radioactive gaseous release pathways i j

at Plant Hatch. '

i I

49 !

i 1

1

.1

TABLE 2-2C8 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Elevated Level Releases h

V Starting :

Unit Site 1-Jul-1998 Ending : 31-Dec-1998 CONTINUOUS MODE

................................................................................l NUCLIDES RELEASED l- UNIT l l BATCH MODE **

l QUARTER 3 l QUARTER 4 l QUARTER 3 4

.....................................................................lQ.UARTER ..........

l FISSION GASES XE 137 CURIES 9.998+01 1.59E+02 0.00E+00 0.00E+00 XE-138 CURIES 3.35E+01 0.00E+00 0.00E+00 XE 135M 0.00E+00 CURIES 1.50E+02 2.16B+01 0.00E+00 0.00E+00 KR-87 CURIES 3.30E+00 0.00E+00 0.00E+00 AR-41 0.00E+00 CURIES 0.00E+00 7.33E+00 0.00E+00 0.00E+00 KR-85M CURIES 1.37E+00 3.93E+00 0.00E+00 XE-135 0.00E+00 CURIES 5.62B+00 3.54B+00 0.00E+00 0.00E+00 XE 133 CURIES 1.53E+01 1.49E+01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.09E+02 l 2.10E+02 0.00E+00 0.00E+00

..........................................................l...........l...........l IODINES 1-133 CURIES 6.058 02 1.85E-02 0.00E+00 I-131 0.00E+00 CURIES 2.73E-03 9.90E-04 0.00E+00 0.00E+00 p TOTAL FOR PERIOD l CURIES l 6.33E-02 l 1.95E-02 0.00E+00 0.00E+00

\ ..........................................................l...........l...........l PARTICULATES

................................................................................ l I-131 CURIES 9.53E.06 6.88E-06 BA-140 0.00E+00 0.00E+00 CURIES 4.46E-04 4.66E-04 0.00E+00 0.00E+00 CH 141 CURIES 5.79E-07 4.30E-07 0.00E+00 SR-89 0.00E+00 CURIES 1.32E-04 1.39E-04 0.00E+00 0.00E+00 ZN-65 CURIES 1.87E-07 5.92E-07 ; 0.00E+00 CE-144 0.00E+00 CURIES 9.36E-08 1.88E-06 0.00E+00 0.00E+00 CO.60 CURIES 1.76E-07 5.56E-07 SR-90 0.00E+00 0.00E+00 CURIES 1.948 06 5.24E-08 0.00E+00 0.00E+00 CS-137 CURIES 1.26E-06 1.90E-06 0.00E+00 TOTAL FOR PERIOD CURIES 0.00E+00 ..........

{

l l 5.92E 04 6.17E-04 0.00E+

...............................................l...........l......00 l 0.00E+00 l i

G-ALPHA ;

H3 CURIES 5.08E-08 l 3.07E-08 0.00E+00 0.00E+00 CURIES 2.02E+00 1.28E+00 0.00B+ 0.00E+00 4

...............................................,................. 00 l

............... )

Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum i detectable concentrations.

There are no batch mode radioactive gaseous release pathways at Plant Hatch.

l 1

'N . {

d l!

50 .

i i

O TABLE 2-3Ae l

E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i-

, t] Gaseous Effluents-Ground Level Releases Unit: 1

( / Starting : 1-Jan-1998 Ending : 30-Jun-1998 l CONTINUOUS MODE BATCH MODE **

..........................................................l......................l NUCLIDES RELEASED UNIT l l QUARTER 1 l QUARTER 2 1 l QUARTER 2 l 5

..........................................................lQ.UARTER .....................

FISSION GASES XE-135 l CURIES l 2.75E-02-l 2.73E-02 0.00E+00

..........................................................l...........l.....E+00 TOTAL FOR PERIOD CURIES 0.00 l

l l 2.75E-02 2.73E.02 0.00E+00 0

...............................................l...........l...........l..00E+00l ........

IODINES I

I.133 CURIES j 2.73E-03 3.73E-03 0.00E+00 0.00E+00 I.131 CURIES l 1.65E.04 2.15E.04 0.00E+00 0.00E+

TOTAL FOR PERIOD CURIES 00 ....

l l 2.89E-03 3.95E-03 0.00E+00 0.00E+

...............................................l...........l...........l......00l ....

PARTICULATES I-131 CURIES 0.00E+00 SR.89 1.17E.06 0.00E+00 0.00E+00 CURIES 4.78E.06 3.08E-06 0.00E+00 0.00E+00 f-~g SR.90 CURIES 2.33E-10 1.73E-07 0.00E+00 g

A .....................................................................

TOTAL FOR PERIOD CURIES 0.00E+00 ..........

l l 4.78E-06 l 4.43E-06 0.00E+00

..........................................................l...........l.0.00B+00 ..........

l G-ALPHA j CURIES 3.64E-07 5.79E-07 H-3 0.00E+00 0.00E+00

' CURIES 7.46E-01 1.16E+00 0.00E+0

........................... ..................................... 0 s

0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.

There are no batch mode radioactive gaseous release pathways at Plant Hatch.

i I

To e e

51 l

I

I TABLE 2 3A* '

E. I. NATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Ground Level Releases i

\ Unit: 1

{J y Starting : 1-Jul.1998 Ending : 31-Dec-1998

{

CONTINUOUS MODE

................................................................................l NUCLIDES RELEASED l UNIT l l BATCH MODE **

l QUARTER 3 l QUARTER 4 l QUARTER 3 4

.....................................................................lQ.UARTER ..........

l j

i FISSION GASES i l

XE-135 CURIES 3.688+00 2.40E.02 0.00E+00 XE.133 0.00E+00 CURIES 0.00E+00 3.14E-02 0.00B+00 0.00E+

TOTAL POR PERIOD CURIES 00 ....

t l l 3.68E+00 l 5.54E-02 0.00E+00 0.00E+ 00 l

..........................................................l...........l...... ....

l IODINES I-133 CURIES 2.85E-03 2.878 03 I.131 0.00E+00 0.00E+00 CURIES 1.70E-04 1.545 04 0.00H+00 0.00E+0 TOTAL _FOR PERIOD' CURIES 0 ...

l l 3.02E-03 3.02E-03 0.00E+00

...............................................l...........l...........l..00E+00l 0 PARTICULATES SR.89 CURIES 2.48E-06 SR-90 1.77E-05 0.00E+00 0.00E+00

,s j CURIES 9.11E.10 1.92E-11

....................................................................... 0.00E+00 00E+00 0

\ TOTAL FOR PERIOD CURIES l l 2.48E-06 l 1.77E.05 0.00E+00 0.00

..........................................................l...........l.....E+00 ......

l G. ALPHA CURIES .4.95E-07 H.3 4.90E-08 0.00E+00 0.00E+00 CURIES 3.09E+00 1.62E+00 0.00E+00

..................................................................... 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2 7 for typical minimum detectable concentrations.

There are no batch mode. radioactive gaseous release pathways at Plant Hatch.

?" -

l - .

52-

F l

TABLE 2-3B2 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

[~~

Gaseous Effluents-Ground Level Releases

' Unit: 2 Starting : 1-Jan-1998 Ending : 30-Jun-1998 CONTINUOUS MODE BATCH MODE **

................................................................................l NUCLIDES RELEASED l UNIT l l l QUARTER 1 lQUARTRR 2 l QUARTER 1 2

.....................................................................lQ.UARTER ..........

l IODINES I.133 CURIES 6.09E-02 9.98E-02 0.00E+00 0.00E+00 I-131 CURIES 2.80E-03 4.33E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l l 6.37E.02 l 1.04E.01 l 0.00E+00 0.00E+00

..................................................................:..l...........l PARTICULATES I.131 CURIES 3.15E-04 3.845 04 0.00E+00 BA.140 0.00E+00 CURIES 5.70E-04 6.275-04 0.00E+00 0.00E400 CE.141 CURIES 2.09E.05 2.48E.05 0.00E+00 SR-89 0.00r+00 CURIES 2.778-04 -3.49E-04 0.00E+00 0.00E+00 SR.90 CURIES 9.87E.07 3.50E.06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.18E-03 l 1.39E-03 0.00E+00 0.00E+00

..........................................................l...........l...........l

, G ALPHA CURIES 7.00E.07 6.27E-07 0.00E+00 H-3 0.00B+00 l CURIES 3.61E+00 5.25E+00 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical mininum detectable concentrations.

There are no batch mode radioactive gaseous release pathways at Plant Hatch.

53

TABLE 2 3B$

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1 / Gaseous Effluents. Ground Level Releases I 5

Unit: 2 !

Starting i 1-Jul-1998 Ending : 31-Dec-1998 l

.l CONTINUOUS MODE

..........................................................l......................l NUCLIDES RELEASED l UNIT BATCH MODE **

l l QUARTER 3 l QUARTER 4 3

..........................................................lQ.UARTER l QUARTER 4 l

)

l FISSION GASES 1 XE 133 l CURIES l 1.64E+01 l 0.00E+00 0.00E+00 0.00

..........................................................l...........l.....E+00l TOTAL FOR PERIOD CURIES l l 1.64E+01 l 0.00E+00 0.00E+00 0.00E+0 0 l

..........................................................l...........l....... ...

IODINES' I-133 CURIES 9.33E-02 8.01E-02 I-131 0.00E+00 0.00E+00 CURIES 4.55E-03 3.37E-03 0.00E+00 0.00E+0 TOTAL FOR PERIOD CURIES 0 ...

l l 9.78E-02 l 8.34E-02 0.00E+00 0.00E+00

..........................................................l...........l...........l PARTICULATES I-131 CURIES 3.35E.04 3.84E-04 0.00E+00 0.00E+00 BA-140 CURIES 6.15E.04 2.625 04 0.00E+00

/~'g CE-141 0.00E+00 CURIES 3.22E.05 2.44E-05 0.00E+00

-( ) SR-89 SR-90 CURIES CURIES 2.658 04 3.25E-06 1.77E-04 2.14E.07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR' PERIOD l CURIES l 1.25E 03 l 8.47E-04 0.00E+00 0.00E+00

..........................................................l...........l...........l G-ALPHA CURIES 2.96E-07 1.72E-08 H-3 0.00E+00 0.00E+00 CURIES .5.49E+00 4.53E+00 0.00E+00- 0.00E+

........................................................................... 00 ....

Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.

There are no batch mode radioactive gaseous release pathways at Plant Hatch.

I

\

$4

b m

l 4 TABLE 2 3C* l E. I. HATCH NUCLEAR PLANT 4 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT j t

Gaseous Effluents Ground Level Releases Unit Site

[')h

(,, Starting : 1-Jan-1998 Ending : 30-Jun-1998 j

I i

i CONTINUOUS MODE

................................................................................l NUCLIDES RELEASED UNIT l l BATCH MODE ** ,

................................................................................l l l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l FISSION GASES !

XE-135 CURIES l l 2.75E-02 l 2.73E-02 l 0.00E+00 l 0.00E+00

................................................................................l l TOTAL FOR PERIOD CURIES l l 2.75E-02 l 2.73E-02 l 0.00E+00 0.00E+00

.....................................................................l...........l l 1

1 IODINES 1 1

I-133 CURIES 5.36E-02 1.04E-01 0.00E+00 0.00E+00 a I-131 CURIES 2.97E.03 4.55E-03 0.00E+00 0.00E+00 l

................................................................................ j TOTAL FOR PERIOD CURIES l 6.66E-02 l 1.08E-01 l 0.00E+00 0.00E+00

.....................................................................l...........l l l i

PARTICULATES l y

................................................................................ j I-131 CURIES 3.15E-04 3.85E-04 0.00E+00 0.00E+00 BA.140 j CURIES 5.70E-04 6.27E-04 0.00E+00 0.00E+00

- [~' CE-141 CURIES 2.09E 05 2.48E-05 0.00E+00 0.00E+00 1

l

( SR-89 SR-90 CURIES 2.81E.04 3.52E-04 0.00E+00 0.00E+00 CURIES 9.87E-07 3.67E.06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.19E-03 l 1.39E-03 l 0.00E+00 0.00E+00

.....................................................................l...........l G-ALPHA CURIES 1.06E-06 1.21E-06 0.00E+00 0.00E+00 H-3 CURIES 4.36E+00 6.41E+00 0.00E+00 0.00E+00 2eroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.

There are no batch mode radioactive gaseous release pathways at Plant Hatch.

,/~'T.

%s I

55

l l TABLE 2 3C8 E. I. HATCH NUCLEAR PLANT ANNUE RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Ground Level Releases

!O lV Starting.:

Unit Site 1.Jul.1998 Ending : 31-Dec.1998 CONTINUOUS MODE

................................................................................l NUCLIDES RELEASED l UNIT l l BATCH MODE **

l QUARTER 3 l QUARTER 4 l QUARTER 3 4 f .....................................................................lQ.UARTER ..........

l FISSION GASES XE.135 CURIES 3.68E+00 2.408 02 0.00E+00 XE-133 0.00E+00 CURIES 1.64B+01 3.14E-02 0.00E+00 0.00E+

TOTE FOR PERIOD CURIES 00 .... !

l l 2.01E+01 l 5.545-02 0.00E+00 0.00E+00 l

..........................................................l...........l...........l IODINES I.133 CURIES 9.61E-02 8.29E-02 0.00E+00 I-131 0.00E+00 CURIES 4.72E-03 3.53E 03 0.00E+00 0.00E+00 TOTE FOR PERIOD l CURIES l 1.01E-01 l 8.65E-02 0.00E+00 0.00E+00

..........................................................l...........l...........l PARTICULATES I-131 CURIES 3.35E.04 3.84E-04 0.00E+00

^ BA.140 0.00E+00 CURIES 6.15B-04 2.628-04 0.00E+00 0.00E+00

( CE.141 CURIES 3.22E-05 2.44E.05 0.00E+00 0.00E+00

\ SR-89 CURIES 2.68E-04 1.94E.04 0.00E+00 0.00E+00 SR-90 CURIES 3.25E-06 2.14H.07 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.25E.03 l 8.65E-04 0.00E+00 0.00E+00

..........................................................l...........l...........l G. ALPHA CURIES 7.91E.07 6.62E-08 H-3 0.00E+00 0.00E+00 CURIES 8.58E+00 6.15E+00 0.00B+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2 7 for typical minimum detectable concentrations.

There are no batch mode radioactive gaseous release pathways at Plant Hatch.

(3 56 i

l l

TABLE 2-4A j E. I. NATCH NUCLEAR PLANT '

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 ,

AIR DOSES DUE TO GASEOUS RELEASES i Unit 1

\ Starting: 01-Jan-1998 Ending: 30-Jun-1998 l i

i I

Cumulative Doses per Quarter

)

Type Tech Units Quarter % of Quarter t of of Spec 1 Tech 2 Tech Radi- Limit Spec Spec ation Limit Limit Ganma 5.0 mrad 1.38E-03 2.75E-02 {

6.67E-04 1.33E-02 i Beta 10.0 mrad 2.56E-03 2.568-02 1.26E-03 1.26E-02 I

-Cumulative Doses per Year Type Tech Units Year to % of :

of Spec Ending Tech '

Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 2.04E-03 2.04E-02 Beta 20.0 mrad 3.82E-03 1.91E-02 '

U u

i I

i i

I l

l.

\

)

57 l l

l l

r i

TABLE 2 4A E. I. HATCH NUCLEAR PLANT l

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 l [s) AIR DOSES DUE TO GASBOUS RELEASES Unit 1 C/ Starting: 01-Jul-1998 Ending: 31-Dec-1998 l

Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 3 Tech 4 Tech Radi. Limit Spec Spec ation Limit Limit Gansna 5.0 mrad 3.10E-03 6.20E-02 6.27E-04 1.25E-02 Beta 10.0 mrad 3.71E-03 3.71E-02 2.06E-03 2.06E-02 I

i Cumulative Domes per Year Type Tech Units Year to % of of Spec Ending Tech Radi. Limit Date Spec l

l ation Limit '

Gamma 10.0 mrad 5.77E-03 5.77E-02 Beta 20.0 mrad 9.58B 03 4.79E-02

(

58

TABLE 2-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2

\ Starting: 01-Jan-1998 Ending: 30-Jun-1998 l Cumulative Domes per Quarter l Type Tech Units Quarter % of l Quarter % of i of Spec 1 Tech 2 Tech j Radi- Limit Spec Spec '

ation Limit Limit Garna 5.0 mrad 1.36E-03 2.73E-02 6.53E-04 1.31E-02 Beta 10.0 mrad 2.54E.03 2.54E-02 1.24E-03 1.24E-02

[

i

.......................................................................... l I 1

\

Cumulative Doses per Year Type Tech Units Year to % of '

of Spec Ending Tech Radi. Limit Date Spec ation Limit a;;;;"""i;:o""m;;r ^";;;;E:;;-" ;;;;;:a;"""""""""" ""-

Beta 20.0 mrad 3.78E.03 1.89E

..............................................-02 ............................

(

I

(

l i

i i

59 !

(_.

TABLE 2-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOAC"fIVE EFFLUENT RELEASE REPORT - 1998 r AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01 Jul-1998 Ending: 31-Dec-1998 ;

1 l

Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 3 Tech 4 Tech l Radi. Limit Spec Spec ation Limit Limit Ganrna 5.0 mrad 2.63E-03 5.26E-02 2.93E-04 5.85E-03 Beta 10.0 mrad 5.34E-03 5.34E-02 6.88E-04 6.88E-03 r

1 Cumulative Doses per Year

.......................................................................... (

Type Tech Units Year to % of i

of Spec Rnding Tech Radi- Limit Date Spec i ation Limit I Gama 10.0 mrad 4.94E-03 4.94E-02 Beta 20.0 mrad 9.81E-03 4.91E-02

\

1 O

i\

. N I

w

%,4 60

l TABLE 2-5A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Q Starting: 01-Jan-1998 Units 1 Ending: 30 Jun-1998 Cumulative Dosos per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 7.5 mrom 3.42E-04 4.56E-03 3.87E-04 5.16E-03 Liver 7.5 mrem 4.258-04 5.67E-03 6.*538-04 TBody 8.71E-03 7.5 mrom 4.31E-04 5.75E-03 6.75E-04 9.00E-03 Thyroid 7.5 mrem 6.98E-03 9.315 02 1.00E-02 1.34E 01 Kidney 7.5 mrom 4.39E-04 5.86E-03 6.76E-04 9.01E-03 Lung 7.5 mrem 4.01E-04 5.34E-03 6.18E-04 GILLI 8.24E-03 7.5 mrom 4.16E-04 5.55E-03 6.35E-04 8.46E 03 Cumulative Doses per Year Or9an Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mrom 7.29E-04 4.86E-03 Liver 15.0 mram 1.08E-03 7.19E-03 TBody 15.0 mrem 1.11E.03 7.37E-03 Thyroid 15.0 mram 1.70E.02 1.13E-01 Kidney 15.0 mrom 1.11E-03 7.43E-03 Lung 15.0 mram 1.02E-03 6.79E 03 GILLI 15.0 mrem 1.05E 7.01E-03

-.................................-03 ........................................

O I

s 61

f 1

TABLE 2-5A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 i DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM,

/7 AND PARTICULATES IN GASEOUS RELEASES l

(- ') Starting: 01-Jul.1998 Unit 1 Ending: 31-Dec-1998

{

)

I 4

Cumulative Doses per Quarter 1

Organ Tech Unit Quarter % of Quarter % of i Spec 3 Tech 4 Tech Limit Spec Spec {

j Limit Limit !

Bone 7.5 mram 2.22E-04 2.96E-03 3.00E-04 4.01E-03 Liver 7.5 mram 1.66E-03 2.21E-02 8.75E-04 1.17E-02 TBody 7.5 mram 1.66E-03 2.21E-02 8.64E-04 1.15E-02 Thyroid 7.5 mram 1.05E-02 1.41E 01 6.80E-03 9.07E-02 3 Kidney 7.5 mram. 1.68E-03 2.24E-02 8.89E-04 1.19E-02 i

Lung 7.5 mram 1.62E-03 2.16E-02 8.56E-04 1.14E-02 )

GILLI 7.5 mram 1.63E-03 2.18E-02 8.69E-04 1.16E-02 i Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mram 1.25E-03 8.34E 03 f

c. Liver 15.0 mram 3.61E-03 2.41E-02 TBody 15.0 mram 3.63E-03 2.42E-02 ks- Thyroid 15.0 mram 3.43E-02 2.29E-01 Kidney 15.0 mram 3.68E-03 2.45E-02 Lung 15.0 mrem 3.50E-03 2.33E-02 GILLI 15.0 mrem 3.55E-03 2.37E-02 1

1

\

V 62

F ]

TABLE 2-5B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE BFFLUENT RELEASE REPORT - 1998 l j

l DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, j[ AND PARTICULATES IN GASBOUS RELEASES I 1

i \s_/

Unit 2 j

Starting: 01-Jan-1998 Ending: 30-Jun-1998 l

l Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter t of Spec 1 Tech 2 Tech i Limit Spec Spec Limit Limit Bone 7.5 'mram- 3.81E-03 5.08E-02 5.64E-03 7.52E-02 Liver 7.5 mrom 2.27E-03 3.03E-02 3.36E-03 4.48E-02 1

TBody 7.5 mram 2.28E-03 3.03E-02 3.50E-03 4.67E-02 Thyroid mrem

)

7.5 8.355-02 1.11E+00 1.33E-01 1.77E+00 '

Kidney 7.5 mram 2.49E-03 3.32E-02 3.71E-03 4.94E-02 Lung 7.5 mram 2.10E-03 2.80E-02 3.02E-03 4.02E 02 GILLI 7.5 mrem 2.17E 03 2.89E-02 3.15E-03 4.20E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec *nding Tech Limit Date Spec Limit Bone 15.0 mram 9.15E-03 6.30E-02

(

Liver TBody 15.0 15.0 mram mram 5.63E-03 5.78E-03 3.75E-02 3.85E-02 Thyroid 15.0 mram 2.16E-01 1.44E+00 Kidney 15.0 mrem 6.20E 03 4.13E-02 Lung 15.0 mram 5.12E-03 3.41E-02 GILLI 15.0 mram 5.32E-03 3.54E-02 l

,O v i l

63 I

t-l -- J

t i

TABLE 2-5B E. I. HATCH NUCLEAR PLANT ]

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 j p\

DOSES TO A MEMBER OF THE PUBLIC DUE 'lV RADIOIODINES, TRITIUM, j

' 'sj AND PARTICULATES IN GASEOUS RELEASES Unit 2 Starting: 01 Jul 1998 Ending: 31-Dec 1998 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Spec Quarter % of 3 Tech 4 Tech Limit Spec Spec Limit

....................................................................t Bone 7.5 mrom 4.59E-03 6.12E 02 Limi Liver 2.40E 03 3.20E-02 7.5 mrem 3.47E-03 4.62E-02 2.84E-03

TBody 3.79E-02 7.5 mrem 3.56E-03 4.75E-02 2.68E-03 3.58E-02 Thyroid 7.5 mrom 1.32E-01 1.76E+00 Kidney 1.03E-01 1.37E+00 7.5 mrem 3.81E 03 5.08E 02 3.11E-03 4.15E-02 Lung 7.5 mrem 3.12E-03 4.16E-02 GILLI 2.51E-03 3.35E-02 l 7.5 mrem 3.22E-03 4.30E-02 2.61E-03

............................................................... 3.48E-02 ..........

l Cumulative Doees per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 15.0 mrom 1.64E 02 1.10E-01 p Liver TBody 15.0 mram 1.19E 02 7.96E-02 15.0 mrem 1.20E-02 8.02E-02 Thyroid 15.0 mrem 4.51E 01 3.00E+00 Kidney 15.0 mrom 1.31E-02 8.75E-02 Lung 15.0 mrem 1.07E-02 7.16E.02 GILLI 15.0 mrem 1.12E-02 7.44E-02 l

l l

1 f

(

l 64

TABLE 2-7 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANAL YSES E. I. HATCH NUCLEAR PLANT

.lANUARY,1996 THROUGH DECEMBER,1998 The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 2.94E-08 uCl/cc Kr-88 3.22E-08 uCl/cc Xe-133 2.30E-08 uCi/cc Xe-133m 7.30E-08 uCi/cc Xe-13S 8.73E-09 uCl/cc Xe-138 1.99E-07 uCi/cc l-131 1.34E-13* uCl/cc l-133 1.53E-13* UCl/cc Mn-54 1.62E-13* uCi/cc Fe-59 3.42E-13* uCl/cc Co-58 1.30E-13' UCl/cc Co-60 1.54E-13* uCl/cc Zn-65 2.54E-13* uCl/cc Mo-99 9.61 E-13* uCi/cc Cs-134 1.42E-13* uCl/cc Cs-137 1.28E-13* uCl/cc Ce-141 1.26E-13* UCl/cc Ce-144 5.64E-13* uCl/cc Sr-89 1.10E-16 uCl/cc Sr-90 6.70E-16 uCi/cc H-3 4.00E-07 uCl/cc

Based on an estimated sample quantity of 4.07BE+07 cc's.

55

)

3.0 Solid Waste 3.1 Regulatory Limits /ODCM The ODCM Limits presented in this section are for Unit 1 and Unit 2 and are stated in part.

3.1.1 Solid Radioactive Waste System A.3.1 Solid Radioactive Waste System control states:

The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure that they meet requirements of 10 CFR Parts 20 and 71, prior to shipment of radioactive wastes from the site.

3.1.2 Reporting Requirements Technical Specification 5.6.3 Th 3 Radioactive Effluent Release Report covering the operation of the unit shall n

,U be submitted in accordance with 10 CFR 50.36a. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1,Section IV.B.1.

3.1.3 Process Control Program (PCP)

A.4.1 states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shallinclude a summary of the quantities of solid radwaste reisased from the units as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of -

Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a 6 month basis following the format of Appendix B thereof.

O a

tG For each type of solid radwaste shipped offsite during the report period, the report V shall include the following information:

a. Container volume.

b. Total curie quantity (specify whether determined by measurement or estimate).

c. Principal radionuclides (specify whether determined by measurement or estimate).

d. Type of waste (such as spent resin, compacted dry waste, evaporator l bottoms). l

e. Type of container (such as LSA, type A, type B, large quantity).

f. Solidification agent (such as cement).

Major changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed and accepted by the PRB.

3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1 A and 3-1B.

67

,O EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 O JANUARY 1,1998 - DECEMBER 31,1998 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS i AND ll 1 TABLE 3 IA SEMI ANNUAL REPORT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l l

PERIOD COVERED: FROM i / i / on TO 6 / 10 / 9R FOR UNIT: ONE & TWO A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) l

1. Type of waste UNIT 6 month Est. Total period ERROR %

a. Spent resms, filter sludges, evaporator m' 6.8776 E I bonoms. etc. Ci 5.7192 E 1 1.0 E 1

b. Dry compressible waste, contaminated equip. m' 3.6165 E 1 etc. Ci 2.6920 E 1 2.0 E 1

c. Irradiated components, control rods, m' E Ci E E

d. Control Rod Drive Filters m' E Ci E E

e. Other (describe) m' E

_ equip. etc. Ci E E g 2. Estimate of mWor nuclide composition (by type of waste)

(

ISOTOPE PERCENT CURIES a.Fe 55 34.98 20.004I Co-60 23.11 13.2174 Zn-65 20.80 11.8963 Mn 54 4.49 2.5679 Other 16.62 9.5063 b.Fe-55 53.73 .1446 Co-60 12.81 .0344 Zn-65 10.68 .0288 Cr 5I i1.39 .0307 Other i1.39 .0307

c. -

d.

e.

~

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 12 Truck Barnwell B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shinments Mode of Transnortation Destination 0 N/A N/A 68

l f

7- s V) t EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 JANUARY 1,1998 - DECEMBER 31,1998 i SOLID WASTE AND IRRADIAsTED FUEL SHIPMENTS FOR UNITS I AND ll TABLE 3-IA (Cont'd) 8 SEMI-ANNUAL REPOAT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD COVERED TROM 07/01/1998 TO 12/31/1998 TOR UNIT One and Two A.

SOLID WASTE SHIPPED OFFSITE FOR BURIfd. OR DISPOSAL (Not irradiated fuell

1. Type of waste UNIT 6 month Est. s period Total I ERROR 4

a. Spent resins, filter sludges, evaporator m3 8.01E 01 .

bottoms, etc. C1 1.69E 02 1.0 E1 I

b. Dry compressible waste, contaminated equip. m3 6.85E 01 etc. C1 1.11E 01 2.0 El

c. Irradiated components, control roda, m' E

_ l C1 E E

d. Control Red Drive T11ters m3 E Ci E E

e. Other (describe) m' E equip. etc. Ci E E

2. Estimate of major nuclide composition (by type of waste)

ISOTOPE PERCENT CURIES e e.En=65 17.68 29.88 f

re-55 35.70 60.33

( Co-60 19.59 33.11 Mn-54 3.31 5.60 other 23.77 40.17 b.En 10.20 1.14 Fe-55 60.47 6.14 Co-60 19.33 2.15 Mn-54 5.34 0.60 Other 4.66 0.52 c.

d.

d Y$ .

3. Solid waste Dispoattion Number of Ehipments Mode of Transportation Destination 15 Tractor and Trailer Barnwell B. 17JLADIATED TUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A O

d 69

G O EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 JANUARY 1,1998 - DECEMBER 31,1998 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND ll TABLE 3-IB FORM TITLE:

OFFSITE DOSE CALCUIATION MANUAL, SECTION 7.2, REPORT PERIOD COVERED FROM: 1 /1 /M TO: 6 /M /M FOR UNIT: ONE&TWO OF ANTITY/ NUCI ESI CONTAINER CONT / NT WASTE DETERMINED DETERMINATION DESCRIPTION SHIFFED COPrTAINER CONTAINER CUBIC FRET FT 3)

Dewensed 57.192 Fe-55, Za45 High 12 202.1 Type A n/a Reses Co40, h 54 inengnty Cask Canamner 14-210 Dry Acuve .2692 Feo5, Zn45 soong 44 912 Soong s's Wasse Ce40,Cr 51 Tight Tight O Contaener B-25 Box B-25 i

70

r l

l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 JANUARY 1,1998 - DECEMBER 31,1998 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND 11 TABLE 3-IB (Cont'd)

FORM TITLE:

OFFSITE DOSE CALCUIATION MANUAL, SEC"fION 7.2, REPORT PERIOD C. OVERED FROM: 07 101/98 TO: 12/31/98 FOR UNIT: ONE AND TWO Type Cume PiuMCrAL sumAL NuussR op vowum op Type op soumPiCAnoN ouAsmTYt u er meni CoNTAmeR CoNTA5dERs EACH SHrtIENTI AGENT waste ostuRanNec cateRanNADoN DESCRPnoN SHFPED CofffAINER CoNTABIER Cusc PasT iPT Si commened See 2nes, Peas,Ce40 High hemyNy 14 382.1 % "A* Cesk 8014 Resen. un4s Co m aner wateH ory 1.14 2f>4sfe48,Ce40 Sweng fight 8 SS S HA Strong Tight selA Asen cr41 Comennare Ceneminers Wesee "* S:

l 5 m) pry Asesse 10 4 an48.Pe.as,Co.co High enemymy i

1 tas.4 Type *A* Caen sen I tumses M Ceneminor 14410h !

(Terus Pillers)

Note: The actual size and number of containers for Dry Active Waste may vary from the recorded values due to the use of different containers by waste processors.

4 O'

71

l I

1 4.0 Changes to the ODCM j

Pursuant to Technical Specification 5.5.1 and ODCM section 7.2.2.5 Licensee initiated changes shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

There were no changes for this period.

5.0 - Doses to Members of the Public inside the Site Boundary The Radioactive Effluent Release Report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with the ODCM.

The locations of concern within the site boundary are the Roadside Park, the Camping Area, the Recreation Area, and the Visitors Center. Listed in Table O 4-1 are: The distance and direction from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the Main Stack (elevated)and from the reactor building (ground level); and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.

The source term is not listed in Table 4-1. The source term is listed in Tables 2-2A and 2-2B, for the elevated releases. Similarly, it is listed in Tables 2-3A and 2-3B for the ground level releases.

The maximum doses in units of mrem accumulated by an individual MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period are presented in Table 4-1.

O 72

1 TABLE 4 1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSE TO A MEMBER OF THE PUBLIC n )

DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site (V . Starting: 01-Jan-1998 Ending: 30-Jun-1998 l l

Page: 1 Location Name ROADSIDE PARK Distance (kilometers) 1.18E+00 4 Sector WNN Occupancy Factor 2.28E-04 (2.00E+00 hr/yr)

Age Group CHILD l

Ground Level Releases:

Noble Gas X/Q (sec/m3) 7.83E-06 Particulate X/Q (sec/m3) 7.00E-06 Particulate D/Q (m-2) 2.018 08 l Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A j Particulate X/Q (sec/m3) N/A Particulate D/Q (m 2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 2.42E-08 l Particulate X/Q (sec/m3) 2.37E-08 Particulate D/Q (m-2) 1.29E-09 '

)

............................................................................. l Units Quarter 1 Quarter 2 Quarters Year to l l

l 1 and 2 Ending

' Date i Bone mrem 7.87E-07 4.41E-07 1.23E-06 3

1.23E-06 Liver mrem 1.03E-06 7.94E-07 1.83E-06 1.83E-06 TBody mram 9.89E-07 7.24E-07 1.71E-06 1.71E-06 Thyroid mrem 1.59E-05 2.47E-05 4.05E-05 4.05E-05 Kidney mrem 1.08E-06 8.72E-07 1.95E-06 1.95E 06 l Lung mrem 1 04E-06 7.73E-07 l 1.82E-06 1.82E-06 1

GI-LLI mrem 9.83E 07 7.12E-07 1.69E-06 1.69E-06 l l

, I j a l

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4 I

' C.)%

I

! 73 5.

i i i

I TABLE 4-1 j E. I. HATCH NUCLEAR PLANT '

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 i

' DOSE.TO A MEMBER OF THE PUBLIC 1;

DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site i\%' Starting: 01-Jan-1998 Ending: 30-Jun-1998 !'

Page 2 Location Name CAMPING AREA Distance (kilometers) 1.27E+00 Sector NNW Occupancy Factor 5.48E-03 (4.80E+01 hr/yr)

Age Group CHILD j

i Ground Level Releases: A Noble Gas X/Q (sec/aG) 7.03E-06 4 Particulate X/Q (sec/m3) 6.27E-06 l

Particulate D/Q (m-2) 1.80E-08 i Mixed Mode Releases:

Noble Gas X/Q (sec/nG) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A i Elevated Releases:

Noble Gas X/Q (sec/m3) 2.38E-08 Particulate X/Q (sec/m3) 2.33E-08 i Particulate D/Q (m.2) 1.21E-09 !

Units Quarter 1 Quarter 2 Quarters Year to

f-wg- f l

1 and 2 Ending (

l

..............................................................te Bone mram 1.75E-05 9.70E-06 Da 2.728-05 2.72E-05 Liver mram 2.28E 05 1.73E-05 4.01E-05 TBody mram 2.19E-05 4.01E-05 l 1.58E-05 3.77E-05 3.77E-05 Thyroid mram 3.43E-04 5.31E-04 8.74E-04 i

Kidney mrem 8.74E-04 2.385-05 1.90E-05 4.28E-05 4.28E-05 Lung mrem 2.30E-05 1.69E-05 3.998-05 GI-LLI mram 3.99E 05

! 2.17E-05 1.55E-05 3. 73 E- 05 t

............................................................. 73E-05 3

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l TABLE 4-1 !

E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSE TO A MEMBER OF THE PUBLIC O\ DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-1998 Ending: 30-Jun-1998 )

Page: 3 l Location Name RECREATION AREA Distance (kilometers) 1.03E+00 ;

l Sector SSE

Occupancy Factor 2.37E-02 (2.08E+02 hr/yr)

Age Group CHILD 1

[

Ground Level Releases:

Noble Gas X/Q (sec/m3) 6.42E-06 Particulate X/Q (sec/m3) 5.73B-06

) Particulate D/Q (m 2) 2.36E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 3.30E-08 Particulate X/Q (sec/m3) 3.21E 08 Particulate D/Q (m-2) 1.56E-09

['"% Units Quarter 1 Quarter 2 Quarters Year to

! ( ,) 1 and 2 Ending

' Date Bone mram 7.15E-05 4.07E-05 1.12E-04 1.12E 04 Liver mram 9.24E-05 7.08E-05 1.63E-04 1.63E-04 TBody mram 8.87E-05 6.48E-05 1.54E-04 Thyroid 1.54E-04 mram 1.36E-03 2.10E-03 3.46E-03 3.46E-03 Kidney mram 9.65E-05 7.74E-05 t

Lung 1.74E-04 1.74E-04 mram 9.32E-05 6.90E-05 1.62E-04 1.62E-04 GI-LLI mram 8.82E-05 6.388-05 1.52E-04 1

............................................................. 52E-04 ...............

S

\

N 75 L-

l' TABLE 4 1 E. I. HATCH NUCLEAR PLANT .

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 l g DOSE TO A MEMBER OF THE PUBLIC '

I p>

DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY i Unit Site Starting: 01-Jan-1998 Ending: 30-Jun-1998 Page: 4 Location Name VISITORS CENTER Distance (kilometers) 6.94E-01 Sector WSW Occupancy Factor 4.57E-04 (4.00E+00 hr/yr) l Age Group CHILD i

Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.87E-05 l

Particulate X/Q (sec/zG) 1.72E-05 '

j i

Particulate D/Q (m-2) 5.47E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A l Particulate X/Q (sec/m3) N/A

(' Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 5.00E-08 l Particulate X/Q (sec/m3) 4.978-08 i Particulate D/Q (m 2) 2.26E-09 i Units Quarter 2 Quarter 2 Quarters Year to l

! ' 1 and 2 Ending Date Bone mrem 3.00E-06 1.85E-06 4.85E-06 4.85E-06 Liver mram 4.20E-06 3.59E-06 7.80E-06 7.80E-06 TBody mrem 3.99E-06 3.25E-06 7.24E-06 7.24E-06 Thyroid mram 7.73E-05 1.21E-04 1.98E-04 1.98E 04 Kidney mram 4.44E-06 3.98E-06 8.42E-06 8.42E-06 i Lung mrem 4.25E 06 3.49E-06 7.748-06 7.74E-06 GI mrem 3.96E-06 3.19E-06 7.15E-06

...-LLI 7.15E-06

.......................................................................... j l

1 l

1 i

i 4

4 j

l vO 1 76

TABLE 4 1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSE TO A MEMBER OF THE PUBLIC

,V DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-1998 Ending: 31-Dec-1990 Page: 1 Location Name ROADSIDE PARK Distance (kilometers) 1.18E+00 Sector WNW Occupancy Factor 2.28E-04 (2.00E+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 7.83E-06 Particulate X/Q (sec/m3) 7.005-06 Particulate D/Q (m-2) 2.01E-08

Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 2.42E-08 Particulate X/Q (sec/m3) 2.37E-08 Particulate D/Q (m-2) 1.29B-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending

..............................................................te Bone mrem 1.37E-06 3.74E-07 Da 1.75E-06 2.98E 06 Liver mrom 1.89E-06 6.95E-07 2.58E 06 4.41E-06 TBody mram 1.82E-06 6.43E-07 2.46E-06 Thyroid mrom 4.18E 06 2.58E-05 1.82E 05 4.40E-05 8.45E-05 Kidney mram 1.97E-06 7.52E-07 2.72E-06 Lung mrom 1.87E-06 4.67E-06 6.47E-07 2.51E-06 4.33E-06 GI mrem 1.81R-06 6.33E-07 2.44E 06 13E-06

....-LLI.........................................................4 ........... ,,.

):

77 g .

V TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSE TO A MEMBER OF THE PUJ" IC DUE TO ACTIVITIES INSIDE THE SITF BOUNDARY O Starting: 01-Jul-1998 Unit: Site Ending: 31-Dec-1998

Page: 2

, Location Name CAMPING AREA Distance (kilometers) 1.275+00 Sector WNW Occupancy Factor 5.48E-03 (4.80E+01 hr/yr)

Age Group CHILD l

, Ground Level Releases:

i Noble Gas X/Q (sec/m3) 7.03E-06 Particulate X/Q (sec/m3) 6.27E-06 Particulate D/Q (m 2) 1.80E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A

' Elevated Releases:

Noble Gas X/Q (sec/m3) 2.38E-08 i

Particulate X/O (sec/m3) 2.33E-08 l

Particulate D/Q (m-2) 1.21E-09 Units Quarter 3 Quarter 4 Quarters Year to l

l

! c 3 and 4 Ending If I Date i

l(/ .............................................................................

Bone mrem 3.01E-05 8.26E-06 3.83E-05 6.55E-05 Liver mrem 4.11E-05 1.52E 05 5.63E-05 9.64E-05 TBody mrom 3.978-05 1.41E-05 5.37E-05 9.14E-05 i

Thyroid nirem 5.55E-04 3.928-04 9.48E-04 1.82E-03 I

Kidney mrem 4.28E 05 1.64E 05 5.92E-05 1.02E-04 Lung l mrem 4.07E-05 1.41E-05 5.48E-05 9.47E-05 GI mram 3.94E-05 1.38E-05 5.32E-05 9.05E-05

...-LLI i

l t

l

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l l

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TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY

.[N-- Starting: 01 Jul-1998 Unit: Site Ending: 31-Dec-1998 Page: 3 Location Name RECREATION AREA Distance (kilometers) 1.03E+00 Sector SSE Occupancy Factor 2.37E-02 (2.08E+02 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 6.42E-06 Particulate X/Q (sec/m3) 5.73E-06 Particulate D/Q (m-2) 2.36E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 3.30E-08 )

Particulate X/Q (sec/m3) 3.21E-08 Particulate D/Q (m-2) 1.568-09 Units Quarter 3 Quarter 4 Quarters Year to n 3 and 4 Ending j

\,)}

c Date Bono mram 1.22E-04 3.44E-05 1.56E-04 2.68E-04 Liver mrem 1.65E-04 6.18E-05 2.27E-04 3.90E-04 TBody mrem 1.59E 04 5.73E 05 2.17E-04 3.70E-04 Thyroid mram 2.20E-03 1.55E-03 3.75E-03 Kidney 7.21E-03 mram 1.72E-04 6.66E-05 2.39E-04 4.13E-04 Lung mrem 1.63E 04 5.76E 05 2.21E-04 3.83E-04 l GI-LLI mram 1.58E-04 5.65E-05 2.15E-04 3.67E-04 i

j l

4 l

I v

79

TABLE 4-l' E. I. NATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1998 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY l' Unit: Site Starting: 01-Jul-1998 Ending: 31-Dec-1998 l

Page: 4 l

Location Name VISITORS CENTER Distance (kilometers) 6.94E-01 i Sector WSW i Occupancy Factor 4.57E-04 (4.00E+00 hr/yr)

, Age Group CHILD l

Ground Level Releases l

Noble Gas X/Q (sec/m3) 1.878-05 i

Particulate X/Q (sec/m3) 1.72E-05 Particulate D/Q (m-2) 5.47E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) N/A i

Particulate X/Q (sec/m3) N/A Particulate D/Q (m 2) N/A Elevated Releases:

Noble Gas X/Q (sec/m3) 5.00E-08

' Particulate X/Q (sec/m3) 4.97E-08 Particulate D/Q (m 2) 2.265-09 Units Quarter 3 Quarter 4 Quarters Year to i .t 3 and 4 Ending

\- Date.

Liver m;""";;;;;:6;""i:;ii:6;""';:i;;:6;""""i:;;;:6;""""-

mrem 8.51E-06 3.10E-06 1.16E-05 1.94E-05 TBody mrem 8.17E-06 2.84E-06 1.10E-05 Thyroid 1.82E-05 mrem 1.26E-04 8.94E 05 2.15E-04 4.14E-04 Kidney mrem 8.89E-06 3.38E-06 1.23E-05 2.07E-05 Lung mrem 8.39E-06 2.86E-06 mrom 1.12E-05 1.90E-05 GI-LLI 8.10E-06 2.79E-06 1.09E-05 1.80E-05 l

1 O

80 t

l l

l.

7 6.0 Major Changes to Liquid, Gaseous, and Solid Radwaste Treatment Systems (O

The Radioactive Effluent Release Report shallinclude. . . . any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to ODCM Chapter 7, Section 7.2.2.7.

Gaseous Radweste System There were no major changes to the gaseous radwaste system during this i reporting period.

Solid Radweste System There were no major changes to the solid radwaste system during this reporting l period.

Liquid Radweste System There were no major changes to the Liquid Radwaste Treatment System during this reporting period.

7.0 Meteorological Data The Radioactive Effluent Release Report, to be submitted by May 1 of each year, shall l Include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured), on magnetic tape, or, in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

1 in lieu of submission with the Radioactive Effluent Release Report, the licensee l

has retained this summary of required meteorological data on site in a file. It will be provided to the NRC upon request.

I 8.0 Inoperable Liquid or Gaseous Effluent Monitoring instrumentation ;

1 ODCM, Chapter 7, Section 7.2.2.6.2 states that the Radioactive Effluent Release !

Report shall include deviations from the liquid and gaseous effluent monitoring Instrumentation operability requirements included in sections 2.1.1 and 3.1.1, l respectively.

4 O !

81 i

l Unit 1 and Unit 2 Liquid Radwasta Manitors (1/2D11-K604)

Unit 1 and 2 Liquid Radwaste Effluent Monitors (1/2D11-K604) were declared out of O service for greater than thirty (30) days. A summary of the event and corrective action is as follows:

The monitors 1/2D11-K604 were declared out of service as a result of actions taken to address an NRC inspector concern, which was raised during an inspection conducted during December 1997. The concem was relative to the procedural adequacy of the source check of the Liquid Radwaste Effluent Monitor (LRW) prior to release, per the ODCM requirements of Table 2-2, footnote (e). Section 10.1 of the ODCM provides a definition for a source check, but footnote (e) to Table 2-2 was considered to provide an exemption to the definition as found in Section 10.1. Plant Hatch procedure (s), which implemented the requirement of the ODCM, utilized the methodology as provided for and as understood in the footnote. This was due to the fact, that, the LRW monitoring system does not have the provision to perform a source check prior to release. As a result of the concern and as a conservative measure the LRW monitor was administratively declared inoperable until such time the matter could be resolved.

AIT RC9800038, IFl 366/97-11-05, is the NRC item related to this item and is being referenced here for information purposes.

An investigation and root cause analysis was performed and it was determined that no deficiency exists. It was determined that the present method of source checking the LRW monitor prior to discharge was an approved and accepted method. Hence, the ODCM requirement was satisfied. Plant Hatch recognizes that a better method could

) be employed to satisfy the ODCM required source check, therefore, a procedure revision was implemented to change our methodology. The procedure revision i provides for a source check of the monitor consistent with the definition in Section 10.1. i The monitors were returned to service following the implementation of the new procedure revisions.

R V .

82 ,

9.0 Tanks Exceeding Curie Content Limits 3.15.1.4 (a): The contents within any outside temporary tank shall be limited to s; 10 curies, excluding tritium and dissolved or entrained noble gases.

There were no outside temporary tanks utilized during this reporting period.

l O

O-83

O SOUTHERN COMPANY l l

E. L HATCH NUCLEAR PLANT UNITS NO.1 & 2 l l

ANNUAL REPORT l JANUARY 1,1998 - DECEMBER 31,1998 APPENDIX A

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Relrass of Radienctiva RHR Servics Water from 1996 An analysis of samples from the Unit 1 RHR "B" Loop service water (RHRSW) system identified several radionuclides at very low concentrations. The first indication of O contamination was noted on August 8,1996 and the second indication was noted on August 23,1996. The total activity in the RHRSW contained within the heat exchanger, which has a volume of approximately 4000 gallons, was respectively estimated to be about 13.7 Ci and 25.6 Cl. On August 23,1996 repairs were made to a Ap instrument in an effort to stop the inleakage into the cervice water side of the heat exchanger. To determine if the leak had been repaired, the service water loop of the heat exchanger was decontaminated by flushing and the service water in the loop was then resampled and analyzed. The circulating water fiume has a blowdown line, which diverts a small portion of the total circulating water to the river via the discharge structure. This resulted in a release to an unrestricted area. Though this release was both monitored and controlled, it was not through the normally utilized liquid radwaste system but the release to the unrestricted area did in fact take the same release path !

to the river. The regulatory discreteness of this release is discussed in the 1996 evaluation of I

the release, which is documented in the 10CFR50.59 Evaluation titled " Unit 1 RHR Service i Water: Release of Contaminated Water." l The requirements of the Radioactive Effluent Controls Program are spelled out in TS 5.5.4.

The Offsite Dose Calculation Manual (ODCM) implements this program and it conforms to the i

requirements of 10CFR50.36a for the control of radioactive effluents and for maintaining the l doses as low as reasonable achievable. Compliance with TS 5.5.4 regarding liquid releases can be assured by adhering to the requirements of ODCM sections 2.1.2,2.1.3 and 2.1.4 which respectively provide limits on the concentration of the radioactive material at the point of release to an unrestricted area, the resultant dose to a member of the public from the release, and the necessity of using the radwaste treatment system.

MWO 1-96-02845 was worked during the Unit 1 outage to repair the leaks in the U1 RHR "B"

. Heat Exchanger. The RHR side of the Heat Exchanger was pressurized with helium and a ,

l helium detector on the RHRSW side was used to look for the presence of leaks. Based on this l it was determined that one of the outermost tubes (tube 1-1) was definitely leaking. No other l tubes were identified as definite leakers; however, the eight tubes closest to tube 1-1 were identified as possible leakers.

Integrated Technologies, Inc. performed an eddy current inspection of 245 of the tubes, I

including all of the suspected leakers and surrounding tubes. This inspection also identified tube 1-1 as a leaker. The tube breach is located next to the top support in the outlet leg. The cause is unknown. No other leaking tubes were identified.

l The conservative decision was made to plug the leaker as well as the eight surrounding tubes.

After plugging the tubes a hydrostatic pressure test was conducted at 300 psi and the Heat Exchanger was inspected for signs of leakage. No leakage was noted at this time. The Heat Exchanger was deconned, closed up and placed back in service. The Chemistry Department has sampled and monitored the activity during the operation of the Heat Exchanger.

U(3

Tha highest concentrations of the radionuclid:s found in the RHRSW samples for 1998 ara from February 9,1998. The total concentration released was 1.69 E-6 pCl/ml. The highest concentration of the radionuclides found in the RHRSW samples for 1997 are from March 4,1997. The total concentration released was 1.21 E-5 pCi/ml.

Radionuclide 1997 Concentration (pCi/ml) 1998 Concentration ( Ci/ml)

Mn-54 2.37 E-6 4.95 E-7 Co-60 4.94 E-6 1.12 E-6 Zn-65 2.06 E-6 7.96 E 8 Cr 1.07 E-6 Co-58 1.06 E-6 l

'Cs-134 2.10 E-7 :

Cs-137 4.43 E-7 I l

No new radionuclides have been identified and the analysis result indicates no new leaks to l the system. The results of the samples analyzed in 1998 indicate we are monitoring residual l contamination from the 1996 leaks.

ODCM section 2.1.2 requires that the concentrations of the radioactive materials released be limited to'10 times (10X) the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, with the exception for dissolved or entrained noble gases whose concentration shall l be limited to 1 E-4 Cl/ml.

The following discussion is based on a release duration of 1 minute, a release volume of 4,000 gallons, a total dilution of gnly 10,000 gallons, and the radionuclide concentrations from 1997. This is a very conservative estimate, since credit for the additional dilution provided by O the circulating water flume was not taken into consideration and the activity from 1997 was higher with more radionuclides. The sum of the ratios of the concentration of each ;

radionuclide in the mixture to its effluent concentration limit (ECL) was 1.15. The sum of the ECL fractions must be less than ten (<10) to ensure that the concentration limit for the mixture is not exceeded. As can be seen, the sum is much less that ten. (10CFR20 Appendix B states that the sum of the fractions of the nuclides divided by their effluent concentration limits (ECLs) must be less than one. Further NRC guidance, Technical Specifications, and the ODCM allow the ECLs in Appendix B to be increased by a factor of 10. Mathematically this can be achieved by dividing the nuclides by the original 10CFR 20 Appendix B ECLs and insuring that the sum of the fractions is less than 10. The plant software performs the sum of the ECL fractions and comparisons this way to insure compliance with 10CRF20 limits.)

ODCM section 2.1.3 requires that the annual dose to a member of the public, in unrestricted areas, due to liquid releases from each unit be limited to 3 mrem to the total body and 10 mrem to any organ. The dose in any quarter is limited to half of the annuallimits. Dose calculations were performed for this release, in accordance with ODCM section 2.4, to evaluate the doses relative to this release. The total body dose was 6.66 E-5 mrem (2.2 E-3 % of its annual limit) and the highest organ dose was 7.39 E-5 mrem to the GI-LLI, gastrointestinal track,'(7.4 E-4 % of its annual limit). The resultant doses are quite low and essentially do not contribute to the quarterly and/or the annual dose limits. This provides a high degree of assurance that the release in no way presented a threat to the health and safety of a member of the public, even using the very low dilution rate. With a higher dilution value the ECL fraction and the resultant doses are reduced further and become even less O si9eificant.

1 ODCM section 2.1.4 requires that the radwaste system be employed to reduce the radioactivity in the liquid waste prior to its discharge whsnever the projected dose dus to the release would exceed 0.06 mrem to the total body and 0.2 mrem to any organ. As shown in the previous j paragraph, the total body dose due to the release of the RHRSW was much less than l

0.06 mrem and the maximum organ dose was much less than 0.2 mrem.

10CFR20.1302 (b)(l) requires that a licensee show compliance with the annual limit of i 100 mrem to any member of the public by demonstrating that certain concentration limits of the j effluent at the point of release are not exceeded. This was addressed above in the j assessment of ODCM section 2.1.2.

10CFR20.1501 (a)(2)(ii) & (iii) requires the licensee to evaluate the concentration or quantities of radioactive materials and the potential radiological hazard, respectively. The concentrations ,

and quantity of the radioactive materials in the release was evaluated by sampling and analysis as discussed above. The potential radiological hazard was also evaluated by performance of the dose calculations, which would be a result of the release, as discussed above in the assessment of ODCM section 2.1.3.

This release does not constitute a Licensee Event Report (LER) based on the following.

10CFR 50.73 (A)(2)(Vill)(B) requires the licensee to report any liquid effluent release which -

exceeds 20 times the applicable concentration specified in 10CFR20, Appendix B, Table 2, column 2, at the point of entry into the receiving waters (i.e., unrestricted area). This is justified as discussed above in the assessment of ODCM section 2.1.3; it can be seen that the concentrations are much less that the applicable limits.

Design Criterion 64 in Appendix A to 10CFR50 requires the monitoring of effluent discharge paths. Performance of the sampling and analysis of the RHRSW service water before its release complied with this criterion.

Compliance with Appendix I to 10CFR50 was assured by adherence to the applicable ODCM sections as discussed above. Furthermore, Appendix I is the bases for one of these ODCM sections.

40CFR190 is concerned with the annual dose to any member of the public due to releases of radioactivity and to radiation from the uranium fuel cycle sources. This is addressed by TS 5.5.4.] and implemented by ODCM section 5.1.2, which states that additional calculation and reporting is required when any of the dose limits as specified in the ODCM sections 2.1.3, 3.1.3, or 3.1.4 are exceeded by a factor of two. This requirement is not applicable for the release based on the doses as discussed above in the assessment of ODCM section 2.1.3.

O

NRC Bulletin 80-10," Contamination of Nonradioactive Systems and Resulting Potential for Unmonitored, Uncontrolled Releases of Radioactivity to the Environment" lists four actions for l the licensee. First: Identify the affected systems; the Unit 1 RHR "B" loop was identified.

O Second: establish a sampling / analysis of monitoring program for the affected systems; this was done. Third: restrict use of the system until the cause of the contamination is identified and corrected, and the system is decontaminated. The release was the result of identifying the leakage, implementation of corrective action and of decontaminating the system. The third action also states, that, if it is considered necessary to continue operation of the system as !

contaminated, then a 10CFR50.59 evaluation must be performed. This was done in 1996. l The fourth action calls attention to the regulations to be complied with and states that releases must be monitored and controlled. The release of the RHR service water was sampled and monitored (evaluated) by the sampling and analysis prior to the flush taking place; the release .

was controlled in the fact that the flush was a planned evolution. i Administrative controls and sampling have been established to ensure that any future releases would be within 10CFR20 limits, reference Lab Standing Order, SO-HPC-001-0199, and 64CH-ADM-001-0S.

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GEORRIA POWER COMPANY PLANT E.I. HATCH FORM im.E:

10 CFR 50.59 EVALUATION 9 SHEET 1 OF 9 NUMBER: N/A PROPOSED REVISION: N/A O TITLE: UNIT 1 RHR SERVICE WATER: RELEASE OF CONTAMINATED WATER DOCUMENT TYPE DEFICIENCY RELATED SAFETY EVALUATION SYNOPSIS OF THE " ACTIVITY" TO WHICH THIS EVALUATION APPLIES:

g Release of Radioactive RHR Service Water An analysis of samples from the Unit 1 RHR "B" Loop service water (RHRSW) system, identified several l

radionuclides at verylow concentrations. The first indication of contamination was noted on August 8,1996 and the second indication was noted on August 23,1996. The total activity in the RHRSW contained within the heat exchanger, which has a volume of around 4000 gallons, was respectively estimated to be about 13.7pCl and 25.6 pCl. On August 23,1996 repairs were made to a Ap instrument which was found to be leaking by in an effort to stop the leak into the service water side of the heat exchanger. To determine if the leak had been repaired, the service water loop of the heat exchanger was decontaminated by flushing and the service water in the loop was then resampled and analyzed. The circulating water fiume has a blowdown line which diverts a small portion of the total circulating water to the river via the discharge structure. This resulted in a release to an unrestricted area, though this release was both monitored and controlled, it was not through the normally utilized liquid radwaste system but the release to the unrestricted area did in fact take the same release path to the river. The regulatory discreteness of this release is discussed below by evaluating the release, using the higher of the two activities for conservatism, for O compliance with the relevant sections of the Technical Specifications (TS), the ODCM, the Code of Federal Regulations and other regulatory documents.

The requirements of the Radioactive Effluent Controls Program are spelled out in TS 5.5.4. This program is implemented by the Offsite Dose Calculation Manual (ODCM) and it conforms to the requirements of 10CFR50.36a for the control of radioactive effluents and for maintaining the doses as icw as reasonably achievable. Compliance with TS 5.5.4 regarding liquid releases can be assured by adhering to the requirements of ODCM section 2.1.2,2.1.3 and 2.1.4 which respectively provide limits on the concentration of the radioactive material at the point of release to an unrestricted area, the resultant dose to a member of the public from the release, and the necessity of using the radwaste treatment system.

ODCM section 2.1.2 requires that the concentrations of the radioactive materials released be limited to 10 times (10X) the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, with the exception for dissolved or entrained noble gases whose concentration shall be limited to 1 E-4 pCl/ml.

The concentrations of the radionuclides found in the RHRSW sample, from August 23,1996 and their corresponding 10CFR20 limits are as follows.

Radionuclide Concentration ( Cl/ml) kmjl(pCi/mt)

Mn-54 4.26 E-7 3 E-5 Co-60 7.75 E-7 3 E-6 Zn-65 3.93 E-7 5 E-6 Xe-135 9.67 E-8 1 E-4 O

MGR-0020 REV.2 N/A 10AC-MGR-010-OS

GEORQlA POWER COMPANY PLANT E,l. HATCH FORM mLE:

10 CFR 50.59 EVALUATION 9 SHEET 2 OF 9 The following discussion is based on a release duration of 1 minute, a release volume of 4,000 gal and a

O total dilution of.gn!y 10,000 gal. This is very conservative estimate, since credit for the additional dilution provided by the circulating water fiume was not taken into consideration. The sum of the ratios of the l

}

concentration of each radionuclide in the mixture to its effluent concentration limit (ECL) was 0.14. The sum of the ECL fractions must be less than ten (<10) to ensure that the concentration limit for the mixture is not exceeded. As can be seen, the sum is much less than ten.

(10CFR20 Appendix B states that the sum of the fractions of the nuclides divided by their effluent l concentration limits (ECLs) must be less than one. Further NRC guidance, Technical Specifications, and I the ODCM allow the ECLs in Appendix B to be increased by a factor of 10. Mathematically this can be )

achieved by dividing the nuclides by the original 10CFR20 Appendix B ECLs and insuring that the sum , ' '

the fractions is less than 10. The plant software performs the sum of the ECL fractions and comparisc: t.his way to insure compliance with 10CFR20 limits.)

ODCM section 2.1.3 requires that the annual dose to a member of the public in unrestricted areas due to liquid releases from each unit be limited to 3 mrem to the total body and 10 mrem to any organ. The dose in any quarter is limited to half of the annuallimits. Dose calculations were performed for this release, in accordance with ODCM section 2.4, to evaluate the doses relative to this release. The total body dose was 2.31 E-6 mrem (7.7 E-5 % of its annuallimit) and the highest organ dose was 1.11 E-5 mrem to the GI-LLI, .,

gastrointestinal track, (1.1 E-4 % of its annual limit). The resultant doses are quite low and essentially do not contribute to the quarterly and/or the annual dose limits. This provides a high degree of assurance that the release in no way presented a threat to the health and safety of a member of the public, even using the very low dilution rate. With a higher dilution value the ECL fraction and the resultant doses are reduced further and become even less significant.

ODCM section 2.1.4 requires that the radwaste system be employed to reduce the radioactivity in the liquid waste prior to its discharge whenever the projected dose due to the release would exceed 0.06 mrem to the total body and 0.2 mrem to any organ. As shown in the previous paragraph, the total body dose due to the O release of the RHRSW was much less than 0.06 mrem and the maximum organ dose was much less than 0.2 mrem.

10CFR20.1302(b)(i) requires that a licensee show compliance with the annual limit of 100 mrem to any member of the public by demonstrating that certain concentration limits of the effluent at the point of release are not exceeded. This was addressed above in the assessment of ODCM section 2.1.2.

10CFR20.1501(a)(2)(ii) & (iii) requires the licensee to evaluate the concentration or quantities of radioactive materials and the potential radiological hazard, respectively. The concentrations and quantity of the radioactive materials in the release was evaluated by sampling and analysis as discussed above. The potential radiological hazard was also evaluated by performance of the dose calculations which would be a result of the release, as discussed above in the assessment of ODCM section 2.1.3.

This release doos not constitute a Ucensee Event Report (LER) based on the following. ;

10CFR50.73(a)(2)(viii)(B) requires the licensee to report any liquid effluent release which exceeds 20 times I the applicable concentrations specified in 10CFR20, Appendix B, Table 2, column 2, at the point of entry into the receiving waters (i.e., unrestricted area). This is justified as discussed above in the assessment of ODCM section 2.1.3, it can be seen that the concentiations are much less than the applicable limits.

Design Criterion 64 in Appendix A to 10CFR50 requires the monitoring of effluent discharge paths. This I criterion was complied with by performance of the sampling and analysis of the RHRSW service water I before its release. I Compliance with Appendix l to 10CFR50 was assured by adherence to the applicable ODCM sections as <

discussed above. Furthermore, Appendix 1is the bases for one of these ODCM sections.

l MGR-0020 REV.2 N/A 10AC-MGR-010-OS

GEORGIA POWER COMPANY PLANT E.l. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION O SHEET 3 OF 9 40CF3190 is concerned with the annual dose to any member of the public due to releases of radioactivity and to radiation from the uranium fuel cycle sources. This is addressed by TS 5.5.4.] and implemented by ODCM section 5.1.2, which states that additional calculation and reporting is required when any of the dose limits as specified in the ODCM sections 2.1.3,3.1.3 or 3.1.4 are exceeded by a factor of two. This l requirement is not applicable for the release based on the doses as discussed above in the assessment of ODCM section 2.1.3.

NRC Bulletin 80-10. " Contamination of Nonradioactive Systems and Resulting Potential for Unmonitored, ;

Uncontrolled Releases of Radioactivity to the Environment" lists four actions for the licensee. First: identify the affected systems; the Unit 1 RHR "B" loop was identified. Second: establish a sampling / analysis or monitoring program for the affected systems; this was done. Third: restrict use of the system until the cause of the contamination is identified and corrected, and the system is decontaminated. The release was the result of identifying the leakage, implementation of corrective action and of decontaminating the system. The third action also states, that, if it is considered necessary to continue operation of the system as contaminated, then a 10CFR50.59 evaluation must be performed. At present, actions have been taken to preclude the use of the system except in the event of an emergency, a plan is being developed to investigate, repair the leakage and perform post repair samples to ensure the leak has indeed been repaired. The fourth action calls attention to the regislations to be complied with (these are all addressed above) and states that releases must be monitored and controlled. The release of the RHR service water was monitored (evaluated) by the sampling and analysis prior to the flush taking place; the release was controlled in the fact that the flush was a planned evolution. Dose calculations were performed after system operation.

To ensure that operation of the RHRSW system will not be adversely affected by the leak, the following cases have been considered:

O Case 1. Normal Operation based on sample results Case 2. Normal Operation with bounding assumptions Case 3. LOSP with bounding assumptions i

1 Case 4. LOCA/LOSP with the estimated smallleakage rate Case 5. LOCA/LOSP with bounding assumptions Case 1 is address the previous discussions. Cases 2 thru 5 are discussed below. LOCA/LOSP is the most conservative accident for RHRSW operation and dose evaluation.

Case 2: Normal Operation with bounding assumptions The reason for the above evaluation is to provide reasonable assurance that future operation of "B" RHRSW loop would not create releases in excess of 10CFR20, Technical Specification, or ODCM limits.

This evaluation is further bounded by calculations performed using the following assumptions:

1) RHRSW loop completely fills with Suppression Pool / Torus water. After starting the RHRSW pump the system volume is flushed out to the flumo in one minute and replaced with non-radioactive service water at a higher pressure than the RHR system which prevents further radioactive water from leaking into the RHRSW system.

2) Minimum dilution flowrate in the fiume is 500,000 gpm.

3) RHRSW discharge flowrate is 4,000 gpm.

This data was put into the Effluent Management System (EMS) computer which performed the dose calculations and sum of the ECL fractions. The results are as follows:

The projected 31 day total body dose is 4.6E-05 mrem which is 0.077% of the 0.06 mrem limit.

The projected 31 day organ dose is 9.13E-05 mrem which is 0.046% of the 0.2 mrem limit.

The cumulative total body dose is 9.79E-05 mrem which is 0.0065% of the quarterly 1.5 mrem limit.

The cumulative organ dose is 1.94E-05 mrem which is 0.00039% of the quarterly 5.0 mrem limit.

The sum of the ECL fractions is 2.7 which is less than the 10 limit.

MGR-0020 REV.2 N/A 10AC-MGR-010-0S i

GEORGIA POWER COMPANY PLANT E 1. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION O SHEET 4 OF 9 Consideration was give to RCS water going in the RHRSW system. However, this is not considered to be a credible event. During normal operation, the RHR system is pressurized via the jocky pumps, using torus water. Thus, the worst case would be if Torus water completely filled the RHRSW loop. This is the case described above. RHR is used to circulete RCS water in the shutdown cooling mode during shutdown operation. In this case, RHRSW would be started before RHR, and the worst case initially would be torus water. If the system were shutdown and restarted during a shutdown, RCS water would not be expected to displace the RHRSW system volume, thus the torus water case is considered to be bounding.

A calculation was also performed using MICROSHIELD to estimate the dose to an individual standing at the RHRSW pipe opening where the water would dump into the fiume. Using the assumption from above that all the contaminated water would pass that point in one minute, MICROSHIELD calculated the dose rate at 2.217E-02 mrem /hr which gives a dose to an individual in that one minute equal to 0.00037 mrem which is much less than any dose limit for a member of the public.

Case 3. LOSP with bounding assumptions if LOSP is considered without a LOCA, then the initial conditions can be assumed to be the same as for normal operation. The circulating water pumps would trip, so dilution by mixing of the circulating water flow stream would not be available. However, the discharge of RHRSW will mix with the fiume volume. The volume of the fiume from RHRSW discharge pit to the point that the fiume overflows to the river is estimated to be about 1,000,000 gallons, diluted with 500,000 gpm is conservatively terminated after one minute, due to the expected RHRSW flowrate of 4,000 gpm. No credit was taken for any mixing of the remainder of the circulating water system volume, and the circulating water pumps are assumed to trip in this case, at the onset of the accHet.

Case 4. LOCA/LOSP with the estimated small leakage rate Consideration was given to LOCA/LOSP post-accident operation of the RHRSW system. Contamination of the RHR system could be very high due to water coming in contact with potentially failed fuel. This water could be transported to the RHRSW system via leakage between the system interfaces. However, the leakage into the RHRSW system is very small. This is evidenced by sampling and analysis of the water in the RHRSW system over time, during normal operation. Samples taken near the heat exchanger show contamination levels much less than that of torus water, which was taken s the bounding case during normal operation. Samples taken further away from the heat exchanger in upstream piping have shown no contamination. Also, during normal operation, the RHR system is pressurized by the jockey pump system, and has been observed to be about 60 psig. RHRSW B" Loop system pressure has been observed to be O psig. Any significant leakage would be expected to pressurize the RHRSW loop. It follows that nay leakage into the RHRSW system prior to post accident operation would be very small. Although there are no time limits for starting RHRSW after an accident, analysis assumes that RHRSW will be started at 10 minutes following an accident which could lead to fuel failure, and thus increase the contamination present in the torus water. During post accident operation, no leakage to RHRSW can occur. Determining the actual leakage rate prior to starting the system is very difficult, thus, rigorous calculations have not been performed. However, samples taken near the heat exchanger within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after flushing the RHRSW system showed contamination levels about 1,000 times less than that of Torus water. Taking the volume of the RHRSW in the heat exchanger of about 1320 gallons (not taking credit for the piping volume), the leakage rate could be estimated to be as small as 0.0027 gpm, with the RHR system at 60 psig, or about 0.005 gpm with the RHR system operating in the LPCI mode, at about 205 psig, taking suction from the Torus. The sensitivity of post-accident dose to various leakage rates have been previously considered in the evaluation for DCR 94-045, at a leak rates from 0.1 gpm to 50 gpm (using accident source terms for torus water). Resultant dose rates at 0.1 gpm (much grater than estimated leakage) are very small, and are within the licensing basis for 10CFR100 limit following an accident.

a MGR-0020 REV.2 N/A 10AC-MGR-010-OS

CEORGIA POWER COMPANY PLANT E,l. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION O SHEET 5 OF 9 Case 5. LOCA/LOSP with bounding assumptions As discussed, the leakage rate during normal operation and post-accident is very small, and expected radiological consequences are not increased. However, because actual leakage rate cannot be easily determined, and for added conservatism, we can assume that 4,000 gallons of Torus Water leaks into the RHRSW system prior to starting the system. Assuming that the system is started in 10 minutes, the leakage rate is 400 gpm. This is roughly equivalent to a complete rupture of a heat exchanger tube, which is very conservative. Prior to starting the system, the RHRSW system valves are closed, and are expected to leak much less than 400 gpm. In order to achieve this leakage rate, the operator wou!d have to open the discharge valve, and then start the RHRSW pump 10 minutes later, or a gross valve failure must occur prior to system startup. This would require a complete tube failure and failure of the operator to start the pump within a reasonable time, or a tube failure with a valve failure. Either of these scenarios would involve more than one failure, which would not be credible event. However, to apply bounding conservatism, dose is calculated assuming this amount of leakage. Using source terms for post-accident torus water, assuming fuel failure, with 500,000 gallon dilution factor, and a release rate of 4,000 gpm.then the resultant dose to the public is about 0.163 Rem Whole Body, and about 35.4 Rem Organ Dose. This is within the licensing basis for 10 CFR100 limits of 25 Rem Whole Body and 300 Rem Organ Dose, after adding this dose to dose from all other sources (ref. Bechtel Calculation 305, rev. O vol. 3, binder 24, folder 2339 for source term concentrations). The dilution factor was determined to be about 1/2 of the volume of the fiume between the RHRSW discharge point and the fiume overflow to the river, which is equivalent to the LOSP case. No credit was taken for any mixing of the remainder of the circulating water system volume, and the circulating water pumps are assumed to trip in this case, at the onset of the accident.

Administrative controls and sampling have been established to ensure that any future releases would be within 10CFR20 limits, reistence Lab Standing Order, SO-HPC-001 0896.

O

l ONCE A. SCREENING QUESTION IS ANSWERED "YES", THE REMAINDER OF THE SCREENING QUESTIONS ARE NOT REQUIRED TO BE ANSWERED.

j MGR-0020 REV.2 N/A 10AC-MGR-010-0S

GEORGIA POWER COMPANY PLANT E.1. HATCH FORM siiLE:

10 CFM 50.59 EVALUATION O SHEET 6 OF 9 Q 0 YES ; @ NO 10 CFR 50.59 SCREENING (i.e., BLOCKS S AND 9):

is the " ACTIVITY"itself a change to one of the following, QB is a change to one of the following ,

required as a result of the " ACTIVITY": I

a. the Technical Specifications and / or the Environmenta! Protection Plan incorporated in the l Operating License, QB

b. other licensing document (s) as defined in 00AC-REG-003 0S7 BASIS FOR ANSWER:

S The event described in the synopsis does not cause a change to any licensing document because this is simply the description of and the relative evaluations for a release via the RHRSW system to an unrestricted area (the river) and a means to provide documentation for the evaluation for the '

safety related. significance of the event. l E the answer is "YES", complete the CONTROL OF CHANGES TO LICENSING DOCUMENTS form, p AND make it a part of the 10 CFR 50.59 EVALUATION package.

10 CFR 50.59 SCREENING (CONTINUED):

E APPLICABLE / DESIRED, GO DIRECTLY TO A QUESTION THAT HAS A "YES" ANSWER l I

Does the " ACTIVITY" to which this evaluation applies represent:

t

1. O YES @ NO A change to the plant (EITHER temporary QB peimanent) as described in i' the FSAR?

BASIS FOR ANSWER:

This event did not change the plant in any way. The plant systems, structures and components were not effected or altered by this activity. l

2. S YES O NO A change to procedures described in the FSAR?

f O

MGR-0020 REV.2 N/A 10AC-MGR-010-OS !

i

GEORGIA POWER COMPANY PLANT E,l. HATCH FORM TITLE:

_10 CFR 50.59 EVALUATION 9 SHEET 7 OF 9 9 BASIS FOR ANSWER:

This is an evaluation of an event and does not cause a change to the FSAR in any way but the RHRSW to flume as a pathway for the release is different from the routine release via the radwaste system. The systems and procedures used for their operation were not effected, the systems were operated as described within the FSAR, thus no change to the FSAR exists.

,.+. , ~ w.n nnmswnmmmnw n ,,.,n n n.msn .,< - . . - . - . ~

3. O YES S NO A test or experiment not described in the FSAR?

BASIS FOR ANSWER:

l This event was neither a test or experiment but a release via the RHRSW system. The safety related function of plant equipment, structures or components required for the safe operation and shutdown was not affected by this event nor was the health and safety of the public threatened by event.

E the answers to M the questions in Blocks 9 and 9 are "NO," complete Blocks 9 through 9.

E the answer to ANY question in Blocks 9 and 9 is "YES," complete Blocks 9 through 9.

PREPARED: DATE: / / l 9 REVIEWED: DATE: / /

APPROVED: DATE: / /

O MGR-0020 REV.2 N/A 10AC-MGR-010-OS

1 GEORGIA POWER COMPANY PLANT E 1. HATCH

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l FORM in LE: l 10 CFR 50.59 EVALUATION $ SHEET 8 OF 9 l SAFETY EVALUATION N 1

1. O YES @ NO Does the proposed " ACTIVITY" increase the probability of occurrence of an l accident previously evaluated in the FSAR? l BASIS FOR ANSWER: l The RHR, RHRSW, and heat exchanger are not affected by the small amount of radioactive inleakage into ,

the RHRSW. The RHR and RHRSW system will continue to operate as designed providing the required l heat sink as described in the FSAR.

l l

2. O YES S NO Does the proposed " ACTIVITY" increase the (radiological) consequences of an accident previously evaluated in the FSAR?

BASIS FOR ANSWER:

O The leakage path into the RHRSW does not occur during periods of RHRSW operation due to the fact that the RHRSW is at a higher pressure. The leakage would be from the RHRSW into the system being cooled.

During normal operation of the system, release of contamination into an unrestricted area is not a credible event. As shown in the synopsis, the slight amount of activity that could possibly be flushed to the flume and the tremendous dilution provided, the radiological consequences would be negligible and therefore not be increased.

3. O YES S NO Does the proposed " ACTIVITY" increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the FSAR?

BASIS FOR ANSWER:

The operation of the RHR system is not affected by the sn.all amount of inleakage as previously discussed and does not increase the probability of malfunction of any equipment important to the operation and shutdown of the plant. A catastrophic failure of a tube would not affect the operability of the system because the tube failure would not prevent the RHRSW from providing the required cooling to the system.

4. O YES S NO Does the proposed " ACTIVITY" increase the (radiological) consequences of a malfunction of equipment important to safety previously evaluated in the FSAR?

BASIS FOR ANSWER:

Due to the fact that the RHRSW operates at a higher pressure, any additional leakage in the heat exchanger would be from RHRSW into the system being cooled. Therefore, no increase in consequences is introduced. When the system is not in operation, the radiological consequences have been evaluated to have no adverse impact on public health and safety.

O MGR-0020 REV.2 N/A 10AC-MGR-010-0S

GEORGIA POWER COMPANY PLANT E.1. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION , 9 SHEET 9 OF 9 l SAFETY EVALUATION

5. O YES @ NO Does the proposed " ACTIVITY" create the possibility of an accident of a dliferent type than any previously evaluated in the FSAR?

BASIS FOR ANSWER:

The suspected leakage in the heat exchanger would not reduce the effectiveness of the RHR system in providirs the required cooling and therefore, does not create the possibility of a different type accident.

l

6. O YES @ NO Does the proposed " ACTIVITY" create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the FSAR?

BASIS FOR ANSWER:

$ Due to the fact that the RHRSW operates at a higher pressure, any additional leakage in the heat exchanger would be from RHRSW into the system being cooled. Therefore, no increase in the possibility of malfunction is introduced. During normal operation with RHRSW not operating, any radioactwity detected l will be measured and evaluated.

j O

7. O YES @ NO Does the proposed " ACTIVITY" reduce the margin of safety as defined in the basis for any Technical Specification?

BASIS FOR ANSWER:

The activity does not affect the margin of safety because the Tech Spec. limitations as specified within Section 5.5.4 are met as previously discusse6.

i? i E a change to ths Technical Specifications or the Environmental Protection Plan is required, QS E ANY sf the questions in Block 9 is answered "YES," an anreviewed safety question /S Indicated. In that case, approval from the NRC is required BEFORE the " ACTIVITY" can be implemented. Refer to subsection 8.5.1.2 for guidance on exceptions to this.

s Y

A U

MGR-0020 REV.2 N/A 10AC-MGR-010-OS

HL-5780, Ei Hatch Unit 1 & 2 Annual Rept of Plant Radioactive Effluent Releases for 1998. with

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Enclosure:

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