Text

Annual Radioactive Effluent Release Rept for Ei Hatch Nuclear Plant Covering Jan-Dec 1997
	ML20247A676
Person / Time
Site:	Hatch
Issue date:	12/31/1997
From:	Sumner H; SOUTHERN NUCLEAR OPERATING CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HL-5621, NUDOCS 9805060202
	Download: ML20247A676 (103)
	v • d • e

. _ _ _ _ _. _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ . ._ ___________. _______ __ _ __ _ - __ -

Lewis Sumner Southern Nuclear Vice President Operating Company. Inc.

Hatch Project Support 40 invemess Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7279 Fax 205.992.0341 SOUTHERN h-COMPANY !

. EnergytoServeYourWorld*

April 28, 1998 Docket Nos. 50-321 HL-5621 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Edwin I. Hatch Nuclear Plant Annual Radioactive Efiluent Release Report Gentlemen:

In accordance with the provisions of Plant Hatch Technical Specifications, Southern Nuclear Operating Company is providing the Plant Hatch Units 1 and 2 Annual -

Radioactive Efiluent Release Report. This report covers the period January 1,1997 through December 31,1997.

Should you have any questions, please advise.

Sincerely,

&1M YJ &

H. L,. Sumner, Jr.

DMC/ld l

Enclosure:

Plant E. I. Hatch Units 1 & 2 /

Annual Radioactive Efiluent Release Report /

l cc: See next page.

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9905060202 971231 PDR R

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U. S. Nuclear Regulatory Commission Page 2 April 28, 1998 cc: Southern Nuclear Operating Company Mr. P. H. Wells, Nuclear Plant General Manager NORMS U. S. Nuclear Regulatory Commission. Washington. D. C.

Mr. L. N. Olshan, Project Manager - Hatch U. S. Nuclear Regulatory Commission. Region H Mr. L. A. Reyes, Regional Administrator Mr. B. L. Holbrook, Senior Resident Inspector Hatch American NuclearInsurers Mr. R. A. Oliveira State ofGeoreia Mr. J. L. Setser, Department of Natural Resources HL-5621

SOUTHERN COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO.1 & 2 ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES JANUARY 1,1997 THROUGH DECEMBER 31,1997 SECTION TITLE PAGG 1.0 Liquid Effluents 1 1.1 Regulatory Limits / Technical Specifications 1 1.1.1 Concentration Limits 1 1.1.2 Dose Limits 1 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 33 2.1 ODCM Specifications 33 2.1.1 Dose Rate Limit 33 O

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SECTION TITLE PAGE 2.1.2 Air Dose Due to Noble Gas 33 1

2.1.3 Dose to Any Organ 33 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 34 2.2 Release Points of Gaseous Effluents 34 2.3 Total Quantities of Radioactivity, Dose Rates 35 and Cumulative Doses 4 2.3.1 Fission and Activation Gas 35 2.3.2 Radiolodine, Tritium and Particulate Releases 35 2.3.3 Gross Alpha Release 36 2.4 Gaseous Effluent Release Data 37 2.4.1 Methodology 37 O ..

2.5 Radiological impact Due to Gaseous Releases 39 2.6 Abnormal Releases 39 !

3.0 Solid Waste 67 3.1 Regulatory Limits / Technical Specifications 67 3.1.1 Solid Radioactive Waste System 67 3.1.2 Reporting Requirements 67 1

3.1.3 Process Control Program (PCP) 67 .

3.2 Solid Waste Data 68 l 4.0 Changes to the Plant Hatch ODCM 73 5.0 Doses to Members of the Public inside The 73 Site Boundary i

SECTION TITLE PAGE 6.0 Major Changes to the Liquid, Gaseous and 82 l Solid Radwaste Treatment Systems 7.0 Meteorological Data 82 8.0 Inoperable Liquid or Gaseous Effluent 82 Monitoring instrumentation 9.0 Tanks Exceeding Curie Content Limits 83 1

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O SOUTHERN COMPANY E. I. 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 D Liquid Effluents - Summation of All Releases 8 )

Unit 2 (Quarters 1,2, 3 and 4) t 11C Liquid Effluents - Summation of All Releases O Site (Quarters 1,2,3 and 4) 10 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) 16 1-2C Liquid Effluents - Site (Quarters 1,2,3 and 4) 20 1-3A Doses to a Member of The Public Due to Liquid. 24 Releases Unit 1 (Quarters 1,2,3 and 4) 1-3B Doses to a Member of The Public Due to Liquid 26 Releases Unit 2 (Quarters 1,2,3 and 4) 1-4A Liquid Effluents - Batch Release Summary 28 Unit 1 1-4B Liquid Effluents - Batch Release Summary 30 Unit 2 0 1-5 Minimum Detectable Concentration -

Liquid Sample Analysis 32 L_----_---__----_------.--- -

TABLE LIST OF TABLES PAGE 2-1 A Gaseous Effluents - Summation of All 40 Releases - Unit 1 (Quarters 1,2,3 and 4) 2-1 B Gaseous Effluents - Summation of All 42 Releases -Unit 2 (Quarters 1,2,3 and 4) 2-1C Gaseous Effluents - Summation of All 44 Releases - Site (Quarters 1, 2, 3 and 4) ;

i 2-2A Gaseous Effluents - Elevated Releases 46 Unit 1 (Quarters 1,2,3 and 4) 2-2B Gaseous Effluents - Elevated Releases 48 Unit 2 (Quarters 1,2,3 and 4) 2-2C Gaseous Effluents - Elevated Releases 50 Site (Quarters 1,2,3 and 4) l 2-3A Gaseous Effluents - Ground Level Release 52 !

Unit 1 (Quarters 1,2,3 and 4) 2-3B Gaseous Effluents - Ground Level Release 54 Unit 2 (Quarters 1,2,3 and 4) 2-3C Gaseous Effluents - Ground Level Release 56 Site (Quarters 1,2,3 and 4) 2-4A Air Doses Due to Gaseous Releases - 58 Unit 1 (Quarters 1, 2,3 and 4) 2-4B Air Doses Due to Gaseous Releases- 60 Unit 2 (Quarters 1,2,3 and 4) 2-5A Doses to a Member of the Public Due to 62 Radiolodine, Tritium, and Particulate in Gaseous Releases - Unit 1 (Quarters 1,2,3 and 4) 2-5B Doses to a Member of the Public Due to 64 Radiolodine, Tritium, and Particulate in Gaseous Releases - Unit 2 (Quarters 1,2,3 and 4) 2-7 Minimum Detectable Concentration - 66 Gaseous Sample Analyses

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TABLE LIST OF TABLES PAGE O 3-1 A,B Solid Waste and Irradiated Fuel Shipments 69,71 4 Dose to A Member of the Public Due to Activities 74 I inside The Site Boundary O l O

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 q radionuclides other than dissolved or entrained noble gases. For I dissolved or entrained noble gases, the concentration shall be limited to 1.0E-4 microcuries/ml total activity.

1 1.1.2 Dose Limits I The dose or dose commitment, to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to 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 l 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 11, Column 2.

For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 uCi/ml 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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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 1. 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 noble gases with computerized data reduction

3. Tritium Monthly Distillation and Cornposite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

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

6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting i

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Gamma isotopic measurements are performed in-house using germanium detectors with a resolution of 2.0 kev or lower. The detectors are shielded T 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, 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 radionuclides 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%.

Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed 4 offsite.

The radionuclides 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 j are not exceeded. j 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.

Radionuclides 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 (3)

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1 is returned from Radwaste Operations to Chemistry with the actual release data provided. These data are input into the computer and a post-release printout is generated. The post release printout contains the actual release rates, the {

actual release concentrations and quantities, the actual dilution flow, and the I calculated doses to an individual.

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1.4 Liquid Effluent Release Data l I

l Regulatory Guide 1.21, Tables 2A and 2B are found in this report as Table 1-1 A, for Unit 1, Table 1-1B, for Unit 2 and Table I-1C, for the site; and Table 1-2A, for i Unit 1,1-28, for Unit 2, and Table 1-2C, 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: I 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 1-1B, 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 the sum of the measured individual radionuclides 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, j (4)

1.5 Radiological Impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated 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, l 1.7 Batch Releases Batch Release information for Units 1 and 2 is summarized in the following tables:

Unit 1 Liquid Batch Releases: Table 1-4A 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 - Summation of All Releases Unit: 1 Starting : 1-Jan-1997 Ending : 30-Jun-1997 i

TYPE OF EFFLU M UNITS QUARTER 1 QUARTER 2 EST. TOT ERRO %

..____.... .___.__...______ __ ____.___......___.............______________.R ____

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 3.06E-02 6.90E-03 4.70E+0

__....__...___........... .___..____...______ .__________.____......._______. _1 _

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.01E-08 9.89E-09

3. PERCENT OF APPLICABLE LIMIT % *

__.......__.__...____________.....__.....____....___....__...__.._. __... ____._ \

3. TRITIUM

1. TOTAL RELEASE CURIES 3.57E+00 2.83E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.66E-06 4.05E-06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 2.87E-02 1.98E-02 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.75E-08 2.83E-08

3. PERCENT OF APPLICAEhE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.09E-06 0.00E+00 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 3.41E+06 3.11E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 7.65E+08 6.97E+08 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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TABLE 1-1A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluento - Summation of All Releacea Unit: 1 Starting : 1-Jul-1997 Ending : 31-Dec-1997 73 i i

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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 2.15E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.30E-08 2.82E-08

3. PERCENT OF APPLICABLE LIMIT % *

B. TRITIUM

1. TOTAL RELEASE CURIES 3.84E+00 2.64E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.55E-06 3.46E.06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

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1. TOTAL RELEASE CURIES 2.74E-02 2.11E-03 1.00E+02 v

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.53E-08 2.77E-09

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3. PERCENT OF APPLICABLE LIMIT % * * '

................................................................................ l D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.75E-06 2.01E-06 1.20E+02 !

E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 4.94E+06 3.50E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.08E+09 7.63E+08 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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TABLE 1-1B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Summation of All Releases Unit: 2 Starting : 1-Jan-1997 Ending : 30-Jun-1997 V

TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2- EST. TOT i

ERROR %

l A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING ,

TRITIUM, GASES, ALPHA) CURIES 3.29E-02 6.11E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.54E-08 6.97E-08

3. PERCENT OF APPLICABLE LIMIT % * *

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l B. TRITIUM j

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1. TOTAL RELEASE CURIES 2.58E+00 3.63E+00 3.70E+01 j

2. AVERAGE DILUTED CONCENTRATION I DURING PERIOD uCi/ML 2.78E-06 4.15E-06

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3. PERCENT OF APPLICABLE LIMIT % *

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................................................................................. j C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 2.13E-03 3.79E-03 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.29E-09 4.32E-09 l

3. PERCENT OF APPLICABLE LIMIT % *

W D. GROSS ALPHA RADIOACTIVITY 4

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1. TOTAL RELEASE CURIES 2.93E-08 3.63E-08 1.20E+02

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

E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 3.89E+06 3.96E+06 1.00E+01 i

................................................................................ l F. VOLUME OF DILUTION WATER USED LITERS 9.27E+08 8.77E+08 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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TABLE 1 1B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT J Liquid Efflu:;nts - Summation of All Releases j

l Unit: 2 O Starting : 1-Jul-1997 Ending : 31-Dec-1997 .

f V) TYPE OF EFFLUENT UNITS i

QUARTER 3 QUARTER 4 EST. TOT I ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.33E-02 1.11E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.07E-08 1.91E-08

3. PERCENT OF APPLICABLE LIMIT i *

1 B. TRITIUM

1. TOTAL RELEASE CURIES 2.41E+00 2.50E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.75E-06 4.31E-06

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES p ................................................................. ..............

(v / 1. TOTAL RELEASE CURIES 2.24E-03 2.49E.03 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.48E-09 4.29E-09

3. PERCENT OF APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 3.26E+06 2.92E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 6.43E+08 5.80E+08 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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F TABLE 1-1C E. I. HATCH NUCLEAR PLANT

]

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i Liquid Effluents . Summation of All Releases '

l Unit: Site Starting : 1-Jan-1997 Ending : 30-Jun-1997 I t TYPE OF EFFLUENT UNITS CCARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS i l

1. TOTAL RELEASE (NOT INCLUDING TRITIUM,' GASES, ALPHA) CURIES 6.35E.02 6.80E.02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION I DURING PERIOD uCi/ML 3.75E-08 4.32E-08

3. PERCENT OF APPLICABLE LIMIT % *

B. TRITIUM

1. TOTAL RELEASE CURIES 6.14E+00 6.46E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.63E-06 4.10E-06 l ................................................................................

l

3. PERCENT OF APPLICABLE LIMIT % *

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 3.08E-02 2.35E-02 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.82E-08 1.50E-08

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3. PERCENT OF APPLICABLE LIMIT % * *

................................................................................ l D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.12E-06 3.63E-08 1.20E+02 1

E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 7.30E+06 7.07E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.69E+09 1.57E+09 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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TABLE 1 1C E. I, HATCH NUCLEAR PLANT I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l Liquid Efflutnts - Summation of All Relcases Unit: Site Starting : 1.Jul.1997 Ending : 31-Dec-1997 t

,s

,O l TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT I ERROR %

1 I

A. FISSION.& ACTIVATION PRODUCTS l

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

1. TOTAL RELEASE (NOT INCLUDING )

TRITIUM, GASES, ALPHA) CURIES 3.82E-02 3.26E-02 4.70E+01 ~

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.22E-08 2.43E-08 1

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

3. PERCENT OF APPLICABLE LIMIT % *

B. TRITIUM q

................................................................................ i

)

1. TOTAL RELEASE CURIES 6.26E+00 5.14E+00 3.70E+01 !

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.63E-06 3.83E-06

3. PERCENT OF APPLICABLE LIMIT % *

1 C. DISSOLVED AND ENTRAINED GASES Q 1. TOTAL RELEASE CURIES 2.96E-02 4.60E-03 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.72E-08 3.42E-09

3. PERCENT OF APPLICABLE LIMIT % *

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.75E-06 2.01E-06 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 8.19E+06 6.42E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.73E+09 1.34E+09 1.60E+02

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

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TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT (

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i Liquid Effluents

} Unit: 1 Starting : 1-Jan-1997 Ending : 30-Jun-1997 l CONTINUOUS MODE ** l BATCH

................................................................................ i MODE l{

NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l H-3 CURIES l l 0.00E+00 l 0.00E+00 l 3.57E+00 l 2.83E+00 l FISSION & ACTIVATION PRODUCTS f

................................................................................ 4 AG-110M CURIES 0.00E+00 0.00E+00 4.81E-06 0.00E+00 AS-76 j CURIES 0.00E+00 0.00E+00 4.51E-03 0.00E+00 BA-140 CURIES 0.00E+00 0.00E+00 4.23E-06 0.00E+00 CE-141 CURIES 0.00E+00 0.00E+00 3.61E-05 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 3.57E-04 3.31E-05 CO-60 CURIES 0.00E+00 0.00E+00 4.62E-03 2.41E-03 CR-51 CURIES 0.00E+00 0.00E+00 5.90E-03 8.78E-05 CS-134 CURIES 0.00E+00 0.00E+00 4.58E-06 1.98E-05 CS-137 CURIES 0.00E+00 0.00E+00 4.79E-04 3.99E-04 CS-138 CURIES 0.00E+00 0.00E+00 1.55E-05 0.00E+00 1 FE-55 CURIES 0.00E+00 0.00E+00 2.97E-03 1.54E-03 fg FE-59 CURIES 0.00E+00 0.00E+00 1.79E-04 4.24E-06 g 4 I-131 CURIES 0.00E+00 0.00E+00 9.55E-04 2.93E-04

'- / I-132 0.00E+00 CURIES 0.00E+00 8.08E-05 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 3.03E-03 5.26E-04 I-135 CURIES 0.00E+00 0.00E+00 1.71E-03 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 3.92E-04 1.09E-05 LA-142 CURIES 0.00E+00 0.00E+00 5.62E-05 0.00E+00 MN-54 CURIES 0.00E+00 0.00E+00 7.47E-04 3.51E-04 NA-24 CURIES 0.00E+00 0.00E+00 5.69E-06' 9.61E-07 NB-95 CURIES 0.00E+00 0.00E+00 1.82E-05 0.00E+00 NB-97 CURIES 0.00E+00 0.00E+00 4.21E-04 0.00E+00 NP-239 CURIES 0.00E+00 0.00E+00 9.87E-05 0.00E+00 )

RU-103 CURIES 0.00H+00 0.00E+00 2.71E-05 0.00E+00 l RU-105 CURIES 0.002+00 0.00E+00 5.12E-05 0.00E+00 SB-122 {

CURIES 0.00E+00 0.00E+00 2.31E-05 0.00E+00 SR-89' CURIES 0.00E+00 0.00E+00 1.05E-04 1.90E-04 SR-90 CURIES 0.00E+00 0.00E+00 1.09E-07 0.00E+00 SR-91 CURIES 0.00E+00 0.00E+00 7.58E-06 0.00E+00 TC-99M CURIES 0.00E+00 0.00E+00 1.08E-04 1.65E-06 Y-91M CURIES 0.00E+00 0.00E+00 1.22E-04 1.71E-06 Y-92 CURIES 0.00E+00 0.00E+00 1.20E-03 0.00E+00 ZN-65 CURIES 0.00E+00 0.00E+00 2.39E-03 1.02E-03 i

f O

s _-

7 _

(12) 1

__________________________A

TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents y Unit: 1 Starting : 1.Jan-1997 Ending : 30-Jun-1997 l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l

-FISSION & ACTIVATION PRODUCTS j

......___.....___..........__..................___...__...._....__..__.......___ j ZN-69M CURIES 0.00E+00 0.00E+00 9.13E-07 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 1.00E.05 0.00E+00

.____...____..______. __..._________........._.... __________________.._________ j TOTALS CURIES l l 0.00E+00 l 0.00E+00 l 3.06E-02 l 6.90E-03 l l

)

1 1

DISSOLVED AND ENTRAINED GASES j AR-41' CURIES 0.00E+00 0.00E+00 2.73E-06 0.00E+00 I XE-133 CURIES 0.00E+00 0.00E+00 5.94E-03 4.48E-03 1 XE-133M CURIES 0.00E+00 0.00E+00 2.85E-05 8.78E-05 XE-135 CURIES 0.00E+00 0.00E+00 1.91E-02 1.51E-02 j XE-135M CURIES 0.00E+00 0.00E+00 3.64E-03 1.29E-04 p TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 2.87E-02 l 1.98E-02 l G-ALPHA l CURIES l 0.00E+00 l 0.00E+00 l 2.09E-06 l 0.00E+00 l Zeroes in this table indica.te that no radioactivity was present at detectable levels. See Tabte 1-5 for typical minimum detectable concentrations.

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

1 1

)

(13)

TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents O Starting : 1-Jul-1997 Unit: 1 Ending : 31-Dec-1997 l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l H-3 CURIES l l 0.00E+00 l 0.00E+00 l 3.84E+00 l 2.64E+00 l FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 1.38E-05 5.75E-05 AS.76 CURIES 0.00E+00 0.00E+00 4.94E-06 1.29E-05 BA-139 CURIES 0.00E+00 0.00E+00 4.86E-05 0.00E+00 BA 140 CURIES 0.00E+00 0.00E+00 2.94E-04 5.94E-05 CE-141 CURIES 0.00E+00 0.00E+00 2.85E-05 8.56E-06 CO-58 CURIES 0.00E+00 0.00E+00 5.45E-04 6.03E.04 CO-60 )

CURIES 0.00E+00 0.00E+00 4.07E-03 3.67E-03 i CR-51 CURIES 0.00E+00 0.00E+00 1.34E-03 3.72E-03 CS-134 CURIES 0.00E+00 0.00E,00 4.85E-05 2.46E-05 CS-137 CURIES 0.00E+00 0.00E+00 8.87E-04 5.40E-04 CS 138 CURIES 0.00E+00 0.00E+00 2.41E-05 0.00E+00 FE-55 CURIES 0.00E+00 0.00E+00 O

FE-59 I-131 CURIES CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.55E-03 2.73E-04 9.59E-04 4.55E-03 2.85E-04 9.41E-05 I-132 CURIES 0.00E+00 0.00E+00 5.41E-05 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 2.56E-03 6.29E-05 ,

I-135 CURIES 0.00E+00 0.00E+00 6.75E-04 0.00E+00 '

LA-140 CURIES 0.00E+00 0.00E+00 3.85E-05 6.78E-05 MN-54 CURIES 0.00E+00 0.00E+00 1.30E-03 1.37E-03 MN-56 CURIES 0.00E+00 0.00E+00- 6.76E-05 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 2.03E-05 2.01E-06 NB-95 CURIES 0.00E+00 0.00E+00 5.15E-05 1.03E-05 NB-97 CURIES 0.00E+00-- 0.00E+00 4.90E-05 1.10E-04 RU.103 CURIES 0.00E+00 0.00E+00 0.00E+00 6.56cr06 RU-106 CURIES 0.00E+00 0.00E+00 0.00E+00 1.36E-05 SB-124 CURIES 0.00E+00 0.00E+00 1.19E-05 6.55E-06 SB.125 CURIES 0.00E+00 0.00E+00 9.94E-06 0.00E+00 SN-113 CURIES 0.00E+00 0.00E+00 1.14E-06 0.00E+00 SR-89 CURIES 0.00E+00 0.00E+00 2.45E-04 2.00E-04 SR-90 CURIES 0.00E+00 0.00E+00 1.16E-12 4.60E-13 SR-91 CURIES 0.00E+00 0.00E+00 5.36E-04 0.00E+00 SR.92 CURIES 0.00E+00 0.00E+00 2.65E-04 3.12E-06 TC-99M CURIES 0.00E+00 0.00E+00 3.88E-05 2.31E-06

k. l (14) i

TABLE 1-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents Unit: 1 Starting : 1.Jul-1997 Ending : 31.Dec.1997 f

l CONTINUOUS MODE **

................................................................................l NUCLIDE' UNIT BATCH MODE l l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION & ACTIVATION PRODUCTS Y-91M CURIES 0.00E+00 0.00E+00 3.79E-04 0.00E+00 ZN-65 CURIES 0.00E+00 0.00E+00 2.41E-03 6.01E-03 ZN-69M CURIES 0.00E+00 0.00E+00 9.75E-05 4.26E-06 ZR-95 CUP.IES 0.00E+00 0.00E+00 2.69E 0.00E+00 1

................................................................................ l TOTALS CURIES l l 0.00E+00 l 0.00E+00 l 2.49E-02 l 2.15E-02 l DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 5.71E-06

-KR-85 CURIES 0.00E+00 0.00E+00 0.00E+00 9.47E-04 KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 1.60E-06 XE-133 CURIES 0.00E+00 0.00E+00 4.20E-03 4.04E-04 XE-133M CURIES 0.00E+00 0.00E+00 2.55E-05 5.33E-06 ys XE 135 CURIES 0.00E+00 0.00E+00 1.79E-02 7.46E.04

( ,) XE-135M CURIES 0.00E+00 0.00E+00 5.23E-03 0.00E+00 TOTALS CURIES l 0.00E+00 l 0.00E+00 l 2.74E-02 l 2.11E-03

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

G-ALPHA CURIES l 0.00E+00 l 0.00E+00 l 2.75E-06 l 2.01E-06

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

2eroes in this table indicate that no radioactivity was present at detectable lerels. See Table 1-5 for typical minimum detectable concentrations.

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

l l '~)

l (O (15)

TABLE 1-2B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents Unit: 2 Starting : 1-Jan-1997 Ending : 30-Jun-1997 l

l l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l H.3 CURIES l l 0.00E+00 l 0.00E+00 l 2.58E+00 l 3.63E+00 l FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 2.71E-06 3.89E-05 AS.76 CURIES 0.00E+00 0.00E+00 7.06E-04 6.37E-03 BA.140 CURIES 0.00E+00 0.00E+00 5.28E-05 0.00E+00 CE-141 CURIES 0.00E+00 0.00E+00 1.82E-05 1.50E-05 CO-58 CURIES 0.00E+00 0.00E+00 1.67E-03 2.33E-03 CO-60 CURIES 0.00E+00 0.00E+00 5.95E-03 1.22E-02 CR-51 CURIES 0.00E+00 0.00E+00 3.31E-03 7.85E-03 CS.134 CURIES 0.00E+00 0.00E+00 1.51E-04 1.58E-04 CS-137 CURIES 0.00E+00 0.00E+00 3.21E-03 2.74E-03' CS-138 CURIES 0.00E+00 0.00E+00 5.16E-05 0.00E+00 FE-55 CURIES 0.00E+00 0.00E+00 9.23E-04 8.05E-04 g FE-59 CURIES 0.00E+00 0.00E+00 2.06E-04 1.02E-03 HF-101 CURIES 0.00E+00 0.00E+00 0.00E+00 3.85E-06 I-131 CURIES 0.00E+00 0.00E+00 3.06E-04 6.60E-05 I-132 CURIES 0.00E+00 0.00E+00 0.00E+00 1.22E-05 I 133 CURIES 0.00E+00 0.00E+00 2.05E-04 3.57E-04 I-135 CURIES .0.00E+00 0.00E+00 2.92E-05 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 6.06E-04 6.54E-06 MN-54 CURIES 0.00E+00 0.00E+00 4.10E-03 8.32E-03 MN-56 CURIES 0.00E+00 0.00E+00 0.00E+00 6.27E-05 MO-99 CURIES 0.00E+00 0.00E+00 0.00E+00 1.20E-04 NA-24 CURIES 0.00E+00 0.00E+00 4.20E-04 4.69E-03 NB-95 CURIES 0.00E+00 0.00E+00 0.00E+00 7.15E-05 NB CURIES 0.00E+00 0.00E+00 7.17E-05 8.34E-04 NP-239 CURIES 0.00E+00 0.00E+00 7.89E-06 3.58E-05 l SB-122 CURIES 0.00E+00 0.00E+00 1.78E-06 8.11E-05 l SR-89 CURIES 0.00E+00 0.00E+00 2.54E-04 8.38E-05 i SR-90 CURIES 0.00E+00 0.00E+00 0.00E+00 4.03E-06 SR-91 CURIES 0.00E+00 0.00E+00 0.00E+00 1.16E-04 SR.12. CURIES 0.00E+00 0.00E+00 1.36E-06 2.79E-05 TC-99M CURIES 0.00E+00 0.00E+00 1.05E-04 6.38E-04 Y-91M CURIES 0.00E+00 0.00E+00 3.82E-06 1.99E-04 Y-92 CURIES 0.00E+00 0.00E+00 0.00E+00 4.55E-05 O

V (16)

TABLE 1-2B*

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

] Starting : 1-Jan-1997 Unit: 2 Ending : 30-Jun-1997 l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 !

FISSION & ACTIVATION PRODUCTS ZN-65 CURIES 0.00E+00 0.00E+00 1.05E-02 1.17E.02 ZN-69M CURIES 0.00E+00 0.00E+00 1.91E-05 4.36E-05 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 4 . 5 6 E'. 0 5 TOTALS CURIES l 0.00E+00 l 0.00E+00 l 3.29E-02 l 6.11E-32

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

DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00- -3.32E-06 7.42E-06 KR-85 CURIES 0.00E+00 0.00E+00 3.00E-04 1.20E-03 XE-133 CURIES 0.00E+00 0.00E+00 1.03E-03 4.29E-04 XE-133M CURIES 0.00E+00 0.00E+00 8.39E-06 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 7.76E-04 2.05E-03 XE-135M CURIES 0.00E+00 0.00E+00 1.26E-05 1.01E-04 g ................................................................................

TOTALS 5 CURIES l 0.00E+00 l 0.00E+00 l 2.13E-03 l 3.79E-03

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

1 G-ALPHA CURIES l 0.00E+00 l 0.00E+00 l 2.93E-08 l 3.63E-08

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

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

U (17)

4 TABLE 1-2B*

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

Liquid Effluents

)

Unit: 2 I

(/N) v Starti.g : 1-Jul-1997 Ending : 31-Dec.1997 I

I l CONTINUOUS MODE ** l BATCH MODE l

................................................................................ l NUCLIDE UNIT

................................................................................l l l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 j

]

................................................................................ l H-3 l CURIES l 0.00E+00 j 0.00E+00 l 2.41E+00 l 2.50E+00 l I FISSION & ACTIVATION PRODUCTS

................................................................................ ]

AG-110M CURIES 0.00E+00 0.00E+00 3.44E-06 1.53E-05 AS-76 CURIES 0.00E+00 0.00E+00 1.03E-03 8.23E-05 BA-139 CURIES 0.00E+00 0.00E+00 2.84E-05 0.00E+00 i BA-140 CURIES 0.00E+00 0.00E+00 1.18E-04 6.63E-05 CE-141 CURIES 0.00E+00 0.00E+00 5.40E-06 7.29E-06 CE.144 CURIES 0.00E+00 0.00E+00 1.82E-05 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 0.00E+00 4.11E-07 CO-58 CURIES 0.00E+00 0.00E+00 3.17E-04 2.07E-04 CO-60 CURIES 0.00E+00 0.00E+00 2.83E-03 2.09E-03 ;

CR-51 CURIES 0.00E+00 0.00E+00 1.11E-03 5.86E-05 i CS-134 CURIES 0.00E+00 0.00E+00 2.60E 05 1.02E-04 CS-137 l g-wg CURIES 0.00E+00 0.00E+00 4.43E-04 1.72E-03

(' ) CS-138 FE-55 CURIES CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.22E-03 3.19E-06 2.51E-03 FE-59 CURIES 0.00E+00 0.00E+00 3.02E-04 2.09E-06 l I-131 CURIES 0.00E+00 0.00E+00 2.13E-05 7.30E-05 I-132 CURIES 0.00E+00 0.00E+00 7.61E.06 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 9.53E-05 3.34E-05 LA-140 CURIES 0.00E+00 0.00E+00 2.91E-05 1.24E-05 MN-54 CURIES 0.00E+00 0.00E+00 2.17E.03 1.03E-03 MN-56 CURIES 0.00E+00 0.00E+00 1.57E-05 0.00E+00 1 NA-24 CURIES 0.00E+00 0.00E+00 9.56E-04 7.60E-06 NB-95 CURIES 0.00E+00 0.00E+00 3.39E 05 0.00E+00 NB-97 CURIES 0.00E+00 0.00E+00 1.05E-04 8.30E-06 NP.239 CURIES 0.00E+00 0.00E+00 0.00E+00 3.68E-05 RU.103 CURIES 0.00E+00 0.00E+00 3.88E-07 0.00E+00 SB-122 CURIES 0.00E+00 0.00E+00 2.87E-06 0.00E+00 SB-124 CURIES 0.00E+00 0.00E+00 1.93E-05 0.00E+00 SR-89 CURIES 0.00E+00 0.00E+00 4.82E-05 1.85E-04 SR-90 CURIES 0.00E+00 0.00E+00 0.00E+00 2.33E-07 SR-91 CURIES 0.00E+00 0.00E+00 6.53E-05 1.24E-04 SR-92 CURIES 0.00E+00 0.00E+00 3.81E-05 3.62E-05 TC-99M CURIES 0.00E+00 0.00E+00 4.81E-05 5.56E-06 p

G l (18)

( - _ _ - - - - - - - -- - ------ ---- _ _ ---------

TABLE 1-2B*

E.-I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents f Starting : 1-Jul-1997 Unit: 2 Ending : 31-Dec-1997 l CONTINUOUS MODE ** l l

................................................................................l NUCLIDE UNIT

. BATCH MODE l l QUARTER 3 l QUARTER 4 l QUARTER 3

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

4 l FISSION & ACTIVATION PRODUCTS Y-91M CURIES 0.00E+00 0.00E+00 8.51E-05 1.24E-04 ZN-65 CURIES 0.00E+00 0.00E+00 1.10E-03 2.54E-03 ZN-69M CURIES 0.00E+00 0.00E+00 1.26E-05 1.67E.06 ZR-95 CURIES 0.00E+00 0.00E+00 2.61E-05 0.00E+00 TOTALS CURIES l l 0.00E+00 l 0.00E+00 l 1.33E-02 1.11E.02

.....................................................................l...........l DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 9.30E-05 0.00E+00 XE-133 CURIES 0.00E+00 0.00E+00 6.75E-04 1.12E-03 !

XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 1.28E-05 XE-135 CURIES 0.00E+00 0.00E+00 1.43E-03 1.35E-03 XE-135M CURIES 0.00E+00 0.00E+00 4.02E-05 0.00E+00 G TOTALS l CURIES l 0.00E+00 l 0.00E+00 2.24E-03 2.49E-03 l

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

J 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.

1 I

I l

1 t

v (19) l l

I TABLE 1-2C* I E. I. HATCH NUCLEAR PLANT ;

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents

/~ Unit: Site

( Starting : 1-Jan-1997 Ending : 30-Jun-1997

)

............................................. l l CONTINUOUS MODE ** l BATCH

................................................................................ i MODE ll NUCLIDE l UNIT l QUARTER 1 l QUARTER 2'l QUARTER 1 l QUARTER 2l H-3 CURIES l l 0.00E+00 l 0.00E+00 l 6.14E+00 l 6.46E+00 l FISSION & ACTIVATION PRODUCTS AG.110M CURIES 0.00E+00 0.00E+00 7.52E-06 3.89E-05 AS-76 CURIES 0.00E+00 0.00E+00 5.21E-03 6.37E-03 BA-140 CURIES 0.00E+00 0.00E+00 5.71E-05 0.00E+00 CE.141 CURIES 0.00E+00 0.00E+00 5.43E-05 1.50E-05 CO-58 CURIES 0.00E+00 0.00E+00 2.03E-03 2.36E-03 CO-60 CURIES 0.00E+00 0.00E+00 1.06E-02 1.46E-02 CR-51 CURIES 0.00E+00 0.00E+00 9.22E-03 7.94E-03 CS-134 CURIES 0.00E+00 0.00E+00 1.56E-04 1.77E-04 CS-137 CURIES 0.00E+00 0.00E+00 3.69E-03 3.14E-03 CS-138 CURIES 0.00E+00 0.00E+00 6.71E-05 0.00E+00 1 FE-55 CURIES 0.00E+00 0.00E+00 3.89E-03 2.35E-03 FE-59 i

(~N CURIES 0.00E+00 0.00E+00 3.85E-04 1.02E-03 i HF-181 CURIES 0.00E+00 0.00E+00 0.00E+00 3.85E-06 I-131 CURIES 0.00E+00 0.00E+00 1.26E-03 3.59E-04 I-132 CURIES 0.00E+00 0.00E+00 8.08E-05 1.22E-05 l I-133 CURIES 0.00E+00- 0.00E+00 3.24E-03 8.84E-04 I-135 CURIES 0.00E+00 0.00E+00 1.74E-03 0.00E+00

)

l LA-140 CURIES 0.00E+00 0.00E+00 9.98E-04 1.75E-05 LA-142 !

CURIES 0.00E+00 0.00E+00 5.62E-05 0.00E+00 1 MN-54 CURIES 0.00E+00 0.00E+00 8.68E-03 MN-56 4.85E-03 )

i CURIES 0.00E+00 0.00E+00 0.00E+00 6.27E-05 l MO-99 CURIES 0.00E+00 0.00E+00 0.00E+00 1.20E-04 NA-24 CURIES 0.00E+00 0.00E+00 4.26E-04 4.70E-03 NB-95 CURIES 0.00E+00 0.00E+00 l 1.82E-05 7.15E-05 '

NB-97 CURIES 0.00E+00 0.00E+00 4.93E-04 8.34E-04 NP-239 CURIES 0.00E+00 0.00E+00 1.07E-04 3.58E-05 RU-103 CURIES 0.00E+00 0.00E+00 2.71E-05 0.00E+00 RU-105 CURIES 0.00E+00 0.00E+00 5.12E-05 0.00E+00 SB-122 CURIES 0.00E+00 0.00E+00 2.49E-05 8.11E-05 SR-89 CURIES 0.00E+00 0.00E+00 3.59E-04 2.74E-04 SR-90 CURIES 0.00E+00 0.00E,00 1.09E-07 4.03E-06 SR-91 CURIES 0.00E+00 0.00E+00 7.58E-06 1.16E-04 SR-92 CURIES 0.00E+00 0.00E+00 1.36E-06 2.79E-05 l 1 l

1 (20)

TABLE 1 2C*

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

[' Starting :

Unit: Site 1-Jan-1997 Ending : 30-Jun-1997 l CONTINUOUS MODE ** l BATCH

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

....................... .............................................jQUARTER l l QUARTER 1 l QUARTER 2 l QUARTER 1 2 l

- FISSION & ACTIVATION PRODUCTS TC-99M CURIES 0.00E+00 0.00E+00- 2.14E-04 6.40E-04 Y-91M CURIES 0.00E+00 0.00E+00 1.26E-04 2.01E-04 Y-92 CURIES 0.00E+00 0.00E+00 1.20E-03 4.55E-05 ZN.65 CURIES 0.00E+00 0.00E+00 1.29E-02 1.28E-02 ZN-69M CURIES 0.00E+00 0.00E+00 2.01E-05 ZR-95 4.36E-05 CURIES 0.00E+00 0.00E+00 1.00E-05 4.56E-05 TOTALS CURIES l 0.00E+00 l 0.00E+00 l 6.35E-02 6.80E-02 l

.....................................................................l...........l DISSOLVED AND ENTRAINED GASES AR.41 CURIES 0.00E+00 0.00E+00 6.05E-06 7.42E-06 KR.85 CURIES 0.00E+00 0.00E+00 3.00E-04 XE-1.33 1.20E-03 CURIES 0.00E+00 0.00E+00 6.97E-03 p XE-133M CURIES 0.00E+00 0.00E+00 3.69E-05 4.91E-03 8.78E-05 v XE-135 XE.135M CURIES 0.00E+00 0.00E+00 1.99E-02 1.71E-02 CURIES 0.00E+00 0.00E+00 3.65E-03 2.29E-04 TOTALS' CURIES 3.08E-02 l l 0.00E+00 l 0.00E+00

..........................................................l...........l...........l 2.35E-02 G. ALPHA' CURIES l l 0.00E+00 l 0.00E+00 2.12E-06

..........................................................l...........l...........l 3.63E-08 Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum detectable concentrations.

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

t 1

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(21)

)

_ _______..m_ _ _ - - - - - - - - - - - - - - - -

r TABLE 1-2C* .

! E. I. HATCH NUCLEAR PLANT I l

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents l Unit: Site f~~]

( j Starting : 1-Jul-1997 Ending : 31-Dec-1997 l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l H-3 CURIES l l 0.00E+00 l 0.00E+00 l 6.26E+00 l 5.14E+00 l FISSION & ACTIVATION PRODUCTS

................................................................................ 1 AG-110M CURIES 0.00E+00 0.00E+00 1.72E-05 7.28E-05 AS-76 CURIES 0.00E+00 0.00E+00 1.03E-03 9.52E-05 BA-139 CURIES 0.00E+00 0.00E+00 7.70E-05 0.00E+00 BA-140 CURIES 0.00E+00 0.00E+00 4.12E-04 1.26E-04 CE-141 CURIES 0.00E+00 0.00E+00 3.39E-05 1.58E-05 CE-144 CURIES 0.00E+00 0.00E+00 1.82E-05 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 0.00E+00 4.11E-07 CO-58 CURIES 0.00E+00 0.00E+00 8.62E-04 8.10E-04 CO-60 CURIES 0.00E+00 0.00E+00 6.89E-03 5.76E-03 CR-51 CURIES 0.00E+00 0.00E+00 2.45E-03 3.77E-03 CS-134 CURIES 0.00E+00 0.00E+00 7.44E-05 1.26E-04 o CS-137 CURIES 0.00E+00 0.00E+00 1.33E-03 2.26E-03 I I CS-138 0.00E+00 CURIES 0.00E+00 2.41E-05 3.19E-06 FE-55 CURIES 0.00E+00 0.00E+00 9.77E-03 7.07E-03 FE-59 CURIES 0.00E+00 0.00E+00 5.75E-04 2.87E-04 I-131 CURIES 0.00E+00 0.00E+00 9.80E-04 1.67E-04 I-132 CURIES 0.00E+00 0.00E+00 6.17E-05 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 2.65E-03 9.63E-05 I-135 CURIES 0.00E+00 0.00E+00 6.75E-04 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 6.76E-05 8.02E-05 MN-54 CURIES 0.00E+00 0.00E+00 3.47E-03 2.39E-03 {

MN-56 CURIES 0.00E+00 0.00E+00 8.32E-05 0.00E+00 i NA-24 CURIES 0.00E+00 0.00E+00 9.77E-04 9.60E-06 NB-95 j CURIES 0.00E+00 0.00E+00 8.53E-05 1.03E-05 1 NB-97 CURIES 0.00E+00 0.00E+00 1.54E-04 1.19E-04 l NP-239 CURIES 0.00E+00 0.00E+00 0.00E+00 3.68E-05 RU-103 CURIES 0.00E+00 0.00E+00 3.88E-07 6.56E-06 i RU-106 CURIES 0.00E+00 0.00E+00 0.00E+00 1.36E-05 '

SB-122 CURIES 0.00E+00 0.00E+00 2.87E-06 0.00E+00 SB-124 CURIES 0.00E+00 0.00E+00 3.12E-05 6.55E-06 SB-125 CURIES 0.00E+00 0.00E+00 9.94E-06 0.00E+00 l SN-113 CURIES 0.00E+00 0.00E+00 1.14E-06 0.00E+00 SR-89 CURIES 0.00E+00 0.00E+00 2.94E-04 3.85E-04

'g)

LJ (22)

1 i

j TABLE 1-2C*

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

( Starting : '1-Jul-1997 Ending : 31-Dec-1997 l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION & ACTIVATION PRODUCTS SR-90 CURIES 0.00E+00 0.00E+00 1.16E-12 2.33E.07 SR.91 CURIES 0.00E+00 0.00E+00 6.01E-04 1.24E-04 SR-92 CURIES 0.00E+00 0.00E+00 3.03E-04 3.93E-05 TC-99M CURIES 0.00E+00 0.00E+00 8.69E-05 7.86E-06 Y.91M CURIES 0.00E+00 0.00E+00 4.65E-04 1.24E-04 ZN-65 CURIES 0.00E+00 0.00E+00 3.52E-03 8.54E-03 ZN-69M CURIES 0.00E+00 0.00E+00 1.10E-04 5.93E-06 ZR-95 CURIES 0.00E+00 0.00E+00 5.30E-05 0.00E+00 TOTALS CURIES l l 0.00E+00 l 0.00E+00 l 3.82E-02 l 3.26E-02 l

DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 9.30E-05 5.71E-06 G KR-85 CURIES 0.00E+00 0.00E+00 0.00E+00 9.47E-04

+ KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 1.60E-06 XE-133 CURIES 0.00E+00 0.00E+00 4.87E-03 1.52E-03 XE-133M CURIES 0.00E+00. 0.00E+00 2.55E-05 1.81E-05 XE-135 CURIES 0.00E+00 0.00E+00 1.94E-02 2.10E-03 XE-135M CURIES 0.00E+00 0.00E+00 5.27E-03 0.00E+00 TOTALS CURIES l l 0.00E+00 l 0.00E+00 l 2.96E-02 l 4.60E-03 l

G-ALPHA CURIES l l 0.00E+00 l 0.00E+00 l 2.75E-06 l 2.01E-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.

1 I

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s (23)

TABLE 1-3A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jan-1997 Ending: 30-Jun-1997 Cumulative Doses per Quarter Organ Tech Units Quarter % of Quarter t of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 1.88E-03 3.76E-02 1.36E-03 Liver 2.73E-02 5.0 mrem 3.16E-03 6.32E-02 2.16E-03 4.32E-02 TBody 1.5 mrem 2.11E-03 1.40E-01 Thyroid 1.46E-03 9.76E-02 5.0 mrem 7.04E-03 1.41E-01 1.93E-03 3.87E-02 Kidney 5.0 mrem 1.34E-03 2.68E-02 8.36E-04 1.67E-02 Lung 5.0 mrem 2.72E-04 5.45E-03 2.16E-04 GILLI 4.31E-03 5.0 mrem 3.10E-03 6.19E-02 1.47E-03

..................................................................... 02 2.94E-Cumulative Doses per Ytrar Organ Tech Un'.ts Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mrem 3.24E-03 3.24E-02 Liver 10.0 mrem 5.32E-03 5.32E-02 TBody 3.0 mrem 3.57E-03 1.19E-01 Thyroid 10.0 mrem 8.97E-03 8.97E.02 Kidney 10.0 mrem 2.18E-03 2.18E-02 Lung 10.0 mrem 4.88E-04 4.88E-03 GILLI 10.0 mrem 4.56E-03 4.56E-02 (24)

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

/~'% Starting: 01-Jul-1997 Ending: 31-Dec-1997 V

Cumulative Doses per Quarter Organ Tech Unite Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit j

.......................................................................... j Bone 5.0 mrem 3.39E 03 6.78E-02 2.61E-03 5.22E-02 l Liver 5.0 mrem 5.37E-03 1.07E-01 4.90E-03 9.80E-02 TBody 1.5 mrem 3.57E-03 2.38E-01 2.99E-03 1.99E-01 Thyroid 5.0 mrem 6.78E-03 1.36E-01 6.37E-04 1.27E-02 Kidney 5.0 mrem 2.10E-03 4.19E-02 2.28E-03 4.57E-02 Lung 5.0 mrem 5.20E-04 1.04E-02 3.32E-04 6.65E-03 t GILLI 5.0 mrem 3.00E.03 6.01E-02 3.55E-03 7.09E-02 l Cumulative Doses per Year 1 Organ Tech Units Year to % of !

Spec Ending Tech l Limit Date Spec j Limit '

A Bone 10.0 mrem 9.25E-03 9.25E-02 i Liver 10.0 mrem 1.56E-02 1.56E-01 I TBody 3.0 mrem 1.01E-02 3.37E-01 Thyroid 10.0 mrem 1.64E.02 1.64E-01 Kidney 10.0 mrem 6.56E-03 6.56E.02 Lung 10.0 mrem 1.34E-03 1.34E-02 GILLI 10.0 mrem 1.11E-02 1.11E-01 IV l

(25)

TABLE 1-3B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 C Starting: 01-Jan-1997 Ending: 30-Jun-1997

(

Cumulative Doses per Quarter Organ Tech Units Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 1.38E-02 2.76E-01 1.18E-02 2.37E-01 Liver 5.0 mrem 2.17E-02 4.35E-01 1.96E-02 3.92E-01 TBody 1.5 mrem 1.39E-02 9.26E-01 1.27E-02 8.44E-01 Thyroid 5.0 mrem 2.09E-03 4.18E-02 6.06E-04 1.21E-02 Kidney 5.0 mrem 8.54E-03 1.71E-01 7.90E-03 1.58E-01 Lung 5.0 mrem 2.01E-03 4.02E-02 1.70E-03 3.41E-02 GILLI 5.0 mrem

.................................-03 6.88E 1.38E-01 1.10E-02 2.20E-01 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Bone 10.0 mrem 2.56E-02 2.56E-01

( Liver TBody 10.0 3.0 mrem mrem 4.13E-02 2.66E-02 4.13E-01 8.85E-01 Thyroid 10.0 mrem 2.69E-03 2.69E-02 Kidney 10.0 mrem 1.64E-02 1.64E-01 Lung 10.0 mrem 3.71E-03 3.71E-02 GILLI 10.0 mrem 1.79E-02. 1.79E-01 l

l 1

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TABLE 1-3B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-1997 O Ending: 31-Dec-1997 Cumulative Doses per Quarter Organ Tech Units Quarter % of -Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec 4 Limit Limit 1 Bone 5.0 mrem 1.64E-03 3.27E-02 7.02E-03 1.40E-01 -

Liver 5.0 mrem 2.65E-03 5.31E-02 1.05E-02 2.09E-01 }

TBody 1.5 mrem 1.79E-03 1.19E-01 6.87E-03 4.58E-01 Thyroid 5.0 mrem 2.03E-04 .4.06E-03 5.07E-04 1.01E-02 ,

Kidney 5.0 mrem 9.98E-04 2.00E-02 3.82E-03 7.65E-02 I Lung 5.0 mrem- 2.61E-04 5.23E-03 1.08E-03 2.17E-02 GILLI 5.0 mrem 2.07E-03 4.13E-02 2.07E-03 4.14E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit p Bone 10.0 mrem 3.43E-02 3.43E-01

- Liver 10.0 mrem 5.'45E-02 5.45E-01 TBody 3.0 mrem 3.52E-02 1.17E+00 Thyroid 10.0 mrem 3.40E-03 3.40E-02 Kidney 10.0 mrem 2.13E-02 2.13E-01 Lung 10.0 mrem 5.06E-03 5.06E-02 GILLI 10.0 mrem 2.20E-02 2.20E-01 j

(27) i u________._.______ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

r--

TABLE 1-4A i E. I. HATCH NUCLEAR PIRIT '

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Batch Release Summary Unit: 1 ,

Starting : 1.Jan-1997 Ending : 30-Jun-1997 l l .__ ..__................ ......._...__._______..__........... ......__.......... j

.__...._.......______..........__..........._...............___.....___..._____. 1 LIQUID RELEASES NUMBER OF BATCH RELEASES.- : 226 )

TOTAL TIME PERIOD FOR BATCH RELEASES : 25717.00 MINUTES '!

MAXIMUM TIME. PERIOD FOR A BATCH RELEASE : 172.00 MINUTES j AVERAGE TIME PERIOD FOR BATCH RELEASES : 113.79 MINUTES 1 MINIMUM TIME PERIOD FOR A BATCH RELEASE : 80.00 MINUTES j AVERAGE STREAM FLOW DURING PERIODS OF {

9.48E+03 RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : CFS l-l

\

(28)

TABLE 1-4A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Batch Release Summary i Unit: 1

O Starting : 1-Jul-1997 Ending : 31-Dec-1997 U {

LIQUID RELEASES NUMBER OF BATCH RELEASES : 263 TOTAL TIME PERIOD FOR BATCH RELEASES : 34237.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 179.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 130.18 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 83.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 9.48E+03 CFS l (29) i L___ _ _ _ _ - . _ _ _ _ _ _ _ - - - - - - - - - -

TABLE 1 4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents - Batch Release Summary Unit: 2

..h Starting : 1-Jan-1997 Ending : 30-Jun-1997 d

LIQUID RELEASES NUMBER OF BATCH RELEASES : 339

' TOTAL TIME PERIOD FOR BATCH RELEASES : 36199.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 183.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 106.78 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 20.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF.

RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 9.48E+03 CFS l

V

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TABLE 1-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Liquid Effluents . Batch Releasa Summary

, Unit: 2

_ Starting : 1-Jul-1997 Ending : 31-Dec-1997 L LIQUID RELEASES l

.......................__....___............ ...........______..............___. j NUMBER OF BATCH RELEASES : 213 i TOTAL TIME PERIOD FOR BATCH RELEASES : 23627.00 MINUTES j MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 148.00 MINUTES j AVERAGE TIME PERIOD FOR BATCH RELEASES : 110.92 MINUTES 4

MINIMUM TIME PERIOD FOR A BATCH RELEASE : 13.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 9.48E+03 CFS i

k 4

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TABLE 1-5 MINIMUM DETECTABLE CONCENTRA TIONS - LIQUID SAMPLE ANALYSES E. I. HATCH NUCLEAR PLANT JANUARY,1997 - DECEMBER,1997 The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDES 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/mi Zn-65 2.92E-08 uCi/mi Mo-99 1.20E-07 O ce-134 Cs-137 1.7ss-os 1.62E-08 uCi/ml eci/mi uCi/ml Co-141 1.92E-08 uCi/ml Ce-144 8.83E-08 uCi/ml 1-131 1.43E-08 uCi/ml Xe-135 1,03E-08 uCi/ml Fe-55 2.34E-08 uCi/ml Sr-89 1.44E-08 uCi/ml Sr-90 8.50E-09 uCi/mi H-3 6.00E-07 uCi/ml O

(32)

O O 2.0 Gaseous Effluents 2.1 ODCM Specifications 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,

b. For lodine-131, lodine-133, tritium and for all radionuclides in 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 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:

a. During any calendar quarter Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar 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 I 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.

.f) v (33) l i

2.1.4 Total Fuel Cycle 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 Gaseous 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 s 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 particulate and iodines. Unless required more frequently under certain circumstances, samples are collected as follows:

1. Noble gas samples are collected by gro sampling monthly. ,

2. Tritium samples are collected by grab sampling monthly.

3.

Radiciodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period.

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

5.

The 7-day particulate filters above are analyzed 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 radionuclides-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 noble gas grab sample analysis results are used along with maximum expected release flow rates from each of the four vents to calculate monitor setpoints for the gaseous effluent monitors serving the four release points. Calculation of monitor setpoints is described in the ODCM.

(34)

I For each release period, released radioactivity, dose rates, and ,

cumulative doses are calculated. Cumulative dose results are tabulated !

along with the percent of the ODCM limit for each release, for the current quarter and year.

2.3 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses 1

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 l

period represented by the collected sample.

Instantaneous dose rates due to noble gases, radioiodines, tritium, and particulate 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, radiciodine, tritium, and particulate. Dose rate calculation methodology is I pres ented in the ODCM.

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 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 Radiciodine, Tritium and Particulate Releases Released quantities of radiciodines are determined using the weekly samples .

and release flow rates for the four release points. Radiciodine concentrations I are determined by gamma spectroscopy.

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

O (35)

After each quarter, the particulate filters from each vent are combined, fused, and 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 dissolved together. Decay corrections are performed back to the middle of the 1 quarterly collection penod. If Sr-89 or Sr-90 is not detected, MDC's are calculated. Strontium concentrations are input into the composite file of ths

. 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 determining water vapor collection efficiencies. The tritium samples are analyzed 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.

Dose rates due to radiciodine, tritium and particulate 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

]

release period, and the total dose rates from both release points are O compared to the dose rate limits specified in ODCM 3.1.2 Individual doses due to radiciodine, tritium and particulate 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 individual doses sie 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 Alpha Release Th'e 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 volume to determine the concentration. This concentration is input into the composite file of the computer and used for release calculations.

O (36)

2.4 Gaseous Effluent Release Data 2.4.1 Methodology Regulatory Guide 1.21 Tables 1 A,18, and 1C are found in this report as Tables 2-1 A,2-18,2-1C,2-2A, ,2-28,2-2C,2-3A,2-38,2-3C, and data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all quarters.

To complete table 2-1 A,2-18, and 2-1C, total release for each of the four categories (fission and activation gases, iodine's, particulate, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/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, radiciodines, and particulate) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases, and due to radiciodine, tritium, and particulate were calculated as part of the pre-release and post-release permits on individual permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Table 2-1 A, 2-1B, and 2-1C, as curies released in each quarter.

O 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 radiciodine, tritium and particulate, are specified in ODCM 3.1.4. Cumulative individual doses are presented in Table 2-5A, and 2-58, along with percent of ODCM limits.

The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total process of sampling and measurement. Dae 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.

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

O (37)

I l

O 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 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 % '

1 Particulate 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%

Vent flow rates 10%

Vent sample flow rates 10%

q Non steady release rates 10%

l 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 %

i O

(38) )

l

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

Statistical error .

60%

l- 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 l 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, l and particulate in gaseous raleases were calculated in accordance with ODCM 3.1.2.

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.

l Cumulative air doses due to noble gas releases were calculated for l each unit in accordance with ODCM 3.1.4. These results are presented in Tables 2-6A ,and 2-68.

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

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

I I

O (39) i

TABLE 2-1A E. I. HATCH NUCLLM PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents - Summation of All Releases Unit: 1 Starting : 1-Jan-1997 Ending : 30-Jun-1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 7.54E+02 9.34E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec. 9.69E+01 1.19E+02

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 8.72E-03 5.40E-03 1.10E+02 '

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.12E-03 6.86E-04

3. PERCENT OF APPLICABLE LIMIT % *

1 l

C. PARTICULATE

1. PARTICULATE (HALF-LIVES >8 DAYS) CURIES 5.62E-03 8.60E-03 1.00E+02

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

p -2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.23E-04 1.09E-03

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 6.19E.07 7.27E-07 D. TRITIUM

1. TOTAL RELEASE CURIES 1.38E+00 2.08E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.77E-01 2.65E-01

3. PERCENT OF APPLICABLE LIMIT % * *

Applicable limits are expressed in terms of dose.

l See Tables l

l 2-4A, 2 4B, 2-5A, and 2-5B of this report

'[ h 0

(40)

L _ _- __ _

I l

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

i Gaccous Effluents - Summation of All Releases Unit: 1 i

yx Starting : 1-Jul-1997 Ending : 31-Dec-1997

(

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

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 6.31E+02 2.80E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.94E+01 3.53E+01 l 3. PERCENT OF APPLICABLE LIMIT % *

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

B. RADIOIODINES 1 l 1. TOTAL IODINE.131 CURIES 2.86E-03 4.46E-03 1.10E+02

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

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.60E-04 5.61E-04 l I

3. PERCENT OF APPLICABLE LIMIT % *

t 1

l t

C. PARTICULATE l ................................................................................

1. PARTICULATE (HALF-LIVES >8 DAYS) CURIES 2.97E-03 5.69E-04 1.00E+02 l (x g

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.73E-04 7.16E-05 l 3. PERCENT OF APPLICABLE LIMIT % *

l

4. GROSS ALPHA RADIOACTIVITY CURIES 1.49E-06 5.16E-07 l

i D. TRITIUM l ................................................................................

l

1. TOTAL RELEASE CURIES 1.24E+00 7.46E-01 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.56E-01 9.38E-02

3. PERCENT OF APPLICABLE LIMIT % *

l l

l I

Applicable limits are expressed in terms of dose. See Tables i

l 2-4A, 2-4B, 2-5A, and.2-5B of this report.

l

/~s

( (41) l L .

TABLE 2-1B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gassous Effluents - Summation of All Releases Unit: 2 Starting : 1-Jan.1997 Ending : 30-Jun-1997

\

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

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE -CURIES 6.13E+02 7.92E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.89E+01 1.01E+02

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES i

1. TOTAL IODINE-131 CURIES 1.13E-02 7.93E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 1.46E-03 1.01E-03

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATE

1. PARTICULATE (EALF-LIVES >8 DAYS) CURIES 5.79E-03 1.92E-02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.45E-04 2.45E-03

\-

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 1.58E-07 2.36E-06 D. TRITIUM

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

1. TOTAL RELEASE CURIES 2.65E+00 _2.90E+00 9.00E+01 h$ kVhkkbh khLkkhh kkTh Fbk Phkkbb ubk/ hec 5$4bh$bk 5$69b$bk

3. PERCENT OF APPLICABLE LIMIT % *

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

(

(42)

TABLE 2-1B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gassous Effluents . Summation of All Releases Unit: 2 Starting : 1-Jul-1997 Ending : 31-Dec-1997

/

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

................................................................................ 1 A. FISSION & ACTIVATION PRODUCTS

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.19E+01 3.80E+01

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 1.14E-02 8.52E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.43E-03 1.07E-03

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATE

1. PARTICULATE (HALF-LIVES >8 DAYS) CURIES 5.94E-03 1.33E-03 1.00E+02 s

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.48E-04 1.68E-04

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 1.75E-06 5.73E-07 D. TRITIUM

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

1. TOTAL RELEASE CURIES 3.58E+00 2.40E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.51E-01 3.02E-01

3. PERCENT OF APPLICABLE LIMIT % *

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

N (43) l l

l

TABLE 2-1C E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents - Summation of All Releases Unit: Site Starting : 1-Jan-1997 Ending : 30-Jun-1997 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.37F+03 1.73E+03 1.76E+02 1.00E+

02..

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.20E+02

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 2.01E-02 1.33E-02

......................................................................... 10E+021

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.58E.03 1.69E.03

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATE

1. PARTICULATE (HALF-LIVES >8 DAYS) CURIES 1.14E.02 2.78E-02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.47E-03 3.54E-0

3. PERCENT OF APPLICABLE LIMIT % *

3.............

4. GROSS ALPHA RADIOACTIVITY CURIES 7.78E-07

............................................................. 09E-06 3.

D. TRITIUM

1. TOTAL RELEASE CURIES 4.02E+00

............................................................. 99E+00 9.00E+01 4

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.18E-01

3. PERCENT OF APPLICABLE LIMIT

6.34E-01 ....................

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

+

i (44)

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

{ Gaseous Effluents - Summation of All Releases 1

Unit: Site

,_ Starting : 1-Jul.1997 Ending : 31-Dec-1997

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

i A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.28E+03 5.82E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.61E+02 7.33E+01 3.~ PERCENT OF APPLICABLE LIMIT 4 *

I B. RADIOIODINES-

1. TOTAL IODINE-131 CURIES 1.42E-02 1.30E-02 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec -1.79E-03 1.63E-03

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATE

1. PARTICULATE (HALF-LIVES >8 DAYS) CURIES 8.91E-03 1.90E-03 1.00E+02

2. AVERAGE. RELEASE RATE.FOR PERIOD uCi/Sec 1.12E-03 2.39E-04

3. PERCENT OF APPLICABLE LIMIT. % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 3.25E-06 1.093-06 D. TRITIUM.

1. TOTAL RELEASE CURIES 4.83E+00 3.15E+00 9.00E+01-

2. AVERAGE RELEASE RATE'FOR PERIOD uCi/Sec 6.07E-01 3.96E-01

3. PERCENT OF APPLICABLE LIMIT % * *

................................................................................ 3 l

1 1

i Applicable limits are expressed in terms of dose. See Tables {

2-4A, 2-4B, 2-5A, and 2-5B of this report. '

\

(45) 4 I

l

TABLE 2-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Elevated Level Releases Unit: 1 Starting : 1-Jan-1997 Ending : 30.Jun.1997 CONTINUOUS MODE BATCH MODE **

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

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

2 l FISSION GASES XE-137 CURIES 4.54E+02 5.89E+02 0.00E+00 XE-138 0.00E+00 CURIES 1. 2E+02 1.96E+02 0.00E+00 0.00E+00 XE.135M CURIES 4.84E+01 7.14E+01 0.00E+00 KR-87 0.00E+00 CURIES 8.92E+00 9.83E+00 0.00E+00 0.00E+00 AR-41 CURIES 0.00E+00 2.82E+00 0.00E+00 KR-85M 0.00E+00 CURIES 9.35E-01 2.15E+00 0.00E+00 0.00E+00 XE-135 CURIES 8.49E+00 1.27E+01 0.00E+00 XE-133 0.00E+00 CURIES 0.00E+00 2.26E+00 0.00E+00 0.00E+00 XE.131M CURIES 0.00E+00 2.75E+01 0.00E+00 0.00E+0 TOTAL FOR PERIOD CURIES 0 ...

l 6.72E+02 l 9.13E+02 0.00E+00

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

l 0.00E+0

..l....... 0 l

IODINES I-133 CURIES 4.36E.02 5.29E-02 I-131 0.00E+00 0.00E+00 CURIES 7.41E.03 2.97E-03 0.00E+00 TOTAL FOR PERIOD CURIES 00E+000 l l 5.10E-02 5.58E-02 0.00E+00

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

l PARTICULATE I-131 CURIES 8.20E-05 9.27E-05 0.00E+00 0.00E+00 BA-140 CURIES 3.73E-03 5.12E-03 CE-141 0.00E+00 0.00E+00 CURIES 1.31E-05 1.83E-05 0.00E+00 0.00E+00 SR-89 CURIES ZN-65 1.02E-03 2.27E-03 0.00E+00 0.00E+00 CURIES 2.74E-06 0.00E+00 0.00E+00 0.00E+00 CE-144 CURIES 5.77E-05 CO-60 7.10E.05 0.00E+00 0.00E+00 CURIES 1.42E-06 0.00E+00 0.00E+00 SR-90 0.00E+00 CURIES 1.51E.05 3.31E-05 0.00E+00 0.00E+00 CS-137 CURIES 2.61E-05 3.60E-05 TOTAL FOR PERIOD CURIES 00E+00 0

0.00E+00 l l 4.95E-03 7.64E-03

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

l 0.00E+00 l G-ALPHA CURIES 9.28E-09 1.18E-07 0.00E+00 H-3 CURIES 0.00E+00 1.59E.01 3.22E.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 Plant areHatch.

no batch mode radioactive gaseous release pathways (46)

TABLE 2-2A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Elevated Level Releases Unit: 1 i Starting : 1-Jul-1997 Ending : 31.Dec-1997 I

)

Oi .............................................

l j

l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l )

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

1

)

FISSION GASES KR-89 CURIES 2.56E+01 0.00E+00 0.00E+00 0.00E+00 XE-137 CURIES 3.69E+02 1.08E+02 0.00E+00 0.00E+00 XE-138 CURIES 1.39E+02 1.10E+02 0.00E+00 0.00E+00 XE-135M CURIES 4.54E+01 2.61E+01 0.00E+00 0.00E+00 KR-87 CURIES 5.58E+00 1.44E+01 0.00E+00 0.00E+00 AR-41 CURIES 7.38E-01 1.11E+00 0.00E+00 0.00E+00 KR 85M CURIES 1.72E+00 2.91E+00 0.00E+00 0.00E+00 XE-135 CURIES 8.06E+00 1.51E+01 0.00E+00 0.00E+00 XE-133 CURIES 5.75E+00 5.64E.01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 6.01E+02 l 2.78E+02 l 0.00E+00 l 0.00E+00 l IODINES I-132 CURIES 5.24E-04 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 4.14E-02 2.12E-02 0.00E+00 0.00E+00 I-131 CURIES 2.31E-03 4.16E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l 4.43E.02 l 2.54E-02 l 0.00E+00 l 0.00E+00 l l

PARTICULATE

................................................................................ 1 BA.140 CURIES 2.18E-03 3.70E-04 0.00E+00 0.00E+00 CR-51 CURIES 0.00E+00 2.58E.05 0.00E+00 0.00E+00 CE-141 CURIES 8.67E-06 1.88E-06 0.00E+00 0.00E+00 SR-89 CURIES 6.08E-04 4.22E-05 0.00E+00 0.00E+00 ZN-65 CURIES 0.00E+00 3.59E-06 0.00E+00 0.00E+00 CE-144 CURIES -3.40E-05 1.53E-06 0.00E+00 0.00E+00 MN-54 CURIES 0.00E+00 2.77E-06 0.00E+00 0.00E+00 CO-60 CURIES 0.00E+00 1.31E-06 0.00E+00 0.00E+00 SR.90 CURIES 7.03E-06 6.49E.07 0.00E+00 0.00E+00 CS.137 CURIES 1.99E.05 3.23E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 2.88E-03 l 4.60E-04 1 0.00E+00 l 0.00E+00 l

~~~~v...........................................................................

G-ALPHA CURIES 3.63E-08 2.15E-08 0.00E+00 0.00E+00 H-3 CURIES 4.03E-01 1.99E-01 0.00E+00 0.00E+00 f

Zeroes in this table indicate that no radioactivity was present

()

I at detectable levels. See Table 2-7 for typical minimum detectable concentrations,

- There are no batch mode radioactive gaseous release pathways t

l at Plant Hatch.

(47)

TABLE 2 2B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Elevated Level Releases l Unit: 2 Starting : 1-Jan.1997 Ending : 30-Jun-1997

/- s $

l k_-) .

l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l I

................................................................................ [

FISSION GASES XE-137 CURIES 3.99E+02 5.14E+02 0.00E+00 0.00E+00 XE-138 CURIES 1.34E+02 1.61E+02 0.00E+00 0.00E+00 XE-135M CURIES 4.23E+01 5.64E+01 0.00E+00 0.00E+00 l KR-87 CURIES 7.85E+00 8.25E+00 0.00E+00 0.00E+00 AR-41 CURIES 0.00E+00 2.82E+00 0.00E+00 0.00E+00 KR-85M CURIES 8.14E-01 1.75E+00 0.00E+00 0.00E+00 XE-135 CURIES 7.51E+00 1.01E+01 0.00E+00 0.00E+00 XE-133 CURIES 0.00E+00 2.26E+00 0.00E+00 0.00E+00 XE-131M CURIES 0.00E+00 2.75E+01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 5.92E+02 l 7.84E+02 l 0.00E+00 l 0.00E+00 l IODINES I-133 CURIES 3.33E-02 4.09E-02 0.00E+00 0.00E+00 I-131 CURIES 6.50E-03 2.33E-03 0.00E+00 0.00E+00 7g ................................................................................

) TOTAL FOR PERIOD l CURIES l 3.98E-02 l 4.32E-02 l 0.00E+00 l 0.00E+00 l

'%s/ ................................................................................

PARTICULATE I-131 CURIES 5.58E-05 5.75E-05 0.00E+00 0.00E+00 BA-140 CURIES 2.73E-03 3.78E-03 0.00E+00 0.00E+00 CE-141 CURIES 1.02E-05 1.41E-05 0.00E+00 0.00E+00 SR-89 CURIES 1.02E-03 2.27E.03 0.00E+00 0.00E+00 ZN-65 CURIES 2.74E-06 0.00E+00 0.00E+00 0.00E+00 l CE-144 CURIES 4.18E-05 5.13E-05 0.00E+00 0.00E+00 CO-60 CURIES 1.42E-06 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 1.51E-05 3.31E-05 0.00E+00 0.00E+00 CS-137 CURIES 1.89E-05 2.77E-05 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l l 3.90E-03 l 6.23E-03 l 0.00E+00 l 0.00E+00 l G-ALPHA CURIES 7.55E-09 1.15E-07 0.00E+00 0.00E+00 H-3 CURIES 1.13E 01 2.57E-01 0.00E+00 0.00E+00

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

fN **

There are no batch mode radioactive gaseous release pathways (J)%

at Plant Hatch.

l 1

(48)

TABLE 2-2B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Elevated Level Releases Unit: 2 Starting : 1-Jul.1997 Ending : 31-Dec-1997 l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION GASES KR-89 CURIES 2.56E+01 0.00E+00 0.00E+00 0.00E+00' XE-137 CURIES 3.69E+02 1.08E+02 0.00E+00 0.00E+00 XE-138 CURIES 1.39E+02 1.10E+02 0.00E+00 0.00E+00 XE-135M CURIES 4.54E+01 2.75E+01 0.00E+00 0.00E+00 KR-87 CURIES 5.58E+00 1.44E+01 0.00E+00 0.00E+00 AR-41 CURIES 7.38E.01 1.11E+00 0.00E+00 0.00E+00 KR-85M CURIES 1.72E+00 2.91E+00 0.00E+00 0.00E+00 XE.135 CURIES 8.06E+00 1.56E+01 0.00E+00 0.00E+00 XE.133 CURIES 5.75E+00 1.20E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 6.01E+02.l 2.81E+02 l 0.00E+00 l 0.00E+00 l IODINES I-132 CURIES 5.24E-04 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 4.14E-02 2.16E-02 0.00E+00 0.00E+00

/"'N I-131 CURIES 2.31E-03 4.59E-03 0.00E+00 0.00E+00 q) ................................................................................

TOTAL FOR PERIOD CURIES l l 4.43E-02 l 2.62E-02 l 0.00E+00 l 0.00E+00 l

................................................................................ l PARTICULATE I-131 CURIES 3.08E-05 6.91E-06 0.00E+00 0.00E+00 BA-140 CURIES 2.18E-03 3.79E-04 0.00E+00 0.00E+00 CR-51 CURIES 0.00E+00 2.58E-05 0.00E+00 0.00E+00 CE-141 CURIES 8.67E-06 1.88E-06 0.00E+00 0.00E+00 SR-89 CURIES 6.08E-04 1.15E-04 0.00E+00 0.00E+00 ZN.65 CURIES 0.00E+00 3.59E-06 0.00E+00 0.00E+00 CE-144 . CURIES 3.40E-05 1.53E-06 0.00E+00 0.00E+00 MN-54 CURIES 0.00E+00 2.77E-06 0.00E+00 0.00E+00 CO-60 CURIES 0.00E+00 1.31E-06 0.00E+00 0.00E+00 SR-90 CURIES 7.03E-06 1.74E-06 0.00E+00 0.00E+00 CS-137 CURIES 1.99E-05 3.23E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOC CURIES l l 2.88E-03 l 5.43E.04 l 0.00E+00 l 0.00E+00 l G-ALPHA CURIES 3.63E-08 2.53E-08 0.00E+00 0.00E+00 H-3 CURIES 4.03E-01 2.51E-01 0.00E+00 0.00E+00 Zeroes in this table indicate that no radioactivity was present O at detectable levels. See detectable concentrations.

Table 2-7 for typical minimum There are no batch mode radioactive gaseous release pathways at Plant Hatch.

(

i (49) l L_--___-___.

TABLE 2-2C*

E. I. HATCH NUCLEAR PLANT !

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Elevated Level Releases Unit: Site fs Starting : 1.Jan.1997 Ending : 30.Jun.1997

()'

t 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 8.53E+02 1.10E+03 0.00E+00 0.00E+00 XE-138 CURIES 2.86E+02 3.57E+02 0.00E+00 0.00E+00 XE-135M CURIES 9.07E+01 1.28E+02 0.00E+00 0.00E+00 KR-87 CURIES 1.68E+01 1.81E+01 0.00E+00 0.00E+00 AR-41 CURIES 0.00E+00 5.64E+00 0.00E+00 0.00E+00 KR-85M CURIES 1.75E+00 3.09E+00 0.00E+00 0.00E+00 XE-135 CURIES 1.60E+01 2.28E+01 0.00E+00 0.00E+00 XE-133 CURIES 0.00E+00 4.52E+00 0.00E+00 0.00E+00 XE-131M CURIES 0.00E+00 5.49E+01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.26E+03 l 1.70E+03 l 0.00E+00 l 0.00E+00 l I

IODINES I.133 CURIES 7.69E-02 9.38E-02 0.00E+09 0.00E+00 I-131 CURIES 1.39E-02 5.31E-03 0.00E+00 0.00E+00

-~s ................................................................................

(' ') TOTAL FOR PERIOD l CURIES l 9.08E-02 l 9.91E-02 l 0.00E+00 l 0.00E+00 l PARTICULATE l I-131 CURIES 1.38E-04 1.50E-04 0.00E+00 0.00E+00 BA-140 CURIES 6.46E-03' 8.90E-03 0.00E+00 0.00E+00 l CE-141 CURIES 2.33E-05 3.24E-05 0.00E+00 0.00E+00 l SR-89 CURIES 2.04E-03 4.54E-03 0.00E+00 0.00E+00 I ZN.65 CURIES 5.48E-06 0.00E+00 0.00E+00 0.00E+00 CE-144 CURIES 9.95E-05 1.22E-04 0.00E+00 0.00E+00 CO.60 CURIES 2.85E-06 0.00E+00 0.00E+00 0.00E+00 !

SR-90 CURIES 3.02E-05 6.61E-05 0.00E+00 0.00E+00 l CS-137 CURIES 4.50E-05 6.37E-05 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l 8.85E-03 l 1.39E.02 l 0.00E+00 l 0.00E+00

................................................................................l l l G-ALPHA CURIES 1.68E.08 2.33E-07 0.00E+00 0.00E+00 H-3 CURIES 2.73E-01 5.78E-01 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.

(

,s

)

There are no batch mode radioactive gaseous release pathways

, , at Plant Hatch.

l l

(50) l

TABLE 2-2C*

E. I. HATCH NUCLEAR PLANT ANFUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Elevated Level Releases Unit: Site i Starting : 1.Jul-1997 Ending : 31-Dec.1997

~, .

l l CONTINUOUS MODE l BATCH MODE ** l 1 NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l I

l l FISSION GASES i KR-89 CURIES 5.13E+01 0.00E+00 0.00E+00 0.00E+00 l XE.137 CURIES 7.38E+02 2.16E+02 0.00E+00 0.00E+00 XE.138 CURIES 2.78E+02 2.20E+02 0.00E+00 0.00E+00 XE-135M CURIES 9.09E+01 5.35E+01 0.00E+00 0.00E+00 KR-87 CURIES 1.12E+01 2.87E+01 0.00E+00 0.00E+00 AR.41 CURIES 1.48E+00 2.22E+00 0.00E+00 0.00E+00 KR-85M CURIES 3.44E+00 5.81E+00 0.00E+00 0.00E+00 XE-135 CURIES 1.61E+01 3.07E+01 0.00E+00 0.00E+00 XE-133 CURIES 1.15E+01 1.76E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l l 1.20E+03 l 5.59E+02 l 0.00E+00 l 0.00E+00 l

................................................................................ i t

IODINES I-132 CURIES 1.05E-03 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES

)

8.29E 02 4.28E-02 0.00E+00 0.00E+00 '

I-131 CURIES 4.62E-03 8.76E-03 0.00E+00 0.00E+00

()

\ ,,/

TOTAL FOR PERIOD CURIES l 8.85E.02 l 5.15E-02 l 0.00E+00 l 0.00E+00

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

PARTICULATE 1 I-131 CURIES 6.16E-05 1.36E-05 0.00E+00 0.00E+00 BA.140 CURIES 4.35E-03 7.50E-04 0.00E+00 0.00E+00 CR-51 CURIES 0.00E+00 5.17E-05 0.00E+00 0.00E+00 CE-141 CURIES 1.73E-05 3.76E-06 0.00E+00 0.00E+00 SR-89 CURIES 1.22E-03 1.57E-04 0.00E+00 0.00E+00 H ZN-65 CURIES 0.00E+00 7.18E-06 0.00E+00 0.00E+00 CE-144 CURIES 6.79E-05 3.06E 06 0.00E+00 0.00E+00 MN-54 CURIES 0.00E+00 5.55E-06 0.00E+00 0.00E+00 CO 60 CURIES 0.00E+00 2.63E-06 0.00E+00 0.00E+00 SR-90 CURIES 1.41E-05 2.39E-06 0.00E+00 0.00E+00 CS-137 CURIES 3.99E-05 6.47E-06 0.00E+00 0.00E+00

................................................................................ l TOTAL FOR PERIOD CURIES

................................................................................l l l 5.77E.03 l 1.00E-03 l 0.00E+00 l 0.00E+00 H-3 CURIES . 8.07E-01 4.50E-01 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 f-s detectable concentrations.

k-/ **

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

(51)

TABLE 2-3A*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Ground Level Releases Unit: 1 Starting : 1-Jan.1997 Ending : 30-Jun-1997 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-135M CURIES 4.48E+01 9.35E-01 0.00E+00 0.00E<00 XE-135 CURIES 3.70E+01 2.03E+01 0.00E+00 0.00E+0C TOTAL FOR PERIOD CURIES l l 8.18E+01 l 2.12E+01 l 0.00E+00 l 0.00E+00 l IODINES I-133 CURIES 1.77E-02 4.78E-02 0.00E+00 0.00E+00 I-131 CURIES 1.16E-03 2.15E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES j.1.89E-02 l 4.99E-02 l 0.00E+00 l 0.00E+00 l PARTICULATE \

Q k,j I-131 BA-140 CURIES CURIES 6.18E-05 2.53E-04 1.84E-04 4.24E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 y

j CR-51 CURIES 1.75E-04 0.00E+00 0.00E+00 0.00E+00 i CE-141 CURIES 4.04E-06 8.95E-06 0.00E+00 0.00E+00 l SR-89 CURIES 8.46E-05 3.41E-04 0.00E+00 0.00E+00 CO-58 CURIES 9.52E-06 0.00E+00 0.00E+00 0.00E+00 -

ZN-65 CURIES 7.21E-05 0.00E+00 0.00E+00 0.00E+00 MN-54 CURIES 3.48E-06 0.00E+00 0.00E+00 0.00E+00 CO-60 CURIES 3.28E-06 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 1.25E-06 2.37E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l l 6.69E-04 l 9.60E-04 l 0.00E+00 l 0.00E+00

.................................................................l ,

1 i

.........................___..............................__.................... i G-ALPHA CURIES- 6.10E-07 6.10E-07 0.00E+00 0.00E+00 '

H3 CURT.ES 1.22E+00 1.76E+00 0.00E+00 0.00E+00 1

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

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

A L

(52)

TABLE 2-3A* l E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ;

Gaseous Effluents-Ground Level Releases I Unit: 1

( Starting : 1-Jul-1997 Ending : 31-Dec-1997

\

l CONTINUOUS MODE l BATCH MODE **

lI NUCLIDES RELEASED l UNIT jQUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION GASES XE-135 CURIES 1.77E+01 2.44E+00 0.00E+00 0.00E+00 XE-133 CURIES 1.30E+01 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.06E+01 l 2.44E+00 l 0.00E+00 l 0.00E+00 l l

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

l IODINES I-133 CURIES 1.07E-02 4.31E-03 0.00E+00 0.00E+00 I-131 CURIES 5.03E-04 2.67E-04 0.00E+00 0.00E+00 TbTkLFbkPbkkbb f bbkkhb f k$kbb5bb f k bbb$bb f b$bbb bb f b$bbb bb f PARTICULATE I-131 CURIEG 1.32E-05 1.88E-05 0.00E+00 0.00E+00 BA-140 CURIES 4.06E-05 4.56E-05 0.00E+00 0.00E+00 CR-51 CURIES 0.00E+00 1.00E-05 0.00E+00 0.00E+00 CE-141 CURIES 1.08E-06 0.00E+00 0.00E+00 0.00E+00 SR-89 CURIES 2.54E-05 3.49E-05 0.00E+00 0.00E+00 CO-60 CURIES 2.08E-06 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 1.16E-07 2.47E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 8.26E-05 l 1.10E-04 l 0.00E+00 l 0.00E+00 l G ALPHA CURIES 1.46E-06 4.95E-07 0.00E+00 0.00E+00 H-3 CURIES 8.39E-01 5.47E-01 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.

(53)

{

TABLE 2-3B0 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Ground Level Releases Unit: 2 Starting : 1-Jan.1997 Ending : 30.Jun-1997 CONTINUOUS MODE

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

l QUARTER 1 l QUARTER 2

..........................................................lQ.UARTER 1 l QUARTER 2 l FISSION GASES XE-135 CURIES 1.25E+01 7.81E+00 XE.133 0.00E+00 0.00E+00 CURIES 9.26E+00 0.00E+00 0.00E+00 0.00E+0

............................................................................ 0...

TOTAL FOR PERIOD l CURIES l 2.18E+01 l 7.81E+00 0.00E+00

..........................................................l...........l...0E+00 0.0 l

IODINES I-133 CURIES 1.00E-01 I-131 1.32E-01 0.00E+00 0.00E+00 CURIES 4.39E-03 5.03E-03 0.00E+00

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

TOTAL FOR PERIOD CURIES 0E+00 0.0 l l 1.04E.01 l 1.37E-01 0.00E+00

..........................................................l...........l..00E+00 0 l

PARTICULATE I-131 O BA-140 CE-141 CURIES CURIES CURIES 4.12E-04 9.03E-04 4.88E-05 5.00E-04 8.93E-04 5.13E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-89 CURIES 5.25E-04 AG-110M 1.15E-02 0.00E+00 0.00E+00 CURIES 0.00E+00 4.81E.06 0.00E+00 0.00E+00 SR-90 CURIES 3.05E-06 9.20E-05 CS-137 0.00E+00 0.00E+00 CURIES 9.32E-07 2.21E-07 0.00E+00 TOTAL FOR PERIOD CURIES 0.00E+00 ..........

l l 1.89E-03 1.30E-02 0.00E+00

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

l G-ALPHA CURIES H-3 1.51E-07 2.25E-06 0.00E+00 0.00E+00 CURIES 2.53E+00 2.65E+00

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

O (54)

TABLE 2-3B*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Ground Level Releases Unit: 2 Starting : 1-Jul-1997 Ending : 31.Dec-1997 I .............................................

l CONTINUOUS MODE BATCH MODE **

..........................................................l......................l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4

..........................................................lQ.UARTER 3 l QUARTER 4 l FISSION GASES XE-135 CURIES 9.25E+00 0.00E+00 0.00E+00 0.00E+00 XE-133 CURIES 4.09E+01 2.14E+01 0.00E+00 TOTAL FOR PERIOD CURIES 0.00E+00 ..........

l l 5.02E+01 l 2.14E+01 0.00E+00

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

l IODINES I-133 CURIES 2.15E-01 4.12E-02 I-131 0.00E+00 0.00E'LO CURIES 8.28E-03 3.72E-03 0.00E+00 TOTAL FOR PERIOD 0.00d+00 ..........

l CURIES l 2.24E-01 4.50E-02 0.00E+0

...............................................l...........l.......0 l 0.00E+00 l PARTICULATE I-131 CURIES 7.31E.04 BA-140 1.98E.04 0.00E+00 0.00E+00 CURIES 1.45E.03 3.59E-04 0.00E+00 0.00E+00 CE-141 CURIES 7.07E.05 SR-89 1.68E-05 0.00E+00 0.00E+00 CURIES 7.74E-04 3.97E-04 0.00E+00 0.00E+00 ZN.65 CURIES 1.88E-05 1.65E-05 AG-110M 0.00E+00 0.00E+00 CURIES 4.02E 06 0.00E+00 0.00E+00 0.00E+00 CO-60 CURIES 0.00E+00 SR-90 1.92E-06 0.00E+00 0.00E+00 CURIES 3.51E-06 1.36E-06 TOTAL FOR PERIOD CURIES 0.00E+00 0.00E+00 l l 3.06E-03 7.90E-04

...............................................l...........l.0.00E+00 l 0.00E+00 l G-ALPHA CURIES 1.72E-06 5.48E-07 H-3 0.00E+00 0.00E,00 CURIES 3.18E+00 2.15E+0

...................................................... 0......................... 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.

(55)

TABLE 2-3C*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents. Ground Level Releases Unit: Site Starting : 1-Jan.1997 Ending : 30-Jun-1997 CONTINUOUS MODE BATCH MODE **

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

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

2 l FISSION GASES XE-135M CURIES 4.48E+01 9.35E-01 0.00E+00 XE-135 0.00E+00 CURIES 4.95E+01 2.81E+01 0.00E+00 0.00E+00 XE-133 CURIES 9.26E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.04E+02 l 2.90E+01 l 0.00E+00 0.00E+00

.....................................................................l...........l IODINES I.133 FURIES 1.18E-01 I-131 1.80E.01 0.00E+00 0.00E+00 i TRIES 5.55E-03 7.18E.03 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES l 1.23E-01 l 1.87E-01 0.00E+00 l 0.00E+00

..........................................................l...........l...........l PARTICULATE I-131 CURIES 4.74E-04 6.84E-04 BA-140 0.00E+00 0.00E+00 CURIES 1.16E-03 1.32E-03 0.00E+00 0.00E+00 CR-51 CURIES 1.75E-04 0.00E+00 CE-141 0.00E+00 0.00E+00 CURIES 5.28E.05 6.02E-05 0.00E+00 0.00E+00 SR-89 CURIES 6.10E-04 1.18E-02 CO-58 0.00E+00 0.00E+00 CURIES 9.52E-06 0.00E+00 0.00E+00 0.00E+00 ZN-65 CURIES 7.11E-05 0.00E+00 AG-110M 0.00E+00 0.00E+00 CURIES 0.00E+00 4.81E.06 0.00E+00 0.00E+00 MN-54 CURIES 3.48E-06 0.00E+00 0.00E+00 0.00E+00 CO-60 CURIES 3.28E-06 0.00E+00 SR-90 0.00E+00 0.00E+00 CURIES 4.30E-06 9.44E-05 0.00E+00 0.00E+00 CS.137 CURIES 9.32E.07 2.21E-07 0.00E+0 TOTAL FOR PERIOD CURIES 0 0.00E+00 l l 2.56E.03 1.40E.02

...............................................l...........l.....E+00 l 0.00E+00 l 0.00 G. ALPHA CURIES 7.61E-07 2.86E.06 H-3 0.00E+00 0.00E+00 CURIES 3.75E+00 4.41E+00

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

(56)

TABLE 2-3C*

E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gaseous Effluents-Ground Level Releases Unit: Site Starting : 1-Jul.1997 Ending : 31-Dec-1997 b("T l CONTINUOUS MODE l BATCH MODE ** l

................................................................................ l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l I

................................................................................ l I

l FISSION GASES I

................................................................................ I XE-135 CURIES 2.69E+01 2.44E+00 0.00E+00 0.00E+00 XE-133 CURIES 5.39E+01 2.14E+01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 8.08E+01 l 2.38E+01 l 0.00E+00 l 0.00E+00 l l IODINES I I-133 CURIES 2.26E-01 4.55E-02 0.00E+00 0.00E+00 I 131 CURIES 8.78E-03 3.99E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 2.35E-01 l 4.95E-02 l 0.00E+00 l 0.00E+00 l PARTICULATE fw I-131 CURIES 7.45E-04 2.17E-04 0.00E+00 0.00E+00 BA-140

( CR-51 CURIES CURIES 1.50E-03 0.00E+00 4.04E-04 1.00E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 CURIES 7.18E-05 1.68E-05 0.00E+00 0.00E+00 SR-89 CURIES 8.00E-04 2.31E-04 0.00E+00 0.00E+00 ZN-65 CURIES 1.88E-05 1.65E-05 0.00E+00 0.00E+00 AG-110M CURIES 4.02E-06 0.00E+00 0.00E+00 0.00E+00 CO-60 CURIES 2.08E-06 1.92E-06 0.00E+00 0.00E+00 .l SR-90 CURIES 3.62E-06 1.61E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.14E-03 l 9.00E-04 l 0.00E+00 l 0.00E+00 l G-ALPHA CURIES 3.17E-06 1.04E-06 0.00E+00 0.00E+00 H-3 CURIES 4.02E+00 2.70E+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. l There are no batch mode radioactive gaseous release pathways at Plant Hatch.

, ?h 1

\ -) '

(57)

TABLE 2-4A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jan-1997 Ending: 30-Jun-1997 5

Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 1 Tech 2 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 6.39E-02 1.28E+00 1.79E-02 3.59E-01 Beta 10.0 mrad 4.16E-02 4.16E-01 2.46E-02 2.46E-01 Cumulative Doses per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 8.18E-02 8.18E-01 J Beta 20.0 mrad 6.62E-02 3.31E-01 ]

.......................................................................... 1 O

1 1

i

,)

l (58)

TABLE 2-4A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 IO 3 Starting: 01-Jul-1997 Ending: 31-Dec-1997 O

Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 3 Tech 4 ,, Tech Radi- Limit Spec Spec ation Limit Limit Beta mrad

.................................-02 10.0 2.26E 2.26E-01 4.33E-03 4.33E-02 Cumulative Doses per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit a;;a"""i;;;"";;r" i:;;;:;i""i:;;;;;;-"""""-~~ ~""""

Beta 20.0 mrad 9.32E-02 4.66E-01 l

l l t 4

)

J

.)

! b i

(59) l

I TABLE 2-4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 f Starting: 01-Jan.1997 Ending: 30-Jun-1997 l Cumulative Doses per Quarter l Type Tech Units Quarter % of Quarter % of of Spec 1 Tech 2 Tech Radi- Limit Spec Spec

! ation Limit Limit Gamma 5.0 mrad 1.18E-02 2.35E-01 9.63E-03 1.93E-01 Beta 10.0 mrad 1.83E-02 1.83E.01 1.48E-02 1.48E-01 i

l ..

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

,of Spec. Ending Tech Radi. Limit Date Spec ation Limit Gamma 10.0 mrad -2.14E-02 2.14E-01 Beta 20.0 mrad 3.32E-02 1.66E-01 t . ()

4 I

i i

k l

I l

(60) 1

TABLE 2-4B E. I. HATCH NUCLEAR PLANT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i AIR DOSES DUE TO GASEOUS RELEASES l

^ Unit: 2 f Starting: 01-Jul-1997 Ending: 31-Dec-1997

\

Cumulative Doses per Quarter Type Tech Units Quarter % of Quarter % of of Spec 3 Tech 4 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 1.39E-02 2.78E-01 5.14E-03 1.03E-01 Beta 10.0 mrad 2.49E-02 2.49E-01 8.71E-03 8.71E-02 Cumulative Doses.per Year Type Tech Units Year to % of of Spec Ending Tech Radi- Limit Date Spec ation Limit Gamma 10.0 mrad 4.04E-02 4.04E-01 Beta 20.0 mrad 6.68E-02 3.34E-01 ;

t, I

I (61)

)

. TABLE 2-5A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATE IN GASEOUS RELEASES Unit: 1 Start'ing: 01-Jan-1997

( Ending: 30-Jun-1997 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 4.46E 03 5.94E-02 1.11E-02 1.49E-01 Liver 7.5 mrem 9.54E-04 1.27E-02 1.31E-03 1.74E-02 TBody 7.5 mrem 1.26E-03 1.69E-02 2.10E-03 2.80E-02 Thyroid 7.5 mrem 4.63E-02 6.18E-01 7.06E-02 9.44E-01 Kidney 7.5 mrem 1.03E-03 1.37E-02 1.47E-03 1.96E-02 Lung 7.5 mrem 8.15E-04 1.09E-02 1.18E-03 1.57E-02 GILLI 7.5 mrem 9.45E-04 1.26E-02 1.48E-03 1.98E-02 Cumulative Doses per Year Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit Liver 15.0 mrem 2.26E-03 1.51E-02 TBody 15.0 mrem 3.37E-03 2.25E-02 Thyroid 15.0 mrem 1.17E-01 7.81E-01 Kidney 15.0 mrem 2.50E-03 1.66E-02 Lung 15.0 mrem 1.99E-03 1.33E-02 GILLI 15.0 mrem

..................................-03 2.43E 1.62E-02 l O (62)

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

AND PARTICULATE IN GASEOUS RELEASES .

Unit: 1

/' {

\, ' Starting: 01-Jul-1997 Ending: 31-Dec-1997 l

1 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter t of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 1.79E-03 2.39E-02 7.15E.04 9.54E-03 Liver 7.5 mrem 5.80E-04 7.73E-03 3.59E.04 4.79E-03 TBody 7.5 mrem 6.62E-04 8.83E-03 3.81E-04 5.08E-03 Thyroid 7.5 mrem 2.12E-02 2.82E-01 1.66E-02 2.21E-01 Kidney 7.5 mrem 6.20E-04 8.26E-03 3.94E.04 5.25E-03 Lung 7.5 mrem 5.06E-04 6.75E-03 3.16E-04 4.22E-03 GILLI 7.5 mrem 5.82E-04 7.75E-03 3.35E-04 4.46E-03 Cumulative Doses per Year Organ Tech Units Year to % of l Spec Ending Tech Limit Date Spec Limit g ..........................................................................

Q Bone Liver 15.0 15.0 mrem mrem 1.81E-02 3.20E-03 1.21E-01 2.13E-02 TBody 15.0 mrem 4.41E-03 2.94E-02 Thyroid 15.0 mrem 1.55E-01 1.03E+00 Kidney 15.0 mrem 3.51E-03 2.34E-02 Lung 15.0 mrem 2.82E-03 1.88E-02 GILLI 15.0 mrem 3.34E-03 2.23E-02 1

i 1

l 1

i k

(63) l

TABLE 2-5B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATE IN GASEOUS RELEASES O Starting: 01-Jan-1997 Unit: 2 Ending: 30-Jun-1997 Cumulative Doses per Quarter Organ Tech Unit Quarter i of Quarter t of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit l

~ ..........................................................................

Bone 7.5 mrem 9.19E-03 1.22E-01 1.54E-01 2.05E+00 l Liver 7.5 mrem 2.03E-03 2.70E-02 2.23E-03 2.98E-02 '

TBody 7.5 mrem 2.34E-03 3.12E-02 1.37E-02 1.83E-01 Thyroid 7.5 mrem 1.43E-01 1.91E+00 1.64E-01 2.19E+00 Kidney 7.5 mrem 2.39E-03 3.18E-02 2.66E-03 3.55E-02 Lung 7.5 mrem 1.73E-03 2.31E-02 4.34E-03 5.79E-02 GILLI 7.5 mrem 1.93E-03 2.58E-02 6.99E-03 9.32E-02 Cumulative Doses per Year Organ Tech Units Year to t of Spec Ending Tech Limit Date Spec Limit iO ..........................................................................

Bone Liver 15.0 15.0 mrem mrem 1.63E-01 4.26E-03 1.09E+00 2.84E-02 TBody 15.0 mrem 1.61E-02 1.07E-01 Thyroid 15.0 mrem 3.08E-01 2.05E+00 Kidney 15.0 mrem 5.05E-03 3.36E-02 Lung 15.0 mrem 6.07E-03 4.05E-02 GILLI 15.0 mrem 8.92E-03 5.95E-02 i

l

,O 5

(64)

TABLE 2-5B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATE IN GASEOUS RELEASES

' Unit: 2 Starting: 01-Jul-1997 Ending: 31-Dec.1997 Cumulative Doses per Quarter Organ Tech Unit Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit !

.......................................................................... ]

Bone 7.5 mrem 1.18E-02 1.57E-01 2.30E-03 3.07E-02 Liver 7.5 mrem 3.00E-03 4.00E-02 1.54E-03 2.05E-02 TBody 7.5 mrem 3.04E-03 4.05E-02 1.48E-03 1.97E-02 Thyroid 7.5 mrem 2.64E-01 3.52E+00 9.24E-02 1.23E+00 Kidney 7.5 mrem 3.70E-03 4.94E-02 1.75E-03 2.33E-02 Lung 7.5 mrem 2.32E-03 3.09E-02 1.30E-03 1.73E-02 GILLI 7.5 mrem 2.62E-03 3.49E-02 1.34E-03 1.79E-02 Cumulative Doses per Year.

l ..........

Organ Tech Units Year to % of Spec Ending Tech Limit Date Spec Limit

("% ..........................................................................

( Bone 15.0 mrem. 1.77E-01 1.18E+00 Liver 15.0 mrem 8.80E-03 5.87E-02 l TBody 15.0 mrem 2.06E-02 1.37E-01 l

Thyroid 15.0 mrem 6.64E-01 4.43E+00 Kidney 15.0 mrem 1.05E-02 7.00E-02 l Lung 15.0 mrem 9.69E-03 6.46E-02 l

GILLI 15.0 mrem 1.29E-02 8.59E-02 l

l l

i i

(65) t t -- - ------- - - - - -- - ------- _ ---- _ -

a TABLE 2-7 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES E. I. HATCH NUCLEAR PLANT JANUARY,1997 THROUGH DECEMBER,1997 The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achievedin laboratory analyses of gaseous radwaste samples.

RADIONUCLIDES MDC- UNITS Kr-87 2.94E-08 uCi/cc Kr-88 3.22E-08 uCi/cc Xe-133 2.30E-08 uCi/cc p Xe-133m 7.30E-08 uCl/cc Xe-135 8.73E-09 uCi/cc Xe-138 1.99E-07 uCi/cc I l-131 1.34E-13* l uCi/cc l-133 1.53E-13* uCi/cc Mn-54 1.62E-13* uCi /cc l Fe-59 3.42E-13* uCi/cc Co-58 1.30E-13* uCl/cc Co-60 1.54E-13* uCi/cc Zn-65 2.54E-13* uCi/cc Mo-99 9.61 E-13* uCi/cc Cs-134 1.42E-13* uCi/cc Cs-137 1.28E-13* uCi/cc Ce-141 1.26E-13* uCi/cc Ce-144 5.64E-13* uCi/cc Sr-89 1.10E-16 uCi/cc Sr-90 6.70E-16 uCi/cc H-3 4.00E-07 uCi/cc

Based on an estimated sample quantity of 4.078E+07 cc's.

O (66) I

i O 3.0 Solid Waste V

3.1 Regulatory Umits/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 l 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 l Technical Specification 5.6.3 The Radioactive Effluent Release Report covering the operation of the unit shall L be submitted in accordance with 10 CFR 50.36a. The report shall include a l summary of the quantities of radioactive liquid and gaseous effluents and solid I

waste released from the unit. The material provided shall be consistent with the l objectives outlined in the ODCM and the Process Control Program and in l conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

j 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, shall include a summary of the quantities of solid radwaste

- released 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.

1 O

(67)

= _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

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

a. Container volume.

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

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

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

1 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 q for the period in which the evaluation was reviewed and accepted by the PRB.

]

O 3.2 Solid Waste Dat .

J Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1 A and 3-1B.

I l

l O

(68) l

)

O EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997

'V JANUARY 1,1997 - DECEMBER 31,1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND ll TABLE 3-IA 1,

SEMI-ANNUAL REPORT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD COVERED: FROM 01/01 /97 TO 08/10/97 FOR UNIT: 1 & 2 i

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) j

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

a. Spent resins, filter sludges, evaporator m' 7.242E1 10 bottoms, etc. ]

C1 4.040E2 . E j i

b. Dry compressible waste, contaminated equip. m' 5.03051 20 etc. C1 0.50650 . E

c. Irradiated components, control rods, m' . E C1 . E . E j

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

e. Other (describe) m' . E equip. etc. C1 . E , E

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

ISOTOPE PERCENT CURIES a.Fe-55 55.25 223.2240 Co-60 25.41 102.6590 En-65 11.27 45.5350 Cs-137 01.39 5.6198 other 06.68 26.9650 b.Fe-55 58.39 4.9668 Co-60 13.72 1.1671 En-65 09.93 .8447 Cs-137 00.16 .0136 other 17.00 1.5141 c.

b e.

3. Solid Waste Disposition Number of Shipments Maia e? Pennenareme4an nameinmeinn i 14 Truck Barnwell B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipmarit a M~4= ef Tranannrenei nn name 4 ndian ,

l 0* N/A E/A 1

(69)

l i

I EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 JANUARY 1,1997 - DECEMBER 31,1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND 11 l i

TABLE 3-lA (c0NT'D)

I I

SEMI-ANNUAL REPORT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD COVERED: FROM 07/01 /97 TO 12/11/97 FOR UNIT i c?

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste UNIT 6 month Est.

Period Total ERROR %

a. Spent resins, filter sludges, evaporator m' 8.763E1 10 bottoms, etc. C1 1.928E3 . E

b. Dry compressible waste, contaminated equip. m' 1.301E2 20 etc. C1 2.279El . E

c. Irradiated components, control rods, m' E C1 . E . E

d. Control Rod Drive Filters m' . E C1 . E . E

e. Other (describe) m' . E equip. etc. C1 E

. . E

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

\

ISOTOPE PERCENT CURIES

~

a.Fe-55 43.56 839.8299 En.65 22.30 429.9508 Co*60 17.06 328.8389 Mn-54 08.61 165.8950 other 08.47 163.3091 b.Fe-55 58.39 13.3097 Co-60 13.72 3.1274 En-65 09.93 2.2635 Co 137 00.16 .0365

~ Eher o 17.80 4.0574 C. l d.

e.

3. Solid waste Disposition Number of shinm.nen Mad. of Tranannreneinn nameinmeinn 23 Truck Barnwell B. IRRADIATED FUEL SHIPMENTS (Disposition) womh.c ef shinm.nem Mna. ef trannnerencinn neneinmeinn 0 N/A /A o

(70)

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 JANUARY 1,1997 - DECEMBER 31,1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND ll TABLE 3-1B FORM TI'TLE:

OFFSITE DOSE CALCULATION MANUAL, SECTION 7.2, REPORT PERIOD COVERED FROM: 01 / 01 /97 TO: 06/30 /97 FOR UNIT: ONE & TWQ TYPE CURIE PRINCIPAL SURIAL NUMBER OF YOLUME OF TYPE SOLIDIFICATION OF QUANTITY / NUCLIDES/ CONTAINER COPrTAINERS EACH SHIPMENTI ACENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CONTAINER CUBIC FEET (77 3)

Dewatered 315 Fe 55, Zn 65 High 132.4 Type B 1

N/A O Resin Co 60, cs 137 Integrity Q Container Cask 10-142 Dewatered 89.00 Fe 55, Zn 65 High 12 202.1 Type A N/A Resin Co 60, Cs 137 Integrity Cask Container 14-210 Torus 7.45 Fe 55, Zn 65 1ligh 132.4 Type A 1 N/A Filters Co 60, cs 137 Integrity Cask DAW Container 14-210 DAW l.0562 Fe 55, Zn 65 Strong # # Strong N/A !

( Dry Active Co 60, Cs 137 Tight 18 92 Tight Waste) Containers Box B-25 B-25

Note that the size of the container and number of shipments varies due to the use of different waste processors.

O V

(71)

q Q EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 JANUARY 1,1997 - DECEMBER 31,1997 J

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND ll TABLE 3-1B (c0NT'D)

FORN TITLEI ~~~

OFFSITE DOSE CALCULATION MANUAL, SECTION 7.2, REPORT l

I PERIOD COVERED FROM: 7 / I /97 TO: 12 /31 /97 FOR UNIT: ONE & TWO J T)PE CURIE PRINCIPAL BURIAL NUMBER OF VOLUME OF TYPE SOLIDIFICATION OF QUANTITY / NUCLIDES/ CONTAINER CONTAINERS EACH SHIPMENT / AGENT WASTE DETERMINED DETERMINATION DESCRIPTION SHIPPED CONTAINER CONTAINER CUBIC FEET (IT 3)

Dewatered 1770 Fe 55, Zn 65 High 2 132.4 Type B N/A Resin Co 60, Mn 54 Integrity Cask Centainer 10-142 d Dewatered 158 Fe 55, Zn 65 High 14 202.1 Type A N/A Resin Co 60, Mn 54 Integrity Cask Container 14-210 Torus 18.5 Fe 55, Zn 65 High 1 132.4 Type A N/A Filters Co 60, Mn 54 Integrity Cask DAW Container 14-210 <

DAW 2.16 Fe 55, Zn 65 High 1 202.1 Type A N/A

( Dry Active Co 60, Cs 137 Integrity Cask Weste) Container 14-210 DAW 2.1344 Fe 55, Zn 65 Strong # # Strong N/A

( Dry Active Co 60, Cs 137 Tight 47 92 Tight Waste) Containers Box B-25 B-25 l # Note that the size of the container and number of shipments varies due to the use of different waste processors.

l l

O V

(72) l l j i

- -----------------J

I O

G 4.0 Changes to the ODCM 1

Pursuant to Technical Specification 5.5.1 and ODCM section 7.2.2.5 Licensee j 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 F 3dioactive 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, p the Camping Area, the Recreation Area, and the Visitors Center. Listed in Table Q 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 Lside the site boundary during the reporting period are presented in Table 4-1.

i

! O v

(73) {

l

_ _ - - - - --- _ - _ - - - - - - - I

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

(,,N) Starting: 01-Jan-1997 Ending: 30-Jun-1997 Page: 1 Location Name ROADSIDE PARK Distance (kilometers) 1.18E+00 Sector WNW Occupancy Factor 2.20E-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) 7.00E-06 Particulate D/Q (m-2) 2.01E-08 l

Mixed Mode Releases:

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

Noble Gas X/Q (sec/nG) 2.42E-08 Particulate X/Q (sec/m3) 2.37E-08 Particulate D/Q (m-2) 1.29E-09 q Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mram 1.60E-05 7.02E-06 2.30E-05 2.30E-05 Liver mrem 1.61E-05 6.45E-06 2.26E-05 2.26E-05 TBody l mrem 1.61E-05 6.37E-06 2.24E-05 2.24E-05 Thyroid mrem ]

4.41E-05 4.69E-05 9.10E-05 9.10E-05 Kidney mrem 1.62E-05 6.58E-06 2.28E-05 2.28E-05 l Lung mrem 1.62E-05 7.74E-06 2.39E-05 2.39E-05 GI-LLI mrem 1.61E-05 6.40E-06 2.25E-05 2.25E-05

............................................................................. j c

I l O

L) l (74) 1 m_________________-_ .

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !

DOSE TO A MEMBER OF THE PUBLIC

\ DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site I Starting: 01-Jan-1997 Ending: 30-Jun-1997 i

Page: 2 l Location Name CAMPING AREA

(

Distance (kilometers) 1.27E+00 Sector WNW Occupancy Factor 5.48E-03 (4.80E+01 hr/yr)

Age Group CHILD Ground Level Releases:

- 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 Particulate X/Q (sec/m3) 2.33E-08 Particulate D/Q (m-2) 1.21E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 3.46E-04 1.54E-04 5.00E-04 5.00E-04 Liver mrem 3.50E-04 1.41E-04 4.92E-04 4.92E-04 TBody mrem' 3.48E-04 1.40E-04 4.88E-04 4.88E-04 Thyroid mrem 9.53E-04 1.01E-03 1.97E-03 1.97E-03 Kidney mrem 3.52E-04 1.44E-04 4.96E-04 4.96E-04 Lung mrem 3.51E-04 1.69E-04 5.21E-04 5.21E-04 GI-LLI r. rem 3.48E-04 1.41E-04 4.89E-04 4.89E-04 s

(75)

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

! Starting: 01-Jan-1997 Ending: 30-Jun-1997 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 j Elev2ted Releases:

Noble Gas X/Q (sec/m3) 3.30E-08 Particulate X/Q (sec/m3) 3.21E-08 i

Particulate D/Q (m-2) 1.56E-09 A) i b

Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 1.37E-03 6.16E-04 1.99E-03 1.99E-03 l Liver mrem 1.39E-03 5.67E-04 1.96E-03 1.96E-03 i TBody mrem 1.38E-03 5.61E-04 1.94E-03 1.94E-03 l Thyroid mrem 3.78E-03 4.01E-03 7.79E-t,3 7.79E-03 Kidney mrem 1.40E-03 5.79E-04 1.98E-03 1.98E-03 Lung mrem 1.39E-03 6.78E-04 2.07E-03 2.07E-03 GI-LLI mrem 1.38E-03 5.64E-04 1.95E-03 1.95E-03 d

I s.J l

(76)

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

.[\ DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-1997 Ending: 30-Jun-1997 Page: 4 Location Name VISITORS CENTER Distance (kilometers) 6,*4E-01 Sector WI W Occupancy Factor 4.. E- 04 (4.00E+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.87E-05 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-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) 2.26E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 7.37E-05 3.01E-05 1.04E-04 1.04E-04 Liver mrem 7.46E-05 2.73E-05 1.02E-04 1.02E-04 TBody mrem 7.42E-05 2.69E-05 1.01E-04 1.01E-04 Thyroid mrem 2.12E 2.27E-04 4.39E-04 4.39E-04 Kidney mrem 7.51E-05 2.80E-05 1.03E-04 1.03E-04 Lung mrem 7.48E-05 3.37E-05 1.09E-04 1.09E-04 GI mrem 7.42E-05 2.71E-05

...-LLI 1.01E-04 1.01E-04 l

l O

(77)

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY t'~~~N Unit: Site

( ,) Starting: 01-Jul-1997 Ending: 31-Dec-1997 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) 7.00E-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) 1.29E-09 f3 .............................................................................

( ) Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 6.45E-06 2.10E-06 8.54E-06 3.15E-05 4 Liver mrem 6.68E-06 2.24E-06 8.92E-06 3.15E-05 1 TBody mrem 6.53E-06 2.21E-06 8.74E-06 3.12E-05 Thyroid mrem 5.78E-05 1.42E-05 7.19E-05

)

1.63E-04 l Kidney mrem 6.85E-06 2.28E-06 9.12E-06 3.19E-05 Lung mrem 6.64E-06 2.25E-06 8.89E-06 3.28E-05

)j GI-LLI mrem 6.50E-06 2.20E-06 8.70E-06 3.12E-05 1

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

l 1

1 of\

f I V

(78)

TABLE 4-1 j E. I. HATCH NUCLEA.R PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT J DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY j

/"' Unit: Site

( Starting: 01-Jul-1997 Ending: 31-Dec-1997 1

Page: 2 Location Name i CAMPING AREA l Distance (kilometers) 1.27E+00 1 Sector WNW Occupancy Factor 5.48E-03 (4.80E+01 hr/yr)

Age Group CHILD -]'

Ground Level Releases:

Noble Gas X/Q (sec/nG) 7.03E-06 Particulate X/Q (sec/m3) 6.27E-06 1 Particulate D/Q (m-2) 1.80E-08 Mixed Mode Releases: '

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

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

Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 1.41E-04 4.63E-05 1.87E-04 6.87E-04 Liver mrem 1.46E-04 4.94E-05 1.95E 04 6.87E-04 TBody mrem 1.43E-04 4.87E-05 1.91h 04 6.80E-04 Thyroid mrem 1.25E-03 3.06E-04 1. 5 E f,- 0 3 3.52E-03 Kidney mrem 1.50E-04 5.02E-05 2.0PE-04 6.96E-04 Lung mrem 1.45E-04 4.95E-05 1.FiE-04 7.15E-04 GI-LLI mrem 1.42E-04 4.85E-05 1,!1E-04 6.79E-04 l

(79) i i

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

-DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY 3

Unit: Site Starting: 01-Jul-1997 Ending: 31-Dec-1997 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 l 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 (soc /nG) N/A Particulate D/Q (m-2) N/A

-Elevated Releases:

Noble Gas X/Q (sec/nG) 3.30E-08 Particulate X/Q (sec/m3) 3.21E-08 Particulate D/Q (m-2) 1.56E-09 0s Units Quarter 3 Quarter 4 Quarters 3 and 4 Year to Ending Date i Bone mrem 5.66E-04 1.87E-04 7.52E-04 2.74E-03 ;

' Liver mrem 5.85E-04 1.99E-04 7.84E-04 2.74E-03 l TBody mrem 5.72E-04 1.96E-04 7.69E-04 2.71E-03 i Thyroid mrem 4.94E-03 1.22E-03 6.15E-03 1.39E-02 Kidney mrem 6.00E-04 2.02E-04 8.02E-04 2.78E-03 Lung mrem 5.82E-04 2.00E-04 7.81E-04 2.85E-03 GI-LLI mrem 5.70E-04 1.96E-04 7.66E-04 2.71E-03 i

1

\

(80)

TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-1997 Ending: 31-Dec-1997 Page: 4 Location Name VISITORS CENTER Distance (kilometers) 6.94E-01 Sector WSW Occupancy Factor 4.57E-04 (4.00E+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 1.87E-05 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 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) 2.26E-09 0 .............................................................................

Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending

............................................................Date Bone mrem 2.81E-05 Liver mrem 8.40E-06 3.65E-05 1.40E-04 2.92E-05 9.11E-06 3.83E-05 1.40E-04 TBody mrem 2.85E-05 8.96E-06 Thyroid mrem 3.74E-05 1.39E-04 2.81E-04 6.78E-05 3.49E-04 7.88E-04 Kidney mrem 3.00E.05 9.29E-06 3.93E-05 Lung mrem 2.90E-05 1.42E-04 GI 9.15E-06 3.82E-05 1.47E-04 mrem 2.83E-05 8.92E-06 3.73E-05 1.39E-04

....-LLI....................................................... .................

(81)

6.0 Major Changes to Liquid, Gaseous, and Solid Radwaste Treatment Systems O The Radioactive Effluent Release Report shall include. . . . any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to ODCM Chapter 7, Section 7.2.2.7.

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

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

Liquid Radwaste 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 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.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has retained this summary of required meteorological data on site in a file. It will be provided to the NRC upon request.

8.0 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 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, respectively.

O (82)

O There were no monitors out of service greater than thirty (30) days.

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.

I l

O (83)

l i

O SOUTHERN COMPANY 1

l l

E. I. HATCH NUCLEAR PLANT UNITS NO.1 & 2 j ANNUAL REPORT JANUARY 1,1997- DECEMBER 31,1997 APPENDIX A O

l O

R lcaso of Radioactive RHR Snrvics Wctar 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 contamination was noted on August 8,

/]

v 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 13.7 Ci and 25.6 Cl. 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 in the 1996 evaluation of the release which is documented in the 10CFR50.59 Evaluation titled " Unit 1 RHR Service Water: Release of Contaminated Water."

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 low 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 j to a member of the public from the release, and the necessity of using the radwaste treatment system. :

i MWO 1-96-02845 was worked during the 1997 Unit 1 outage to repair the leaks in the U1 FHR *B' Heat !

Exchanger. The RHR side of the Heat Exchanger was pressurized with helium and a heliur.: detector on !

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

in)

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

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, 1 closed up and placed back in service. The Chemistry Department has sampled and monitored the activity !

during operation of the Heat Exchanger.

]

l The highest concentrations of the radionuclides found in the RHRSW samples for 1997 are from March 4, l 1997. The total concentration released was 1.21 E-5 uci/ml.

Radionuclides Concentration ( Cl/ml)

Cr-51 1.07 E-6 Mn-54 2.37 E-6 Co-58 1.06 E-6 i Co-60 4.94 E-6 Zn-65 2.06 E-6 Cs-134 2.10 E-7 l

Cs-137 4.43 E-7 l

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 j for dissolved or entrained noble gases whose concentration shall be limited to 1 E-4 Cl/ml.

l-

The following discussion is based on a release duration of 1 minute, a release volume of 4,000 gal and a total dilution of only 10,000 gal. This !s a 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 n the concentration of each radionuclides in the mixture to its effluent concentration limit (ECL) was 1.15.

(j 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 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 10CFR20 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 comparison this 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 l was 6.66 E 5 mrem (2.2 E-3 % of its annuallimit) and the highest organ dose was 7.39 E 5 mrem to the l GI-LLI, gastrointestinal track, (7.4 E-4 % of its an.tual limit). The resultant doses are quite low and i essentially do not contribute to the quarterly and/or the annual dose limits. This provides a high degree of l 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 release of the RHRSW was much less than 0.06 mrem and the maximum organ dose was much less than 0.2 mrem.

1

] 10CFR20.1302(b)(i) requires that a licensee show compliance with the annual limit of 100 mrem to any (V 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 does not constitute a Licensee 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 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 concentrations are much less than the applicable limits.

Design Criterion 64 in Appendix A to 10CFR50 requires the monitoring of effluent discharge paths. This criterion was complied with by performance of the sampling and analysis of the RHRSW service water before its release.

l Compliance with Appendix 1 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 b 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 ssction 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 forthe licensee. First:

h)

%/

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 ofidentifying 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. The fourth action calls attention to the regulations 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 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.

Administrative controls and sampling have been established to ensure that any future releases would be within 10CFR20 limits, reference Lab Standing Order, SO-HPC-001-0896, and 64CH-ADM-001-OS.

O(N.

I O

O

GEORGIA POWER COMPANY PLANT E.I. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION 9 SHEET 1 OF 8

. . ~ . . ~ .

~

NUMBER: ~ N/A PROPOSED REVISION

N/A ,

l 0 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:

$ Release of Radioactive RHR Service Water 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 contamination was noted on August 8, 1996 and the second indication was noted on August 23,1996. The total activity in the RHRSW contained j I

within the heat exchanger and adjacent piping, which was conservatively estimated to be about 4,000 gallons, was respectively estimated to be about 13.7 Ci 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 j water side of the heat exchanger. To determine if the leak had been repaired, the service water loop of 1 the heat exchanger was decontaminated.by operating the RHRSW *B' Loop, and flushing the water to the circulating water fiume. 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 i I

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 f O

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 compliance with the relevant sections of the Technical Specifications (TS), the OOCM, 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 low 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.

t Radionuclides Concentration ( Cl/ml) Limjl( C1/mi)

Mn-54 4.26 E-7 3E5 Co-60 7.75 E 7 3 E-6 Zn-65 3.93 E-7 5E6 Xe-135 9.67 E-8 1 E-4 The following discussion is based on a release duration of 1 minute, a release volume of 4,000 gal and a total dilution of 2njy 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 concentration of each radionuclides in the mixture to its effluent concentration limit (ECL) was 0.14.

N/A 10AC-MGR-010-OS MGR-0020 REV 2

I GEORGIA POWER COMPANY PLANT E.I. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION 9 SHEET 2 OF 8 O sum of the EC is not exceede s tions must be less than ten (<10) to ensure that the concentration limit for the mixture s can be seen, the sum is much less than ten. .

(10CFR20 App .Jtx B states that the sum of the fractions of the nuclides divided by their effluent i

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 10CFR20 Appendix B ECLs and ensuring that the sum of the fractions is less than 10. The plant software performs the sum of the ECL fractions to ensure that it is less than 10. This ensures 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 3r 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 mrom (7.7 E-5 % of its annual limit) and the highest organ dose was 1.11 E-5 mrom to the G1-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 l assurance that the release in no way presented a threat to the hesith and safety of a member of the public, f 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 pnor to its discharge whenever the projected dose due to the release would exceed 0.06 l

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 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 mism 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 ccetion 2.1.2.

10CFR20.1501(a)(2)(li) & (iii) requires the licensee to evaluate the concentration or quantitles 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.

f This release does not constitute a Licensee Event Report (LER) based on the (11 lowing.

10CFR50.73(a)(2)(viii)(B) requires the licensee to report any liquid effluent release which exceeds 20 times the applicable concentrations specified in

0CFR20, 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 than the applicable limits.

Design Criterion 64 in Appendix A to 10CFR50 requires the monitoring of effluent discharge paths. This )

criterion was complied with by performance of the sampling and analysis of the RHRSW service water before its release.

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 concemed 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.J 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 o ODCM section 2.1.3.

N/A 10AC-MGR-010-OS MGR-0020 REV. 2

GEORGIA POWER COMPANY PLANT E.1. HATCH ,

FORM TITLE:

10 CFR 50.59 EVALUATION O SHEET 3 OF 8 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 i 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 to characterize the leak and test repairs, if required for safe plant operatiori, for required surveillance, or during an emergency. A plan is being developed to investigate, repair the leakage and perform post repair samples to ensure the leek has indeed been repaired. The fourth ac% calls attention to the regulations to be complied with (these are all addressed above) and states snat relemes must be monitored and cont elled. 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:

Case 1. Normal Operation based on sample results Case 2. Normal Operation with bounding assumptions Case 3. LOSP with bounding assumptions Case 4. LOCA/LOSP with the estimated smallleakage rate Case 5. LOCA/LOSP with bounding assumptions Case 1 is addressed in 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 conservative assumptions:

1) RHRSW heat exchanger and piping is filled with 4,000 gallons of Suppression Pool / Torus water. After starting the RHRSW pump the system volume b flushed out to the fiume 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. This assumes mixing with the circulating water flow stream. No credit is taken for dilution by the circulating water system volume, which is about 6,280,000 gallons. l 1

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 quarteny 1.5 mrem limit.

The cumulative organ dose is 1.94E-05 mrem which is 0.00039% of the quarter 1y 5.0 mrem limit.

The sum of the ECL fractions is 2.7 which is less than the 10 limit.

Consideration was given to RCS water being in it'e TLRSW system. However, this is not considered to j

be a credible event. During normal operation,ine: RHR system is presmrized via the jocky pumps, t! sing torus water. Thus, the worst case would be if To'us water completely b .1 the RHRSW loop. This is the !

case described above. RHR is used to circulate RCS water in the shutdown cooling mode during q shutdown operation. In this case, RHRSW wouk' 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 N/A 10AC-MGR-010-0S MGR-0020 REV. 2

GEORGIA POWER COMPANY PLANT E.L HATCH FORM TITLE:

10 CFR 50.59 EVALUATION O SHEET 4 OF 8

, O 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 flume. 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 es 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 flume from RHRSW discharge point to the point that the fiume overflows to the river is estimated to be about 1,000,000 gallons. For simplicity, and because complete mixing of the volumes cannot be assured,1/2 of this volume is considered for dilution. Thus, this case will be equivalent to the normal operating case, because the release of 4,000 gallons, diluted with 500,000 gpm is conservatively terminated after one minute, due to the expected RHRSW flow rate 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 accident.

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 O water could be transported to the RHRSW syskm 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 as the bounding case during normal operation. Samples taken f'trther 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 any 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 toms water. During post accident operation, no feakage to RHRSW can occur. Determining the actual leakage rate crior 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 greater than estimated leakage) are very small, and are within the licensing basis for 10CFR100 limit following an accident.

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 actualleakage 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 haat exchanger tube, which MGR-0020 REV. 2 N/A 10AC-MGR-010-OS

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GEORGIA POWER COMPANY PLANT E.I. HATCH FORM TITLE:

O SHEET 5 OF 8 q 10 CFR 50.59 EVALUATION 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 would 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 tutxa failure and failure of the operator l

l 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 a 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 Rom Whois Body, and about 35.4 Rem Organ Dose.

This is within the licensing basis for 10CFR100 limits of 25 Rem Whole Body and 300 Rem Organ Dose, after adding this dose to dose from all other sources (ref. Bechte! Calculation 305, rev. O, vol. 3, binder 24, {

I folder 2339 for source term concentrations). The dilution factor wus determined to be about 1/2 of the volume of the fiume between the RHRSW o scharge point and the fiume overflow to the river, which is equivalent to the LOSP case. No credit was taken for any mixing o'the remainder of the circulating water system volume, and the circulating w ater pumps are assumed to trip in this case, at the onset of the accident.

Administrative controls and sampling have been established to ensule that any future releases during normal operation would be within 10CFR20 limits reference Lab Standing Order. SO-HPC-001-0896. l h

M ONCE A. SCREENING QUESTION IS ANSWERED "YES", THE REMAINDER OF THE SCREENING QUESTIONS ARE NOT REQUIRED TO BE ANSWERED.

1 10 CFR 50.59 SCREENING (i.e., BLOCKS S AND O):

0 YES : @ No l

is the " ACTIVITY"itself a change to one of the following, OR is a change to one of the following required as a result of the " ACTIVITY":

a. the Technical Specifications and / or the Environmental Protection Plan (Non-Radiological) incorporated in the Operating License, 98 other licensing document (s) as defined in 00AC-REG 403-0S? l

b. l BASIS FOR ANSWER: l 9 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.

g JF the answer is "YES", ::omplete the CONTROL OF CHANGES TO LICENSING DOCUMENT M AND make it a part of the 10 CFR 50.59 EVALUATION package.

O N/A 10AC-MGR-010-OS MGR 0020 REV. 2

GEORGIA POWER COMPANY l l

PLANT E.I. HATCH FORM TITLE: O SHEET $ OF 8 10 CFR 50.59 EVALUATION O 10 CFR 50.59 SCREENING (CONTINUED): l l

E APPLICABLE / DESIRED, GO DIRECTLY TO A QUESTION THAT HAS A"YES" ANSWER Does the " ACTIVITY" to which this evaluation applies represent:

@ NO A change to the plant (EITHER temporary QB permanent) as described in

1. O YES the FSAR7 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.

,, , . . %. ,y 0 NO A change procedures described in the FSAR?

BASIS FOR ANSWER: l i

0 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 f O system. The systems and procedures used for their operation were not effected, the system operated as described within the FSAR, thus no change to the FSAR exists.

{

)

BASIS FOR ANSWER: l I

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 shutdown was not affected by this event nor was the health and safety of the public threatened event.

E the answers to ALL the questions in Blocks O and O are "No," complete Block IF the answer to ANY question In Blocks O and O is "YES," complete Blocks O tbj ogh G Tds DATE: 9/AP/94 PREPARED: Jhn Wadf DATE: 7/4/rg O REVIEWED: d APPROVED: / LLtd N /d M/NF/ DATE: 7 //// f4 e

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10AC-MGR-010-OS N/A MGR-0020 REV. 2

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GEORGIA POWER COMPANY PLANT E.I. HATCH FORM TITLE:

O SHEET 7 OF S 10 CFR 50.59 EVALUATION SAFETY EVALUATION

1. O YES @ NO Does the proposed "ACTNITY"incinase the probability of occurrence of an accident previously evaluated in the FSAR7

BASIS FOR ANSWER

1 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 heat sink as described in the FSAR.

2. O YES @ 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 system 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, a bounding case was considered, assuming that 4,000 gallons of torus water were in RHRSW prior to starting the system. ,

i For post accident cperation, a bounding case.was considered, assuming 4,000 gallons of torus water '

(using post-accident source terms) were in RHRSW prior to starting the system. This would require two single failures, which would not be a credible event. Even so, in both bounding cases, the radiological consequences are not increased above the licensing basis 10CFR100 limits evaluated in the FSAR. (See U1 FSAR, section 14.7, and U2 FSAR, section 15). In actuality, the leakage rates and anticipated releases are expected to be much lower than the bounding cases, which demonstrate this very conservative approach.

3. O YES @ NO Does the proposed "ACTNITY" increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the FSAR7 BASIS FOR ANSWER:

The operation of the RHR system is not affected by the small amount of inleakage as previously di==

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. l

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+. . - +-n n, ,n- . w,_

4. O YES @ NO Does the proposed " ACTIVITY" increase the (radiological) consequences of a malfunction of equipment important to safety previously evaluated in 0 the FSAR?

)

BASIS FOR ANSWER:

I N/A 10AC-MGR-010-OS l MGR-0020 REV. 2

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l

GEORGIA POWER COMPANY PLANT E.I. HATCH FORM TITLE:

10 CFR 50.59 EVALUATION O SHEET 8 OF 8 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. As discussed in the synopsis and the answer to question 2, conservative bounding cases are considered. Complete rupture of a heat exchangertube, coupled with excess leakage out of the system, or operator failure to start a pump, would be the only failures that could lead to the bounding case for post-LOCA/LOSP operation. Thus, the consequences due to failure or malfunction of eculoment ars, not increased.

5. [. YES @ NO Does the proposed " ACTIVITY" create the possibility of an accident of a different type than any previously evaluated in the FSAR7 BASIS FOR ANSWER:

The suspected leakage in the heat exchanger would not reduce the effectiveness of the RHR system in providing the required cooling and therefnre, does not create the possibility of a different type socident.

,;. nw . . ., -n, , . ~ ,-_ an.wwnne

6. O YES @ NO Does the proposed " ACTIVITY" create the possibility of a malfunction of O equipment important to safety of a different type than any previously evaluated in the FSAR7 BASIS FOR ANSWER:

O Due to the fact that the RHRSW opemtes at a higher pressure, any additional leairage in the heat exchanger would be from RHRSW into the system be'.ng cooled. Therefore, no increase in the possibility j of malfunction is introduced. During riormal operation with RHRSW not operating, any radioactivity detected will be measured and evaluated. No new failure modes are being introduced in the operation of '

i the RHRSW heat exchanger with this small leak. The leak rate has been bounded with conservative case considerations, thus, the possibility of malfunction of equipment of a different type is not created.

7. O YES @ NO Does the proposed " ACTIVITY" reduce the margin of safety as defined in f the basis for any Technical Specification? 1 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 discussed. This is further supported by consideration of NRCB 80-10, which requires this evaluation to be performed.

E a change to the Technical Specifications or ^3e Environmental Protection Plan (Non-Radiological) i required, QS E ANY of the questions in Block 9 is answered "YES," an unreviewed safety question IS indicated. In that case, approval from the NRC is required SEFORE the " ACTIVITY" can be implemented. Refer to subsection 8.5.1.2 for guidance on exceptions to this.

N/A 10AC-MGR-010-OS MGR-0020 REV. 2 A

HL-5621, Annual Radioactive Effluent Release Rept for Ei Hatch Nuclear Plant Covering Jan-Dec 1997

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HL-5621, Annual Radioactive Effluent Release Rept for Ei Hatch Nuclear Plant Covering Jan-Dec 1997

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Enclosure:

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