Text

Ei Hatch Nuclear Plant Annual Radioactive Effluent Release Rept for Jan-Dec 1995
	ML20108B297
Person / Time
Site:	Hatch
Issue date:	12/31/1995
From:	Beckham J; GEORGIA POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HL-5149, NUDOCS 9605030244
	Download: ML20108B297 (324)
	v • d • e

{{#Wiki_filter:I Georgia Power Company 40 inverness Center Parkway Post Offi::o Dox 1295 Birmingham, Alabama 35201 Telephone 205 877-7279 m

       $c'$r*e*IIe*/ Essa,                                                            GeorgiaPower Hatch Project                                                                te souttaxn ebctnc systixn April 30, 1996 Docket Nos. 50-321 50-366                                                       HL-5149 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, Georgia Power Company is providing six copies of the Plant Hatch Units 1 and 2 Annual Radioactive Efiluent Release RepoLThis report covers the period January 1,1995 through December 31,1995. Should you have any questions, please advise. Sincerely, y lk =- J. T. Beckham, Jr. DMC/eb

Enclosure:

Plant E. I. Hatch Units 1 & 2 Annual Radioactive Effluent Release Repon ec: (See next page.) 030043 9605030244 951231 '- PDR ADOCK 05000321 R PDR w .

GeorgiaPower d U.S. Nuclear Regulatory Commission Page Two April 30, 1996 cc: Georgia Power Company (w/o copies) Mr. H. L. Sumner, Jr., Nuclear Plant General Manager NORMS U.S. Nuclear Regulatory Commission. Washington. D.C. Mr. K. Jabbour, Licensing Project Manager - Hatch LLS. Nuclear Regulatory Commission. RegionJ1 Mr. S. D. Ebneter, Regional Administrator Mr. B. L. Holbrook, Senior Resident Inspector - Hatch American NuclearInsurers Mr. M. Marugg , State of Georgia Mr. J. L. Setser, Department of Natural Resources l HL-5149 1

I i

GEORGIA POWER COMPANY I >

} E. I. HATCH NUCLEAR PLANT UNITS NO.1 & 2 , i ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES t JANUARY 1,1995 THROUGH DECEMBER 31,1995 SECTION TITLE PAGE J 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 Radiologicalimpact on Man Due to Liquid Release 5 1.6 Abnormal Releases 5 2.0 Gaseous Effluents 29 2.1 ODCM Specifications 29 2.1.1 Dose Rate Limit 29 2.1.2 Air Dose Dem .4oble Gas 29

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. SECTION TITLE PAGE 2.1.3 Dose to Any Organ 29 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 30 2.2 Release Points of Gaseous Effluents 30 2.3 Total Quantities of Radioactivity, Dose Rates 31 and Cumulative Doses j 2.3.1 Fission and Activation Gas 31 2.3.2 Radiolodine, Tritium and Particulate Releases 31 2.3.3 Gross Alpha Release 32 j i 2.4 Gaseous Effluent Release Data 33 i l 2.4.1 Methodology 33 2.5 Radiological Impact Due to Gaseous Releases 35 2.6 . Abnormal Releases 35 3.0 Solid Waste 72 3.1 Regulatory LimitsITechnical Specifications 72 3.1.1 Solid Radioactive Waste System 72 3.1.2 Reporting Requirements 72 3.1.3 Process Control Program (PCP) 72 3.2 Solid Waste Data 73 4.0 Changes to the Plant Hatch ODCM 78 5.0 Doses to Members of the Public inside The 78 1 Site Boundary 6.0 Major Changes to the Liquid, Gaseous and 87 Solid Radwaste Treatment Systems

 . .. _ . _.._m._ . _ ... . . _ . __     . . . _ , . _ . _

O I SECTION TITLE PAGE 7.0 Meteorological Data 87 8.0 Inoperable Liquid or Gaseous Effluent 87 Monitoring instrumentation 9.0 Tanks Exceeding Curie Content Limits 88 i O i i 9 4 l 1 O ! l l I

O GEORGIA POWER COMPANY E. I. HATCH NUCLEAR PLANT UNITS NO.1 & 2 ANNUAL REPORT i PLANT RADIOACTIVE EFFLUENT RELEASES l TABLE LIST OF TABLES PAGE 1-1 A Liquid Effluents - Summation of All Releases 6 Unit 1 (Quarters 1 and 2) l 1-1 B Liquid Effluents - Summation of All Releases 7 Unit 2 (Quarters 1 and 2) 1-1C Liquid Effluents - Summation of All Releases 8 Site (Quarters 1 and 2) j 1-1 AA Liquid Effluents - Summation of All Releases 9 Unit 1 (Quarters 3 and 4) 1-1BB Liquid Effluents - Summation of All Releases 10 Unit 2 (Quarters 3 and 4) l 1-1CC Liquid Effluents - Summation Lf All Releases 11 Site (Quarters 3 and 4) 1-2A Liquid Effluents - Unit 1 (Quarters 1 and 2) 12 1-2B Liquid Effluents - Unit 2 (Quaders 1 and 2) 14 1-2C Liquid Effluents - Site (Quarters 1 and 2) 16 1-2AA Liquid Effluents - Unit 1 (Quarters 3 and 4) 18 1-2BB Liquid Effluents - Unit 2 (Quarters 3 and 4) 20 1-2CC Liquid Effluents - Site (Quarters 3 and 4) 22 l j

e 1 l l O TABLE UST OF TABLES PAGE 1-3A Doses to a Member of The Public Due to Liquid 24 Releases Unit 1 (Quarters 1 and 2) 1-38 Doses to a Member of The Public Due to Liquid 25 Releases Unit 2 (Quarters 1 and 2) 1-3AA Doses to a Member of The Public Due to Liquid 26 Releases Unit 1 (Quarters 3 and 4) 1-3BB Doses to a Member of The Public Due to Liquid 27 Releases Unit 2 (Quarters 3 and 4) 1-5 Minimum Detectable Concentration - 28 Liquid Sample Analysis 1 2-1A Gaseous Effluents - Summation of All 36 ! Releases - Unit 1 (Quarters 1 and 2) / O 2-1 B Gaseous Effluents - Summation of All 37 Releases -Unit 2 (Quarters 1 and 2) 2-1C Gaseous Effluents - Summation of All 38 ! Releases - Site (Quarters 1 and 2) j 2-1AA Gaseous Effluents - Summation of All 39 Releases - Unit 1 (Quarters 3 and 4) 2-1BB Gaseous Effluents - Summation of All 40 Releases -Unit 2 (Quarters 3 and 4) 2-1CC Gaseous Effluents - Summation of All 41 Releases - Site (Quarters 3 and 4) 2-2A Gaseous Effluents - Elevated Releases 42 Unit 1 (Quarters 1 and 2) 2-2B Gaseous Effluents - Elevated Releases 44 Unit 2 (Quarters 1 and 2)

1 TABLE LIST OF TABLES PAGE l 2-2C Gaseous Effluents - Elevated Releases 46 Site (Quarters 1 and 2) 2-2AA Gaseous Effluents - Elevated Releases 48 Unit 1 (Quarters 3 and 4) 2-2BB Gaseous Effluents - Elevated Releases 50 Unit 2 (Quarters 3 and 4) 2-2CC Gaseous Effluents - Elevated Releases & Site (Quarters 3 and 4) 2-3A Gaseous Effluents - Ground Level Release 54 Unit 1 (Quarters 1 and 2) 2-3B Gaseous Effluents - Ground Level Release 56 Unit 2 (Quarters 1 and 2) IN 2-3C Gaseous Effluents - Ground Level Release 58 Site (Quarters 1 and 2) 2-3AA Gaseous Effluents - Ground Level Release 60 Unit 1 (Quarters 3 and 4) 2-3BB Gaseous Effluents - Ground Level Release 61 i Unit 2 (Quarters 3 and 4) 2-3CC Gaseous Effluents - Ground Level Release 62 Site (Quarters 3 and 4) 2-4A Air Doses Due to Gaseous Releases - 63 Unit 1 (Quarters 1 and 2) 2-4B Air Doses Due to Gaseous Releases- 64 Unit 2 (Quarters 1 and 2) 2-4AA Air Doses Due to Gaseous Releases - 65 Unit 1 (Quarters 3 and 4) e

i 4 O O TABLE LIST OF TABLES PAGE 2-4BB Air Doses Due to Gaseous Releases - 66 Unit 2 (Quarters 3 and 4) 2-5A- Doses to a Member of the Public Due to 67 Radiolodine, Tritium, and Particulates in Gaseous Releases - Unit 1 (Quarters 1 and 2) 2-5B Doses to a Member of the Public Due to 68 Radiolodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 1 and 2) 2-5AA Doses to a Member of the Public Due to 69 Radiolodine, Tritiura, and Particulates in Gaseous Releases - Unit 1 (Quarters 3 and 4) 2-5BB Doses to a Member of the Public Due to 70 Radiolodine, Tritium, and Particulates in Gaseous Releases - Unit 2 (Quarters 3 and 4) 2-7 Minimum Detectable Concentration - 71 Gaseous Sample Ar. !yses 3-1 A,B Solid Waste and irradiated Fuel Shipments 74,76 4-1 Dose to A Member of the Public Due to Activities 79 Inside The Site Boundary 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 the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-4 microcuries/ml total activity. 1.1.2 Dose Limits The dose or dose commitment to a MEMDER OF THE PUBLIC from i 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 body and to less than or equal to 10 mrems to any organ, l 1.2 Effluent Concentration Limit (ECL) l ECL values used in determining allowable liquid radwaste release rates and concentrations for principal gamma emitters,1-131, tritium, 1

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 the establishment of prr ctical monitor set points which can accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table ll, Column 2. For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 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. (1)

l l 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 l                    Prior to release of any tank containing liquid radwaste, following               ,

the required recirculations, samples are collected and analyzed in ' accordance with the 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 which are released. Liquid radwaste sample analyses are performed as follows: ( MEASUREMENT FREQUENCY METHOD 1 l 1. Gamma isotopic Each Batch Gamma Spectroscopy , l with computerized l data reduction.

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

! 3. Tritium Monthly Distillation and Composite liquid scintillation counting i

4. Gross Alpha Monthly Gas flow proportional l Composite counting l !

5. Sr-89 & Sr-90 Quarterly Chemical separation )

Composite and gas flow I proportional or scintillation counting

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

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i i i I Gamma isotopic measurements are performed in-house using germanium . L detectors with a resolution of 2.0 kev or lower. The detectors are shielded by four inches of lead. A liquid radwaste sample is typically counted for 3000 seconds L and a peak search of the renulting gamma ray spectrum is performed. Energy , , and net count data for all significant peaks are determined, and a quantitative j reduction or MDC calculation is performed. This ensures that the MDC's are l 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-17,4, Cs-137, Ce-141 and Ce-144). The quantitative calculations, corrections for counting time, decay time, sample volume, sample ! geometry, detector efficiency, baseline counts, branching ratio and MDC ' calculations, are made based on the counts at the location in the spectrum where the peak for that radionuclide would be located, if present. 1 Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed

          . offsite.

The radionuclide concentrations determined by gamma spectroscopic analysis of a sample taken from a tank planned for release in addition to the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55 are used along with the corresponding ECL values to determine the ECL fraction for the tank planned for release. This ECL fraction is then used, with the appropriate safety factors, tolerance factors, and the expected dilution stream flow to calculate maximum permissible

 ;O         release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual' (ODCM) are not exceeded.

A monitor reading in excess of the calculated setpoint results 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. i Radionuclide concentrations, safety factors, dilution stream flow rate, j and the liquid effluent radiation monitor calibration factor are entered into the computer and a pre-release printout is generated. If the release is ! not permissible, appropriate warnings will be displayed on the computer screen. If the release is permissible, it is approved by the Chemistry Foreman on duty. The pertinent information is transferred manually from the prerelease printout to a one-page release permit which is forwarded to Radwaste Operations. When the release is completed, the release permit , is returned from Radwaste Operations to Chemistry with the actual release ! data included. These data are input into the computer and a post-release printout O , (3) , i

is generated. The post release printout contains the actual release rates, actual f release concentrations and quantities, actual dilution flow, and the calculated j doses to an individual. i 1.4 Liquid Effluent Release Data ! l 1 Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-1 A, 1-1 AA for Unit 1, Table 1-1B,1-1BB for Unit 2 and Table I-1C,1-1CC for the site; i and Table 1-2A,1-2AA for Unit 1,1-28,1-2BB for Unit 2, and Table 1-2C,1-2CC for the site. ; The values for the four categories of Tables 1-1 A,1-1 AA and 1-18,1-1BB and I- I 1C,1-1CC are calculated and the Tables completed as follows: 1 1

1. Fission and activation products - The total release values (not including 1 I

tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective quarter.

2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted y 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 radioaci;vity. l I O i (4)

i Other data pertinent to batch releases of radioactive liquid effluent from both units are as follows: Number of batch releases: 635 Total time period for batch releases: 83,182 minutes Maximum time period for a batch release: 210.0 minutes Average time period for batch releases: 131.00 minutes Minimum time period for a batch i release: 11 minutes Average stream flow during periods of release of liquid effluent into a flowing stream: 15,570 CFS 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,1-3AA for Unit 1 and 1-3B,1-3BB for Unit 2, for all four ! , g quarters. l V 1.6 Abnormal Releases There were no abnormal releases for this reporting period. i i

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TABLE 1-1A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents . Summation of All Releases Unit: 1 Starting : 1-Jan-1995 Ending : 30-Jun-1995 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR % l A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPRA) CURIES 4.54E-02 5.61E-02 4.70E+01 1

i l 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.39E-08 5.49E-08 ! 3. PERCENT OF APPLICABLE LIMIT % [ ................................................................................ l B. TRITIUM l

1. TOTAL RELEASE CURIES 8.72E+00 7.49E+00 3.70E+01

2. AVERAGE DILUTED CONCENTRATION l

   \[v ]/               DURING PERIOD                        uCi/ML       1.42E-05     7.33E-06 1

3. PERCENT OF APPLICABLE LIMIT %

C. DISSOLVED AND ENTRAINED GASES l 1. TOTAL RELEASE CURIES 5.07E-05 1.46E-04 1.00E+02 l ................................................................................ ! 2. AVERAGE ~ DILUTED CONCENTRATION l DURING PERIOD uCi/ML 8.26E.11 1.42E-10 l 3. PERCENT OF APPLICABLE LIMIT %

t D. GROSS ALPHA RADIOACTIVITY l

1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 1.20E+02 l

E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 2.92E+06 3.76E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 6.14E+08 1.02E+09 1.60E+02 i ................................................................................ I

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

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l i TABLE 1-1B l E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l l Liquid Effluents - Summation of All Releases l Unit: 2 l Starting : 1-Jan-1995 Ending : 30-Jun-1995 l l l

TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR % l 1 A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPRA) CURIES 1.81E-02 4.49E-02 4.70E+01 :

1

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uC1/ML 2.35E-08 5.40E-08 l

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

3. PERCENT OF APPLICABLE LIMIT %

B. TRITIUM

       ...............................__.............__................................                i

1. TOTAL RELEASE CURIES 2.86E+00 2.28E+00 3.70E+01 ;

["~} 2. AVERAGE DILUTED CONCENTRATION ) ( / DURING PERIOD uCi/ML 3.72E-06 2.75E-06

3. PERCENT OF APPLICABLE LIMIT %

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.90E-02 2.41E-02 1.00E+02

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

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.47E-08 2.89E-08

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 3.14E+06 3.16E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 7.69E+08 8.31E+08 1.60E+02 i

i

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

1-3A and 1-3B of this report. s

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TABLE 1-1C E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE, EFFLUENT RELEASE REPORT - 1995 i Liquid Effluents - Summation of All Releases Unit: Site Starting : 1-Jan-1995 Ending : 30.Jun-1995. TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT, ERROR % l l A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 6.35E-02 1.01E.01 4.70E+01
2. AVERAGE DILUTED CONCENTRATION L DURING PERIOD uCi/ML 4.59E-08 5.45E-08 I 3. PERCENT OF APPLICABLE LIMIT %

l B. TRITIUM l ................................................................................ l 1. TOTAL RELEASE CURIES 1.16E+01 9.78E+00 3.70E+01 l.

2. AVERAGE DILUTED CONCENTRATION (s.

DURING PERIOD uCi/ML 8.37E-06 5.28E-06 j _j

3. PERCENT OF APPLICABLE LIMIT %.

l ................................................................................ i C. DISSOLVED AND ENTRAINED GASES l l

            .1. TOTAL RELEASE                        CURIES      1.91E-02     2.42E-02  1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.38E-08 1.31E-08

3. PERCENT OF APPLICABLE LIMIT %

t I

D. GROSS ALPHA RADIOACTIVITY I

1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 1.20E+02 1.00E+01 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 6.06E+06 6.92E+06 F. VOLUME OF DILUTION WATER USED LITERS 1.38E+09 1.85E+09 1.60E+02

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

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l 4 l I t i ! rT TABLE 1-1AA I E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 i Liquid Effluents - Summation of All Releases Unit: 1 Starting : 1-Jul-1995 Ending : 31-Dec-1995 l TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT l ERROR % I i

             .....__.........................................................................            j 1

A. FISSION & ACTIVATION PRODUCTS i I

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.71E-02 1.92E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.23E-08 1.49E-08

3. PERCENT OF APPLICABLE LIMIT %

B. TRITIUM

1. TOTAL RELEASE CURIES 8.06E+00 1.06E+01 3.70E+01

  /'"T            2. AVERAGE DILUTED CONCENTRATION DURING PERIOD                       uCi/ML      5.82E-06     8.22E-06 I

l

  \x )'       ..............................__..............__................................

3. PERCENT OF APPLICABLE LIMIT %

i 1 C. DISSOLVED AND ENTRAINED GASES l

1. TOTAL RELEASE CURIES 1.04E-03 6.95E-03 1.00E+02 )

              ...........___ .................................................................            l

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.54E-10 5.40E-09

3. PERCENT OF APPLICABLE LIMIT %

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 1.91E-06 5.29E-07 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 5.03E+06 4.89E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.38E+09 1.29E+09 1.60E+02 I

I l I

Applicable limits are expressed in terms of dose. See Tables

! 1-3A and 1-3B of this report. !O l\ /

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TABLE 1-1BB ! E. I. HATCH NUCLEAR PLANT 1 l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 I l Liquid Effluents - Summation of All Releases l Unit: 2 l- Starting : 1-Jul-1995 Ending : 31-Dec-1995 i TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT I ERROR %

          ................................................................................                                                j A. FISSION f: ACTIVATION PRODUCTS I

1. TOTAL RELEASE (NOT INCLUDING .

TRITIUM, GASES, ALPHA) CURIES 4.61E-02 4.47E-02 4.70E+01 l

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.06E.08 3.36E-08

3. PERCENT OF APPLICABLE LIMIT % ,

I B. TRITIUM l g 2. AVERAGE DILUTED CONCENTRATION

    -j                   DURING PERIOD                                         uCi/ML        2.03E-06        2.69E-06 v        ................................................................................                                               l

3. PERCENT OF APPLICABLE LIMIT % j i

C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 3.70E-02 7.80E-03 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.26E-08 5.87E-09

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

3. PERCENT OF APPLICABLE LIMIT % l D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 5.80E-07 2.22E-06 1.20E+02 l E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 4.08E+06 4.28E+06 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.14E+09 1.33E+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 1-1CC E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995                            )

Liquid Effluents - Summation of All Releases j Unit: Site Starting : 1-Jul-1995 Ending : 31-Dec-1995 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR % 2............................................................................... l A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 6.32E-02 6.39E-02 4.70E+01

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.51E-08 2.44E.08

3. PERCENT OF APPLICABLE LIMIT %

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

l B. TRITIUM

1. TOTAL RELEASE CURIES 1.04E+01 1.42E+01 3.70E+01

2. AVERAGE DILUTED CONCENTRATION !

fN 4.11E-06 5.41E-06 ( i DURING PERIOD uCi/ML ! N- / ................................................................................

3. PERCENT OF APPLICABLE LIMIT %

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

1 C. DISSOLVED AND ENTRAINED GASES l

1. TOTAL RELEASE CURIES 3.80E-02 1.48E-02 1.00E+02

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.51E-08 5.64E-09

3. PERCENT OF APPLICABLE LIMIT %

D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 2.49E.06 2.75E.06 1.20E+02 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 9.11E+06 9.17E+06 1.00E+01 l F. VOLUME OF DILUTION WATER USED LITERS 2.52E+09 2.62E+09 1.60E+02 l, l

l

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

N t l i l I (11)

TABLE 1 2A* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents Unit: 1 Starting : 1-Jan-1995 Ending : 30-Jun-1995 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 l CURIES l 0.00E+00 l 0.00E+00 l 8.72E+00 l 7.49E+00 l FISSICN & ACTIVATION PRODUCTS AS-76 CURIES 0.00E+00 0.00E+00 1.91E-04 2.19E-04 BA-139 CURIES 0.00E+00 0.00E+00 0.00E+00 7.79E-06 BA-140 CURIES 0.00E+00 0.00E+00 1.65E-04 2.97E-04 CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00- 2.74E-04 CO-58 CURIES 0.00E+00 0.00E+00 6.47E-04 4.56E-04 ( CO-60 CR-51 CURIES CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.04E-02 1.38E-03 1.34E-02 1.66E-03 CS-134 CURIES 0.00E+00 0.00E+00 2.76E-05 3.12E-06 CS-137 CURIES 0.00E+00 0.00E+00 1.40E-03 1.12E-03 CU-64 CURIES 0.00E+00 0.00E+00 0.00E+00 6.49E-04 FE-55 CURIES 0.00E+00 0.00E+00 3.66E-03 8.15E-03 FE-59 CURIES 0.00E+00 0.00E+00 2.82E-04 5.27E-04' I-131 CURIES 0.00E+00 0.00E+00 1.11E-05 0.00E+00 I-133 CURIES 0.00E+00 0.00E+00 2.67E-05 2.97E-06 LA-140 CURIES 0.00E+00 0.00E+00 9.07E-06 1.26E-05 MN-54 CURIES 0.00E+00 0.00E+00 3.42E-03 3.09E-03 MN-56 CURIES 0.00E+00 0.00E+00 2.13E-05 1.91E-05 MO-99 CURIES 0.00E+00 0.00E+00 1.63E-05 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 2.50E-04 1.29E-05 NB-95 CURIES 0.00E+00 0.00E+00 3.22E-05 2.80E-05 NB-97 CURIES 0.00E+00 0.00E+00 1.37E-06 6.94E-05 RU-103 CURIES 0.00E+00 0.00E+00 0.00E+00 1.55E-06 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 2.41E-05 SB-125 CURIES 0.00E+00 0.00E+00 0.00E+00 2.97E-05 SR-89 CURIES 0.00E+00 0.00E+00 2.95E-05 1.19E-04 SR-90 CURIES 0.00E+00 0.00E+00 6.25E-13 2.70E-13 SR-91 CURIES 0.00Et00 0.00E+00 2.72E-04 6.57E-04 SR-92 CURIES 0.00E+00 0.00E+00 5.55E-05 6.72E-05 TC-99M CURIES 0.00E+00 0.00E+00 1.29E-04 2.72E-05 Y-91M CURIES 0.00E+00 0.00E+00 1.23E-04 5.12E-04 ZN-65 CURIES 0.00E+00 0.00E+00 2.28E-02 2.43E-02 ZN-69M CURIES 0.00E+00 0.00E+00 5.10E-05 2.38E-04 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 3.80E-05 (12)

. ~

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

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

 -- %                                                                                                                                  t
                                                                                                                                       ?

TABLE 1-2A* < E. I. HATCH NUCLEAR PLANT > ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995

Liquid Effluents ,

                                                                   -Unit: 1
                                        ; Starting :      1-Jan-1995               Ending : 30-Jun-1995                                 ,

l CONTINUOUS MODE ** l BATCH MODE l l

           ................................................................................                                             t NUCLIDE'                                 l    UNIT    l QUARTER 1 \ QUARTER 2 l QUARTER 1,\ QUARTER 2 l                     j 1

FISSION & ACTIVATION PRODUCTS l

           .................................................................................                                            3 TOTALS                                    l  CURIES    l 0.00E+00 l 0.00E+00 l 4.54E-02 l 5.61E-02 l l
                                                                                                                                        )

DISSOLVED AND ENTRAINED GASES 5 AR-41 CURIES 0.00E+00 0.00E+00 9.07E-06 7.68E-06 ! XE-133 CURIES 0.00E+00 0.00E+00 3.95E.06 1.57E-05 'l XE-135 0.00E+00 0.00E+00 f g CURIES 3.77E-05 1.22E-04 j TOTALS l CURIES l.0.00E+00 l 0.00E+00-l 5.07E.05 l 1.46E-04 l l

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

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

(13)

                                                              - ~~         --- -          -..a.,n.,,,         _ . , _ , . ,.
         ~                                               ~

i < 1 l l J

    %                                                                                                                        l
      )-

TABLE-1-2B* E. I. HATCH NUCLEAR. PLANT i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents Unit: 2 Starting : 1-Jan-1995 Ending : 30-Jun-1995 i 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 l CURIES l 0.00E+00 l 0.00E+00 l 2.86E+00 l 2.28E+00 l' i FISSION & ACTIVATION PRODUCTS l AS-76 CURIES 0.00E+00 0.00E+00 7.46E-04 3.63E-03 BA-133 CURIES 0.00E+00 0.00E+00 6.56E-06 0.00E+00 BA-140 CURIES 0.00E+00 0.00E+00 1.43E-04 3.70E-04 , CE-141 CURIES 0.00E+00 0.00E+00 0.00E+00 2.45E-05 l

 /       CE-144                      CURIES        0.00E+00      0.00E+00        1.48E-05           0.00E+00 (j%       CO-57                       CURIES        0.00E+00      0.00E+00        1.28E-06           5.22E-06 CO 58                       CURIES        0.00E+00      0.00E+00        2.50E-04           1.18E-03 l

CO-60 CURIES 0.00E+00 0.00E+00 1.62E-03 3.48E-03 i l CR-51 CURIES 0.00E+00 0.00E+00 6.37E-04 8.53E-03 CS-134 CURIES 0.00E+00 0.00E+00 1.03E-06 2.77E-05 CS-137 CURIES 0.00E+00 0.00E+00 5.35E-04 6.95E CS-138 CURIES 0.00E+00 0.00E+00 0.00E+00 2.60E-05 FE-55 CURIES 0.00E+00 0.00E+00 3.20E-04 3.15E-04 ! FE-59 CURIES 0.00E+00 0.00E+00 1.68E-04 1.63E-04 I-131 CURIES 0.00E+00 0.00E+00 3.12E-04 1.04E-03 I-132 CURIES 0.00E+00 0.00E+00 1.32E 04 3.38E-04 I-133 CURIES 0.00E+00 0.00E+00 1.87E-03 3.25E-03 I-134 CURIES 0.00E+00 0.00E+00 7.70E-06 0.00E+00 I-135 CURIES 0.00E+00 0.00E+00 1.14E-03 1.84E-03 LA-140 CURIES 0.00E+00 0.00E+00 4.9tE-05 3.92E-04 i MN-54 CURIES 0.00E+00 0.00E+00 7.65?.-04 1.23E-03 MN-56 CURIES 0.00E+00 0.00E+00 8.371 05 2.01E-05 MO-99 CURIES 0.00E+00 0.00E+00 0.00L+00 4.26E-04 NA-24 CURIES 0.00E+00 0.00E+00 5.56E-04 3.18E-03 NB-95 CURIES 0.00E+00 0.00E+00 1.08E-04 3.27E-06 NB-97 CURIES 0.00E+00 0.00E+00 8.76E-05 3.70E-04 NP-239 CURIES 0.00E+00 0.00E+00 1.54E-04 6.97E-04 RB-89 CURIES 0.00E+00 0.00E+00 0.00E+00 2.87E-05 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 6.41E-06 i SR-89 CURIES 0.00E+00 0.00E+00 1.48E-04 1.96E-04 SR-90 CURIES 0.00E+00 0.00E+00 1.77E-12 9.75E-06 l , SR-91 CURIES 0.00E+00 0.00E+00 5.52E-04 5.14E-04 ! SR-92 CURIES 0.00E+00 0.00E+00 9.34E-05 5.40E-05 r 4 (14)

q i

   \.l                                                                                                                       ;

I. L TABLE 1 2B* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 I Liquid Effluents I Unit: 2 I I Starting : 1-Jan-1995 Ending : 30.Jun-1995 l l , 1 i l l CONTINUOUS MODE ** j BATCH. MODE l NUCLIDE l- UNIT l QUARTER l'] QUARTER 2 l QUARTER 1 l QUART 7R 2 l ] FISSION & ACTIVATION PRODUCTS TC.99M CURIES 0.00E+00 0.00E+00 1.17E-04 1.92E.03 Y-91M' CURIES 0.00E+00 0.00E+00 1.08E-03 1.08E-03 l Y-92 CURIES 0.00E+00 0.00E+00 0.00E+00 5.64E-05 l ZN-65 CURIES 0.00E+00 0.00E+00 6.18E-03 9.68E-03 l ZN-69M CURIES 0.00E+00 0.00E+00 1.20E-04 9.63E 05 l ZR-95 CURIES 0.00E+00 0.00E+00 9.39E-05 5.98E.06 TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 1.81E-02 l 4.49E-02 l

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

(- DISSOLVED AND ENTRAINED GASES

          .................................................................................                                    i KR-85                               CURIES        0.00E+00          0.00E+00           0.00E+00      1.01E.03 i          XE-131M                             CURIES        0.00E+00          0.00E+00           0.00E+00      9.93E-05

XE-133 CURIES 0.00E+00 0.00E+00 2.65E-03 3.78E.03 )

i XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 1.59E.05 i ! XE-135 CURIES 0.00E+00 0.00E+00- 1.45E.02 1.33E-02 XE-135M CURIES 0.00E+00 0.00E+00 1.87E-03 5.90E-03 l

l. TOTALS l CURIES l 0.00E+00 \ 0.00E+00 l 1.90E-02 l 2.41E-02 l !

L ................................................................................ t V

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.

i t ! ( (15)

1 ( i O ! TABLE 1-2C* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents Unit: Site Starting : 1-Jan-1995 Ending : 30-Jun-1995 l CONTINUOUS MODE ** l BATCH MODE l l l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l-H-3 l CURIES l 0.00E+00 l 0.00E+00 l 1.16E+01 l 9.78E+00 l ' t l FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0.00E+00 0.00E+00 9.37E-04 3.85E-03 BA-133 CURIES 0.00E+00 0.00E+00 6.56E-06 0.00E+00 l BA-139 CURIES 0.00E+00 0.00E+00 0.00E+00 7.79E-06 l BA-140 CURIES- 0.00E+00 0.00E+00 3.08E-04 6.67E-04 CE-141 CURIES 0.00E+00 0.00E+00 0.00E+00 2.45E-05 ( CE-144 CURIES 0.00E+00 0.00E+00 1.48E-05 2.74E-04 i CO-57 CURIES 0.00E+00 0.00E+00 1.28E-06 5.22E-06 ! CO-58 CURIES 0.00E+00 0.00E+00 8.97E-04 1.63E-03 i i CO 60 CURIES 0.00E+00 0.00E+00 1.20E-02 1.69E-02 < l CR-51 CURIES 0.00E+00 0.00E+00 2.02E-03 1.02E 02 l l CS-134 CURIES 0.00E+00 0.00E+00 2.87E-05 3.08E-05 ! CS-137 CURIES 0.00E+00 0.00E+00- 1.93E-03 1.82E-03 l 0.00E+00 2.60E-05 CS-138 CURIES 0.00E+00 0.00E+00 CU-64 CURIES 0.00E+00 0.00E+00 0.00E+00 6.49E-04 FE-55 CURIES 0.00E+00 0.00E+00 3.98E 03 8.47E-03 FE-59 CURIES 0.00E+00 0.00E+00 4.50E-04 6.90E-04 I-131 CURIES 0.00E+00 0.00E+00 3.23E-04 1.04E-03 I-132~ CURIES 0.00E+00 0.00E+00 1.32E-04 3.38E-04 ( I-133 CURIES 0.00E+00 0.00E+00 1.90E-03 3.26E-03 I-134 CURIES 0.00E+00 0.00E+00 7.70E-06 0.00E+00 I-135 CURIES 0.00E+00 0.00E+00 1.14E-03 1.84E-03 ! LA-140 CURIES 0.00E+00 0.00E+00 5.85E-05 4.04E-04 l J MN-54 CURIES 0.00E+00 0.00E+00 4.18E-03 4.31E-03 i MN-56 CURIES 0.00E+00 0.00E+00 1.05E-04 3.92E-05 MO-99 CURIES 0.00E+00 0.00E+00 1.63E-05 4.26E-04 ! NA-24 CURIES 0.00E+00 0.00E+00 8.05E-04 3.20E-03 NB-95 CURIES 0.00E+00 0.00E+00 1.40E-04 3.13E-05 NB-97 CURIES 0.00E+00 0.00E+00 8.90E-05 4.39E-04 NP-239 CURIES 0.00E+00 0.00E+00 . 54E-04 6.97E-04 RB-89 CURIES 0.00E+00 0.00E+00 0.00E+00 2.87E-05 , RU-103 CURIES 0.00E+00 0.00E+00 0.00E+00 1.55E-06 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 3.06E-05 SB-125 CURIES 0.00E+00 0.00E+00 0.00E+00 2.97E-05 O (16)

l l

/"'

l \ TABLE 1-2C* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 3995 Liquid Effluents l Unit: Site Starting : 1-Jan-1995 Ending : 30-Jun-1995 l CONTINUOUS MODE ** l BATCH MODE l. NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER l'l QUARTER 2 l

       . FISSION & ACTIVATION PRODUCTS                                     ,

SR-89 CURIES 0.00E+00 0.00E+00 1.78E-04 3.15E-04 SR-90 CURIES 0.00E+00 0.00E+00 2.39E-12 9.75E-06 SR-91 CURIES 0.00E+00 0.00E+00 8.24E-04 1.17E-03 SR-92 CURIES 0.00E+00 0.00E+00 1.49E 1.21E-04 TC-99M CURIES 0.00E+00 0.00E+00 2.47E-04 1.94E-03 Y-91M CURIES 0.00E+00 0.00E+0C 1.20E-03 1.60E-03 Y-92 CURIES 0.00E+00 0.00E+00 0.00E+00 5.64E-05 ZN-65 CURIES 0.00E+00 C.00E+00 2.90E-02 3.40E-02 , ZN-69M CURIES 0.00E+00 1.71E-04 3.34E-04 ! ZR-95 -CURIES l0.00E+00 0.00E+00 l 0.00E+00 9.39E-05 4.40E-05 TOTALS l CURIES l 0.00E+00.1 0.00E+00 l 6.35E-02 l 1.01E-01 l DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 9.07E-06 7.68E-06 KR-85 CURIES 0.00E+00 0.00E+00 0.00E+00 1.01E-03 XE-131M CURIES 0.00E+00 0.00E+00 0.00E+00 9.93E-05 . XE-133 CURIES 0.00E+00 0.00E+00 2.66E-03 3.80E-03 i XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 1.59E-05 XE-135 CURIES 0.00E+00 0.00E+00 1.45E-02 1.34E-02 XE-135M CURIES 0.00E+00 0.00E+00 1.87E-03 5.90E-03 j TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 1.91E-02 l 2.42E-02 l

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

1 1 ** There are no continuous mode radioactive liquid release pathways at Plant Hatch. l (17)

l l

\~

TABLE 1-2AA* i E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents Unit: 1 Starting : 1-Jul-1995 Ending : 31-Dec-1995 t ! l CONTINUOUS MODE ** l BATCH MODE l i , I NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l I H-3 l CURIES l 0.00E+00 l 0.00E+00 l 8.06E+00 l 1.06E+01 [ 1 i FISSION & ACTIVATION PRODUCTS AS-76 CURIES 0.00E+00 0.00E+00 6.25E-05 7.39E-05 CO-58 CURIES 0.00E+00 0.00E+00 1.02E-06 5.51E-05 CO-60. CURIES 0.00E+00 0.00E+00 5.66E-03 3.37E-03 l CS-134 CURIES 0.00E+00 0.00E+00 1.24E-04 7.71E-04 i g"'s CS-136 CURIES 0.00E+00 0.00E+00 0.00E+00 3.56E-06 CS-137 CURIES 0.00E+00 0.00E+00 3.36E-03 8.17E-03 l( FE-55 I-131 CURIES CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.47E-03 2.98E-04 1.89E-03 5.53E-04 l I-132 CURIES 0.00E+00 0.00E+00 1.16E-05 0.00E+00 l I-133 CURIES 0.00E+00 0.00E+00 8.51E.05 3.16E-04 MN-54 CURIES 0.00E+00 0.00E+00 8.29E-04 4.45E-04 i NA-24 CURIES 0.00E+00 0.00E+00 1.41E-06 4.59E-04 l NP-239 CURIES 0.00E+00 0.00E+00 0.00E+00 2.03E-05 SR-89 CURIES 0.00E+00 0.00E+00 8.19E-05 1.53E-04 TC-99M CURIES 0.00E+00 0.00E+00 7.26E-06 6.21E-06 l TE-131 CURIES 0.00E+00 0.00E+00 0.00E+00 1.98E-06 Y-91M CURIES 0.00E+00 0.00E+00 0.00E+00 6.18E-07 ! l ZN-65 CURIES 0.00E+00 0.00E+00 4.07E-03 2.90E-03 ) ZN-69M CURIES 0.00E+00 0.00E+00 0.00E+00 2.70E-06 TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 1.71E-02 l 1.92E-02 l

                     ................................................................................                                           7 l

l DISSOLVED AND ENTRAINED GASES l ................................................................................ KR-85 CURIES 0.00E+00 0.00E+00 4.71E-04 5.55E-04 XE-133 CURIES 0.00E+00 0.00E+00 1.08E-04 1.28E-03 XE-135 CURIES 0.00E+00 0.00E+00 3.71E-04 5.06E-03 XE-135M CURIES 0.00E+00 0.00E+00 9.32E-05 6.52E-05 I ................................................................................ TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 1.04E-03 l 6.95E-03 l l

   /"'}              G-ALPHA                              l    CURIES      l 0.00E+00 l 0.00E+00 l 1.91E-06 l 5.29E-07                      l    1 q,                 ................................................................................

(18) l 4

/\

/ i \j TABLE 1-2AA* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents Unit: 1 Starting - 1-Jul-1995 Ending : 31-Dec-1995 l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 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.
,s m v

(19)

i i I TABLE 1-2BB* ! U. I. HATCH NUCLEAR PLANT ! ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 ; Liquid Effluents ; Unit: 2 ; Starting : 1-Jul-1995 Ending : 31-Dec-1995 i l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 \ QUARTER 3 l QUARTER 4 l H-3. l CURIES l 0.00E+00 l 0.00E+00 l 2.30E+00 l 3.58E+00.l i FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 6.79E-06 0.00E+00 AS-76 CURIES 0.00E+00 0.00E+00 1.07E-02 8.25E-03 BA-140 CURIES 0.00E+00 0.00E+00 7.62E-04 5.33E-05 CE-141 CURIES 0.00E+00 0.00E+00 3.90E-05 3.38E-06 CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.57E-95 0.00E+00 0.00E+00 5.53E-06 0.00E+00 Os CO-57 CO-58 CURIES CURIES 0.00E+00 0.00E+00 1.37E-03 1.71E-03 CO-60 CURIES 0.00E+00 0.00E+00 3.39E-03 1.19E-02 1 CR-51 CURIES 0.00E+00 0.00E+00 2.83E-04 2.15E-03 CS-134 CURIES 0.00E+00 0.00E+00 2.52E-05 1.76E-04 CS-136 CURIES 0.00E+00 0.00E+00 2.71E-05 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 7.02E-04 1.76E-03 FE-55 CURIES 0.00E+00 0.00E+00 1.63E-04 5.09E-04 FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 7.31E-05 i I-131 CURIES 0.00E+00 0.00E+00 1.02E-03 1.64E-04 l I-132 CURIES 0.00E+00 0.00E+00 2.90E-04 1.25E-05 ( I-133 CURIES 0.00E+00 0.00E+00 3.20E-03 2.48E-04 I-135 CURIES 0.00E+00 0.00E+00 1.76E-03 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 8.64E-04 6.73E-05 MN-54 ) CURIES 0.00E+00 0.00E+00 1.50E-03 2.77E-03 MN-56 CURIES 0.00E+00 0.00E+00 5.85E-05 3.11E-05 MO-99 CURIES 0.00E+00 0.00E+00 1.4]E-03 1.21E-04 NA-24 CURIES 0.00E+00 0.00E+00 4.15E-03 1.14E-03 NB-97 CURIES 0.00E+00 0.00E+00 1.65E-03 6.86E-04 NP-239 CURIES 0.00E+00 0.00E+00 5.93E-04 1.71E-04 SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 9.75E-06 SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 3.21E-06 SR 89 CURIES 0.00E+00 0.00E+00 2.72E-04 1.30E-04 SR-90 CURIES 0.00E+00 0.00E+00 5.72E-06 2.59E-05 SR-91 CUD.IES 0.00E+00 0.00E+00 1.23E-03 8.14E-05 SR-92 CURIES 0.00E+00 0.00E+00 1.89E-04 9.83E-06 TC-99M CURIES 0.00E+00 0.00E+00 3.01E-03 3.47E-04 ) TE-129 CURIES 0.00E+00 0.00E+00 0.00E+00 2.05E-05 l C (20)

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

L i i i TABLE 1-2BB* E. I. HATCH NUCLEAR PIANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 i Liquid Effluents Unit: 2 l Starting : 1-Jul-1995 Ending : 31-Dec-1995 i l CONTINUOUS MODE ** l BATCH MODE l l NUCLIDE 'l UNIT lQUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION & ACTIVATION PRODUCTS Y-91M CURIES 0.00E+00 0.00E+00 1.63E-03 1.46E-04 l Y-92 CURIES 0.00E+00 0.00E+00 2.89E-04 3.01E-04 l ZN.65 CURIES 0.00E+00 0.00E+00 5.45E-03 1.15E-02 ZN-69M CURIES 0.00E+00 0.00E+00 5.48E-05 3.46E-05 l l TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 4.61E 02 l 4.47E-02 l l ' 1 ! C DISSOLVED AND ENTRAINED GASES l AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 5.55E-06 , KR-85 CURIES 0.00E+00 0.00E+00 5.50E-04 3.33E-04 I i XE-131M CURIES 0.00E+00 0.00E+00 1.19E-04 0.00E+00 l XE-133 CURIES 0.00E+00 0.00E+00 7.87E-03 1.11E-03 l XE-133M CURIES 0.00E+00 0.00E+00 9.68E-05 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 2.46E-02 6.19E-03 XE-135M CURIES 0.00E+00 0.00E+00 3.79E-03 1.62E-04

         . TOTALS                                 l   CURIES              l 0.00E+00 l 0.00E+00 l 3.70E-02 l 7.80E-03 l                .

l ..................................................................... : l G-ALPHA l CURIES l 0.00E+00 l 0.00E+00 l 5.80E-07 l 2.22E-06 l

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

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

I [ (21)

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TABLE 1-2CC* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Liquid Effluents . Unit: Site Starting : 1-Jul-1995 Ending : 31-Dec-1995 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 l CURIES l 0.00E+00 l 0.00E+00 l 1.04E+01 l 1.42E+01 l l FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 6.79E-06 0.00E+00 ) AS-76 CURIES 0.00E+00 0.00E+00 1.07E-02 8.32E-03 ' BA-140 CURIES 0.00E+00 0 . 0 0.c: + 00 7.82E-04 5.33E-05 , CE-141 CURIES 0.00E+00 0.00E4?0 3.90E-05 3.38E-06 CE-144 CURIES 0.00E+00 0.00E+b2 0.00E+00 1.57E-05 CO-57 CURIES 0.00E+00 0.00E+00 5.53E-06 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 1.37E-03 1.76E-03 CO-60 CURIES 0.00E+00 0.00E+00 9.05E-03 1.53E-02 CR-51 CURIES 0.00E+00 0.00E+00 2.83E-04 2.15E-03 CS-134 CURIES 0.00E+00 0.00E+00 1.49E-04 9.47E-04 CS-136 CURIES 0.00E+00 0.00E+00 2.71E-05 3.56E-06 CS-137 CURIES 0.00E+00 0.00E+00 4.06E-03 9.93E-03 FE 55 CURIES 0.00E+00 0.00E+00 2.63E-03 2.40E-03 FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 7.31E-05 I-131 CURIES 0.00E+00 0.00E+00 1.32E-03 7.17E-04 I-132 CURIES 0.00E+00 0.00E+00 3.02E-04 1.25E-05 I-133 CURIES 0.00E+00 0.00E+00 3.29E-03 5.64E-04 I 135 CURIES 0.00E+00 0.00E+00 1.76E-03 0.00E+00 LA-140 CURIES 0.00E+00 0.00E+00 8.64E-04 6.73E-05 MN-54 CURIES 0.00E+00 0.00E+00 2.33E-03 3.21E-03 MN-56 CURIES 0.00E+00 0.00E+00 5.85E-05 3.11E-05 MO-99 CURIES 0.00E+00 0.00E+00 1.41E-03 1.81E-04 NA-24 CURIES 0.00E+00 0.00E+00 4.15E-03 1.60E-03 NB-97 CURIES 0.00E+00 0.00E+00 1.65E-03 6.86E-04 NP-239 CURIES 3.00E+00 0.00E+00 5.93E-04 1.91E-04 . SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 9.75E-06 SB 124 CURIES 0.00E+00 0.00E+00 0.00E+00 3.21E-06 SR-89 CURIES 0.00E+00 0.00E+00 3.54E-04 2.83E-04 l SR-90 CURIES 0.00E+00 0.00E+00 5.72E-06 2.59E-05 SR-91 CURIES 0.00E+00 0.00E+00 1.23E-03 8.14E-05 SR-92 CURIES 0.00E+00 0.00E+00 1.89E-04 9.83E-06 TC-99M CURIES 0.00E+00 0.00E+00 3.02E-03 3.53E-04 < TE-129 CURIES 0.00E+00 0.00E+00 0.00E+00 2.05E-05 r%

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i l TABLE 1-2CC* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 i Liquid Effluents Unit: Site Starting : 1-Jul-1995 Ending : 31-Dec-1995 l l CONTINUOUS MODE ** l BATCH MODE l NUCLIDE l UNIT l QUARTER 3 lQUARTER 4 l QUARTER 3 lQUARTER 4 l FI3SION & ACTIVATION PRODUCTS TE-131 CURIES 0.00E+00 0.00E+00 0.00E+00 1.98E-06 Y-91M CURIES 0.00E+00 0.00E+00 1.63E-03 1.47E-04 Y-92 CURIES 0.00E+00 0.00E+00 2.89E.04 3.01E-04 ZN-65 CURIES 0.00E+00 0.00E+00 9.52E-03 1.44E-02 ZN-69M CURIES 0.00E+00 0.00E+00 5.48E-05 3.73E.05 TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 6'.32E-02 l 6.39E-02 l DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 5.55E-06 KR-85 CURIES 0.00E+00 0.00E+00 1.02E-03 8.89E-04 XE-131M CURIES 0.00E+00 0.00E+00 1.19E-04 0.00E+00 l l XE-133 CURIES 0.00E+00 0.00E+00 7.97E-03 2.39E-03 XE-133M CURIES 0.00E+00 0.00E+00 9.68E-05 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 2.49E-02 1.12E-02 XE-135M CURIES 0.00E+00 0.00E+00 3.88E-03 2.27E-04 TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 3.80E-02 l 1.48E-02 l G-ALPEA l CURIES l 0.00E+00 l 0.00E+00 l 2.49E-06 l 2.75E-06 l

Zeroes in this table indicate that no radioactivity was present

at detectable levels. See Table 1-5 for typical minimum l detectable concentrations. j i

           **        There are no continuous mode radioactive ligtid release                                                                !

pathways at Plant Hatch. i l 1 , 1 i I i 1 (23)

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TABLE 1-3A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Utit: 1 Starting: 01-Jan-1995 Ending: 30-Jun-1995 Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of l Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mrem 7.36E-03 1.47E-01 5.27E-03 1.05E-01 Liver 5.0 mrem 1.49E-02 2.98E-01 1.15E-02 2.29E-01 TBody 1.5 mrem 8.67E-03 5.78E-01 6.59E-03 4,39E-01 l Thyroid 5.0 mrem 1.44E-04 2.88E-03 4.24E-05 3.48E-04 i Kidney 5.0 mrem 7.48E-03 1.50E-01 6.03E-03 1.21E-01 Lung 5.0 mrem 8.42E-04 1.68E-02 5.30E-04 1.06E-02 , GILLI 5.0 mrem 1.08E-02 2.16E-01 1.05E-02 2.10E-01 ("'}j Cumulative Doses per Year

               ..........................................................................                                l Organ             CDCM          Units          Year to                % of                              1 Limit                         Ending                ODCM Date                 Limit Bone               10.0         mrem           1.26E-02               1.26E-01 Liver              10.0         mrem           2.64E-02               2.64E-01 TBody                3.0        mrem           1.53E-02               5.09E-01 Thyroid             10.0        mrem           1.87E-04               1.87E.03 Kidney              10.0        mrem           1.35E-02               1.35E-01 Lung                10.0        mrem           1.37E-03               1.37E-02 GILLI               10.0        mrem           2.13E-02               2.13E-01
   /"'N (24)

r . . TABLE 1-3B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jan-1995 Ending: 30-Jun-1995 Cumulative Doses per Quarter l l Organ ODCM Units Quarter % of Quarter % of l Limit 1 ODCM 2 ODCM l Limit Limit Bone 5.0 mrem 2.90E-03 5.79E-02 3.80E-03 7.60E-02 i Liver 5.0 mrem 5.40E-03 1.08E-01 7.30E-03 1.46E-01 TBody 1.5 mrem 3.13E-03 2.09E-01 4.28E-03 2.85E-01 Thyroid 5.0 mrem 3.23E-03 6.46E-02 8.10E-03 1.62E-01 i' l Kidney 5.0 mrem 2.63E-03 5.26E-02 3.65E-03 7.30E-02 Lung 5.0 mrem 3.54E-04 7.07E-03 4.44E-04 8.87E-03 , GILLI 5.0 mrem 2.76E 03 5.53E-02 4.59E-03 9.19E-02 i Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 6.70E-03 6.70E-02 Liver 10.0 mrem 1.27E-02 1.27E-01 TBody 3.0 mrem 7.41E-03 2.47E-01 Thyroid 10.0 mrem 1.13E-02 1.13E-01 Kidney 10.0 mrem 6.28E-03 6.28E-02 Lung 10.0 mrem 7.97E-04 7.97E-03 GILLI 10.0 mrem 7.36E-03 7.36E-02 i i J 1 4 1 1 1 (25) ; M

7 l r p b l ! s 6 t g , i I 5 TABLE 1 3AA E. I. HATCH NUCLEAR PLANT , ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES 1 Unit: 1 Starting: 01-Jul-1995 Ending: 31-Dec-1995 l I Cumulative Doses per Quarter. Organ .ODCM Units Quarter % of Quarter % of i Limit 3 ODCM 4 ODCM ! Limit Limit Bone 5.0 mrem 9.93E-03 1.99E-01 2.59E-02 5.18E-01 Liver 5.0 mrem 1.46E-02 2.93E-01 3.78E-02 7.56E-01 TBody 1.5 mrem 9.67E-03 6.45E-01 2.54E-02 1.69E+00 Thyroid 5.0 mrem 1.44E-03 2.88E-02 2.89E-03 5.77E-02 Kidney 5.0 mrem 5.30E-03 1.06E-01 1.31E-02 2.61E-01 l Lung 5.0 mrem 1.55E-03 3.10E-02 4.20E-03 8.40E-02 l GILLI 5.0 mrem 3.29E-03 6. 5!v E- 02 2.78E-03 5.56E-02 Cumulative Doses per Year Organ- ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 10.0 mrem 4.85E-02 4.85E-01 Liver 10.0 mrem, 7.88E-02 7.88E-01 TBody 3.0 mrem 5.03E-02 1.68E+00 Thyroid 10.0 mrem 4.51E-03 4.51E-02 l Kidney 10.0 mrem 3.19E-02 3.19E-01 Lung 10.0 mrem 7.12E-03 7.12E-02 GILLI 10.0 mrem 2.74E-02 2.74E-01 i 4 (26)

, _ . .. . - -.-._- _._.-._ _._.._.... _- . ~ . . - - - , . _..-. ,. , .. . - i t i i i I ! TABLE 1-3BB E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES ' l

                                                                       ' Unit: 2 Starting: 01-Jul-1995                                     Ending: 31-Dec-1995 l                                                                                                                                                     l l

t I Cumulative Doses per Quarter

                 ~ Organ                     ODCM    Units      Quarter                % of                 Quarter             % of                 I Limit                   3                 ODCM                      4              ODCM-                ,

! Limit Limit ! l t ( .......................................................................... l Bone 5.0 mrem 3.35E-03 6.71E-02 7.03E-03 1.41E-01 I L Liver 5.0 mrem 5.85E-03 1.17E-01 1.23E-02 2.45E-01 j TBody 1.5 mrem 3.62E.03 2.41E-01 7.97E-03 5.31E.01 , Thyroid' 5.0 mrem 7.63E-03 1.53E-01 1.13E-03 2.26E-02 l Kidney 5.0 mrem 2.75E-03 5.51E-02 5.18E-03 1.04E-01 Lung 5.0 mrem 4.47E-04 8.95E-03 9.83E-04 1.97E-02 r GILLI 5.0 mrem 3.75E-03 7.51E-02 8.12E-03 1.62E-01 ., r ( Cumulative Doses per Year Organ OnM Units Year to %'of L'ait Ending ODCM l Date Limit , Bone 10.0 mrem 1.71E-02 1.71E.01 , Liver 10.0 mrem 3.08E-02 3.08E-01 I l TBody 3.0 mrem 1.90E-02 6.33E-01 Thyroid 10.0 mrem 2.01E-02 2.01E-01 Kidney 10.0 mrem 1.42E.02 1.42E-01 Lung. 10.0 mrem 2.23E-03 2.23E-02 GILLI 10.0 mrem 1.92E-02 1.92E-01 l I l I' I h (27)

. .- .- . . - - -. . _ = _ - t TABLE 1-5 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES E. I. HATCH NUCLEAR PLANT JANUARY,1995 - DECEMBER,1995 The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of liquid radwaste samples. RADIONUCLIDE MDC UNITS Mn-54 1.97E-08 uCi/ml Fe-59 3.94E-08 uCi/mi Co-58 1.59E-08 uCi/ml Co-60 1.72E-08 uCi/ml Zn-65 2.92E-08 uCi/mi

 -       Mo-99                                         1.20E-07                 uCi/mi Cs-134                                        1.75E-08                 uCi/ml Cs-137                                        1.62E-08                 uCi/mi Ce-141                                        1.92E-08                 uCi/mi 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/mi   l Sr-89                                         1.44E-08                 uCi/mi    l Sr-90                                         8.50E-09                 uCi/ml H-3                                           6.00E-07                 uCi/mi l

4 i O (28)

i

           ;                  2.0           Gaseous Effluents 2.1           ODCM Specifications The ODCM Specifications presented in this section are for Unit 1 and Unit 2.           l l                                                                                                                                   ,

2.1.1 Dose Rate I.imit The dose rate due to radioactive materials released in gaseous effluents from the ! l 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 AirDose 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 , and all radionu^lides 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.

O (29)

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

2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) l O The annual (calendar year) dose or dose commitment to any MEMBER OF THE 1 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 l' 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 ven.t), Unit 1 reactor building vent; Unit 2 reactor building , vent, and the recombiner building vent. Each of these four paths is continuously ' monitored for gaseous radioactivity. Each is equipped with an integrating-type , sample collection device for collecting particulates and iodines. Unless required more frequently under certain circumstances samples are collected as follows: l 1. Noble gas samples are collected by grab sampling monthly. ) l l

2. Tritium samples are collected by grab sampling monthly. !

l 3. Radiciodine samples are collected by pulling the sample stream tnrough a charcoal cartridge over a 7-day period. L O 4. Particulates are collected by pulling the sample stream through a i particulate filter over a 7-day period.

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

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

Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, dose rates associated with gaseous releases, and 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 Plant Hatch ODCM.

iO (30)

              .               __             -_ _          -__                         _ _ _ _                      . _ _ . _ u

With 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 Quantitles of Radioactivity, Dose Rates, and Cumulative Doses l The methods for determining release quantities of radioactivity, dose ! rates, and cumulative doses follow: ! l 2.3.1 Fission and Activation Gas The released radioactivity is determined using sample analyses results I collected as described above and the average release flow rates over the period represented by the collected sample. Instantaneous dose rates due to noble gases, radioiodines, tritium, and particulates are calculated (with computer assistance). Calculated l dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for i noble gases, radiciodine, tritium, and particulates. Dose rate calculation i methodology is presented in the ODCM. i 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 Radiolodine, 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 are determined by gamma spectroscopy. Release quantities of particulates are determined using the weekly (filter) samples and release flow rates for the four release points. Gamma spectroscopy is used to quantify concentrations of principal gamma emitters. 1 (31)

        -.------.--...7.-.-                                                                                 ..

? 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 i dissolved together. Decay corrections are made back to the middle of the quarterly collection period. If Sr-89 or Sr-90 is not detected, MDC's are calculated. Strontium concentrations are input into the composite file of the : computer and used for release dose rate and individual dose calculations. l 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 indeperident laboratory and 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. ' l Dose rates due to radiciodine, tritium, and particulates are calculated for a hypothetical child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated for each release point, for each ; release period, and the total dose rates from both release points are l ,y compared to the dose rate limits specified in ODCM 3.1.2 : l l l Individual doses due to radiciodine, tritium and particulates are calculated l for the controlling receptor, which is described in the Plant Hatch ODCM. I 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 are compared to the dose limits specified in ODCM 3.1.4. The current percent of ODCM limits are shown on the printout for each release period. 2.3.3 Gmss Alpha Release The gross alpha release is computed each month by counting the particulate filters for each week for gross alpha activity in a proportional counter. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. The summed activity is then divided by the total monthly volume to determine the concentration. This concentration is input into the composite file of the computer and used for release calculations. I IO 1 (32)

i 2.4 ' Gaseous Effluent Release Data l O 2.4.1 Methodology i Regulatory Guide 1.21 Tables 1 A,1B, and 1C are found in this report as Tables ; 2-1 A, 2-1 AA,2-1 B, 2-1 BB, 2-1 C, 2-1 CC, 2-2A,' 2-2AA, 2-2B, 2-2BB, 2-2C, 2-2CC, 2-3A,2-3AA,2-3B,2-3BB,2-3C, and 2-3CC. 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, particulates, and tritium) was l 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 l ODCM limits are not applicable because we have no curie limits for gaseous releases. l Applicable limits are expressed in terms of dose. Noble gases are limited as ! specified in ODCM 3.1.2. The other three categcries (tritium, radioiodines, and , particulates) are limited as a group as specified in ODCM 3.1.2. j Dose rates due to noble gas releases, and due to radiciodine, tritium, and particulates 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. 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 particulates, are specified in ODCM 3.1.4. Cumulative individual doses j are presented in Table 2-5A, and 2-58, along with percent of ODCM limits. j The total or maximum error associated with the effluent measurement will include i the cumulative errors resulting from the total process of sampling and , measurement. Due to the difficulty with assigning error terms for each parameter ! affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective is to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste. Estimated errors are based on errors in 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. (33)

Fission and activation total release was calculated from sample analysis l results and release point flow rates. I Statistical error 60% Counting equipment calibration 10% l Vent flow Rates 10% l Non-steady release rates 20%- l TOTAL ERROR 100 % i l-131 releases were calculated from each weekly sample:- Statistical error 60% , l Counting equipment calibration 10% : l Vent Flow Rates 10% . Vent Sample Flow Rates 10% l Non-Steady release rates 10% ' l Losses from charcoal cartridges 10% ; i TOTAL ERROR 110 % Particulates with half lives greater than 8 days releases were calculated l l from sample and analysis results and release point flow rates. I Statistical error at MDC concentration 60% Counting equipment calibration 10% i Vent flow rates 10% l Vent sample flow rates 10% Non steady release rates 10% l TOTAL ERROR 100 % Total tritium releases were calculated from sample analysis results ! and release point flow rates. l Water vapor in sample stream determination 20 % l Vent flow rates 10% i Counting calibration and statistics 10% l Non-steady release rates 50% i TOTAL ERROR 90 % l iO , (34)

                                                                                          ~ _ _ _

l Gross Alpha radioactivity was calculated from sample analysis results ; and release point flow rates. Statistical error at MDC concentration 60% Counting equipment calibration 10% Vent flow rates 10% Vent sample flow rates 10% Non Steady release rates 10% TOTAL ERROR - 100 % j 2.5 RadiologicalImpact Due to Gaseous Releases Dose rates due to noble gas release were calculated for the site in accordance with ODCM 3.1.2. Dose rates due to radiciodine, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.1.2. These dose rates were calculated as part of the pre-release and post releasu .) . individual release permits. No limits were exceeded for this reporting period. Cumulative air doses due to noble gas releases were calculated for each unit in accordance with ODCM 3.1.4. These results are presented lO in Tables 2-6A ,and 2-6B,. Dose rates and doses were calculated using the methodology presented in the E. l. Hatch Nuclear Plant Offsite Dose Calculation Manual. 2.6 Abnormal Releases There were no unplanned releases during this reporting period. l f I !O (35)

   .__     . .                                                 _ _ _ . _ . .                        .    ._, __. , _ . _ _                m . _

l-. 1 TABLE 2-1A E. I. HATCH NUCLEAR PLANT ' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents - Summation of All Releases Unit: 1 , Starting : 1-Jan-1995 Ending : 30-Jun-1995 i 1 '? ! TYPE OF EFFLUENT UNITS' QUARTER 1 QUARTER 2 EST. TOT l ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE 2.69E+02 1.00E+02 CURIES 1.78E+02 !; 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.46E+01 2.27E+01; 3. PERCENT OF APPLICABLE LIMIT % * *
B. RADIOIODINES l I: 1. TOTAL IODINE-131 CURIES 7.30E-03 7.57E-03 1.10E+02 '; 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.39E-04 9.62E-04

       %             3. PERCENT OF APPLICABLE' LIMIT                                           %                  *               *                   ,

C. PARTICULATES

                ....-...........................................................................                                                        I

1. PARTICULATES(RALF-LIVES >8 DAYS) CURIES 2.51E-03 2.45E-03 1.00E+02 2.; AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.23E-04 3.12E-04

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPRA RADIOACTIVITY CURIES 9.34E-08 1.27E-07 l D. TRITIUM

1. TOTAL RELEASE CURIES 4.60E+00 5.11E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uC1/Sec 5.92E-01 6.50E.01

3. PERCENT OF APPLICABLE LIMIT % * *

                 ................................................................................                                                       I 1

i 1 l i

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

I (36) l

j h i TABLE 2-1B i E. I. HATCH NUCLEAR PLANT ) ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : 1-Jan-1995 Ending : 30-Jun-1995 TYPE OF EFFLUENT- UNITS QUARTER 1 QUARTER 2 'EST. TOT ERROR % A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 3.54E+02 1.34E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PhiIOD uCi/Sec 4.56E+01 1.70E+01

3. PERCENT OF APPLICABLE LIMIT % *

l B. RADIOIODINES i

1. TOTAL IODINE-131 CURIES 3.45E-03 4.27E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.44E-04 5.43E-04 4 l

3. PERCENT OF APPLICABLE LIMIT

 /"N                                                                                    %            *           *
    )                                                                                                                               1

( , ...................-............................................................ I' C. PARTICULATES

1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 2.03E-03 8.24E-04 1.00E+02 l

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.61E-04 1.05E-04

3. PERCENT OF APPLICABLE LIMIT % *

j

4. GROSS ALPHA RADIOACTIVITY CURIES 2.46E-07 3.22E-07 D. TRITIUM

1. TOTAL RELEASE CURIES 7.47E+00 7.78E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.60E.01 9.89E-01

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. (37)

                             - - . . ..~                    -

t l I l t f'" TABLE 2-1C i E. I. HATCH NUCLEAR PLANT : ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l Gaseous Effluents - Summation of All Releases , Unit: Site Starting : 1-Jan-1995 Ending : 30-Jun-1995 l r I E l l TYPE OF EFFLUENT UNITS QUARTER.1 QUARTER 2 EST. TOT l ERROR t , l l-A.' FISSION & ACTIVATION PRODUCTS l

1. TOTAL RELEASE CURIES 6.23E+02 3.12E+02 1.00E+02 r l ................................................................................

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec ~8.01E+01 3.97E+01 l ..................................._............................................

l 3. PERCENT OF APPLICABLE LIMIT %

t

[ B. RADIOIODINES j

1. TOTAL IODINE-131 CURIES 1.08E-02 1.18E-02 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.38E-03 1.51E-03

("' (

3. PERCENT OF APPLICABLE LIMIT t ~*

i C. PARTICULATES

1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 4.54E-03 3.28E-03 1.00E+02 ,

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.84E-04 4.17E-04 l 3. PERCENT OF APPLICABLE LIMIT %

I

, 4. GROSS ALPRA RADIOACTIVITY CURIES 3.40E-07 4.49E-07 t l i l D. TRITIUM j ................................................................................ 1 l 1. TOTAL RELEASE CURIES 1.21E+01 1.29E+01 9.00E+01 2 kVbkkbb kbLbkhb kkTb Fbk Pbkkbb ubi/bec k$hhbbb k$hkbbb -

3. PERCENT OF APPLICABLE LIMIT %

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

t 6 d (38) i __ .

TABLE 2-1AA E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents - Summation of AJ1 Releases Unit: 1 Starting : 1-Jul-1995 Ending : 31-Dec-1995 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR % A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.41E+02 1.30E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.78E+01 1.63E+01

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 8.91E-03 1.48E-03 1.10E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.12E-03 1.87E-04

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 8.69E-04 4.04E-04 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.09E-04 5.08E-05

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 4.20E-07 8.19E-07 D. TRITIUM

1. TOTAL RELEASE CURIES 9.22E+00 1.52E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.16E+00 1.91E-01

3. PERCENT OF APPLICABLE LIMIT % *

I l

l f l

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

(39)

i l l 1 r 1 2

i t i TABLE 2-1BB E. I. HATCH NUCLEAR PLANT t I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 t Gaseous Effluents - Summation of All-Releases Unit: 2 ; Starting : 1-Jul-1995 Ending : 31_-Dec-1995 l TYPE OF EFFLUENT UNITS . QUARTER 3 QUARTER 4 EST. TOT j ERROR % l 1 l A. FISSION & ACTIVATION PRODUCTS l

1. TOTAL RELEASE CURIES - 1.' 2 9 E + 0 2 1.17E+02 1.00E+02 ,;

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

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec- 1.62E+01 1.47E+01 l

                              -3. PERCENT OF APPLICABLE LIMIT                                                      %                   *              *                                :

B. RADIOIODINES l

1. TOTAL IODINE-131 CURIES 6.38E-03 1.5BE-03 1.10E+02;

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.03E-04 1.99E-04 i

3. PERCENT OF APPLICABLE LIMIT % *

l

                         ................................................................................l l
                       ' C. PARTICULATES

1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES. 2.64E-03 5.30E-04 1.00E+02'i

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

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec_ 3.33E-04 6.66E-05 j

3. PERCENT OF APPLICABLE LIMIT % *

l

4. GROSS ALPHA RADIOACTIVITY CURIES 6.73E-07 6.15E-07 I

D. TRITIUM l

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

1. TOTAL RELEASE CURIES 5.09E+00 2.70E+00 9.00E+01

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec .6.41E-01 3.40E-01

3. PERCENT OF APPLICABLE LIMIT %

1 1

1

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

(40)

 -                                                                                                                                                                  t t

TABLE 2-1CC E. I. HATCH NUCLEAR PLANT t i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 , l Gaseous Effluents - Summation of All Releases , Unit: Site l Starting : 1-Jul-1995 Ending : 31-Dec-1995 i ( ' TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT i ERROR % ! A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 2.70E+02 2.46E+02 1.00E+02

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.40E+01 3.10E+01 ;

   ................................................................................                                                                                 4

3. PERCENT OF APPLICABLE LIMIT % *

B. RADIOIODINES l

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

1. TOTAL IODINE-131 CURIES 1.53E-02 3.06E-03 1.10E+02 ,i

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.92E-03 3.85E-04 l

3. PERCENT OF APPLICABLE LIMIT % *

C. PARTICULATES

1. PARTICULATES(HALF. LIVES >8 DAYS) CURIES 3.51E-03 9.33E-04 1.00E+02 j

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.42E-04 1.17E-04 !

    ...............................................................................1                                                                                   <

3. PERCENT OF APPLICABLE LIMIT % * *

4. GROSS ALPHA RADIOACTIVITY CURIES 1.09E-06 1.43E-06 i

D. TRITIUM i

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

1. TOTAL RELEASE CURIES 1.43E+01 4.22E+00 9.00E+01l 2

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.80E+00 5.31E-01

3. PERCENT OF APPLICABLE LIMIT %

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

(41)

j i i p~ \ r TABLE 2-2A* E. I. HATCH NUCLEAR PLANT t ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Elevated Level Releases l Unit: 1 i Starting : 1-Jan-1995 Ending : 30-Jun-1995

                                                                .............................................                       i
                                                                 }        CONTINUOUS MODE       l          BATCH MODE **       l NUCLIDE3 RELEASED                         l     UNIT     l QUARTER 1 l QUARTER 2 \ QUARTER 1 l QUARTER 2 l l

FISSION GASES XE-138 CURIES 3.62E+01 3.51E+01 0.00E+00 0.00E+00 XE-135M CURIES 9.7BE+00 9.24E+00 0.00E+00 0.00E+00 KR 87 CURIES 2.24E+00 2.36E+00 0.00E+00 0.00E+00

       -AR-41                                          CURIES         3.99E-01      6.56E-01         0.00E+00        0.00E+00 KR-85M                                         CURIES         1.58E+00      1.75E+00          0.00E+00       0.00E+00 XE-135                                         CURIES         2.36E+00      2.64E+00          0.00E+00       0.00E+00       l XE-133                                         CURIES         9.48E+00      1.85E+01      -0.00E+00          0.00E+00 TOTAL FOR PERIOD                            l  CURIES      l 6.20E+01 l 7.02E+01 l 0.00E+00 l 0.00E+00 l f- g     ................................................................................

O IODINES I-135 CURIES 8.14E.04 0.00E+00 0.00E+00 0.00E+00 , I-133 CURIES 6.13E-03 7.80E-03 0.00E+00 0.00E+00 f I-131 CURIES 3.31E-04 1.08E-03 0.00E+00 0.00E+00 l TOTAL FOR PERIOD l CURIES l 7.28E-03 l 8.88E-03 l 0.00E+00 l 0.00E+00 l {

          ................................................................................                                          j PARTICULATES I-131                                         CURIES          4.60E-07      6.98E-07         0.00E+00       0.00E+00      !

BA-140 CURIES 1.40E-04 1.27E-04 0.00E+00 0.00E+00 SR-89 CURIES 6.85E-05 6.52E-06 0.00E+00 0.00E+00 ZN-65 CURIES 1.60E-06 1.21E-06 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 7.34E-07 0.00E+00 0.00E+00 SR-90 CURIES 1.30E-06 1.53E-07 0.00E+00 0.00E+00 : CS-137 CURIES 1.20E-06 1.10E-06 0.00E+00 0.00E+00

                                      ~                               ~             ~                ~           ~ '

TbTkL hbk'bbkkbb '} ~~Cbkkbb} b$5bb$bk'} 5$57b'bk'} b$bbb bb i b$bbb"bb +

H-3 CURIES 5.84E-01 7.19E-01 0.00E+00 0.00E+00 G (42)

TABLE 2 2A* E. I HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Elevated Level Releases Unit: 1 Starting : 1-Jan-1995 Ending : 30-Jun-1995 l CONTINUOUS MODE l BATCH MODE **. l NUCLIDES RELEASED. l UNIT l QUARTER 1 l QUARTER 2.l QUARTER 1 l QUARTER 2 l l

                 ................................................................................                                       i I

t

Zeroes in this' table indicate that no radioactivity was present ,l at detectable levels. See Table 2-7 for typical mir.imum i detectable concentrations. !

i

                 **      There are no batch mode radioactive gaseous release pathways                                                   ;

at Plant Hatch. ! l I i 9

                                                                                                                                        .I J

(43)

_ _ __ ...__.__._____.__m __ . . - . _ . . __ _ . . . _ ._ _. i . . r l

    .i~'                                                                                                                                                                                  ,

i I TABLE 2-2B* , E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Elevated Level Releases Unit: 2 Starting : 1-Jan-1995 Ending : 30.Jun-1995 l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l . t FISSION GASES , XE-138 CURIES 3.62E+01 3.51E+01 0.00E+00 0.00E+00 i . XE-135M CURIES 9.78E+00 9.24E+00 0.00E+00 0.00E+00 ! KR-87 CURIES 2.24E+00 2.36E+00 0.00E+00 0.00E+00 ' AR-41 CURIES 3.99E-01 6.56E-01 0.00E+00 0.00E+00 ; KR-85M CURIES 1.58E+00 1.75E+00 0.00E+00 0.00E+00 XE-135 CURIES 2.36E+00 2.64E+00 0.00E400 0.00E+00 XE-133 CURIES 9.48E+00 1.85E+01 0.00E+00 0.00E+00

                          . TOTAL FOR PERIOD                                   l       CURIES          l 6.20E+01 l 7.02E+01 l 0.00E+00 l 0.00E+00 l                                      l
   .("'T
      'v/                    IODINES
                             ................................................................................                                                                               l I-135                                                     CURIES               8.14E-04                  0.00E+00           0.00E+00        0.00E+00           l I-133                                                     CURIES               6.13E-03                  7.80E-03           0.00E+00        0.00E+00           l I-131                                                      CURIES              3.31E-04                  1.08E.03           0.00E+00        0.00E+00 TOTAL FOR PERIOD                                   l       CURIES          l 7.28E-03 l 8.88E-03 l 0.00E+00 l 0.00E+00 l 1

PARTICULATES . .. BA-140 CURIES 1.40E.04 1.27E.04 0.00E+00 0.00E+00 SR-89 CURIES 6.85E-05 6.52E-06 0.00E+00 0.00E+00 ZN-65 CURIES 1.60E-06 1.21E-06 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 7.34E-07 0.00E+00 0.00E+00 SR-90 CURIES 1.30E-06 1.53E.07 0.00E+00 0.00E+00 CS-137 CURIES 1.20E-06 1.10E.06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 2.13E-04 l 1.37E-04 l 0.00E+00 l 0.00E+00 l

                            .G-ALPHA                                                     CURIES              1.29E.08                   1.75E-08          0.00E+00          0.00E+00 H-3                                                        CURIES              5.84E-01                   7.19E-01          0.00E+00          0.00E+00 S

h \ . (44)

     ..-...>._._,.__.___,m                        . _ . - - _ _ _ . _ . -               . . _ . _          _ _ .    .- . _ _ . . _ _ . _ .

i TABLE 2-2B*'

                                                 .E. I. HATCH NUCLEAR PLANT                                                                     !

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 i reaseous Effluents-Elevated Level Releases ' Unit: 2 Starting : 1-Jan-1995 Ending : 30-Jun-1995 I i f l l CONTINUOUS MODE .l BATCH MODE ** . l, NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l l l

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

detectable concentrations. I

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

i i i I I i i 1 i I l d J (45) i

ks TABLE 2-2C* - E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Elevated Level Releases > Unit: Site j Starting : 1-Jan-1995 Ending : 30-Jun-1995 [ ............................................. f l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l l FISSION GASES XE-138 CURIES 7.23E+01 7.01E+01 0.00E+00 0.00E+00 XE-135M CURIES 1.96E+01 1.85E+01 0.00E+00 0.00E+00 l KR-87 CURIES 4.48E+00 4.72E+00 0.00E+00 0.00E+00 l AR-41 CURIES 7.97E-01 1.31E+00 0.00E+00 0.00E+00 l KR-85M CURIES 3.16E+00 3.49E+00 0.00E+00- 0.002+00 XE-135 CURIES 4.73E+00 5.29E+00 0.00E+00 0.00E+00 i XE-133 CURIES 1.90E+01 3.70E+01 0.00E+00 0.00E+00 l TOTAL FOR PERIOD l CURIES l 1.24E+02 l 1.40E+02 l 0.00E+00 l 0.00E+00 l ("'

j IODINES I-135 CURIES 1.63E-03 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 1.23E-02 1.56E-02 0.00E+00 0.00E+00 I.131 CURIES 6.61E-04 2.16E-03 0.00E+00 0.00E+00 l ................................................................................ t TOTAL FOR PERIOD l CURIES l 1.46E-02 l 1.78E-02 \~0.00E+00 l 0.00E+00 l PARTICULATES 1-131 CURIES 9.21E-07 1.40E-06 0.00E+00 0.00E+00 BA-140 CURIES 2.81E-04 2.53E-04 0.00E+00 0.00E+00 SR-89 CURIES 1.37E-04 1.30E-05 0.00E+00 0.00E+00 l ZN.65 CURIES 3.19E-06 2.42E-06 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 1.47E.06 0.00E+00 0.00E+00 SR-90 CURIES 2.60E-06 3.05E.07 0.00E+00 0.00E+00 CS-137 CURIES 2.40E-06 2.20E-06 0.00E+00 0.00E+00 j ................................................................................ TOTAL FOR PERIOD l CURIES l 4.27E-04 l 2.74E-04 l 0.00E+00 l 0.00E+00 l , G-ALPHA CURIES 2.58E-08 3.50E-08 0.00E+00 0.00E+00 H-3 CURIES 1.17E+00 1.44E+00 0.00E+00 0.00E+00 4 1 1 Q (46)

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

y~_-..---.- - -, .. -- l l l l. I

  .[N
  \                                                                                                                                                 l l

TABLE 2-2C* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 19.95 Gaseous Effluents-Elevated Level Releases Unit: Site Starting : 1-Jan-1995 Ending : 30-Jun-1995 l CONTINUOUS MODE l. BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l l

              ................................................................................                                                      1 i

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 gaseou's release pathways                                                          y at Plant Hatch.

O t I. l-r I l l i !' 1 0 i l l (47)

i . t . [ l

                                                                                         -                                                                          1 1

TABLE'2-2AA* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 ' Gaseous Effluents-Elevated Level Releases Unit: 1 ; Starting : 1-Jul-1995 Ending : 31-Dec-1995 I 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 XE-137 CURIES 6.36E+01 6.04E+01 0.00E+00 0.00E+00 XE-138 CURIES 2.12E+01 3.25E+01 0.00E+00 0.00E+00 XE-135M CURIES 9.75E+00 1.24E+01 0.00E+00 0.00E+00 KR-87 CURIES 1.74E+00 3.35E+00 0.00E+00 0.00E+00 AR-41 CURIES 5.90E-01 0.00E+00 0.00E+00 0.00E+00 l KR.85M CURIES 2.19E+00 1.96E+00 0.00E+00 0.00E+00 1 XE-135 CURIES 2.38E+00 3.78E+00 0.00E+00 0.00E+00 XE-133 CURIES 8.95E+00 1.03E+01 0.00E+00 0.00E+00

   ................................................................................l TOTAL FOR PERIOD                                 l    CURIES           l 1.10E+02 l 1.25E+02 l 0.00E+00 l 0.00E+00 l' l

1 l l IODINES

I.133 CURIES 1.40E-02 1.04E-02 U.00E+00 0.00E+00 I-131 CURIES 2 31E-03 1.37E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.63E-02 l 1.18E.02 l 0.00E+00 l 0.00E+00 l; PARTICULATES I-131 CURIES 6.36E-06 1.06E-05 0.00E+00 0.00E+00 l

BA-140 CURIES 1.59E-04 2.79E-04 0.00E+00 0.00E+00 CE-141 CURIES 0.00E+00 2.90E-07 0.00E+00 0.00E+00 SR-89 CURIES 2.21E-06 1.062-04 0.00E+00 0.00E+00 , CO-58 CURIES 2.01E-07 0.00E+00 0.00E+00 0.00E+00 ZN-65 CURIES 1.24E-06 0.00E+00 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 6.40E-07 0.00E+00 0.00E+00 CO-60 CURIES 2.61E-07 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 3.54E-08 4.96E-06 0. ' 'E+00 0.00E+00 CS 137 CURIES 1.255 06 2.0BE-06 0 !+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.70o-04 l 4.03E-04 l 0.00E+00 l 0.00E+00 l GeALPHA CURIES 2.41E-08 2.79E-08 0.00E+00 0.00E+00 H-3 CURIES 7.28E-01 3.78E-01 0.00E+00 0.00E+00 (48) i i

                   ~
                                                            .                                              1 i

i l

TABLE 2-2AA* ! E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 ; Gaseous Effluents-Elevated Level Releases ! Unit: 1 > Starting : 1-Jul.1995 Ending : 31-Dec-1995 ) 1 l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l

         .........__............................................................___......j l
         .............__..................................................................j Zeroes in this table indica.te 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.

1 l l I 1 l 1 l i i < q l 1 5 l i (49)

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

L l t 4 TABLE 2-2BB* ! E. I. HATCH NUCLEAR PLANT ' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Elevated Level Releases Unit: 2

                                             ' Starting :               1.Jul-1995                      Ending : 31-Dec-1995                          '

t l CONTINUOUS MODE l BATCH MODE ** ll NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION GASES '

          ................................................................................j XE-137                                                      CURIES         6.36E+01               5.36E+01     0.00E+00         0.00E+00 '  .

XE-138 CURIES 2.12E+01 2.94E+01 0.00E+00 0.00E+00 XE-135M CURIES 9.52E+00 8.70E+00 0.00E+00 0.00E+00 KR-87 CURIES 1.74E+00 2.97E+00 0.00E+00 0.00E+00 ' AR-41 CURIES 5.90E-01 0.00E+00 0.00E+00 0.00E+00 KR-85M- CURIES 2.19E+00 1.33E+00 0.00E+00 0.00E+00 XE-135 CURIES 2.30E+00 2.62E+00 0.00E+00 0.00E+00 ' XE-133 CURIES 8.45E+00 6.04E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l ' CURIES l 1.10E+02 l 1.05E+02 l 0.00E+00 l 0.00E+00 l} l l IODINES 1 I-133 CURIES 1.38E-02 5.64E-03 0.00E+00 0.00E+00

I.131 CURIES 2.18E-03 6.03E-04 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.60E-02 l 6.24E-03 l 0.00E+00 l 0.00E+00 l ....__...................................___................................... 1 PARTICULATES l I-131 CURIES 6.08E-06 6.38E-06 0.00E+00 0.00E+00 BA-140 CURIES 1.56E-04 1.99E-04 0.00E+00 0.00E+00 l CE-141 CURIES 0.00E+00 2.14E-07 0.00E+00 0.00E+00

! SR-89 CURIES 2.03E-06 1.04E-04 0.00E+00 0.00E+00 I CO-58 CURIES 2.01E-07 0.00E+00 0.00E+00 0.00E+00 ! ZN-65 CURIES 1.24E-06 0.00E+00 0.00E+00 0.00E+00 l CE-144 CURIES 0.00E+00 6.40E-07 0.00E+00 0.00E+00 ) CO-60 CURIES 2.61E-07 0.00E+00 0.00E+00 0.00E+00 j , SR-90 CURIES 3.04E-08 4.91E-06 0.00E+00 0.00E+00 '

l. CS-137 CURIES 1.25E-06 1.75E-06 0.00E+00 0.00E+00

! TOTAL FOR PERIOD l CURIES l 1.67E-04 l 3.17E-04 l 0.00E+00 l 0.00E+00 G-ALPHA CURIES 2.24E 08 1.66E-08 0.00E+00 0.00E+00 i H-3 CURIES 7.53E-01 1.14E-01 0.00E+00 0.00E+00 I

            ....__........................................................................i (50)                                              ,

i !

TABLE 2-2BB* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Elevated Level Releases Unit: 2 Starting : 1-Jul-1995 Ending : 31-Dec-1995 l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l

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.

(51)

i l l

I

TABLE 2-2CC* , E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1995 I Gaseous Effluents-Elevated Level Releases , Unit: Site Starting : 1.Jul-1995 Ending : 31-Dec-1995 l l l CONTINUOUS MODE l BATCH MODE ** l) NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l l i

  ,                                                                                                                                                                       1 FISSION GASES                                                                                                                                                    i XE-137                                                CURIES               1.27E+02             1.14E+02                      0.00E+00      0.00E+00              )

XE-138 CURIES 4.25E+01 6.20E+01 0.00E+00 0.00E+00 l XE-135M CURIES 1.93E+01 2.11E+01 0.00E+00 0.00E+00 , KR-87 CURIES 3.48E+00 6.31E+00 0.00E+00 0.00E+00 l AR-41 CiletIES 1.18E+00 0.00E+00 0.00E+00 0.00E+00 KR-85M CURIES 4.37E+00 3.29E+00 0.00E+00 0.00E+00- I XE-135 CURIES 4.68E+00 6.40E+00 0.00E+00 0.00E+00 ) ! XE-133 CURIES 1.74E+01 1.63E+01 0.00E+00 0.00E+00 ! TOTAL FOR PERIOD l CURIES l 2.20E+02 l 2.29E+02 l 0.00E+00 l 0.00E+00 l) IODINES ! l I-133 CURIES 2.78E-02 1.61E 0.00E+00 0.00E+00 i I-131 CURIES 4.49E-03 1.97E-03 0.00E+00 0.00E+00

         .................____........__.                                  .......___.....................................j l

TOTAL FOR PERIOD l CUR 1r.. l 3.23E-02 l 1.80E-02 l 0.00E+00 l 0.00E+00 ll

         ....................__..........                                       ...........................______........____l f-t PARTICULATES I-131                                                CURIES               1.24E-05              1.69E-05                     0.00E+00      0.00E+00 BA-140                                                CURIES              3.14E-04              4.78E-04                     0.00E+00      0.00E+00 CE-141                                                CURIES              0.00E+00              5.04E-07                     0.00E+00      0.00E+00 SR.89                                                 CURIES              4.24E-06              2.09E-04                     0.00E+00       0.00E+00 CO-58                                                 CURIES              4.03E-07              0.00E+00                     0.00E+00       0.00E+00 ZN-65                                                CURIES              2.49E-06              0,00E+00                     0.00E+00       0.00E+00 CE-144                                               CURIES               0.00E+00             1.28E-06                     0.00E+00       0.00E+00 i          CO-60                                                CURIES               5.22E-07             0.00E+00                      0.00E+00      0.00E+00 SR-90                                                CURIES               6.58E-08             9.86E-06                      0.00E+00      0.00E+00 CS-137                                               CURIES               2.50E-06             3.83E-06                      0.00E+00      0.00E+00

TOTAL FOR PERIOD l CURIES l 3.37E-04 l 7.1PE-04 l 0.00E+00 l 0.00E+00 l l

GRALPHA CURIES 4.64E-08 4.45E-08 0.00E+00 0.00E+00 ! H-3 CURIES 1.54E+00 4.92E-01 0.00E+00 0.00E+00 (52) l

g. _ _._.

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

L o t i j l : l-TABLE 2-2CC* l E. I. HATCH NUCLEAR PLANT ,

ANNUAL RADIOACTIVE EFFL 3NT RELEASE REPORT - 1995 l l Gaseous Effluents-Elevated Level Releases l Unit: Site >

L Starting : 1-Jul-1995 Ending : 31-Dec-1995' ! l l CONTINUOUS MODE l BATCH MODE ** l! l

            ..............__...........................................______.....___.__...t NUCLIDES RELEASED                          l      UNIT         l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l[

l t t

            *~         Zeroes in this table indicate that no radioactivity was present                                                            ;

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

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

l l l l l l + a I (53)

TABLE 2 3A* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : 1-Jan-1995 Ending : 30-Jun-1995 l l CONTINUOUS MODE l BATCH MODE ** l f NUCLIDES RELEASED l UNIT [ QUARTER 1 l QUARTER 2 l QUARTER 1 [ QUARTER 2 l , FISSION GASES XE-135M CURIES 0.00E+00 2.40E+01 0.00E+00 0.00E+00 KR-87 CURIES 0.00E+00 2.70E.02 0.00E+00 0.00E+00 KR-85M CURIES 2.57E-02 1.75E-02 0.00E+00 0.00E+00 XE-135 CURIES 7.00E+00 6.61E+01 0.00E+00 0.00E+00 XE-133 CURIES 2.00E+02 1.80E+01 0.00E+00 0.00E+00 l TOTAL FOR PERIOD l CURIES l 2.07E+02 l 1.08E+02 l 0.00E+00 l 0.00E+00 l l 4 I(D:NES s_) ................................................................................ 0.00E+00 I-;35 CURIES 5.30E-02 0.00E+00 0.00E+00 I-133 CURIES 2.14E-01' 2.19E-01 0.00E+00 0.00E+00 , I.131 CURIES 6.59E-03 6.23E-03 0.00E+00 0.00E+00 , f [ ................................................................................ TOTAL FOR PERTOD l CURIES l 2.73E-01 l 2.26E-01 l 0.00E+00 l 0.00E+00 \ , PARTICULATES , I-131 CURIES 3.78E-04 2.52E-04 0.00E+00 0.00E+00 BA-140 CURIES 8.69E-04 4.57E-04 0.00E+00 0.00E+00 CR.51 CURIES 2.84E-04 0.00E+00 0.00E+00 0.00E+00 CE-141 CURIES 5.34E-05 4.11E-05 0.00E+00 0.00E+00 NB-95 CURIES 3.62E-06 0.00E+00 0.00E+00 0.00E+00 SR-89 CURIES 3.14E-04 1.42E-03 0.00E+00 0.00E+00 CO-58 CURIES 1.98E-05 6.96E-06 0.00E+00 0.00E+00 ZN-65 CURIES 3.37E-04 1.11E-04 0.00E+00 0.00E+00 MN-54 CURIES 1.97E-05 1.56E.06 0.00E+00 0.00E+00 CO.60 CURIES 1.41E-05 3.47E-06 0.00E+00 0.00E+00 ' SR-90 CURIES 5.26E-06 2.47E.05 0.00E+00 0.00E+00 CS-137 CURIES 1.99E-06 6.14E-10 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 2.30E-03 l 2.32E-03 l 0.00E+00 l 0.00E+00 l l

           ................................................................................                  I f

l H-3 CURIES 4.02E+00 4.39E+00 0.00E+00 0.00E+00 (54)

i l 4 TABLE 2-3A* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 i Gaseous Effluents-Ground Level Releases j Unit: 1 l Starting : 1-Jan-1995' Ending : 30-Jun-1995 l 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 l ................................................................................ 1 i

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

      **       There are no batch mode radioactive gaseous release pathways at Plant Hatch, l

l l l-l r i s !O l l l l l (55) I

    -.   - - -       -    .   . . - ~
                                                          . . - ~ ~ - - . . -             -    -- ~. .             - . .       .

c

TABLE 2-3B* E. I. HATCH NUCLEAR PLANT + ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l Gaseous Effluents-Ground Level Releases i Unit: 2 Starting : 1-Jan-1995 Ending : 30-Jun-1995 [ l CONTINUOUS MODE l BATCH MODE ** l < NUCLIDES RELEASED j UNIT l QUARTER 1 l QUARTER 2 lQUA.RTER 1 \ QUARTER 2 l t l FISSION GASES XE-135 CURIES 1.80E+01 5.03E+01 0.00E+00 0.00E+00 XE-133 CURIES 2.74E+02 1.32E+01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 2.92E+02 l 6.36E+01 l 0.00E+00 l 0.00E+00 l IODINES I-132 ' CURIES 0.00E+00 1.24E-02 0.00E+00 0.00E+00

 -(~g           I-135                                       CURIES        2.93E-02          2.55E-03           0.00E+00     0.00E+00 I-133                                       CURIES        8.34E-02          9.66E-02           0.00E+00     0.00E+00

t\j I-131 CURIES 2.88E-03 3.00E-03 0.00E+00 0.00E+00 ,

TOTAL FOR PERIOD l CURIES l 1.16E-01 l 1.15E-01 l 0.00E+00 l 0.00E+00 l PARTICULATES ! I-131 CURIES 2.41E-04 1.88E-04 0.00E+00 0.00E+00 BA-140 CURIES 9.89E-04 4.31E-04 0.00E+00 0.00E+00 CR-51 CURIES 1.00E-05 0.00E+00 0.00E+00 0.00E+00 CE-141 CURIES 3.78E-05 2.41E-05 0.00E+00 0.00E+00 SR-89 CURIES 5.26E-04 3.78E-05 0.00E+00 0.00E+00 ZN-65 CURIES 0.00E+00 5.12E-00 0.00E+00 0.00E+00 SR-90 CURIES 4.74E-06 2.92E-07 0.00E+00 0.00E+00 CS-137 CURIES 6.96E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.81E-03 l 6.87E-04 l 0.00E+00 l 0.00E+00 l I L G-ALPHA CURIES 2.33E-07 3.05E-07 0.00E+00 0.00E+00 H-3 CURIES 6.88E+00 7.06E+00 0.00E+00 0.00E+00 l l l (56) l

   . '\ )

TABLE 2-3B* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT. RELEASE REPORT - 1995

                                       -Gaseous Effluents-Ground Level Releases                                                i Unit: 2                                                       l; Starting :         1-Jan-1995             Ending : 30-Jun 1995 BATCH' MODE **       l l      CONTINUOUS MODE                l                      l NUCLIDES RELEASED                       l UNIT      l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l                  1
          ................................................................................                                      j
          ................................................................................                                      i l

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 mode radioactive gaseous release pathways

! at Plant Hatch. l t l l i l l t l I l t I 1 (57)

I TABLE 2-3C* l E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT. RELEASE REPORT - 1995 Gaseous Effluents-Ground Level Releases Unit: Site ! Starting . 1-Jan-1995 Ending . 30-Jun-1995 l l l CONTINUOUS MODE l BATCH MODE **- l i NUCLIDES RELEASED. l UNIT l QUARTER 1 lQUARTER 2 jQUARTER 1 l QUARTER 2 l l. l i i : l ? ! FISSION GASES , j ................................................................................ l XE-135M CURIES 0.00E+00 2.40E+01 '0.00E+00 0.00E+00 l KR-87 CURIES. 0.00E+00 2.70E-02 0.00E+00 0.00E+00 KR-85M CURIES 2.57E-02 1.75E-02 0.00E+00 0.00E+00 XE-135 CURIES 2.50E+01 1.16E+02 0.00E+00 0.00E+00 , r XE-133 CURIES 4.74E+02 3.12E+01 0.00E+00 0.00E+00 ; i TOTAL FOR PERIOD l CURIES l 4.99E+02 l 1.72E+02 l 0.00E+00 l 0.00E+00 l

  .Q (j                   IODINES                                                                                                                          ;

I-132 CURIES 0.00E+00 1.24E-02 0.00E+00 0.00E+00 - [ I-135 CURIES 8.22E-02 2.55E-03 0.00E+00 0.00E+00 ' I-133 CURIES 2.97E-01 3.26E-01 0.00E+00 0.00E+00 I-131 CURIES 9.47E-03 9.23E-03 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.89E-01 l 3.40E-01 l 0.00E+00 l 0.00E+00 l PARTICULATES h I-131 CURIES 6.18E-04 4.40E-04 0.00E+00 0.00E+00 BA-140 CURIES 1.86E-03 8.88E-04 0.00E+00 0.00E+00 CR-51 CURIES 2.94E-04 0.00E+00 0.00E+00 0.00E+00

                       .CE-141                                        CURIES              9.12E-05             6.51E-05       0.00E+00    0.00E+00 NB-95                                         CURIES              3.62E-06             0.00E+00       0.00E+00    0.00E+00 SR-89                                         CURIES              8.40E-04             1.46E-03       0.00E+00    0.00E+00      t CO-58                                         CURIES              1.98E-05             6.96E-06       0.00E+00    0.00E+00 ZN-65                                         CURIES              3.37E-04             1.16E-04       0.00E+00    0.00E+00 MN-54                                         CURIES              1.97E-05             1.56E-06       0.00E+00    0.00E,00 CO-60                                         CURIES              1.41E-05             3.47E-06       0.00E+00    0.00E+00 SR-90                                         CURIES              1.00E-05             2.50E-05       0.00E+00    0.00E+00 CS-137                                       CURIES              8.95E-06             6.14E-10       0.00E+00    0.00E+00 l                         TOTAL FOR PERIOD                       l     CURIES           l 4.11F-03 l 3.00E-03 l 0.00E+00 l 0.00E+00                    l  ,

6 i I i ................................................................................ 1 G-ALPHA CURIES 3.14E-07 4.14E-07 0.00E+00 0.00E+00 ' H-3 CURIES 1.09E+01 1.15E+01 0.00E+00 0.00E+00 l (58) L l l

i j L t ' TABLE 2-3C* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous-Effluents-Ground Level Releases Unit: Site Starting : 1-Jan-1995 Ending : 30-Jun-1995 l i l CONTINUOUS MODE l BATCH MODE ** l NUCLIDES RELE". SED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l : l ................................................................................ l [

          *.         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.

i _s! l i 1 i I

J t

usl j l 1 (59) !

     ,                      .                                            -     -        .- ..           .,   , - _ _   ,,               .-.   .?

? l l l l l TABLE 2-3AA* E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : 1-Jul.1995 Ending : 31-Dec-1995 l 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 FISSION GASES XE-135 CURIES 2.43E-02 4.91E-02 0.00E+00 0.00E+00 XE-133 CURIES 3.09E+01 4.92E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.09E+01 l 4.97E+00 l 0.00E+00 l 0.00E+00 l l ....__..___................__. ____.........__...............______......... __.; l IODINES l I-135 CURIES 4.52E-03 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 1.58E-01 4.19E-04 0.00E+00 0.00E+00 l I-131 CURIES 6.36E-03 1.05E-04 0.00E+00 0.00E+00 l TOTAL FOR PERIOD l CURIES l 1.68E-01 l 5.24E-04 l 0.00E+00 l 0.00E+00 l l 4 l PARTICULATES I l

                  ..........................__                    ........,..........__.__.___,.......__.........__..)
                 .I-131                                        CURIES          2.28E-04             1.22E-06            0.00E+00     0.00E+00 I BA-140                                        CURIES          2.98E-04             0.00E+00            0.00E+00     0.00E+00 CE-141                                        CURIES          1.97E-05             0.00E+00            0.00E+00     0.00E+00 j SR-89                                         CURIES          7.43E-05             3.20E-08            0.00E+00     0.00E+00 !

ZN-65 CURIES 6.92E-05 0.00E+00 0.00E+00 0.00E+00

CS-134 CURIES 2.23E-06 0.00E+00 0.00E+00 0.00E+00 l l SR-90 CURIES 1.28E-06 5.13E-08 0.00E+00 0.00E+00 CS-137 CURIES 5.36E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 6.99E-04 l 1.30E-06 l 0.00E+00 l 0.00E+00 ll

     .            G-ALPHA                                      CURIES          3.96E-07             7.91E-07            0.00E+00     0.00E+00 H-3                                          CURIES          8.43E+00             1.14E+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 j detectable concentrations. i l ** There are no batch mode radioactive gaseous release pathways at Plant Hatch. (60)

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

r TABLE 2-3BB* S. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : 1-Jul-1995 Ending : 31-Dec-1995 i l CONTINUOUS MODE l BATCH MODE ** l& NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l;

   .......................................................__.....___...............l i

FISSION GASES XE-135 CURIES 1.94E+01 0. 0 011+ 00 0.00E+00 0.00E+00 - XE-133 CURIES 0.00E+00 1.19E+01 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.94E+01 l 1.19E+01 l 0.00E+00 l 0.00E+00 lI IODINES I-135 CURIES 8.80E-05 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 6.63E-02 6.00E-03 0.00E+00 0.00E+00 l I-131 CURIES 4.00E-03 9.22E-04 0.00E+00 0.00E+00 ! TOTAL FOR PERIOD l CURIES l 7.04E-02 l 6.92E.03 l 0.00E+00 l 0.00E+00 ll PARTICULATES I-131 CURIES 1.93E-04 4.71E-05 0.00E+00 0.00E+00 l BA-140 CURIES 2.80E-04 6.64E-05 0.00E+00 0.00E+00 j CE-141 CURIES 9.27E-06 0.00E+00 0.00E+00 0.00E+00 l SR-89 CURIES 1.96E-03 9.69E-05 0.00E+00 0.00E+00 l SR-90 CURIES 3.20E-05 2.41E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 2.48E-03 l 2.13E-04 l 0.00E+00 l 0.00E+00 l G-ALPHA CURIES 6.51E-07 5.9BE-07 0.00E+00 0.00E+00 H-3 CURIES 4.34E+00 2.59E+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.                                                                                                             I i

(61)

TABLE 2-3CC* ; E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 Gaseous Effluents-Ground Level Releases Unit: Site Starting : 1-Jul-1995 Ending : 31-Dec-1995 l CONTINUOUS MODE BATCH MODE ** l

  . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .l . . . . . . . . . . . . _ . . . . . . .

NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION GASES l

 -XE-135                                                CURIES              1.94E+01               4.91E-02             0.00E+00             0.00E+00 XE-133                                                CURIES              3.09E+01                1.68E+01            0.00E+00             0.00E+00 TOTAL FOR PERIOD                                 l    CURIES           l 5.04E+01 l 1.69E+01 l 0.00E+00 l 0.00E+00 l1 IODINES I-135                                                 CURIES              4.61E-03                0.00E+00            0.00E+00              0.00E+00              l I-133                                                 CURIES               2.24E-01               6.42E-03            0.00E+00              0.00E+00              !

I-131 CURIES 1.04E-02 1.03E-03 0.00E+00 0.00E+00 l

  ............__........................__................___..__......____......)

TOTAL FOR PERIOD l CURIES l 2.39E-01 l 7.45E-03 l 0.00E+00 l 0.00E+00 ll 1 l PARTICULATES 1 I-131 CURIES 4.21E-04 4.84E-05 0.00E+00 0.00E+00 , BA-140 CURIES 5.78E-04 6.64E-05 0.00E+00 0.00E+00 CE-141 CURIES 2.90E-05 0.00E+00 0.00E+00 0.00E+00 SR-89 CURIES 2.04E-03 9.69E-05 0.00E+00 0.00E+00 ZN-65 CURIES 6.92E-05 0.00E+00 0.00E+00 0.00E+0D CS-134 CURIES 2.23E-06 0.00E+00 0.00E+00 0.00E+00 SR-90 CURIES 3.33E.05 2.4GE-06 0.00E+00 0.00E+00 CS-137 CURIES 5.36E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.18E-03 l 2.14E-04 l 0.00E+00 l 0.00E+00 G-ALPHA CURIES 1.05E-06 1.39E-06 0.00E+00 0.00E+00 i H-3 CURIES 1.28E+01 3.73E+00 0.00E+00 0.00E+00 l l l

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

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

(62)

i l t l , i l l \ J l i 1 TABLE 2-4A 1 E. I. HATCH NUCLEAR PLANT j ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 1 AIR DOSES DUE TO GASEOUS RELEASES t Unit: 1 l Starting: 01-Jan-1995 Ending: 30-Jun-1995 l r-l Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit l i ation t l- .......................................................................... 'i l Gamma 5.0 mrad 2.32E-02 4.63E-01 5.77E-02 1.15E+00 t 10.0 mrad 6.05E 6.05E-01 5.33E-02 5.33E-01 i r

       .................................-02 Beta
                                                    .........................................        ]

I ' l l Cumulative Doses per Year l l i Type ODCM Units Year to % of l of Limit Ending ODCM

        .Radi-                              Date             Limit k     ation Gamma         10.0    mrad       8.09E-02            8.09E-01                                ]

Beta 20.0 mrad 1.14E-01 5.69E-01 , l l l j i l l. l I (63)

_ . . .. . . , - - - - ... ... ~ (_ TABLE 2 4B E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jan-1995 Ending: 30-Jun-1995 t Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 1 ODCM 2 ODCM Radi- Limit LLmit ' ation ; Gamma 5.0 mrad 3.57E-02 7.15E-01 2.78E-02 5.55E-01 Beta 10.0 mrad 8.84E-02 8.84E-01 3.68E-02 3.68E-01 Cumulative Doses per Year Type ODCM Units Year to % of of Limit Ending ODCM O Radi- Date Limit V ation Gamma 10.0 mrad 6.35E-02 6.35E-01 Beta 20.0 mrad 1.25E-01 6.26E-01 l (64)

_ . _ . _ . _ . . . . _ ._- _. - . _ . . _ . . _ . . _ . _ _ _ - .m

        -4                                                                               ,

I i i L 7' l i

     ^)                                                                                                                               t TABLE 2-4AA E. I. HATCH NUCLEAR PLANT                 .

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 AIR DOSES DUE TO GASEOUS RELEASES l- , Unit: 1 Starting: 01-Jul-1995 Ending: 31-Dec-1995 i Cumulative Doses per Quarter Type ODCM Units Quarter % of Quarter % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit , ation Gamma 5.0 mrad 3.69E-03 7.38E.02 1.52E-03 3.05E-02 Beta 10.0 mrad 9.87E-03 9.87E-02 2.69E.03 2.69E-02 I l Cumulative Doses per Year j l . ......................................................................... ;

                                                                                         % of

! Type ODCM Units Year to i of . Limit Ending ODCM Radi- Date Limit l' ation l l Gamma 10.0 mrad 8.61E-02 8.61E-01 l Beta 20.0 mrad 1.26E-01 6.32E.01 l i i , v l (65)

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

l O-1 l

  \_)                                                                                                                                                     '

TABLE 2-4BB E. I. HATCH NUCLEAR PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 , i AIR DOSES DUE TO GASEOUS RELEASES ! Unit: 2 Starting: 01.Jul-1995 Ending: 31-Dec-1995 ! l Cumulative Doses per Quarter l Type ODCM Units Quarter % of Quarter i of ! of Limit 3 ODCM 4 ODCM l Radi- Limit Limit ation l j Gamma 5.0 mrad 1.07E-02 2.13E-01 2.02E-03 4.05E-02 mrad 4.46E-03 4.46E-02 l .............................................-01 Beta 10.0 1.39E.02 1.39E l Cumulative Doses per Year !- Type ODCM Units Year to % of of Limit Ending ODCM Radi- Date Limit (Q) ation Gamma 10.0 mrad 7.62E.02 7.62E-01 < l Beta 20.0 mrad 1.44E-01 '/.18E-01 f .......................................................................... I I i e i I

  .a                                                                                                                                                       l 4

(66) I I

V(D TABLE 2-5A E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Ending: .0-Jun-1995 Starting: 01-Jan-1995 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of- Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 6.24E-03 8.33E-02 2.37E 3.16E-01 Liver 7.5 mrem 3.75E-03 5.00E-02 3.59E-03 4.78E-02 TBody 7.5 mrem 3.55E-03 4.73E-02 5.43E-03 7.24E-02 Thyroid 7.5 mrem 2.37E-01 3.16E+00 2.33E-01 3.10E+00 Kidney 7.5 mrem 4.34E-03 5.79E-02 4.22E-03' 5.63E-02 Lung 7.5 mrem 2.76E-03 3.68E.02 2.95E-03 3.93E-02 GILLI 7.5 mrem 3.01E-03 4.01E-02 3.49E-03 4.66E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date- Limit Bone 15.0 mrem 2.99E-02 2.00E-01 Liver 15.0 mrem 7.34E-03 4.89E-02 TBody 15.0 mrem 8.98E-03 5.99E-02 Thyroid 15.0 mrem 4.70E-01 3.13E+00 Kidney 15.0 mrem 8.56E-03 5.71E-02 Lung 15.0 mrem 5.71E-03 3.81E-02 GILLI 15.0 mrem 6.50E-03 4.33E-02 (67)

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

r i

r r i F TABLE 2-5B *

. E. I. HATCH NUCLEAR PLANT I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSES TO A MEM3ER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, l
AND PARTICULATES IN GASEOUS RELEASES l Unit: 2 Starting: 01-Jan-1995 Ending: 30-Jun-1995 Cumulative Doses per Quarter j Organ ODCM Unit Quarter % of Quarter i of -

Limit 1 ODCM 2 ODCM i Limit Limit i Bone 7.5 mrem 7.79E-03 1.04E-01 1.04E-03 1.39E-02 Liver 7.5 mrem 4.16E-03 5.55E-02 4.22E-03 5.63E-02

TBody 7.5 mrem 4.48E-03 5.97E-02 4.00E-03 5.33E-02 Thyroid 7.5 mrem 1.01E-01 1.35E+00 1.11E.01 1.48E+00 Kidney 7.5 mrem 4.41E.03 5.88E-02 4.53E.03 6.03E-02 Lung 7.5 mrem 3.99E-03 5.32E-02 3.84E+03 5.12E-02 i GILLI 7.5 mrem 4.09E-03 5.46E-02 3.91E-03 5.22E.02 l<

l l

                                                                                                                                             '1 Cumulative Doses per Year Organ             ODCM         Units          Year to               % of Limit                         Ending              ODCM Date              Limit Bone              15.0         mrem          8.83E-03             5.89E-02 Liver             15.0         mrem          8.39E-03             5.59E-02 TBody             15.0         mrem          8.48E-03             5.65E-02 Thyroid           15.0         mrem          2.12E-01             1.41E+00 Kidney            15.0         mrem          8.94E-03             5.96E-02 Lung              15.0         mrem          7.83E-03             5.22E-02 GILLI             15.0         mrem          8.01E.03             5.34E-02 1

j l (68) w

                                                                 ,                                    a s

l 1 l \ l TABLE 2-5AA i E. I. HATCH NUCLEAR PLANT ! , ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l l DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, l ' AND PARTICULATES IN GASEOUS RELEASES l Unit: 1 l l Starting: 01.Jul-1995 Ending: 31-Dec-1995 l Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit l Bone 7.5 mrem 2.21E-03 2.94E-02 6.98E-04 9.31E-03 l Liver 7.5 mrem 5.47E-03 7.29E-02 6.16E-04 8.21E-03 TBody 7.5 mrem 5.09E-03 6.79E-02 7.21E-04 9.61E-03 Thyroid 7.5 mrem' 2.02E-01 2.69E+00 5.73E-03 7.64E-02 Kidney 7.5 mrem 5.96E.03 7.94E-02 6.26E-04 8.34E-03 l l Lung 7.5 mrem 4.64E-03 6.10E-02 5.99E-04 7.99E-03 ! GILLI 7.5 mrem 4.81E-03 6.41E-02 6.17E-04 8.22E-03 l l l Cwmulative Doses per Year l \ l Organ ODCM Units Year to % of L Limit Ending ODCM l Date Limit i I Liver 15.0 mrem 1.34E.02 8.95E-02 T3ody 15.0 mrem 1.48E-02 9.86E-02 Thyroid 15.0 mrem 6.77E-01 4.52E+00 i Kidney 15.0 mrem 1.51E-02 1.01E-01 l Lung 15.0 mrem 1.09E-02 7.30E-02 GiLLI 15.0 mrem 1.19E-02 7.95E.02 I l 1 P i (69) 1

l l i TABLE 2-5BB ; l E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRIT 1UM, l AND PARTICULATES IN GASEOUS RELEASES ! Unit: 2 Starting: 01-Jul-1995 Ending: 31-Dec-1995 l Cumulative Doses per Quarter Organ ODCM Unit ~ Quarter % of Quarter % of l Limit 3 ODCM 4 ODCM l Limit Limit Bone 7.5 mrem 3.17E-02 4.23E-01 2.13E.03 2.84E-02 Liver 7.5 mrem 2.74E-03 3.65E-02 1.42E-03 1.89E-02 ' IEody 7.5 mrem 5.92E-03 7.89E-02 1.66E-03 2.22E-02 , Thyroid 7.5 mrem 1.08E-01 1.44E+00 2.03E-02 2.70E-01 Kidney 7.5 mrem 3.01E-03 4.01E-02 1.46E-03 1.95E-02 l Lung 7.5 mrem 2.85E-03 3.80E-02 1.39E-03 1.85E-02

    .GILLI               7.5        mrem          3.37E-03              4.50E-02        1.42E-03    1.90E.02 I

I Cumulative Doses per Year l ........................................................................-. l Organ ODCM Units Year to % of Limit Ending ODCM Date Limit l Bone 15.0 mrem 4.27E-02 2.84E-01 l Liver 15.0 mrem 1.25E-01 8.36E-02 l TBody 15.0 mrem 1.61E-02 1.07E-01 ! Thyroid 15.0 mrem 3.40E-01 2.27E+00 l Kidney 15.0 mrem 1.34E-02 8.94E-02 Lung 15.0 mrem 1.21E-02 8.04E-02 GILLI 15.0 mrem 1.28E-02 8.53E-02 4 (70) l

i 1 l i TABLE 2-7 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES E. I. HATCH NUCLEAR PLANT l l JANUARY,1995 THROUGH DECEMBER,1995 l l , The values in this table represent a pnon Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of gaseous radwaste samples. t RADIONUCLIDE MDC UNITS l Kr-87 2.94E-08 uCi/cc Kr-88 3.22E-08 uCi/cc l Xe-133 2.30E-08 uCi/cc l Xe-133m 7.30E-08 uCi/cc ! Xe-135 8.73E-09 uCi/cc Xe-138 1.99E-07 I l-131 1.34E-13* uCi/cc l-133 1.53E-13* uCi/cc Mn-54 1.62E-13* uCi/cc Fe-59 3.42E-13* uCi/cc Co-58 1.30E-13* uCi/cc Co-60 1.54E-13* uCi/cc l Zn-65 2.54E-13* uCi/cc Mo-99 9.61 E-13* uCi/cc Cs-134 1.42E-13* uCi/cc l Cs-137 1.28E-13* uCi/cc ) Ce-141 1.26E-13* uCi/cc l Ce-144 5.64E-13* uCi/cc Sr-89 1.10E-16 uCi/cc Sr-90 6.70E-16 uCi/cc I H-3 4.00E-07 uCl/cc , 4

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

i l (71)

. . j l

I 3.0 Solid Waste 3.1 Regulatory Limits /ODCM l The ODCM Limits presented in this section are for Unit 1 and Unit 2 and are stated in part. i 3.1.1 Solid Radioactive Waste System A.3.1 Solid Radioactive Waste System control states: The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure that they meet requirements of 10 CFR Parts 20 and 71, prior to shipment of radioactive wastes from the site. l l 3.1.2 Reporting Requirements l Technical Specification 5.6.3 O- The Radioactive Effluent Re: ease Report covering the operation of the unit shall j be submitted in accordmice with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in . conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1, Section IV.B.1. I 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 i 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. l l O (72)

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).

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

f. Solidification agent (such as cement).

j Major changes to the solid radioactive waste treatment system shall be reported I to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed and accepted by the PRB. 3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1 A and 3-1 B. t u (73)

( i. i EFFLUENT AND WASTE DISPOSAL- ANNUAL REPORT 1995 JANUARY 1,1995 - DECEMBER 31,1995 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND 11 TABLE 3-IA

-~

FORM TITLE: REG GUIDE 1.21 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1 / 1 / 95 TO.6 / 30 / 95 FOR UNIT: 1&2 PERIOD COVERED: FROM A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) I

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

i

a. Spent resins, filter sludges, evaporator m' 1 919 E?

bottoms, etc. C1 2 416 E3 10 El

b. Dry compressible waste, contaminated equip. m' 3 84 El etc. Ci 5.79 EO 2O El

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

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

e. Other (describe)

C1 . E . E equip. etc.

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

ISOTOPE PERCENT CURIES

a. In65 46 1111 Co-60 24 580 Fe3) 7 169 Cs-137 14 338 g other 9 217 cr 4 R7 h hM Fe-55 9 .52 Co-60

18 1.04 m Cs-137

2 .12 rs 70 new. d. e.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 32 Truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (Disposition)

O Number of Shipments N/A Mode of Transportation N/A Destination N/A (74)

1 I l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 JANUARY 1,1995 - DECEMBER 31,1995 , ( SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l FOR UNITS I AND Il TABLE 3-IA (CONT'D)

FORM TITLE: REG GUIDE 1.21 EFFLUENT AND WASTE DISPOSAL ANNUAL' REPORT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD COVERED: FROM 7 / I / 95 TO 12 / 31 / 95 FOR UNIT: 1&2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) UNIT 6 month Est. Total !

1. Type of waste ERROR %

period m' l.03 E2 10

a. Spent resins, filter sludges, evaporator 4.JZ EZ l. O E1 bottoms, etc. C1 m' q.on Et i

b. Dry compressible waste, contaminated equip.

C1 1 8g EO ?- 0 E1 etc. 3 m . E

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

d. Control Rod Drive Filters .

E E l Ci . . m' E

e. Other (describe) .

E E equip. etc. Ci . .

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

PERCENT CURIES ISOTOPE 11 it

a. yn.Aq 4A RA l en An 19 in r.-sq 4 9 Mn-54 14 32 f st. Other 1.25 2n-65 66 b.

18 .34 Co-60 9 .17 Fe-55 2 .04 us. Mn-54 5 .09 Other d. e. l

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Barnwell,SC 37 Truck b

G B. IRRADIATED FUEL SHIPMENTS (Disposition) Mode of Transportation Destination Number of Shipments ! N/A N/A N/A (75) 1

O EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 JANUARY 1,1995 - DECEMBER 31,1995 SOLID WASTE AND 1RRAD!ATED FUEL SHIPMENTS FOR UNITS I AND ll TABLE 3-IB FORM TITLE: OFFSITE DOSE CALCULATION MANUAL, SECTION *1.2, REPORT PERIOD COVERED FROM: 1/1 / 95 TO: 6 / 30 / 95 FOR UNIT: 1 t, 9 ma coars - razuczrz,a senzas, samaa or vouse or sacu ma sostazrzcarrou or genuTITr/ pucLIDas/ comm2mma c e ==== com mInsa ssInert/ mer unsrs onrunemo ner==== nom nascar m as surpruo care rame contazusa arr si Dewater - Measured Zn-65,Co-60 High 2 132.4 Type B NA g ed Fe-55,Cs13: Integrity Cask 10-142 1 Resins Dewater -Measured Zn-65,Co-60 High 21 202.1 Type A NA ed Fe-55,Cs13 Integrity Cask 14-21 3 Resins Container DAW Estimated Zn65,Co60 Strong 14 95 Strong NA (Dry Fe55,Cs137 Tight tight active Container boxes waste) B-25 O 4 (76)

O ,- EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 JANUARY 1,1995 - DECEMBER 31,1995 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND 11 TABLE 3 IB (CONT'D)

~~

FORM TITLE: OFFSITE DOSE CALCULATION MANUAL, SECTION 7.2, REPORT PERIOD COVERED FROM: 7/ 1 / 95 TO: 12 / 31 / 95 FOR UNIT: 1 &? razucrez.s suazaz, summam or vaLiens or sacu trys satznzrzcartou Trra conzs Or guaPFITY/ NUcLIDES/ c0rAINER CEFEhzMERs CXINEhzNER sErstsNT/ AdEIFF unses oss==--a nes====new casenzerzan surreno conze rear courazuna l ter 31 O kj d Measured Zn-65,Co60 High 1 17 202.1 Typa A N/A Fe-55,Mn54 Integrit'y Cask Resins l l Container 14-210 DAW Estimated Zn-65,Co60 Strong 15 95 Strong N/A (Dry Fe55,Mn-58 Tight tight Active Container container Waste) B-25 B-25 4 (77)

i i 4 i j 4.0 Changes to the Plant Hatch ODCM - 1 . i Pursuant to Technical Specification 5.5.1 and ODCM section 7.2.2.5 Licensee . initiated _ changes shall be submitted to the NRC in the form of a complete, legible -

!:                           copy of the entire ODCM as part of or concurrent with the Radioactive Effluent

[ Release Report for the period of the report in which any change in the ODCM was 3 , 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 i , indicate the date (i.e., month and year) the change was implemented. j l l On July 31,1995, the PRB recommended approval of changes to the Plant Hatch j 4 ODCM so that changes to definitions and references within the ODCM comply { 4 ' with changes made by the Technical Specifications improvement Program (TSIP). Appendix A of this report contains documentation of PRB review and approval of i these changes and the revised Plant Hatch ODCM. The modifications are I identified as Revision 10. a f 5.0 Doses to Members of the Public Inside the Site Boundary O rne s oioective erfieeni aeie e aenort 8 iiai oiocivoe am a radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF memiof18e l THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with the Plant Hatch ODCM. The locations of concern within the site boundary are the Roadside Park, l the Camping Area, the Recreation Area, and the Visitors Center. Listed in Table j j 4-1 are: The distance and direction from a point midway between the center of j j Unit 1 and the Unit 2 reactors, the dispersion and deposition fnctors 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 i assumed age group of this individual. i i

i The source term is not listed in Table 4-1. The source term is listed in j j Tables 2-2A, 2-2AA, 2-2B, and 2-2BB for the elevated releases. , 1 Similarly, it is listed in Tables 2-3A, 2-3AA, 2-38, and 2-3BB for the ground ! ! level releases. 1 The maximum doses in units of mrem accumulated by an individual MEMBER

i. OF THE PUBLIC due to their activities inside the site boundary during i

!Q the reporting period are presented in Table 4-1. 'O r 1 i j ' 08)

I - l l l !O TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l DOSE TO A MEMBER OF THE PUBLIC l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-1995 Ending: 30-Jun-1995 Page: 1 Location Name ROADSIDE PARK Distance (kilometers) 1.18E+00 i Sector WNW l Occupancy Factor 2.28E-04 (2.00E+00 hr/yr) Age Group CHILD Ground Level Releases: Noble Gas X/O (sec/m3) 7.83E-06 Particulate X/Q (sec/m3) 7.GOE-06 ; Particulate D/Q (m-2) 2.01E-08 l l Mixed Mode Releases: . , ~g Noble Gas X/Q (sec/m3) N/A l t Particulate X/O (sec/m3) N/A i Particulate D/Q (m-2) N/A Elevated Releases: Noble Gas X/O (sec/m3) 2.42E-08 Particulate X/Q (sec/m3) 2.37E-08 Particulate D/Q (m-2) 1.29E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending i i Date Bone mrem 1.17E-05 1.76E-05 2.94E-05 2.94E-05 Liver mrem 1.24E-05 1.82E-05 3.05E-05 3.05E-05 TBody mrem 1.21E-05 1.80E-05 3.01E-05 3.01E-05 Thyroid mrem 8.56E-05 8.55E-05 1.71E-04 1.71E-04 Kidney mrem 1.26E-05 1.84E-05 3.10E-05 3.10E-05 Lung mrem 1.23E-05 1.81E-05 3.04E-05 3.04E-05 GI-LLI mrem 1.21E-05 1.79E-05 3.00E-05 3.00E-05 l ( I l (79)

I I l i TABLE 4-1 . E. I. HATCH NUCLEAR PLANT ! ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 i DOSE TO A MEMBER OF THE PUBLIC ' DUE TO ACTIVITIES INSIDE THE' SITE BOUNDARY Unit: Site , i Starting: 01-Jul-1995 Ending: 31-Dec-3995 I Page: 1 l Location Name ROADSIDE PARK l Distance (kilometers) 1.18E+00 ! t Sector WNW ! Occupancy Factor 2.28E-04 (2.00E+00 hr/yr) Age Group CHILD i Ground Level Releases: Noble Gas X/Q (sec/nG) 7.83E-06 ; Particulate X/Q (sec/m3) 7.00E-06 Particulate D/Q (m-2) 2.01E-08 Mixed Mode Releases: j

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

Particulate X/O (sec/m3) N/A Particulate D/O (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 i Units Quarcer 3 Quarter 4 Quarters Year to 3 and 4 Ending l Date Bone mrem 3.32E-06 7.61E-07 4.09E-06 3.35E-05 Liver mrem 3.84E-06 9.57E-07 4.80E-06 3.53E.05 TBody mrem 3.70E-06 9.53E-07 4.66E-06 3.48E-05 i Thyroid mrem 5.30E-05 2.97E-06 5.60E-05 2.27E-04 i Kidney mrem 4.00E-06 9.63E-07 4.96E-06 3.60E-05 j Lung mrem 3.89E-06 9.59E.07 4.85E-06 3.52E-05 GI-LLI mrem 3.68E-06 9.51E-07 4.63E-06 3.47E-05

     .............................................................................                                         ?

i I r (80) l

. _ . _ _ . _ . _ _ . . . _ _ . _ . _ _ . _ _ _ . _ _ _. ._ __.._.m. _ __ _ __ _ . _ . _

     -                                                                                       .                                                    (

s i i O . TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSE TO A MEMBER OF THE PUBLIC l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY ' Unit: Site ! Starting: 01-Jan-1995 Ending: 30-Jun-1995 Page: 2 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 i Particulate X/Q (sec/m3) 6.27E-06 i Particulate D/O (m-2) 1.80E-08 l l Mixed Mode Releases: l Noble Gas X/Q (sec/m3) N/A j O Particulate X/Q (sec/m3) N/A l V Particulate D/Q (m-2) N/A j l Elevated Releases: Noble Gas X/O (sec/m3) 2.38E-08 Particulate X/Q (sec/m3) 2.33E-08 Particulate D/O (m-2) 1.21E-09 Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 2.53E-04 3.81E-04 6.34E-04 6.34E-04 , Liver mrem 2.67E-04 3.92E-04 6.59E-04 6.59E-04 TBody mrem 2.62E-04 3.88E-04 6.50E-04 6.50E-04 Thyroid mrem 1.84E-03 1.84E-03 3.68E-03 3.68E-03 Kidney mrem 2.73E-04 3.97E-04 6.70E-04 6.70E-04 Lung mrem 2.66E-04 3.90E-04 6.56E-04 6.56E-04 GI.LLI mrem 2.62E-04 3.87E-04 6.49E-04 6.49E-04 1 O (81) ,

                     .=      -_

I i i

\

w TABLE 4-l' E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site l Starting: 01-Jul-1995 Ending: 31-Dec-1995 l Page: 2 Location Name CAMPING AREA Distance (kilometers) 1.27E+00 Sector WNW , Occupancy Factor 5.48E.03 .. (4.80E+01 hr/yr) ' Age Group CHILD . j Ground Level Releases: I Noble Gas X/Q (sec/m3) 7.03E-06 : Particulate X/C (sec/m3) 6.27E-06 , Particulate D/Q (m-2) 1.80E-08

Mixed Mode Releases: Noble Gas X/O (sec/m3) N/A l /^s 1 Particulate X/Q (sec/m3) N/A l Particulate D/Q (m-2) N/A ' Elevated Releases: 'l Noble Gas X/Q (sec/m3) 2.38E-08 l Particulate X/Q (sec/m3) 2.33E-08 Particulate D/Q (m-2) 1.21E-09 l Units Quarter 3 Quarter 4 Quarters Year to l 3 and 4 Ending

j. Date

( Bone- mrem 7.20E-05 1.68E-05 8.88E-05 7.23E-04 Liver mrem 8.31E-05 2.10E-05 1.04E-04 7.64E-04 TBody mrem 8.02E-05 2.09E-05 1.01E-04 7.51E-04 Thyroid mrem 1.14E-03 6.44E-05 1.21E-03 4.89E-03 l Kidney mrem 8.65E-05 2.11E-05 1.08E-04 7.77E-04 l Lung. mrem 8.42E-05 2.10E-05 1.05E-04 7.61E-04 GI-LLI mrem 7.96E-05 2.09E-05 1.00E-04 7.49E-04 B 4 . l (82) l

  . . - . ...  ... -        ---- ~ . - -. -.                      . -      . - . .                .              .         .

l' l l

l TABLE 4-1 , l E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 l DOSE TO A MEMBER OF THE PUBLIC l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-1995 Ending: 30-Jun-1995 Page: 3 l l Location Name RECREATION AREA ! Distance (kilometers) 1.03E+00 Sector SSE l Occupancy Factor 2.37E-02 (2.08E+02 hr/yr) l Age Group CHILD i 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                                                    l C_f s                  Particulate D/Q (m-2)                            N/A Elevated Releases:                                                                                            1 Noble Gas X/Q (sec/m3)                           3.30E-08 Particulate X/Q (sec/m3)                         3.21E-08 Particulate D/O (m-2)                            1.56E-09                                                l Units         Quarter 1         Quarter 2              Quarters          Year to 1 and 2         Ending De.ce Bone            mrem            1.01E-03         1.51E-03              2.52E-03          2.52E-03 Liver          mrem            1.07E-03         1.55E-03              2.62E-03          2.62E-03 TBody          mrem            1.05E-03         1.54E-03              2.59E-03          2.59E-03 Thyroid         mrem           7.30E-03         7.28E-03               1.46E-02         1.46E-02 Kidney         mrem            1.09E-03         1.57E-03              2.66E-03          2.66E-03 Lung            mrem           1.06E-03         1.55E-03               2.61E-03         2.61E-03 GI-LLI          mrem           1.04E-03         1.53E-03               2.58E-03         2.58E-03 l

(83)

1 i O V l TABLE 4-1 l E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site . Starting: 01-Jul-1995 Ending: 31-Dec-1995 l Page: 3 ! l 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 i Particulate D/Q (m-2) 2.36E-08 ' Mixed Mode Releases: Noble Gas X/Q (sec/m3) N/A b Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Elevated Releases: Noble Gas X/Q (sec/m3) 3.30E-08 Particulate X/O (sec/m3) 3.21E-08 Particulate D/Q (m-2) 1.56E-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Bone mrem 2.89E-04 6.73E-05 3.57E-04 2.88E-03 Liver mrem 3.33E-04 8.40E-05 4.17E-04 3.04E-03 I TBody mrem 3.22E-04 8.36E-05 4.05E.04 2.99E-03 l Thyroid mrem 4.52E-03 2.57E-04 4.78E-03 1.94E-02 Kidney mrem 3.47E-04 8.45E-05 4.31E-04 3.09E-03 Lung mrem 3.38E-04 8.42E-05 4.22E-04 3.03E-03 GI-LLI mrem 3.19E-04 8.35E-05 4.03E-04 2.98E-03 i

O ,. V (84) r l l

l . . i I 1 l I . ( TABLE 4-1 . E. I. HATCH NUCLEAR PLANT j ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 . DOSE TO A MEMBER OF THE PUBLIC ! l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-1995 Ending: 30-Jun-1995 Page: 4 F

          . Location Name                                      VISITORS CENTER                                                l Distance (kilometers)                             6.94E-01                                                       ,

Sector WSW ; Occupancy Factor 4.57E-04 (4.00E+00 hr/yr) Age Group CHILD l Ground Level Releases: Noble Gas X/Q (sec/m3) 1.87E-05 l Particulate X/Q (sec/nG) 1.72E-05 Particulate D/Q (m-2) 5.47E-08 i Mixed Mode Releases-

    "            Noble Gas X/O (sec/m3)                                N/A                                                    !

Particulate X/Q (sec/nG) N/A i Particulate D/Q (m-2) N/A l 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 ; y ............................................................................. ! Units Quarter 1 Quarter 2 Quarters Year to ' 1 and 2 Ending Date Bone mrem 5.59E-05 8.41E-05 1.40E-04 1.40E-04 Liver mrem 5.91E-05 8.67E-05 1.46E-04 1.46E-04 l TBody mrem 5.80E-05 8.57E-05 1.44E-04 1.44E-04 Thyroid mrem 4.20E-04 4.18E-04 8.38E-04 8.38E-04 Kidney mrem 6.03E-05 8.78E-05 1.48E-04 1.48E-04 i Lung mrem 5.87E-05 8.63E-05 1.45E-04 1.45E-04 l GI-LLI mrem 5.78E-05 8.56E-05 1.43E-04 1.43E-04 [ l_ ' t U (85) l r . . .-

/%

b TABLE 4-1 E. I. HATCH NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit- Site Starting: 01-Jul-1995 Ending: 31-Dec-1995 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 i Particulate D/Q (m-2) 5.47E-08 l Mixed Mode Releases: Noble Gas X/Q (sec/m3) N/A i O 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) 4.27E-08 Particulate D/Q (m-2) 2.26E-09 Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending , Date Bone mrem 1.56E-05 3.09E-06 1.87E-05 1.59E-04 Liver mrem 1.82E-05 4.05E-06 2.22E-05 1.68E-04 TBody mrem 1.75E-05 4.03E-06 2.15E-05 1.65E-04 Thyroid. mrem 2.60E-04 1.40E-05 2.74E-04 1.11E-03 , Kidney mrem 1.90E-05 4.08E-06 2.30E-05 1.71E-04' l Lung mrem 1.84E-05 4.06E-06 2.25E-05 1.67E-04 GI-LLI mrem 1.74E-05 4.02E-06 2.14E-05 1.65E-04 (86) . l

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

rei aic i o i-The Radiological Effluent Release Report to be submitted by May 1 of each year shall include an annual ,ummary 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 that shall be provided to the NRC upon request. 8.0 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation The Offsite Dose Calculation Manual Chapter 7, Section 7.2.2.6.2 states that the i Radiological Effluent Release Report shall include deviations from the liquid and i gaseous effluent monitoring instrumentation operability requirements included in sections 2.1.1 and 3.1.1, respectively. O (87)

l l l Specifically, Section 3.1.1, Table 3-1 Radioactive Gaseous Effluent Monitoring

Instrumentation, Action 104 states that with the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided the flowrate is estimated at least once per l 4 hours. If the number of channels operable remains less than required by the minimum channels operable requirement for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.

, The Main Stack flow recorder 1D11-R625 was tagged out of service on l September 22,1995, due to the flow recorder failing a channel check. The probe l l and monitor were repaired and reinstalled. After repair, a loop calibration was ! performed and all indications were reading correctly. The Main Stack flow recorder was placed back into service November 3,1995. ! 9.0 Tanks Exceeding Curie Content Limits l 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 1 l i (88)

O GEORGIA POWER COMPANY 1 E. I. HATCH NUCLEAR PLANT l UNITS NO.1 & 2 l l ANNUAL REPORT JANUARY 1,1995 - DECEMBER 31,1995 l l l APPENDIX A O i l i i ! I l l 1 1 l 1 l lO

~.

( i l l I OFFSITE DOSE CALCUIATION MANUAL FOR GEORGIA POWER COMPANY EDWIN I. HATCH NU m p m i r Revision 10 July 13, 1995 s 4 f 1 4

Hatch ODCM

V EFFECTIVE PAGE LIST P.Agg, Revision No. DAj;g i 10 7/95 11 9 2/94 111 8 1/94 iv 10 7/95 v, vi 9 2/94 l vii 10 7/95 viii, ix 8 1/94 1-1 10 7/95 2-1 10 7/95 2-2 9 2/94 I 2-3 8 1/94 l 2-4 10 7/95 2-5 8 1/94 2-6 8 1/94 l 2-7 10 7/95 i 2-8 8 1/94 2-9 8 1/94 2-10 10 7/95 l 2-11 8 1/94 l 2-12 10 7/95 l 2-13 10 7/95 l 2-14 thru 2-33 8 1/94 l 2-34 9 2/94 ! 2-35 thru 2-47 C 1/94 j 7/95 3-1 10 O 3-2 3-3 3-4 10 9 8 2/94 1/94 7/95 3-5 8 1/94 3-6 8 1/94 I 3-7 10 7/95 l 3-8 8 1/94 3-9 8 1/94 3-10 10 7/95 3-11 10 7/95 3-12 8 1/94 3-13 10 7/95 ( 3-14 8 1/94 3-15 10 7/95 3-16 10 7/95

3-17 thru 3-30 8 1/94 l 3-31 10 7/95 3-32 thru 3-41 8 1/94 3-42 10 7/95 3-43 thru 3-55 8 1/94

! 4-1 thru 4-3 10 7/95 4-4 thru 4-8 8 1/94 4-9 thru 4-11 10 7/95 4-12 thru 4-19 8 1/94 5-1 10 7/95 ! 5-2 thru 5-4 8 1/94 6-1 thru 6-6 8 1/94 7-1 10 7/95 7-2 8 1/94 7-3 10 7/95 1 b 7-4 thru 7-7 10 7/95 ( >) 8-1 thru 8-20 8 8 1/94 1/94 i 9-1 thru 9-45 10-1 thru 10-8 10 7/95 i Rev. 10, 7/95 l

l I 1 Match ODcM 1 (~~) l k/ s TABLE OF CONTENTS ; l 1 EAEK l 1 i DISTRIBUTION LIST . . . . . . . . . . . . . . . . . . . . . . . . . . . . i TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii l CHAPTER 1: INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . 1-1 CHAPTER 2: LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . 2-1 l 4 2.1 LIMITS OF OPERATION 2-1 l j 2.1.1 Lieuld Effluent Monitorina Instrumentation Control 2-1 l 1 i 2.1.2 Lieuld Effluent concentration control 2-7 -

( 2.1.3 Liould Effluent Dese control 2-10 2.1.4 Liauid Radwaste Treatment System control 2-12 l 2.1.5 Maior chances to Liauid Radioactive Waste Treatment Systems 2-13 l
2.2 LIQUID RADWASTE TREATMENT SYSTEM 2-14 )

2.3 LIQUID EFFLUENT MONITOR SETPOINTS 2-17 ) ^ 2.3.1 ceneral Provisions Recardina Setooints 2-17 ! 2.3.2 Setooints for Radwaste System Discharoe Monitors 2-19 2.3.3 Setootnts for Monitors on Normally Low-Radioactivity Streams 2-27 2.4 LIQUID EFFLUENT DOSE CALCULATIONS 2-29 1 I 2.4.1 calculation of Dese 2-29 2.4.2 calculation of Ag 2-30 2.4.3 calculation of CFg 2-31 2.5 LIQUID EFFLUENT DOSE PROJECTIONS 2-41 4 2.5.1 Thirtv-One Day Dose Proisetions 2-41 2.5.2 Dome Proiections for Soecific Releases 2-41 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS 2-42 CHAPTER 3: GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . 3-1 3.1 LIMITS OF OPERATION 3-1 3.1.1 cameous Effluent Monitorina Instrumentation control 3-1 3.1.2 Gaseous Effluent Dose Rate Control 3-7

 \m.           3.1.3 Caseous Effluent Air Dose Control                                                 3-11
                                                                                                             )

3.1.4 control on Gaseous Effluent Dose to a Member of the Public 3-13 11 Rev. 9, 2/94

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

i t Hatch ODCM i

                                   -TABLE OF CONTENTS (Continued)

EEtl 3.1.5 Gaseous Radwaste Treatment System control 3-15 3.1.6 Maior Chances to Gaseous Radioactive Waste Treatment Systems 3-16 i 3.2 GASEOUS RADWASTE TREATMENT SYSTEM 3-17 3.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3-19 3.3.1 General Provisions Recardina Noble Gas Monitor Setcoints 3-19 . 1 3.3.2 Satooint for the Final Noble Gas Monitor on Each Release ; Pathway 3-21 l 3.3.3 Satooints for Noble Gas Monitors on Effluent Source Stre=== 3-26 l 3.3.4 Determination of Allocatton Factors. AG 3-29 3.3.5 Setoointe for Noble Gas Monitors with Soecial Reauirements 3-31 3.3.6 Satooints for Particulate and Iodine Monitors- 3-32

     '3.4      GASEOUS EFFLUENT COMPLIANCE CALCULATIONS                                                                 3-33 3.4.1     Dose Rates at and Beyond the Site Boundarv                                                        3-33 3.4.2     Noble Gas Air Dose at'or Beyond Site Boundarv                                                      3-35 3.4.3     Dose to a Member of the Public at er Beyond Site Boundarv                                          3-39 3.4.4     Dose Calculations to Suonort Other Reauirements                                                    3-42 3.5      GASEOUS EFFLUENT DOSE PROJECTIONS                                                                         3-47 3.5.1     Thirty-One Day Dose Proinctions                                                                    3-47 O-            3.5.2    Dose Proiections for Specific Releases                                                             3-48 3.6     DEFINITIONS OF GASEOUS EFFLUENT TERMS                                                                     3-49 CHAPTER 4:        RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM                                 . . . . . . .         4-1 4.1     LIMITS OF OPERATION                                                                                        4-1 4.1.1 Radioloaical Environmental Monitorino                                                                  4-1 4.1.2    Land Use Census                                                                                      4-9 4.1.3     Interlaboratory Comnarison Procram                                                                4-11 4.2     RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS                                                           4-12 i

l CHAPTER 5:- TOTAL DOSE DETERMINATIONS . . . . . . . . . . . . . . . . . 5-1 5.1 LIMIT OF OPERATION 5-1 ! 5.1.1 Anolicability 5-1 : 5.1.2 Actions 5-1 5.1.3 Surveillance Raouirements 5-2 5.1.4 Basis 5-2 5.2 DEMONSTRATION OF COMPLIANCE 5-3 CHAPTER 6: POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY . . . . . . . . . . . . 6-1 6.1 REQUIREMENT FOR CALCULATION 6-1 6.2 CALCULATIONAL METHOD 6-1 iii Rev. 8, 1/94

_.._.____-__.-._m _ _ . . _ . - . . _ . _ . _ _ . _ . . _ . . . _ _ _ _ . . _ _ . . . . . _ _ _ . _ _ . _ _ . . . . . _ . . . _ . _ . . _ _ _ _ _

              ~                                                                                                                          -

j - > 3 i l , l Match ODCM TABLE OF COniENis (Centinued) EMil CHAPTER 7 REPORTS . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 ] j 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 7-1 l 7.1.1 Recuirement for Recort 7-1 i j

7.1.2 Recort Contents 7-1 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT 7-3 l l

l 7.2.1 Reauirement for Report 7-3 7.2.2 Recort Contents 7-3 7.3 MONTHLY OPERATING REPORT 7-7 i 7.4 SPECIAL REPORTS 7-7 j 3 i f I CHAPTER 8: METEOROLOGICAL MODELS . . . . . . . . . . . . . . . . . . . 8-1 a 8.1 ATMOSPHERIC DISPERSION 8-1 i 8.1.1 Ground-Level Releases 8-1 8.1.2 Elevated Releases 8-3 8.1.3 Mixed-Mode Releases 8-4 8.2 REI.ATIVE DEPOSITION 8-5 8.2.1 Ground-Level Releases 8-5 8-5 O 8.2.2 8.2.3 Elevated Releases Mixed-Mode Releases 8-6 8-7 8.3 ELEVATED PLUME DOSE FACTORS CHAPTER 9: METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUENT PATHWAY DOSE FACTORS, R. . . . . . . . . . . . . . . . . . 9-1 9.1 INHALATION PATHWAY FACTOR 9-1 9.2 GROUND PLANE PATHWAY FACTOR 9-2 9.3 GARDEN VEGETATION PATHWAY FACTOR 9-3 9.4 GRASS-COW-MILK PATHWAY FACTOR 9-6 9.5 GRASS-GOAT-MILK PATHWAY FACTOR 9-10 l 9.6 GRASS-COW-MEAT PATHWAY FACTOR 9-14 l 10-1 CHAPTER los DEFINITIONS OF EFFLUENT CONTROL TERMS . . . . . . . . . . . 10.1 TERMS SPECIFIC TO THE ODCM 10-1 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS 10-6 l O iv Rev. 10, 7/95 l

Hatch ODCM LIST OF TABLES Table 2-1. Radioactive Liquid Effluent Monitoring Instrumentation 2-3 Table 2-2. Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements '2-5 Table 2-3. Radioactive Liquid Waste Sampling and Analysis Program 2-9 Table 2-4. Applicability of Liquid Monitor Setpoint Methodologies 2-18 l Table 2-5. Parameters for Calculation of Doses Due to Liquid l Effluent Releases 2-34 Table 2-6. Element Transfer Factors 2-35 Table 2-7. Adule Ingestion Dose Factors 2-36 Table 2-8. Site-Related Ingestion Dose Factors, Aj7 2-39 Table 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation 3-3 Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation j Surveillance Requirements 3-5 l Table 3-3. Radioactive Gaseous Waste Sampling and Analysis Program 3-9 Table 3-4. Applicability of Gaseous Monitor Setpoint Methodologies 3-20 l j Table 3-5. Dose Factors for Exposure to a Semi-Infinite Cloud of l Noble Cases 3-37 Table 3-6. Dose Factors for Exposure to Direct Radiation from Noble l Gases in an Elevated Finite Plume 3-38 Table 3-7. Attributes of the controlling Receptor 3-41 Table 3-8. Rapj j for Ground Plane Pathway, All Age Groups 3-44 Table 3-9. Raipj for Inhalation Pathway, Child Age Group 3-45 Table 3-10. Rapj j for Garden Vegetation Pathway, Child Age Group 3-46 l Table 4-1. Radiological Environmental Monitoring Program 4-4 Table 4-2. Reporting Levels for Radioactivity Concentrations in l l Environmental Samples 4-7 I l Table 4-3. Values for the Minimum Detectable Concentration 4-8 Table 4-4. Radiological Environmental Monitoring Locations 4-13 Table 6-1. Attributes of Member of the Public Recaptor Locations Inside the SITE BOUNDARY 6-3 Table 8-1. Terrain Elevation Above Plant Site Grade 8-10 Table 9-1. Miscellaneous Parameters for the Garden Vegetation Pathway 9-5 Table 9-2. Miscellaneous Parameters for the Grass-Cow-Milk Pathway 9-9 e 4. Mi allan e Parameters r e Gr as-C a P th -7 Table 9-5. Individual Usage Factors 9-18 t Table 9-6. Stable Element Transfer Data 9-19 Table 9-7. Inhalation Dose Factors for the Infant Age Group 9-20 v Rev. 9, 2/94

Hatch ODCM LIST OF TABLES (Continued) P. Mil Table 9-8. Inhalation Dose Factors for the Child Age Group 9-23 Table 9-9. Inhalation Dose Factors for the Teenager Age Group 9-26 Table 9-10. Inhalation Dose Factors for the Adult Age Group 9-29 Table 9-11. Ingestion Dose Factors for the Infant Age Group 9-32 Table 9-12. Ingestion Dose Factors for the Child Age Group 9-35 Table 9-13. Ingestion Dose Factors for the Teenager Age Group 9-38 Table 9-14. Ingastion Dose Factors for the Adult Age Group 9-41 Table 9-15. External Dose Factors for Standing on Contaminated Ground 9-44 I i l l O b i i l 1 I O vi Rev. 9, 2/94

LIST OF FIGURES Figure 2-1. Unit 1 Liquid Radwaste Treatment System 2-15 Figure 2-2. Unit 2 Liquid Radwaste Treatment System 2-16 Figure 3-1. Schematic Diagram of the condenser offgas Treatment System 3-18 Figure 4-1. Sampling Location Map, Site Periphery 4-15 Figure 4-2. Sampling Location Map Beyond Site Periphery, North and West of Site 4-16 Figure 4-3. Sampling Location Map Beyond Site Periphery, South and West of site 4-17 Figure 4-4. Sampling Location Map Beyond Site Periphery, East of Site 4-18 Figure 4-5. Location of Additional control Station for TLDs and i Vegetation 4-19 Figure 8-1. Vertical Standard Deviation of Material in a Plume (c ) 8-11 Figure 8-2. Terrain Recirculation Factor (F,) 8-12 Figure 8-3. Plume Depletion Effect for Ground Level Releases 8-13

Figure 8-4. Plume Depletion Effect for 30-Meter Releases 8-14 1 Figure 8-5. Plume Depletion Effect for 60-Meter Releases 8-15 Plume Depletion Effect for 100-Meter Releases 8-16

p Figure 8-6.

   \    Figure 8-7. Relative Deposition for Ground-Level Releases                 8-17.

Figure 8-8. Relative Deposition for 30-Meter Releases 8-18 Figure 8-9. Relative Deposition for 60-Meter Releases 8-19 Figure 8-10. Relative Deposition for 100-Meter (or Greater) Releases 8-20 Figure 10-1. Site Map for Effluent Controls 10-8 l l

O, vii Rev. 10, 7/95 l

l l

    .-.1                -,      . _ _ . _     _  -             .        .       ._         ___           . _-
         ~ .                                                     .

4 Hatch ODCM i O REFEREECEE

1. J.S. Boegli, R.R. Bellamy, W.L. Britz, and R.L. Waterfield, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-1033, October 1978.

1

2. "Lticulation of Annual Domes to Man from Routine Releases of Reactor filuents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U.S. NRC Reoulatorv Guide 1.109, March 1976.

                    " Calculation of Annual Doses to Man from Routine Releases of Reactor

~ 3. Effluents for the Purpose of Evaluating Compliance with 10 CFR 50,

Appendix I," U.S. NRC Reculatory Guide 1.109. Revision 1, October 1977.

4. " Methods for Estimating Atmospheric Transport and Dispersion of. Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors," U.S. NRC Bagulatory Guide 1.111, March 1976.: 5. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous i

Effluents in Routine Releases from Light-Water-cooled Reactors," U.S. NRC ! Reculatory Guide 1.111. Revision 1, July 1977. j 6. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," U.S. NRC Raoulatory Guide 1.113, April 1977. 4 7. Edwin I. Hatch Nuclear Plant - Unit 1 Final Safety Analysis Recort, Georgia Power Company.

8. Edwin I. Hatch Nuclear Plant - Unit 2 Final Safety Analysis Report, g Georgia Power Company.

9. HNP-2 Environmental Reoort - operatino License Stace, Georgia Power j company, July 1975 (including Appendix A, "Edwin I. Hatch Plant - Unit 1 Preoperational Environmental Surveillance Report Number 1," March 1975).

10. Hatch Nuclear Plant L&nd Use Survey - 1987, Georgia Power Company, February 1987. ,

11. Hatch Nuclear Plant Land Use Survey, Georgia Power Company, November 1987.

12. Hatch Nuclear Plant Land Use Survey - 1988, Georgia Power Company, November 16, 1988 and December 20, 1988.

13. Letter to Georcia Power comoany from P(Ekgrd. Lowe, and Garrick. Inc.,

Washington, D.C., May 11, 1987.

14. Letter to Georcia Power comoany from Pickard. Lowe, and Garrick. Inc.,

Washington, D.C., June 3, 1987.

15. Letter to Georoia Power comoany from Pickard. Lowe, and Carrick. Inc.,

Washington, D.C., June 11, 1987.

16. Letter to Georcia Power comoany from Pickard, Lowe, and Garrick. Inc.,

Washington, D.C., November 30, 1987.

17. L.A. Currie, Lower Limit of Detection: Definition and Elaboration of a Proposed Position of Radiolooical Effluent and Environmental Measurements, U.S. NRC Report NUREG/CR-4007, 1984.

18. " Radiological Assessment Branch Technical Position", U.S. Nuclear Regulatory Commission, Revision 1, November 1979.

viii Rev. 8, 1/94

Hatch ODCM 7-

   -                                      REFERENCES (Continued)

19. D.H. Slade (ed.), Meteoroloov and Atomic Enerov - 1968, U.S. Department of Commerce, July 1968.

20. M. Abramowitz and I.A. Stegun (eds.), Handbook of Mathematical Functions with Formulas. Graohs, and Mathematical Tables, National Bureau of Standards, U.S. Department of Commerce, 1965.

21. M.C. Nichols and S.D. Holder, Plant Edwin I. Hatch Units 1 and 2 Therr.al Plume Model Verification, Georgia Power Company Environmental Affairs Center, March 1981.

22. Internal Memorandum. Bill Duval to Howard Rocers, Georgia Power Company, October 11, 1990.

23. Internal Memorandum. W.H. Ollinoer to D.M. Hooper, Georgia Power company, June 9, 1987.

24. Letter to Georola Power Comoany from Quantum Technoloov. TQE2, Marietta, Georgia, June 17, 1987.

25. W.W. Meinke and T.H. Essig, "Offsite Dose Calculation Manual Guidances Standard Radiological Effluent Controls for Boiling Water Resctors,"

Generic Letter 89-01 Supplement No. 1, NUREG-1302, April 1991.

26. D.C. Kocher, " Radioactive Decay Data Tables," U.S. DOE Report DOE / TIC-11026, 1981.

     ~s    27. J.E. Till and H.R. Meyer, eds., Radiolooical Assessment, U.S. NRC Report NUREG/CR-3332, 1983.

28. Letter to Georcia Power comoany from J.H. Davis. Health Physics gonsultant, Lilburn, Georgia, September 17, 1990.

29. Letter to Georoia Power comoany from J.H. Davis. Health Physics Consultant, Lilburn, Georgia, March 25, 1991.

O O ix Rev. 8, 1/94

9 14

m. .... . T*a .

Hatch ODCM f\ d CHAPTER 1 INTRODUCTION The Of f site Dese Calculation Manual is a supporting document of the Technical Specifications. As such, it describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous l l effluents, and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm setpoints. In addition, it contains the followings j e The controls required by the Technical Specifications, governing the l radioactive effluent and radiological environmental monitoring programs. l I i l e Schematics of liquid and gaseous radwaste effluent treatment systems, which include designation of release points to UNRESTRICTED AREAS. l

             . A list and maps indicating the specific sample locations for the Radio-logical Environmental Monitoring Program.

pFA e Specifications and descriptions of the in ormation tha mu t be included , p irr r illn:: eport and the ( l

Annual Radiological Environment i

l

  %)              ' . _ _1   adioactive Effluent Release Repo .        i     by  the Technical ci ications.

j The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in the

f. calculational methods or parameters will be incorporated into the ODCM in order to ensure that it represents current methodology in all applicable areas. Any l

computer sof tware used to perform the calculations described will be maintained I current with the ODCM. i Equations and metbods used in the ODCM are based on those presented in NUREG-0133 l I (Ref erence 1), in Regulatory Guide 1.109 (References 2 and 3), in Regulatory l Guide 1.111 (References 4 and 5), and in Regulatory Guide 1.113 (Reference 6). l l l O ~ 1 i l l-1 Rev. 8, 1/94 ; l

r

                                                                                     . -. e_

a Hatch ODCM CHAPTER 2 ( LIOUID EFFLUENTS l l l 2.1 LIMITS OF OPERATION The following Liquid Ef fluent C is implement requirements established by Technical Specifications Secti -4,4s Terms printed in all capital letters are detined in Chapter 10. 8.0+ i 2.1.1 Liouid Effluent Monitorino Instrumentation control l 6 L 4 a.., In accordance with Technical Specificatio -!.la'11, he radioactive liquid l ef fluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm / trip s et point s set to ensure that the limits specified in Section 2.1.2 are not exceeded. The alarm / trip setpoints of these channels shall i be determined in accordance with section 2.3. 2.1.1.1 Applicability l IV Q i As shown in Table 2-1. 2.1.1.2 Actions With a radioactive liquid of fluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above control, innediately suspend the release of radioactive liquid ef fluents monitored by the af fected channel, declare the channel inoperable, or change the setpoint to a conservative valus. l l With less than the minimum number of radioactive liquid effluent monitoring l instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. ! One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS. l When the ACTION statement or other requirements of this control cannot be met, l l steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements cf the ACTION statement are satisfied. t i 2-1 Rev. 9, 2/94 l

6 Hatch ODCM 2.1.1.3 Surveillance Requirements Each radioactive liquid ef fluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2. i 2.1.1.4 Basis The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents l . during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance q with the methodology and parameters in Section 2.3 to ensure that the alare/ trip I will occur prior to exceeding the limits of Section 2.1.2. The OPERABILITY and i use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. i

.                                                                                                   )

i O 4 1 2-2 Rev. 9, 2/94 I i

l Hatch ODCM

,O' Table 2-1.        Radioactive Liquid Effluent Monitoring Instrumentation 1

l I j 2 OPERABILITY Requirements" 'l Minimum Channels Instrument OPERABLE Applicability b ACTION f

1. Gross Radioactivity Monitors Providing Automatic Termination of Release Liquid Radwaste (1) 100 Effluent Linst ,,

1 I+ 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water Systea Effluent Line 1 (2) 101

3. Flowrate Measurement Devices C i a. Liquid Radwaste Effluent Line 1 (1) 102

b. Discharge Canal 1 (1),(2) 102 l

4. Differential Pressure Measurement Devices Service Water System to Closed Cooling Water System 1 At all times 103

a. All requirements in this Table apply to each unit.

b. Applicability of requirements is as follows:

(1) Whenever the radwaste discharge valves are not locked closed. (2) Whenever the Service Water System pressure is below the Closed Cooling Water System pressure, or AP indication is not available,

c. Pump curves may be used to estimate flow; in such cases, ACTION statement 102 is not required.

O 2-3 Rev. 8, 1/94

{ Hatch ODCM Table 2-1 (contd). Notation for Table 2 ACTION Statements i ACTION 200 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a releases

a. At least two independent samples are analyzed in accordance with Section 2.1.2.3, and

b. At least two technically qualified individuals independently release verify rate discharge line valving and verify the the calculations.

If Otherwise, suspend release of radioactive ef fluentsan viaexplanation this pathway. of the the channel remains inoperable for over 30 , circumstances must be included in the nex+ "-.ur' Radioactive Effluent Release Report. ACTION 101 - With the number of enannels OPERABLE less than required by the Minimum Channel s OPERABLE requirement, effluent releases via this pathway may continue, provided that once per shift grab samples are collected and analyzed f or gross gadioactivity at aIfMINIMUM DETECTABLE the channel CONCENTRATION remains inoperable for overno higher than 1 x 10' yC1/mL.

                         , an explanation of the circumstances must be included in the next
            -eu u m = 6    adioactive Effluent Release Report.

ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that the flowrate is estimated at least once per 4 hou a during actual releases. If the channel remains inoperable for over v da an explanation of tne circumstances must be included an the next d...- adioactive Effluent Release Report. ACTION 103 - W(th the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the Serytce Water System effluent monitor is CPERABLE. l l l Rev. 8, 1/94 2-4

                                                                                 !f atch ODCM Table 2-2.      Radioactive Liquid Ef fluent Monitoring Instrumentation Surveillance Requirements
                                          .-   Surveillance Requirementsa ,',             ,h g                                 Jr ,            N e                  .,           .;       CHANNEL CHANNEL            SOURCE'       CHANNEL

FUNCTIONAL Instrument CHECK CHECK CALIBRATION TEST

1. Gross Radioactivity Monitors Providing Automatic Termination of Release Liquid Radwaste c Effluent Line Db Pe R Q

2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System f Effluent Line Db M R Q

3. Flowrate Measurement Devices

a. Liquid Radwaste Effluent Line Db,d NA R Q O b. Discharge Canal Db 'd NA R Q

4. Differential Pressure Measurement Devices Service Wa'.er System to Cicv3d Ooling Water Syo;em D NA R NA O

I i 2-5 Rev. 8, 1/94

l _, Hatch ODCM Table 2-2 (contd). Notation for Table 2 Surveillance Requirements 1 l l

a. All requirements in this Table apply to each unit.

b. During releases via this pathway.

l

c. In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

l l (1) Instrument indicates measured levels above the alarm / trip setpoint; (2) Instrument indicates an isolation on high alarm; or 1 (3) Instrument controls are not set in operate mode.

d. CRANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which CONTINUOUS, periodic, or BATCH releases are made.

e. The SOURCE CHECK shall consist of verifying that the instrument is reading onseale.

f. In addition to the basic functions of a CHANNEL FUNCTIONAL c" (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate ' ,- control room alarm annunciation occurs if any of the following condit (one exists:

(1) Instrument indicates measured levels above the alarm setpoint; 1 (2) Instrument indicates a downscale failure; or l (3) Instrument controls are not set in operate mode. l l 1 2-6 Rev. 8, 1/94

Hatch ODCM 2.1.2 Licuid Effluent Ceneentration Control su.yand

                                                       -5 i?; ;

5s!_IS;?; s.*c., he In accordance with Technical Specification concentration of radioactive material released An A qu id effluents to UNRESTRICTED AREAS (see Figure 10-1) shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained notle gases. For dissolved or d entrained noble gases, the concentration shall be limited to 1 x 10 pCi/mL total activity. 2.1.2.1 Applicability This limit applies at all times. 2.1.2.2 Actions With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the limits stated in Section 2.1.2, immediately restore the concentration to within the stated limits. When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the untt. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. l 2.1.2.3 Surveillance Requirements . The radioactivity content of each batch of radicactive liquid waste shall be determined by sampling and analysis in accordance with Tab'.e 2-3. The results of radioactive analyses shall be used with the calculational methods in Section 2.3 to assure that the concentration at the point of release is maintained within the limits of Section 2.1.2. 2.1.2.4 Basis This control is provided to ensure that the concentration of radioactive materials released in liquid waste ef fluents to UNREi'TRICTED AREAS will be less than ten times the concentration levels specified in 10 CFR 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in expoeures within (1) the Section II. A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is I 2-7 Rev. 8, 1/94 l l

s l Hatch ODCM l t , based upon the assumption that Xe-135 is the controlling radioisotope and its MPC i i in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2 (1959). The resulting concentration of 2 x 10-4 was then ; multiplied by the ratio of the effluent concentration limit for Xe-135, stated ) in Appendix B, Table 2, Column 1 of 10 CFR 20 (paragraphs 20.1001 to 20.2401), to the MPC for Xe-135, stated in Appendix E, Table II, Column 1 of 10 CFR 20 (paragraphs 20.1 to 20.601), to obtain the limiting concentration of 1 x 10-4 i i yC1/mL. l l l l i l i lO i 1 l l { l l l l l l 1 i 1 1 2-8 Rev. 8, 1/94 i l

i f . l Hatch ODCM l V Table 2-3. Radioactive Liquid Waste Sampling and Analysis Program I Sampling and Analysis Requirements a,b MINIMUM DETECTABLE I Minimum CONCENTRATION Liquid Sampling Analysis Type of Activity (MDC) Release Type FREQUENCY FREQUENCY Analysis (uci/mL) PRINCIPAL GAMMA 5 E-7 C P P EMITTERS Each BATCH Each BATCH I-131 1 E-6 P Dissolved and 1 E-5 One M Entrained Gases Batch Waste BATCH /M (Gamma Emitters) Release Tanks p g H-3 1 E-5 Each BATCH COMPOSITE Gross Alpha 1 E-7 Sr-89, Sr-90 5 E-8 p g Each BATCH COMPOSITE Fe-55 2 E-6 (

 \    a. All requirements in this table apply to each unit.

b. Terms printed in all capital letters are defined in Chapter 10.

c. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio-nuclides at or near the required MINIMUM DETECTABLE CONCENTRATICN. Under these circumstances, the required MINIMUM DETECTABLE CONCENTRATION may be increased inversely proportionally to the magnitude of the gamma yield (i.e., SE-7/I, where I = photon abundance expressed as a decimal fraction). In no case shall the MINIMUM DETECTABLE CONCENTRATION, as calculated in this manner for a specific radionuclide, be greater than 10 percent of the corresponding Ef fluent Concentration Limit value specified in 10 CFR 20 Appendix B, Table 2, Column 2.

'n lN 2-9 Rev. 8, 1/94

+ - . . .,.

m m .e 4.,d .4w

                                                                                                        .           at . .e  4. . . . .

Hate-h ODCM 2.1.3 Liauid Effluent Dose Control Ow 5. +. d. S. S.4. e, In accordance with Technical Specificatio s4.10ier and 6-1*(5), t e dose or dose a et a materials in liquid commitment to a MEMBER OF THE PUBLIC r ef fluents released, f rom each unit, to UNRESTRICTED AREAS (see Figure 10-1) shall be limited:

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

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrom to any orga1.

4 2.1.3.1 Applicability l i These limits apply at all times. 2.1.3.2 Actions j With the calculated dose from the release of radioactive materials in liquid e n ef fluents exceeding any of the limits of Sect . , prepar and su ar Regulatory Commission within 30 days pc : :; _. . . s v T.u...in ! !;:rifiertin ces f 4r t-t a Special Report which identifies the to t at ( , the corrective actions to be taken to reduce the releases; and defines the proposed corrective actions to be taken to as subsequen relea 2.1.3. - "-. it 2 , t h i; . q::t in +%nce wiMe limt ir ir 1.;; ;f ny :th_. ..yw.. s pis.4 by "nt '.ie ! ;c.. '.en i r f ? . h This a so ude e s . 1.. olo cal yse . e drinking water source, and (2) the radiological impact en finished water supplies with regard to the requirements of 40 CFR 141, the Safe Drinking Water Act. When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 2.1.3.3 Surveillance Requirements At least once per 31 days, cumulative dose contributions from liquid affluents l for the current calendar quarter and the current calendar year shall be ; determined, for each unit, in accordance with Section 2.4. l 2-10 Rev. 8, 1/94

i f ! Hatch ODCM l l

t 2.1.3.4 Basis l I

This control is provided to implement the requirements of Sections II.A, III.A ] l and IV.A of Appendix I, 10 CFR Part 50. The limits stated in Section 2.1.3 implement the guides set forth in Section II. A of Appendix I. The ACTIONS stated in Section 2.1.3.2 provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in liquid ef fluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water ; supplies that can be potentially affected by plant operations, there is l

reasonable assurance that the operation of the f acility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculations in Section 2.4 !

, 1 l implement the requirements in Section III.A of Appendix I, which state that l conformance with the guides of Appendix I be shown by calculational procedures l based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC l through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 2.4 for calculating the doses due to the actual ! release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory cuide 1.109 (Reference 3) and Regulatory J Guide 1.113 (Reference 6). This control applies to the release of liquid effluents from each unit at the l l site. The liquid effluents from shared LIQUID RADWASTE TREATMENT SYSTEMS are to l be proportioned between the units. l l i { l l l O G 2-11 Rev. 8, 1/94 i

~__

Hatch ODCM i

 /q 5 V              2.1.4   Licuid Padwaste Treatrent S y s tsw1"o hGb1 5.5.U.)

In accordance with Technical Specificati n i . '. ? ' E ; , t LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE. The appropriate ns of the system shall be used to reduce radioactivity in liquid wastes prior to their discharge when the projected doses due to the liquid ef fluent, f rom each unit, to UNRESTRICTED AREAS (see Figure 10-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ of a KEMBER OF THE PUBLIC in 31 days. 2.1.4.1 Applicability This limit applies at all times. 1 2.1.4.2 Actions l With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the LIQUID RADWASTE TREATMENT SYSTEM not in oper . , ar Regulatory Commission within 30

2 Special Report which includes day purrur-t *? Tr '-ir?! Sper!'i r*!-

the o g ormation v Explanation of why liquid radwaste was being discharged without treatment, I a. t identification of any inoperable equipment or subsystems and the reason l for inoperability, i

b. Action (s) taken to restore the ineperable equ;p ent to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence.

When the ACTION statement or other requirements of this control cannot be met, Entry into steps need not be taken to change the Operational Mode of the unit. as a minimum, an Operational Mode or other specified CONDITION may be made if, the requirements of the ACTION statement are satisfied. 2.1.4.3 Surveillance Requirements I Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least f in which the once per 31 days, in accordance with Section 2.5, during per rials occurs discharge of untreated liquid ef fluent containing radioactiv or is expected to occur. (y 1 2-12 Rev. 8, 1/94

                                                                              - , . . .  . . . ' . [."J 'I C Hatch 00CM The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting the controls of Section 2.1.2 and 2.1.3.

2.1.4.4 Basis The OPERABILITY of the LIQUID RADWASTE TREATMINT SYSTEM ensures that this system will be available for use whenever liquid ef fluents require treatment prior to release to the UNRESTRICTED ARIAS. The requirement that the appropriate portions the releases of of this system be used when specified provides assurance that

                                                                          *as low as is reasonably radioactive materials in liquid ef fluents will be kept achievable." This control implementr %e requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objective given in Section II.D of Appendix I to 10 CFR Part 50.

The specified limits governing the use of appropriate portions of the LIQUID RADWASTE TREATMENT ] SYSTEM were specified as a suitable fraction of the dose design objectives set l I forth in Section II.A of Appendix I, 10 CFR Part 50, f or liquid ef f; .ents. I j This control applies to the release of radioactive materials in liquid ef fluents from each unit at the site. For units with shared radwaste systems, the liquid ef fluents f rom the shared system are to be proportioned among the units sharing , n that sy sterr. l I l systers 2.1.5 Ma1er chances to Lieuid Padicactive Waste Treatrent , Licensee initiated MAJOR CHANGES TO LIQUID RADI0 ACTIVE WASTE TREATMENT SYS 1

a. Shall be reportod to the Nuclear Regulatory Commission in th -dwwreet Radioactive Ef fluents Release Report for the period in which the e ne was implemented, in accordance with Section 7.2.2.7.

V iew Bo d

b. ecome ef fective upon review H _;;;: 1:1 by the F1 nt oa t yp r. v.,1 y n Ac/w Pk /~~! MA~. '

.)

Rev. 8, 1/94 2-13 l l

Hatch ODCM 7 2.2 LIQUID RADWASTE TREATMENT SYSTEM l The Edwin I. Hatch Nuclear Plant is located on the south bank of the Altamaha River, which supplies make-up water to the circulating water system and receives l blowdown from the cooling tower. There are two boiling water reactors on the site. Each unit is served by a separate liquid radwaste treatment system. Schematics of the lig radwaste treatment systems are presented in Figure 2-1 and Figure 2-2. The uotted lines indicate alternate pathways through which liquid radwaste may be routed. The two units release liquid radwaste to separate discharge lines. Dilution flow is furnished by the cooling tower blowdown and plant service water systems, if necessary. Releases from plant service water systems are to the main condenser circulating flume, or to the cooling tower blowdown discharge line when needed , for additional dilution. Since each unit is served by a separate dilution stream, liquid releases may be made independently from each of the two units. I Although no significant quantities of radioactivity are expected in the plant l I service water systems, these effluent pathways are monitored as a precautionary measure, j i i i I i 4 i 4 j k i i i 2-14 Rev. 8, 1/94 i

                                                      . ~ . . ~ . .

Match ODCM ! O U l l

                  . WASTE             OFF STANDARO RECYCLE SURGE       4 TJ.DK
                                                ,,I,,,,,,,.,__                                 8 1

I i 1 t I l OFF ETANDARO RECYCLE : 8 i r - - - -T- - - - - - - - - - - - - - - -. r .T- - - - -- - - - I I I i i WASTE waste i TO WASTE WASTE , COLLECTOR COLLECTOR DemeN I EAMPLg i C MOE N TE A e , TANK FILTE R T N TANK a STORAGE TANK J I e i g

                                             ;8                       1g                         e
             , . _ _   _----______[,_____---

oFF sTANDAmo RECYCtt 4 I l I I floor floor I floor floor I RAo AfioN ORAiN CRAIN I DRAIN 3 DRAIN i MONITOR COLLECTOR v FILTE R ,_ OEMIN + SAMPLE ', , TANK j i TANK l i ! I a

i. ., . J TO OtSCMAmes CANAL CNe MsCAL CNEmicat warTE wagyg

                        =                                                                    "

TANE gampg,g TANK l DEMIN FEED TANK LAUNORY LAWORY ORA N 0 "" TANG FILTER O d Figure 2-1. Unit 1 Liquid Radwaste Treatment System 2-15 Rev. 8, 1/94

Hatch ODCM (r) 'w)

                               *6 088 STANDARO RECYCLE SURSE           4-.-..                    .--                     p-         .--.q TAWK                                                              e t                   '

l ' 8 l 6

                                                                                                 '                   8 I                   I 3

I p 4. ._ _ _OFF STANDARD RECYCLE _____.--.-.m.____-_.'

                                ?        I                                                        i                  '

l I l

                                                                                                  '                               TO waste             3     MASTE                                              i      waste        i E

COLLECTOR 4 COLLECTOR g , ,;g_- gagptg _ COWENEATE TAME FILTER j, I TAmu e M RADE II I il i ;

i u _ _ _ _ _ _a i , 4 I g OFF ETANOARO RECYCLE l 8 g

p. _ - - - . ./76 - - - /L - -

                             '                                         I                             I             I I                             I             8 g                             g             g          RADIATION FLOOR                    PLOOR          ,      a            FLOOR            ,    FLOOR    I          M ITOR r                       ORAIN          -.

ORAIN *. DRAIN gggggg f ' V { COLLECTOR FILTE R l DEM4N g gagpgg

%                       TA88K                                            8 1          TAasu                       9 l                     s

t. - _ _ - - _ _ J ;a_ ,,,,

CANAL CNEMsCAL e,,,,,,g

                         "#I                                                                              waste TAME                ,
                                                                                                       ,  gg TANK o

9F CHEM 0 CAL WASTE fvtWTR ALAZE R TAhK Figure 2-2. Unit 2 Liquid Radwaste Tratatment System 2-16 Rev. 8, 1/94

                        .m..___m.   . .                                        _  _ _ _ . - _ _ . . .

l 2.3 LIQUID EFFLUENT HONITOR SETPOINTS 2.3.1 General' Provisions Recardino Setooints l Liquid monitor setpoints calculated in accordance with the methodology presented J l in this section will be regarded as upper bounds for the actual high alarm f setpoints. That is, a lower value for the high alarm setpoint may be established j or retained on the monitor, if desired. Intermediate level setpoints should be l I established at an appropriate level to give suf ficient warning prior to reaching the high r.larm setpoint. If no release is planned for a particular pathway, or if there is no detectable activity in the planned release, the monitor setpoint j should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inadvertent release occur. Two basic setpoint methodologies are presented below. For radwaste system discharge monitors, setpoints are determined to assure that the limits of Section 2.1.2 are not exceeded. For monitors on streams that are not expected to contain significant radioactivity, the purpose of the monitor setpoints is to cause an alarm on low levels of radioactivity, and to terminate the release where this is possible. Section 2.1.1 establishes the requirements for liquid effluent monitoring instrumentation. Table 2-4 lists the monitors for which each of the setpoint methodologies is applicable. , l W I I I i t t i i. 2-17 Rev. 8, 1/94 l l - .--

Hatch ODCM i Table 2-4. Applicability of Liquid Monitor Setpoint Methodologies Liquid Radwaste Discharge Monitors Setpoint Method Section 2.3.2 Release Type BATCH , Unit 1 or Unit 2 Liouid Radwaste System Effluent Monitor: 1D11-N007 / 2D11-N007 I I Normally Low-Radioactivity Streams with Termination or Diversion upon Alarm : Plant Hatch has no liquid effluent streams in this category. Normally Low-Radioactivity Streams with Alarm Only Setpoint Method Section 2.3.3 Release Type: CONTINUOUS Unit 1 or Unit 2 Plant Service Water System Effluent Monitor 1D11-N008 / 2D11-N008 i l i N, l 2-18 Rev. 8, 1/94

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

l Hatch ODCM ! l ! k 2.3.2 Setooints for Radwaste System Discharoe Monitors i l 1 2.3.2.1 overview of Method LIQUID RADWASTE TREATMENT SYSTEM effluent line radioactivity monitors are intended to provide alarm and automatic termination of release prior to exceeding j the limits specified in Section 2.1.2 at the point of release of the diluted ! effluent into the UNRESTRICTED AREA. Therefore, their alarm / trip setpoints are i established to ensure compliance with the following equation (equation adapted l from Addendum to Reference 1): s TT

CECL (2.1)

! F+f l I where: I i the Ef fluent Concentration Limit corresponding to the mix CECL = , l of radionuclides in the effluent being considered for l discharge, in pCi/mL. O lV c= the setpoint, in pC1/mL, of the radioactivity monitor measuring the l concentration of radioactivity in the effluent line prior to f dilution and subsequent release. The setpoint represents a concen-tration which, if exceeded, could result in concentrations i exceeding the limits of Section 2.1.2 in the UNRESTRICTED AREA. f= the ef fluent flowrate at the location of the radioactivity monitor, in gpm. F= the dilution stream flowrate which can be assured prior to the i release point to the UNRESTRICTED AREA, in gpm. A predetermined dilution flowrate must be assured for use in the calculation of the radioactivity monitor cetpoint. l l TF = the tolerance factor selected to allow flexibility in the establishment of a practical monitor setpoint which could accommodate affluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2; the i tolerance factor must not exceed a value of 10. i j While equation (2.1) shows the relationships of the critical parameters that < determine the setpoint, it cannot be applied practically to a mixture of radio-l 2-19 Rev. 8, 1/94

Hatch ODCM > O. nuclides with different Effluent Concentration Limits (ECLs). For a mixture of , radionuclides, equation (2.1) is satisfied in a practicable manner based on the calculated ECL fraction-of the radionuclide mixture and the dilution stream flowrate that can be assured for the duration of the release (F d ), by calculating the maximum permissible affluent flowrate (fm) and the radioactivity monitor setpoint (c). , The setpoint method presented below is applicable to the release of only one tank of liquid radwaste per reactor unit at a given time. Liquid releases must be ! controlled administratively to ensure that this condition is met; otherwise, the setpoint method may not ensure that the limits of Section 2.1.2 are not exceeded. 2.3.2.2 Setpoint Calculation Steps 1 Sten 1: Determine the radionuclido concentrations in the liquid waste being j l ' considered for release in accordance with the sampling and analysis requirements of Section 2.1.2. All liquid radwastes are collected in tanks for sampling and analysis prior to release. To ensure that a representative sample can be taken from a tank, its lO contents will be recirculated for a minimum time period to allow adequate mixing of the contents. Minimum recirculation times are as follows (Reference 22): I Minimum Recirculation Time (minutes) Tankfs) Unit 1 Unit 2 l Waste sample tanks 40 40 Floor drain sample tanks 70 105 Chemical waste sample tanks 65 65 Domineralizer feed tank 115 NA Laundry drain tanks 50 NA The total concentration of the liquid waste is determined by the results of all required analyses on the collected sample, as follows: {Cj = C,+{C,+Cf+Cf + {Cg (2.2) i s E i where: 1 i Ca= the gross concentration of alpha emitterm in the liquid waste, not less than that measured in the mos'. recent applicable composite sample. 2-20 Rev. 8, 1/94

Hatch ODCM Cs = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in the liquid waste, not less than that measured in the most recent applicable composite sample. Cf= the concentration of Fe-55 in the liquid waste, not less than that measured in the most recent applicable composite sample. Ct= the concentration of H-3 in the liquid waste, not less than that measured in the most recent applicable composite sample. 4 1 I Cg = the concentration of gamma emitter g in the liquid waste as measured by gamma ray spectroscopy performed on the sample for the release under consideration. , l l The Cg term will be included in the analysis of each waste sample; terms for gross concentrations of alpha emitters, Sr-89, Sr-90, Fe-55, and tritium will be included in accordance with the sampling and analysis program required for the waste stream (see Section 2.1.2). For each analysis, only radionuclides identified and detected above background for the given measurement should be included in the calculation. When using the alternate setpoint methodology of step 5.b, the historical maximum values of C,, C,, cf, and Ct shall be used. Steo 2: Determine the required dilution factor for the mix of radionuclides I detected in the waste. j l Measured radionuclide concentrations are used to calculate ECL fractions. The ECL fractions are used along with a safety factor to calculate the required dilution f actor; this is the minimum ratio of dilution flowrate to waste flowrate that must be maintained throughout the release to ensure that the limits of Section 2.1.2 are not exceeded at the point of discharge into the UNRESTRICTED AREA. The required dilution factor, RDF, is calculated as the sum of the dilution factors required for gamma emitters (RDF )yand for non-gamma-emitters (RDFny)8 Cl RDF = ggg + \ (m W) } (2.3)

RDry + RDFny D 2-21 Rev. 8, 1/94

Hatch ODCM CI C ECL (2.4) RDF = E W 7 (SF) (TE) Ca C C Cg ECL a

                                                              .r,.f.

y ECL, ECL g, ECLj g2,g} RDTny * (SF) (TT) 1 l where: ; cj = the measured concentration of radionuclide i as defined in step 1, J in pci/mL. The C,, C' s C,f and Cg terms will be included in the l calculation as appropriate. ECL; = the Effluent Concentration Limit for radionuclide i from 10 CFR Part 20, Appendix B, Table 2, Column 2 (except for noble gases as ) discussed below). In the absence of information regarding the i solubility classification of a given radionuclide in the waste stream, the solubility class with the lowest ECL shall be assumed. For dissolved or entrained noble gases, the concentration shall be limited to lx10 4 pci/mL. For gross alpha, the ECL shall be 2x10~9 pC1/mL; if specific alpha-emitting radionuclides are measured, the ECL for the specific radionuclide(s) should be used. SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement. The value for the safety factor must be between 0 and 1. A value of 0.5 is reasonable for liquid releases; a more precise value may be developed if desired. l 1 TF = the tolerance factor (as defined in Section 2.3.2.1). Sten 3: Determine the release-specific assured dilution stream flowrate. Determine the dilution stream flowrate that can be assured during the release period, designated F; d this value is the setpoint for the dilution stream flowrate measurement dev!,ce. If simultaneous radioactive releases are planned from the same reactor unit, the unit's dilution stream must be allocated among all the simultaneous releases, whether or not they are monitored during release. Normally, only the batch tank 2-22 Rev. 8, 1/94

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

Hatch ODCM ef fluents need be considered, unless there is detectable radioactivity in one of the normally low-radioactivity streams (see Table 2-4). Allocation of the dilution stream to multiple release paths is accomplished as follows: Edp

Id ( AFp) (2.6) where Fdp = the dilution flowrate allocated to release pathway p, in gpm.

AFp= the dilution allocation factor for release pathway p. AFp may be assigned any value between 0 and 1 for each active release pathway, under the condition that the sum of the AFp for all active release pathways for each unit does not exceed 1. (Notes Because the two units have separate dilution streams, the two units do not affect each other with respect to dilution allocation.) the assured minimum dilution flow for the unit, in gpm. For Plant Fd= Hatch, Fd is normally established at 10,000 gpm. If more precise allocation factor values are desired, they may be determined based on the relative radiological impact of each active release pathway; this i may be approximated by multiplying the RDF of each effluent stream by its ! respective planned release flowrate, and comparing these values. If only one release pathway for a given reactor unit contains detectable radioactivity, its j AFp may be assigned the value of 1, making Fdp equal to Fd* For the case where RDF 51, the planned release meets the limits of Section 2.1.2 without dilution, and may be released with any desired effluent flowrate and dilution flowrate. I steo 4: Determine the maximum allowable waste discharge flowrate. For the case where RDF > 1, the maximum permissible effluent discharge flowrate for this release pathway, fmp (in 9Pm), is calculated as follows: f mp . IdP (2.7) (RDF) l n\ For the case RDF s 1, equation (2.7) is not valid. However, as discussed above, (V J when RDF 51, the release may be made at full discharge pump capacity; the radio-2-23 Rev. 8, 1/94 I

Hatch ODCM activity monitor setpoint must still be calculated in accordance with Step 5 below. I NOTE la Discharge flowrates are actually limited by the discharge pump capacity. When the calculated maximum permissible release flowrate exceeds the pump capacity, the release may be made at full capacity. Discharge flowrates less than the pump capacity must be achieved by throttling if this is available; if throttling is not available, the release may not be made as planned. NOTE 2: If, at the time of the planned release, there is detectable radio-l activity due to plant operations in the dilution stream, the diluting capacity of the dilution stream is diminished. (In addition, sampling and analysis ref the other radioactive af fluents af fecting the dilution stream mtst be sufficient to ensure that the liquid effluent done limits spacified in the controls of Section 2.1.3 are not exceeded.) Undes these conditions, equation (2.7) must be modified to account for the radioactivity present in the dilution stream prior to the introduction of the planned release r , l Tgp Cir gg,gy f ,p = PDF r Ed i r ECLg, , where: I , C r= the measured concentration of radionuclide i in release ' l pathway r that is contributing to radioactivity in the ) dilution stream.

f r

                              =     the effluent discharge flowrate of release pathway r.

If the entire dilution stream contains detectable activity due to plant operations, whether or not its source is identified, f r =F'd and Cj, is the concentration in the total dilution system. This note does not apply: a) if the RDF of the planned release is s it or b) if the release contributing radioactivity to the dilution i stream has been accounted for by the assignment of an allocation factor. o) 2-24 Rev. 8, 1/94 j

j Hatch ODCM ' 1 V steo 5: Determine the maximum radioactivity monitor setpoint concentration. Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the limits of Section 2.1.2 will not be exceeded. Because the radioactivity monitor responds primarily to gamma radiation, the monitor setpoint cp for release pathway p (in pCi/mL) is based on the concentration of gamma emitters in the waste stream, as follows: C p

                                              " ApbC       g                               (2.9) l where:

l i A p= an adjustment factor which will allow the setpoint to be ; ! established in a practical manner to prevent spurious alatme while f allowing a margin between measured concentrations and the limits l ! of Section 2.1.2. l l Stoo 5.a. If the concentration of gamma emitters in the effluent to ) be released is sufficient that the high alarm setpoint l ! can be established at a level that will prevent spurious alarms, Ap should be calculated as folicws: 1 Ap = x ADF l RDF 1 Idp (2.10) i

                                              .        x RDF      f ap where ADF =   the assured dilution factor, f,p =   the anticipated actual discharge flowrate for the planned release (in gpm), a value less than f g.

The release must then be controlled so that the actual effluent discharge flowrate does not exceed f,p at any time.

 ,O            Stoo 5.b.         Alternatively, A may p       be calculated as follows:

2-25 Rev. 8, 1/94 l l

 .._.~.-m..,__-                        . ~ . . .     .m___..._...____                         _ _ . . - . . . _ _ . . - _ . _ - _ _ .._._ . . . _ _ . _ _ . . _ _ . .                  - . -

I Hatch ODcM i ADT - RDT ny

                                                                           -A p   =                                                                                          (2.11)
                                                                                                 #         7                                                                                    f sten 5.c.                              Evaluate the computed value of Ap as follows:

If Ap 2 1, calculate the monitor setpoint, c. p However, if cp is ; within about_10 percent of cg , it may be impractical to [- ' use this value of e. p This situation indicates - that measured concentrations are approaching values which f would cause the limits of section 2.1.2 to be exceeded. j l Therefore, steps should be taken to reduce potential con- ! centrations at the point of discharge; these steps may include decreasing the planned effluent discharge l l~ . flowrate, increasing the dilution stream- flowrate, j postponing simultaneous releases, and/or decreasing the effluent concentrations by further processing the liquid planned for release. Alternatively, allocation factors

                                                                  - for the active liquid release pathways may be reassigned.

l When one or more of these actions has been taken, repeat l steps 1-5 to calculate a new radioactivity monitor setpoint. If Ap < 1, the release may not be made as planned. Consider the alternatives discussed in the paragraph above, and calculate a new setpoint based on the results of the actions taken. 2.3.2.3- Use of the calculated setpoint The setpoint calculated above is in the units pCi/mL. The monitor actually measures a count rate that includes background, so that the calculated setpoint must be converted accordingly: cp = p p+By c *E (2.7a) where: cp = the monitor setpoint as a count rate. Ep = the monitor calibration factor, in count rate /(pci/mL). Monitor calibration data for conversion between count rate and f concentration may include operational cata obtained from I 2-26 Rev. 8, 1/94 I

Hatch ODCM determining the monitor response to stream concentrations measured I by liquid sample analysin. l l- the monitor background count rate. In all carss, monitor Sp = l background must be controlled so that the monitor is capable of responding to concentrations in the range of the setpoint value. ] The count rate units of ep , Ep , and Bp in equation (2.7a) must be the same (cpm l l or cps). f 2.3.3 setnoints for Monitors on Normally Low-Radioactivity Streams f Radioactivity in these streams (listed in Table 2-4 above) is expected to be at l very low levels, generally below detection limits. Accordingly, the purpose of

these monitors is to alarm upon the occurrence of significant radioactivity in l

j . these streams, and to terminate or divert the release where this is possible. 2.3.3.1 Normal Conditions i l- : When radioactivity in one of these streams is at its normal low level, its radio-activity monitor setpoint should be established as close to background as practical to prevent spurious alarms, and yet alarm should an inadvertent release occur. l 2.3.3.2 Conditions Requiring an Elevated Setpoint i j Under the following conditions, radionuclide concentrations must be determined i and an elevated radioactivity monitor setpoint determined for these pathways: e i' e For streams that can be diverted or isolated, a new monitor setpoint must be established when it is desired to discharge the stream directly to the dilution water even though the radioactivity in the stream exceeds the l level which would normally be diverted or isolated. e For streams that cannot be diverted or isolated, a new monitor setpoint must be established whenever: the radioactivity in the stream becomes i detectable above the background levels of the applicable laboratory f analyses; or the associated radioactivity monitor detects activity in the stream at levels above the established alarm setpoint. .O I When an elevated monitor setpoint is required for any of these effluent streams, it should be determined in the same manner as described in Section 2.3.2. 2-27 Rev. 8, 1/94

Hatch ODCM

    ]
  %.)   However, special consideration must be given to Step 3. An allocation factor must be assigned to the normally low-radioactivity release pathway under consideration, and allocation factors for other release pathways discharging simultaneously must be adjusted downward (if necessary) to ensure that the sum of the allocation factors does not exceed 1.       Sampling and analysis of the normally low-radioactivity streams must be sufficient to ensure that the liquid ef fluent dose limits specified in the controls of Section 2.1.3 are not exceeded.

1 i l l l l' i I t i t i I 2-28 Rev. 8, 1/94

l n Hatch ODCM , t 2.4 LIQUID EFFLUENT DOSE CALCULATIONS The following sub-sections present the methods required for liquid ef fluent dose calculations, in deepening levels of detail. Applicable site-specific pathways and parameter values for the calculation of D , Aj7, 7 and CFjy aro summarized in l Table 2-5. 2.4.1 Calculation of Dose l l The dose limits for a MEMBER OF THE PUBLIC specified in Section 2.1.3 are on a ! per-unit basis. Therefore, the doses calculated in accordance with this section i must be determined and recorded on a per-unit basis, including apportionment of l releases shared between the two units. l For the purpose of implementing Section 2.1.3, the dose to the maximum exposed individual due to radionuclides identified in liquid ef fluents released from each unit to UNRESTRICTED AREAS will be calculated as follows (equation from Ref-erence 1, page 15): l m

   .                                   D7 =

Aj7 { ( Atj Cif Fj) (2.12) s , !=1 I where: D7 = the cumulative dose commitment to the total body or to any organ 7, l in mrom, due to radioactivity in liquid effluents released during the total of the m time periods Atg. I Aj7 = the site-related adult ingestion dose commitment factor, for the total body or for any organ 7, due to identified radionuclide 1, in (mromamL)/(h pci). Methods for the calculation of Aj7 are presented below in Section 2.4.2. The values of Air to be used in dose calculations for releases from the plant site are listed in Table 2-8. Atg = the length of time period 1, over which C g iand Fg are averaged for liquid releases, in h.

      /         Cg=

i the average concentration of radionuclide i in undiluted liquid effluent during time period 1, in pCi/mL. Only radionuclides 2-29 Rev. 8, 1/94

l l Hatch ODCM l identified and detected above background in their respective samples should be included in the calculation. Fg = the near-field average dilution factor in the receiving water of the UNRESTRICTED AREA: St Ef = (2.13) l E g xZ where: ! i ft= the average undiluted liquid waste flowrate actually ; j observed during the period of radioactivity release, in 9Pm. i 1 Ft= the average dilution stream flowrate actually observed l 1 during the period of radioactivity release, in gpm. Z= the applicable dilution factor for the receiving water body, in the near field of the discharge structure, during the period of radioactivity release, from Table 2-5. ! \O) l NOTE: In equation (2.13), the product (Fg x Z) is limited to ' 1000 cfs (= 448,000 gpm) or less. (Reference 1, Section l 4.3.) 1 2.4.2 calculation of A;7 The site-related adult ingestion dose commitment factor, A 7, is calculated as follows (equation adapted from Reference 1, page 16, by addition of the irrigated l garden vegetation pathway):

                                ,                                                 3 5        , -hi 'w                       'l + U CFfy                      (2.14)

Aj7 = 1.14 x 10 + Uf stfe y Drj7 l l l l where: 1.14 x 105 = a units conversion factor, determined by: 106 pci/pci x 10 3 mL/L + 8760 h/y. 2-30 Rev. 8, 1/94

i Hatch ODCM Uw= the adult drinking water consumption rate applicable to the plant site (L/y). l D, = the dilution f actor from the near field of the discharge structure for the plant site to the potable water intake location. the decay constant for radionuclide 1 (h-I) . Values of 1; used in

1 = effluent calculations should be based on decay data from a recognized and current source, such as Reference 26. l tw = the transit time from release to receptor for potable water consumption (h). l Uf= the adult rate of fish consumption applicable to the plant site l (kg/y). l i BFj = the bicaccumulation factor for radionuclide i applicable to freshwater fish in the receiving water body for the plant site, in (pci/kg)/(pci/L) = (L/kg). For specific values applicable to the j( plant site, see Table 2-6. ( tg = the transit time from release to receptor for fish consumption (h). i Uy = the adult consumption rate for irrigated garden vegetation applicable to the plant site (kg/y). 1 CFjy = the concentration factor for radionuclide i in irrigated garden i vegetation, as applicable to the vicinity of the plant site, in (pci/kg)/(pci/L). Methods for calculation of CFjy are presented below in Section 2.4.3. l j DFj7 = the dose conversion factor for radionuclide i for adults, in j organ 7 (mrem /pci). For specific values, see Table 2-7. 2.4.3 Calculation of CFjy . The concentration factor for radionuclide i in irrigated garden vegetation, CFjy in (L/kg), is calculated as follows: (~. 2-31 Rev. 8, 1/94

Hatch ODCM o For radionuclides other than tritium (equation adapted from Reference 3, equations A-8 and A-9): cy r (1 - e El le y ty agy (1 - e i %) -ki 'h (2.15)

                                    ,   y,3                         .

YyAgg P kg o For tritium (equation adapted from Reference 3. equations A-9 and A-10): CEgy =M*L y (2.16) where: M= the additional river dilution f actor from the near field of the discharge structure for the plant site to the point of irrigation water usage. I= the average irrigation rate during the growing season (L)/(m 2*h). r= the fraction of irrigation-deposited activity retained on the edible portions of leafy garden vegetation. Yy= the areal density (agricultural productivity) of leafy garden vegetation (kg/m 2) fg = the fraction of the year that garden vegetation is irrigated. Bjy = the crop to soil concentration factor applicable to radionuclide 1 (pci/kg garden vtgetation)/(pci/kg soil). . i P= the ef fective surf ace density of soil (kg/m )2 . l lj = the decay constant for radionuclide 1 (h-I). Values of 1; used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 26. 1, = the rate constant for removal of activity from plant leaves by weathering (h-I) . 2-32 Rev. 8, 1/94

j - i e Hatch ODCM

\

( lei = the effective removal rate for activity deposited on crop leaves 1 (h-I) calculated as lei " li*A w' i i t, = the period of leafy garden vegetation exposure during the growing , season (h). tb= the period of long-term buildup of activity in soil (h). , th= the time between harvest of garden vegetation and human consumption (h). Ly = the water content of leafy garden vegetation edible parts (L/kg). I i t i t f l f i

i ' t 1 2-33 Rev. 8, 1/94 i

1 Match ODCM Table 2-5. Parameters for Calculation of Doses Due to Liquid Ef fluent Releases Dose calculation Receptor Locations: T.ith Vicinity of plant discharge Drinkino Water None + + Irricated Garden Vecetation None + + Numerical Parameters Parameter Value Reference Z 10 Ref. 9, Sec. 5.1; Ref. 6, Sec. B; Ref. 21 U, O L/y (Pathway not applicable) Dw 1.0 + tw 12 h Ref. 3, Sec. A.2 Ur 21 kg/y Ref. 3, Table E-5 tg 24 h Ref. 3, Sec. A.2 Uy 0 kg/y (Pathway not applicable) M 1.0 + 1 No value ** r 0.25 Ref. 3, Table E-15 Yy 2.0 kg/m2 Ref. 3, Table E-15 fg 1. 0 + P 240 kg/m2 Ref. 3, Table E-15 lw 0.0021 h"I (i.e., half- Ref. 3, Table E-15 life of 14 d) t, 1440 h (= 60 d) Ref. 3, Table E-15 tb 1.31 x 105 h (= 15 y) Ref. 3, Table E-15 th 24 h Ref. 3, Table E-15 Ly 0.92 L/kg Based on Ref. 2*/, Table 5.16 (for lettuce, cabbage, etc.)

      * - Because there is no known drinking water pathway or irrigated garden vegetation pathway downstream of the plant site, the parameters for these pathways are default values, and the usage factors are set to 0.
      + - There is no established default value for this parameter.               The most conservative physically realistic value is 1.0.
     ** - There is no established def ault value for this parameter. A value will be supplied if the pathway is ever observed.
     ++ - Confirmed during the annual river water use survey.

2-34 Rev. 9, 2/94

Hatch ODCM Table 2-6. Element Transfer Factors Freshwater Fish Element , 8Fj H 9.0 E-01 C 4.6 E+03 Na 6.6 E+01 _ P 2.5 E+04 Cr 1.5 E+02 Mn 8.9 E+01 Fe 6.0 E+00 Co 1.7 E+02 Ni 1.0 E+02 Cu 4.4 E+01 Zn 2.9 E+02 i Br 4.2 E+02 Rb 2.0 E+03 Sr 3.8 E+00 1 Y 2.5 E+01 l /' 4 Zr Nb 1.9 E+02 4.1 E+01 Mo 1.8 E+02 Tc 1.5 E+01 Ru 4.6 E+00 Rh 1.0 E+01 Ag 3.5 E+02 Sb 1.0 E+00 Te 4.0 E+02 I 4.3 E+01 Cs 5.8 E+02 ! Ba 5.0 E+00 La 2.5 E+01 Ce 8.4 E+01 Pr 2.5 E+01 Nd 4.6 E+01 W 1.2 E+03 Np 1.0 E+01

       *-    Bioaccumulation Factors for freshwater fish, in (pCi/kg)/(pCi/L).

They are obtained from Reference 9 (Appendix A, Table 2.3-1), except as follows: Reference 2 (Table A-8) for Sb. O 2-35 Rev. 8, 1/94

j l ! Hatch ODCM V Table 2-7. Adult Ingestion Dose Factors l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI I H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 l C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 i Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 l Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 1 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 ! Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 l Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2.14E-09 No Data No Data No Data No Data Rb-86 No Data 2.11E-05 9.83E-C6 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 l Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 l All values are in (mrem /pci ingested) . They are obtained from Reference 3 (Table E-11), except as follows: Reference 2 (Table O A-3) for Rh-105, sb-124, and Sb-125. 2-36 Rev. 8, 1/94

                                                  .                                       l 7

Hatch ODCM Table 2-7 (contd). Adult Ingestion Dose Factors l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 l Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 l Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Uta No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 l l Y-93 2.68E-09 No Data 7.40E-11 No Data No Data ' No Data 8.50E-05 l Zr-95 3.34E-08 9.75E-09 6.6CE-09 No Data 1.53E-08 No Data 3.09E-05 l Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.2EE-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 i Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41E-05 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05 Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.3*/E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 ! Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 O G 2-37 Rev. 8, 1/94

Hatch ODCM Table 2-7 (contd). Adult Ingestion Dose Factors Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 i Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 ) Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 l l Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 ! Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 I Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 l W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 l Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 O , 2-38 Rev. 8, 1/94

Hatch ODCM -. Table 2-8. Site-Related Ingestion Dose Factors, Ajy Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 8.86E+01 8.86E+01 8.86E+01 8.86E+01 8.86E+01 8.86E+01 8.86E+01 P-32 1.10E+07 6.84E+05 4.25Evo5 0.00 0.00 0.00 1.24E+06 Cr-51 0.00 0.00 9.32E-01 5.57E-01 2.05E-01 1.24E+00 2.34E+02 Mn-54 0.00 9.72E+02 1.85E+02 0.00 2.89E+02 0.00 2.98E+03 Mn-56 0.00 3.87E-02 6.86E-03 0.00 4.91E-02 0.00 1.23E+00 Fe-55 3.95E+01 2.73E+01 6.36E+00 0.00 0.00 1.52E+01 1.56E+01 Fe-59 6.14E+01 1.44E+02 5.53E+01 0.00 0.00 4.03E+01 4.81E+02 Co-58 0.00 3.00E+02 6.73E+02 0.00 0.00 0.00 6.09E+03 Co-60 0.00 8.71E+02 1.92E+03 0.00 0.00 0.00 1.64E+04 ) Ni-63 3.11E+04 2.16E+03 1.04E+03 0.0C 0.00 0.00 4.50E+02 l Ni-65 1.72E-01 2.23E-02 1.02E-02 0.00 0.00 0.00 5.66E-01 Cu-64 0.00 2.37E+00 1.11E+00 0.00 5.97E+00 0.00 2.02E+02 Zn-65 3.35E+03 1.07E+04 4.82E+03 0.00 7.13E+03 0.00 6.72E+03 Zn-69 1.14E-07 2.19E-07 1.52E-08 0.00 1.42E-07 0.00 3.28E-08 Br-83 0.00 0.00 3.83E-02 0.00 0.00 0.00 5.52E-02 Br-84 0.00 0.00 1.22E-12 0.00 0.00 0.00 9.61E-18 O Br-85 Rb-86 Rb-88 0.00 0.00 0.00 0.00 9.73E+04 4.53E+04 0.00 1.29E-22 6.82E-23 0.00 0.00 0.00 0.00 0.00 0.00 I 0.00 0.00 0.00 1.92E+04 0.00 1.78E-33 Rb-89 0.00 1.61E-26 1.14E-26 0.00 0.00 0.00 0.00 Sr-89 2.76E+03 0.00 7.93E+01 0.00 0.00 0.00 4.43E+02 Sr-90 6.90E+04 0.00 1.69E+04 0.00 0.00 0.00 1.99E+03 Sr-91 8.95E+00 0.00 3.62E-01 0.00 0.00 0.00 4.26E+01 J Sr-92 4.22E-02 0.00 1.83E-03 0.00 0.00 0.00 8.36E-01 l Y-90 4.44E-01 0.00 1.19E-02 0.00 0.00 0.00 4.71E+03 Y-91m 1.04E-11 0.00 4.01E-13 0.00 0.00 0.00 3.04E-11 Y-91 8.34E+00 0.00 2.23E-01 0.00 0.00 0.00 4.59E+03 Y-92 4.60E-04 0.00 1.35E-05 0.00 0.00 0.00 8.06E+00 Y-93 3.09E-02 0.00 8.53E-04 0.00 0.00 0.00 9.80E+02 Zr-95 1.37E+01 4.39E+00 2.97E+00 0.00 6.88E+00 0.00 1.39E+04 Zr-97 2.86E-01 5.76E-02 2.63E-02 0.00 8.70E-02 0.03 1.78E+04 Nb-95 5.99E-01 3.33E-01 1.79E-01 0.00 3.29E-01 0.00 2.02E+03 Mo-99 0.00 1.44E+03 2.75E+02 0.00 3.27E+03 0.00 3.35E+03 ; Tc-99m 5.59E-04 1.58E-03 2.01E-02 0.00 2.40E-02 7.75E-04 9.36E-01 All values are in (mremamL)/(h*pci). They are calculated using equation (2.14), and data from Table 2-5, Table 2-6, and Table 2-7. When "No Data" is shown for a radionuclide-organ combination in () Table 2-7, Ag f actors in this table are presented as zero. 2-39 Rev. 8, 1/94

Hatch ODCM Table 2-8 (contd). Site-Related Ingestion Dose Factors, Ag I l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI__ Tc-101 2.71E-33 3.91E-33 3.83E-32 0.00 7.03E-32 2.00E-33 0.00 i Ru-103 2.00E+02 0.00 8.62E-01 0.00 7.64E+00 0.00 2.34E+02 l Ru-105 4.00E-Oat 0.00 1.58E-03 0.00 5.17E-02 0.00 2.45E+00 Ru-106 3.02E+01 0.00 3.83E+00 0.00 5.84E+01 0.00 1.96E+03 Rh-105 1.83E+00 1.33E+00 8.72E-01 0.00 5.63E+00 0.00 2.11E+02 Ag-110m 1.34E+02 1.24E+02 7.34E+01 0.00 2.43E+02 0.00 5.05E+04 Sb-124 6.65E+00 1.25E-01 2.63E+00 1.61E-02 0.00 5.16E+00 1.88E+02 Sb-125 5.33E+00 5.74E-02 1.07E+00 4.74E-03 0.00 5.57E+02 4.71E+01 l Te-125m 2.54E+03 9.19E+02 3.40E+02 7.63E+02 1.03E+04 0.00 1.01E+04 l Te-127m 6.44E+0J 2.30E+03 7.85E+02 1.65E+03 2.62E+04 0.00 2.16E+04 l l Te-127 1.780+01 6.38E+00 3.85E+00 1.32E+01 7.24E+01 0.00 1.40E+03 l l Te-129m 1.08E+04 4.02E+03 1.71E+03 3.71E+03 4.50E+04 0.00 5.43E+04 l l Te-129 1.78E-05 6.68E-06 4.33E-06 1.36E-05 7.47E-05 0.00 1.34E-05 l Te-131m 9.51E+02 4.65E+02 3.88E+02 7.37E+02 4.71E+03 0.00 4.62E+04 Te-131 8.64E-17 3.61E-17 2.73E-17 7.10E-17 3.78E-16 0.00 1.22E-17 Te-132 1.95E+03 1.26E+03 1.18E+03 1.39E+03 1.22E+04 0.00 5.97E+04 I-130 2.03E+01 5.98E+01 2.36E+01 5.06E+03 9.32E+01 0.00 5.14E+01 I-131 3.93E+02 5.62E+02 3.22E+02 1.84E+05 9.63E+02 0.00 1.48E+02 I-132 1.51E-02 4.04E-02 1.41E-02 1.41E+00 6.43E-02 0.00 7.59E-03 I-133 6.57E+01 1.14E+02 3.48E+01 1.68E+04 1.99F+02 0.00 1.03E+02 I-134 6.26E-08 1.70E-07 6.09E-08 2.95E-06 2.71E-07 0.00 1.48E-10 I-135 3.68E+00 9.64E+00 3.56E+00 6.36E+02 1.55E+01 0.00 1.09E+01 ! Cs-134 8.63E+04 2.05E+05 1.68E+05 0.00 6.64E+04 2.21E+04 3.59E+03 0.00 1.88E+04 2.58E+03 3.85E+03 Cs-136 8.58E+03 3.39E+04 2.44E+04 Cs-137 1.11E+05 1.51E+05 9.91E+04 0.00 5.14E+04 1.71E+04 2.93E+03 Cs-138 2.64E-12 5.22E-12 2.59E-12 0.00 3.84E-12 3.79E-13 2.23E-17 l Ba-139 7.05E-06 5.03E-09 2.07E-07 0.00 4.70E-09 2.85E-09 1.25E-05 Ba-140 2.30E+02 2.89E-01 1.51E+01 9.00 9.83E-02 1.66E-01 4.74E+02 l Ba-141 1.06E-24 8.00E-28 3.57E-26 0.00 7.44E-28 4.54E-28 4.99E-34 l Ba-142 0.00 0.00 0.00 0.00 0.00 0.00 0.00 La-140 9.89E-02 4.99E-02 1.32E-02 0.00 0.00 0.00 3.66E+03 La-142 2.19E-07 9.96E-08 2.48E-08 0.00 0.00 0.00 7.27E-04 Co-141 1.84E+00 1.25E+00 1.41E-01 0.00 5.79E-01 0.00 4.76E+03 Ce-143 2.00E-01 1.48E+02 1.64E-02 0.00 6.52E-02 0.00 5.54E+03 Ce-144 9.79E+01 4.09E+01 5.26E+00 0.00 2.43E+01 0.00 3.31E+04 Pr-143 5.23E-01 2.10E-01 2.59E-02 0.00 1.21E-01 0.00 2.29E+03 Pr-144 1.48E-28 6.14E-29 7.51E-30 0.00 3.46E-29 0.00 2.13E-35 Nd-147 6.50E-01 7.52E-01 4.50E-02 0.00 4.39E-01 0.00 3.61E+03

W-187 1.47E+02 1.23E+02 4.30E+01 0.00 0.00 0.00 4.03E+04 Np-239 2.12E-02 2.09E-03 1.15E-03 0.00 6.51E-03 0.00 4.28E+02 2-40 Rev. 8, 1/94

i Hatch ODCM O L 2.5 LIQUID EFFLUENT DOSE PROJECTIONS 2.5.1 Thirty-One Day Dose Proiections In order to meet the requirements for operation of the LIQUID RADWASTE TREATMENT SYSTEM (see Section 2.1.4), dose projections must be made at least once each 31 days; this applies during periods in which a discharge to UNRESTRICTED AREAS cf liquid affluents containing radioactive materials occurs or is expected. Projected 31-day doses to individuals due to liquid affluents may be determined as follows: rp , D yp = x 31 + D, 7 (2.17) i I where D = the projected dose to the total body or organ r, for the next 31 9 days of liquid releases. the cumulative dose to the total body or organ r, for liquid D7e = releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration. t= the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration (even if the release continues into the next quarter). l l l D,= 7 the anticipated dose contribution to the total body or any organ r, due to any planned activities during the next 31-day period, if those activities will result in liquid releases that are in addition to routine liquid effluents. If only routine liquid effluents are anticipated, D , 7may be set to zero. 2.5.2 Dose Proiections for Specific Releases j Dose projections may be performed for a particular release by performing a pre- . release dose calculation assuming that the planned release will proceed as I anticipated. For individual dose projections due to liquid releases, follow the

methodology of Section 2.4, using sample analysis results for the source to be released, and parameter values expected to exist during the release period.

2-41 Rev. 8, 1/94

i I l 2.6 DEFINITIONS OF LIQUID EFFLUENT TERMS The following symbolic terms are used in the presentation of liquid effluent calculations in the sub-sections above. I Section of IRIm Definition Initial Use , 1 Ap = the adjustment factor used in calculating the l effluent monitor setpoint for liquid release pathway 1 p the ratio of the assured dilution to the required dilution [unitless). 2.3.2.2 ADF = the assured dilution factor for a planned release (unitiess). 2.3.2.2 AFp = the dilution allocation factor for liquid release pathway p (unitiess). 2.3.2.2 Aj7 = the site-related adult ingestion dose commitment p factor, for the total body or for any organ r, due to d identified radionuclide i ((mrem mL)/(h pCi)). The 2.4.1 values of Air are listed in Table 2-8. Bjy = the crop to soil concentration factor applicable to radionuclide 1, ((pci/kg garden vegetation)/(pci/kg soil)). 2.4.3 i l BFj = the bioaccumulation factor for radionuclide i for , freshwater fish ((pci/kg)/(pci/L)) . Values are listed in Table 2-6. 2.4.2 e= the setpoint of the radioactivity monitor measuring the concentration of radioactivity in the effluent line, prior to dilution and subsequent release (pci/mL). 2.3.2.1 ep = the calculated effluent radioactivity monitor setpoint for liquid release pathway p (pci/mL). 2.3.2.2 t C, = the gross concentration of alpha emitters in the I liquid waste as measured in the applicable composite l sample (pC1/mL). 2.3.2.2 2-42 Rev. 8, 1/94

( . , l l Match ODCM , Section of IgIgl Definition Initla1 Use the Ef fluent Concentration Limit stated in 10 CFR 20, , CECL = Appendix B, Table 2, Column 2 [yci/mL). 2.3.2.1 the concentration of Fe-55 in the liquid waste as Cr = composite sample I measured in the applicable [pci/mL). 2.3.2.2 , f I C the e n entration of gamma emitter g in the liquid E= waste as measured by gamma ray spectroscopy performed on the applicable pre-release waste sample [pci/mL). 2.3.2.2 ) C = the measured concentration of radionuclide i in a. sample of liquid effluent ( C1/mL). 2.3.2.2 Cd= the average concentration of radionuclide i in undiluted liquid effluent during time period 1 [ [pci/mL). 2.4.1 Cir = - the measured concentration of radionuclide i ' in release pathway r that is contributing to radio-activity in the dilution stream [pci/mL). 2.3.2.2 Cs = the concentration of strontium radioisotope s (Sr-89 or Sr-90) in the liquid waste as measured in the applicable composite sample [pci/mL) . 2.3.2.2 Ct= the concentration of H-3 in the liquid waste as measured in the applicable composite sample [pci/mL). 2.3.2.2 j CFjy = the concentration f a'stor for radionuclide i in irrigated garden vege tation ((pci/kg)/(pci/L)). 2.4.2 D, = the dilution factor from the near field of the l discharge structure to the potable water intake location (unitiess). 2.4.2 4 2-43 Rev. 8, 1/94 l _ -. _, ._. . -

Hatch ODCM Section of T.RIE Definition Initial Use D7 = the cumulative dose commitment to the total body or to any organ 7, due to radioactivity in liquid effluents released during a given time period (mrem). 2.4.1 D,= 7 the anticipated dose contribution to the total body or any organ 7, due to any planned activities during the next 31-day period (nxem) . 2.5.1 Dg = the cumulative dose to t!:a total body or organ r, for liquid releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration (mrem). 2.5.1 D rp = the projected dose to the total body or organ 7, for the next 31 days of liquid releases (mrom). 2.5.1 d DFir = the dose conversion factor for radionuclide i for adults, in organ T [mram/pci). Values are listed in Table 2-7. 2.4.2 ECL = the liquid Ef fluent Ccincentration Limit for radio-nuclide i from 10 CFR Part 20, Appendix B, Table 2, Column 2 (pci/mL). 2.3.2.2 f= the effluent flowrate at the location of the radio-activity monitor (gpm). 2.3.2.1 f,p = the anticipated actual discharge flowrate for a planned release from liquid release pathway p (gpm). 2.3.2.2 fg = the fraction of the year that garden vegetation is irrigated (unitiess). 2.4.3 f, = the maximum permissible effluent discharge flowrate for release pathway p [gpm). 2.3.2.2 2-44 Rev. 8, 1/94

1

Hatch ODCM Section of IRIE Definition Initial Use f r

          =     the effluent discharge flowrate of release pathway r (gpm).                                                                   2.3.2.2 fg=        the average undiluted liquid waste flowrate actually observed during the period of a liquid release (gpm).                                                                     2.4.1 F=        the dilution stream flowrate which can be assured prior to the release point to the UNRESTRICTED AREA

[gpm). 2.3.2.1 the entire assured dilution flowra*.e for the plant Fd= site during the release period (gpml. 2.3.2.2 F dp the dilution flowrate allocated to release pathway p

[gpm]. 2.3.2.2 Fg = the near-field average dilution factor in the receiving water of the UNRESTRICTED AREA (unitiess). 2.4.1 average dilution stream flowrate actually Ft= the observed during the period of a liquid release (gpm). 2.4.1 I= the average irrigation rate during the growing season (L/(m2 .h)). 2.4.3 Ly = the water content of leafy garden vegetation edible parts [L/kg). 2.4.3 M= the additional river dilution f actor f rom the near field of the discharge structure for the plant site to the point of irrigation water usage (unitiess). 2.4.3 P= the ef fective surf ace density of soil [kg/m 2 ). 2.4.3 O 2-45 Rev. 8, 1/94

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

J 2 Match ODCM Section of I~ If.DD Definition Initial Use r= the fraction of irrigation-deposited activity , retained on the edible portions of leafy garden vegetation. 2.4.3 RDF = the required dilution factors the minimum ratio by which liquid effluent must be diluted before reaching the UNRESTRICTED AREA, in order to ensure that the limits of Section 2.1.2 are not exceeded [unitiess). 2.3.2.2 RDF = the RDF for a liquid release due only to its concen-l 7 tration of gamma-emitting radionuclides [unitiess). 2.3.2.2 l RDF ny = the RDF for a liquid release due only to its concen-i tration of non-gamma-emitting radionuclides [unitiess). 2.3.2.2 i SF = the safety factor selected to compensate for statistical fluctuations and errors of measurement [unitiess). 2.3.2.2 t= the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration. 2.5.1 tb= the period of long-term buildup of activity in soil [h). 2.4.3 1 t, = the period of leafy garden vegetation exposure during the growing season [h). 2.4.3 tg = the transit time f rom release to receptor for fish consumption [h). 2.4.2 th= the time between harvest of garden vegetation and human consumption [h). 2.4.3 0' t, = the transit time from release to receptor for potable water consumption [h). 2.4.2 2-46 Rev. 8, 1/94

1

     -                                                                         Hatch ODCM
   \- /                                                                        Section of    l 112m                          Definition                         Initial Use       l TF =   the tolerance f actor selected to allow flexibility in the establishment of a practical monitor setpoint which    could    accommodate    effluent   releases  at j                  concentrations higher than the ECL values stated in                        j 10 CFR 20, Appendix B, Table 2, Column 2 [unitiess);                       l the tolerance factor must not exceed a value of 10.              3.3.2.2   !

i 1 Ug = the adult rate of fish consumption [kg/y). 2.4.2 ' I l Uy = the adult consumption rate for irrigated garden l l vegetation [kg/y). 2.4.2 U, = the adult drinking water consumption rate applicable to the plant site [L/y). 2.4.2 Yy = the areal density (agricultural productivity) of leafy garden vegetation [kg/m 2). 2.4.3 Z= the applicable dilution factor for the receiving water body, in the near field of the discharge structure, during'the period of radioactivity release [unitless). 2.4.1 1 l Atg = the length of time period 1, over which C g and Fg are l averaged for liquid releases [h). 2.4.1 AEi = the effective removal rate for activity deposited on f crop leaves [h-I) . 2.4.3 i 1 = the decay constant for radionuclide i [h-I). 2.4.2 1, = the rate constant for removal of activity from plant leaves by weathering [h-I) . 2.4.3 l L

l 2-47 Rev. 8, 1/94 l l

I Hatch ODCM

t CHAPTER 3 CASEOUS EFFLUENTS 3.1 LIMITS OF OPERATION The following Limits o ation implement requirements established by Technical specifications secti /,. 0. Terms printed in all capital letters are defined in Chapter 10. O 3.1.1 caseous Effluent Monitorine Instr 2-ent+clon control

k. S.$. 0.y In accordance with Technical specificati i. .;;1 L radioactive gaseous ef fluent monitoring instrumentation channels shown able 3-1 shall be OPERABLE

{ with their alarm / trip setpoints set to ensure that the limits of section 3.1.2.a are not exceeded. The alarm / trip setpoints of these channels shall be determined ; in accordance with Section 3.3. l 3.1.1.1 Applicability I ! These limits apply as shown in Table 3-1. l 3.1.1.2 Actions ; l i l With a radioactive gaseous of fluent monitoring instrumentation channel alarm / trip setpoint less conservative than requ ir ed by the above control, immediately- ; suspend the release of radioactive gaseous ef fluents monitored by the affected channel, declare the channel inoperable, or restore the setpoint to a value that l l will ensure that the limits of section 3.1.2.a are met. l l With less than the minimum number of radioactive gaseous ef fluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3-1. l One instrument channel may be inoperable for up to 6 hours to perform required l surveillances prior to entering other applicable ACTIONS. l When the ACTION statement or other requiremente of this control cannot be met, eteps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, ! the requirements of the ACTION statement are satisfied. .v 1 3-1 Rev. 9, 2/94 j l

L Hatch ODCM 1 3.1.1.3 Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3-2. 3.1.1.4 Basis The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 3.3 to ensure that the alarm / trip will occur prior to exceeding the limits of Section 3.1.2.a. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. l l O l I l l l i L lO 3-2 Rev. 9, 2/94

Hatch ODCM Table 3-1. Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Channels Applica-Instrument OPERABLE bility ACTION

1. Reactor Building Vent Stack Monitoring System (Each Unit)

a. Noble Gas Activity Monitor C 1 (a) 105

b. Iodine Sampler Cartridge 1 (a) 107

c. Particulate Sampler Filter 1 (a) 107

d. Effluent System Flowrate Measurement Device 1 (a) 104

e. Sampler Flowrate Measurement Device 1 (a) 104

2. Recombiner Building Ventilation Monitoring System

a. Noble Gas Activity Monitor c 1 (a) 105

b. Iodine Sampler Cartridge 1 (a) 107

c. Particulate Sampler Filter 1 (a) 107 s

d. Sampler Fl'owrate Monitor 1 (a) 104

3. Main Stack Monitoring System

a. Noble Gas Activity Monitor C 1 (a) 105

b. Iodine Sampler Cartridge 1 (a) 107

c. Particulate Sampler Filter 1 (a) 107

d. Effluent System Flowrate Measurement Device 1 (a) 104

e. Sampler Flowrate Measurement Device 1 (a) 104

4. Condenser Offgas Pretreatment Monitor (Each Unit) l

a. Noble Gas Activity Monitor 1 (b) 108 l i

{ (c, r \~ ) ! l 3-3 Rev. 8, 1/94

                                                                                      * ,          :~
                                                                               .s,       u.               .i u.

I Hatch ODCM (' Table 3-1 (contd). Notation for Table 3-1

a. During radicactive releases via this pathway.

b. During operation of the main condenser air ejector.

responding to a MINIMUM DETECTABLE

c. Monitor must be capajle of pCL/mL.

CONCENTRATION of 1 x 10 ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway least once per 4 hours. l may continue provided the flowrate is estimated at If the number of channels OPERABLE remains less than nrequired by the lanation of minimum channels OPERABLE requirement for over 30 day ,' .m.' adioactive the circumstances shall be included in the ne Effluent Release Report. ACTION 105 - With the number of channels OPERABLE less than required by the l Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken daily andthe With these samples number are of main analyzed for gross activity within 24 hours. stack monitoring system channels OPERABLE less than required by the minimum channels OPERABLE requirement, immediately suspend drywell by equired purge. the If the number of channels OPERABLE remains less tha,a lanation of minimum channels OPERABLE requirement for over 30 da '-- ' adioactive f the circumstances shall be included in the nex* (( Effluent Release Report. i i l ACTION 107 - With the nu:rter of channels OPERABLE less than effluent releases viarequired by the this pathway Minimum Channels OPERABLE requirement, may continue, provided samples are continuously collected with auxiliary i l equipeent for periods on the Order of 7 days and analyzed within 48 hours f l af ter the end of the sampling period. If the number of channels OPERABLE j remains less than required by the minimum channels OPERABLE requirement for ove y an explanation of the circumstances shall be included in , the ne *c....'. .adioactive Effluent Release Report. less than required by the ACTION 108 - With the number of channels OPERABLE i Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 72 hours, provided:

a. The offgas treatment system is not bypassed; and

b. The of fgas post-treatment monitor (Dll-K615) or the main stack monitor (Dil-K600) is OPERABLE.

Otherwise, be in at least HOT STAND 5Y within 12 hours. If the number of l channels OPERABLE remains less than required by the minimum channels l OPERABLE requirement for ove 0 a an explanation of the circumstances

                                                     ". c. d adioactive Ef fluent Release Report.

l shall be included in the ne t O Rev. 8, 1/94 3-4

i Hatch ODCM i

a Table 3-2. Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements

',)

( $ ( ;

                                                                      'e       CHANNEL            CHANNEL CHANNEL                    -s           CALIBRA-         FUNCTIONAL      l Instrument             CHECK           SOURCE CHECK             TION              TEST
                                                                                                                )

1. Reactor Building Vent Stack Monitoring System (Each Unit)

a. Noble Gas Activity 3 - .

Monitor D" '* M R Q"

b. Iodine Sampler Cartridge W"' NA NA NA

c. Particulate Sampler Filter W"'d NA NA NA

d. Effluent System \

Flowrate Measuring Device D" NA R Q

e. Sampler Flowrate Measuring Device D* NA R Q

2. Recombiner Building. Ventilation Monitoring System

a. Noble Gas Activity #

Monitor D" _ M R Q

b. Iodine Sampler Cartridge W"'d NA NA NA E c. Particulate Sampler Filter W"' NA NA NA

d. Sampler Flowrate :-

Measuring Device Da NA R Q

3. Main Stack Monitoring System

a. Noble Gas Activity ->

Monitor Da N M R Q" ,

b. Iodine Sampler Wa,d NA Cartridge NA NA

c. Particulate Sampler Filter W"'d NA NA NA

d. Effluent Flowrate '

Monitor Da G- NA R Q

e. Sampler Flowrate 5 Monitor D, _T NA R Q

4. Condenser Offgas Pretreatment Monitor (Each Unit)

a. Noble Gas Activity Monitor Db M R Qc nv 3-5 Rev. 8, 1/94

I l

  /"'                                                                                                        Hatch ODCM i

Table 3-2 (contd). Notation for Table 3-2 l

a. Requirement applies during releases via this pathway. !

b. Requirement applies during operation of the main condenser air ejector,

c. In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that control

, room alarm annunciation occurs if any of the following conditions exists: I (1) Instrument indicates measured levels above the alarm / trip setpoint. (2) Circuit failure occurs. (3) Instrument indicates a downscale failure. i l l d. The CHANNEL CHECK shall consist of verifying sampler flow and the presence of the collection device (i.e. , particulate filter or charcoal cartridge, etc.) at the weekly changeout. 1 l l

i I l l : l l } 4 4 I 3-6 Rev. 8, 1/94

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

1 . -. Hatch ODCM Caseous Effluent Dose Pate Control O 3.1.2

                                                                           . C.

In accordance with Technical Specificati ns 5.1 * ' 3' and 0.10 ; 7 ; , he licensee shall conduct operations so that the dos at due to radioactive materials } released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see rigure 10-1) are limited as follows:

a. For noble gases: Less than or equal to a dose rate of 500 mrem /y to the total body and less than or equal to a dose rate of 3000 mrem /y to the skin, and

b. For Iodine-131, Iodine-133, tritium, and for all radionuclides in Less than or equal particulate f orm with half-lives greater than 8 days:

l to a dose rate of 1500 mrem /y to any organ. 3.1.2.1 Applicability l I This limit applies at all times. 3.1.2.2 Actions b with a dose rate due to radioactive material released in gaseous effluents exceeding the limit stated in Section 3.1.2, immediately decrease the release rate to within the stated limit. be met, When the ACTION statement or other requirements of this control cannot Entry into steps need not be taken to change the operational Mode of the unit. an operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. I 3.1.2.3 Surveillance Requirements The dose rates due to radioactive materials in areas at or beyond the SITE BOUNDARY due to releases of gaseous ef fluents shall be determined to be within the above limits, in accordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-3. 3.1.2.4 Basis This control is provided to ensure that gaseous effluent dose rates will be 4 maintained within the limits that historically have provided reasonable assurance

O that radioactive material discharged in gaseous ef fluents will not result in a 3-7 Rev. 8, 1/94 l

. _ . . _ . . - _ _ _ _ . .       . _ . . _ ._ .. m. m . . _ , _ . _ _ - . . . . _ . . ~ . .       . . . . . . . . . - . . . . _ . . . .
          ~                                                                                    .

1 I Hatch ODCM s O l dose to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside i the SITE BOUNDARY, exceeding the limits specified in Appendix I of 10 CFR Part' 50, while allowing operational flexibility for effluent releases. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The dose rate lLait for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days specifically applies to dose rates to a child via the inhalation pathway. This control applies to the release of gaseous effluents from all reactors at the I site. l J l O i l l 1 .O 3-8 Rev. 8, 1/94

l ! Hatch ODCM

lf-~

Table 3-3. Radioactive Gaseous Waste Sampling and Analysis Program l Sampling and Analysis Requirements a MINIMUM DETECTABLE Minimum Type of CONCENTRA-l Gaseous Release Sampling Analysis Activity TION (MDC) Type FREQUENCY FREQUENCY Analysis (uCi/mL) PRINCIPAL GAMMA 1 E-4 l M" gc EMITTERS

Grab Sample l

H-3 1 E-6 Wd I-131 1 E-12 Environmental Charcoal or Release Points CONTINUOUS

Silver I-133 1 E-10 Zeolite

1. Main Stack Sample

2. Reactor Wd CONTINUOUSe PRINCIPAL GAMMA E-11 Building Vent Particulate EMITTERS (Each Unit) Sample

3. Recombine M CO OSI E

( Building Vent CONTINUOUSe p Sample e Gross Alpha 1 E-11 l Q CONTINUOUSc COMPOSI E Sr-89, Sr-90 1 E-11 p Sample l I I l t t i l (~')\ s_- i 3-9 Rev. 8, 1/94 l

Hatch OOCM /~'% U Table 3-3 (contd). Notation for Tabt. ?-3 7 1 l 1

a. Terms printed in all capital letters are defined in Chapter 10. tWhen he l

l unusual circumstances result in a MINIMUM DETECTABLE CONCENTRATION than requited, the reasons shall be documented in the next enneed Radioactive Effluent Release Report,

b. The Recombiner Building Vent serves Unit 1. Sample analysis results and associated source terms must be assigned to Unit 1 for the purpose of release accountability and dose calculations. l I

c. Sampling and analyses f or PRINCIPAL GAMMA EMITTERS shall also be performed following shutdown, st a rtup, or a THERMAL POWER change exceeding 15% of The more frequent the RATED THERMAL Poh*ER within a one-hour period.

sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have both increased by a factor of 3.

d. Sampling shall be performed weekly, and analyses completed Samplingwithin shall also48 hours be of changing (or after removal from sampler).

performed once per 24 hours for 7 days following each shutdown, startup, ' or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one-hour period, with analyses completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding [} r MINIMUM DETECTABLE CONCENTRATIONS may be increased by a f actor of 10. The more f requent sampling and analysis requirement applies only if analysis (,,j shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have both increased l by a factor of 3.

e. The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation j made in accordance with controls specified in Sections 3.1.2, 3.1.3, and 3.1.4.

l O Rev. 8, 1/94 3-10

                                                                               .,..s     .      .                   .         ..

Hatch ODCM 3.1.3 Caseous Effluent Air Dose Cent

                                                                $'.$. 4.gl
                                                                                        =

In accordance with Technical Specificati s +. ;; 'd and ' 1" : " L t he a tr d se due to noble gases released in gaseous effluent , e a un t, to areas at and beyond the SITE BOUNDARY (see Figure 10-1) shall be limited to the followings

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

b. During any calendar years Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

3.1.3.1 Applicability This limit applies at all times. 3.1.3.2 Actions With the calculated air dose from radioactive noble gases in gaseous ef fluents O exceeding any of the above , re and t to hw i. - Regulatory Commission within 30 days p:: _ _.. w W Jm n.1 W .fic :i.. C.^L - Special Re port which identifies t s or ee , ines the corrective actions trat have been taken to reduce the releases; and defines the proposed corrective actions to be taken to assure that subsequent releases of radioactive noble gases in gaseous effluents will be in compliance with the limits of Section 3.1.3. When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. 3.1.3.3 Surveillance Requirements Cumulative air dc.s e contributions from noble gas radionuclides released in gaseous effluents from each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be determined in accordance with Section 3.4.2 at least once per 31 days. v 3-11 Rev. 8, 1/94

3.1.3.4 Basis l l l This control is provided to implement the requirements of Sections II.8, III.A and IV. A of Appendix I, 10 CFR Part 50. Section 3.1.3 implements the guides set forth in Section II.B of Appendix I. The ACTION statements in Section 3.1.3.2 provide the required operating flexibility and at the same time implement the-guides set forth in Section IV.A of Appendix I, assuring that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as j low as is reasonably achievable." The Surveillance requirements in Section 3.1.3.3 implement the requirements in Section III. A of Appendix I, which require that conformance with the guides of Appendix I be shown by calculational procedures based 'o n models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in Section 3.4.2 for calculating the doses due to the actual releases of noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109 l- (Reference 3), and Regulatory Guide 1.111 (Reference 5). The equations in ! Section 3.4.2 provided for determining the air doses at the SITE BOUNDARY are based upon the historical annual average atmospheric conditions. l I i l l i O ! l 3-12 Rev. 8, 1/94

p

                                                                                             - - . e .. s .

Hatch ODCM

lic

 \             3.1.4  Control on Caseous Ef fluent

s. s.+...y 7s.s.+ i ., .

In accordance with Technical Specificati ns v. 6sLr and '.10;t1, the ese to a KEMBER OF THE PUBLIC from I-131, I-133, t ..tum, and .'radtonue1Ldes in particulate form with half-lives greater than 8 days in gaseous effluer.ts released, f rom each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figv m 10'1) shall be limited to the f ollowing:

a. During any calendar quarter: Less than or equal to 1.5 mrem to any organ, and

b. During any calendar years Less than or equal to 15 mrem to any organ.

3.1.4.1 Applicability This limit applies at all times. 3.1.4.2 Actions With the calculated dose from the release of I-131, I-133, tritium, or rt.dio- ; nuclides in particulate form with half-lives greater than 8 days, in gaseous ef fluents exceeding any of the abov , repa n -... a t ^ l n e .~ h . - . ; .- f " E Regulatory Commission within 30 da w . . .w. w tecnnicaA ar a Special Report which tdentifies e sets) for exc '.ng . mt the corrective actions that have been taken to reduce the releases of radiotodines and radtenuclides in particulate f erm with half-lives greater than 8 days in gaseous ef fluents; and defines proposed corrective actions to assure that subsequent releases will be in compliance with the limits stated in Section 3.1.4. When the ACTIC I statement or other requirements of this control cannot be met, Entry into steps nesd not be takea to change the Operational Mode of the unit. an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satasfied. 3.1.4.3 Surveillance Requirements Cumulative organ dose contributions to a MEMBER OF THE PUBLIC f rom I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days released in gaseous ef fluents f rom each unit to areas at and beyond the SITE BOUNDARY, for the current calendar quarter and current calendar year, shall be b determined in accordance with Section 3.4.3 at least once per 31 days. l 3-13 Rev. 8, 1/94

                                      . . _ _ _ _ . . _ _ _                   . . _       m _ . . - , _ . __    ~ . _ - _ _ _ . _ _ _ _.

l . .. ( l Hatch ODCM 3.1.4.4 Basis I r This control is provided to implement the requirements of Section II.C, III. A and i IV.A of Appendix I, 10 CFR Part 50. The limits stated in Section 3.1.4 are the guides set forth in Section II.C of Appendix I. The ACTION statements in Section f ~! , 3.1.4.2 provide the required operating flexibility and at tre same time implement l the guides set forth in Section IV.A of Appendix I to assure that tha releases j of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The calculational methods specified in the Surveillance Requirements of Section J.4.4.3 implement the requirements in f- ' Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE pub!.IC through appropriate pathways is unlikely to be substantially underestimated. The ca;.culational methods in Section 3.4.3 for ; calculating the doses due to the actual releases of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109 (Reference 3), and Regulatory Guide 1.111 (Reference 5). These equations provide for j determining the actual doses based upon the historical annual average atmospheric j conditions. The release specifications for radir. 'oc'.ines, radioactive materials in particulate form and radionuclides other thats noble gases are dependent on the existing radionuclide pathways to man, in the areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy garden vegetation with subsequent I consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. b i 1 eO 3-14 Rev. 8, 1/94

I Hatch ODCM f 1

I'i 3.1.5 Caseous Padweste Treatrent System ... i l s.s.+.Eph 4.;"f'!_ t CASEOUS PADWASTE In accordance with Technical Specificatic e in operation. l TRIATMENT SYSTEM as described in Section 3.2 snal ) 1 3.1.5.1 Applicability l i l Whenever the main condenser air ejector is in operation. 3.1.5.2 Actions i With gaseous radwaste f rom the main condenser air ejector system being discharged

                                                             -                        s u bu. i'              Nu    at without treatment for more than 7                         ,

w. i..il:.- 5.a 2,

                                                      ,_..m.s      .s   4wwonic.4 ay Regulatory Commission within 30 da        m a Special Report which includes the el                .g i... . . ...a t i on s

a. Identification of the inoperable equipmer.t or subsystem and the reason for l

i inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, p..s and

c. Summary description of action (s) taken to prevent a recurrence. 1 When the ACTION statement or other requirements of this control cannot be met, Entry into steps need not be taken to change the Operatitr.al M:de of the unit.

an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satisfied. l 3.1.5.3 Surveillance Requiremtents l I The GASEOUS RADWASTE TREATMENT SYSTEM shall be demonstrated to be OPERABLE by administrative controls which ensure that the offgas treatment system is not bypassed. 3.1.5.4 Pasis I l l The OPERABILITY of t he GASEOUS RADWASTE TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous ef fluents require treatment prior to release to the environment. The requirement that the t.ppropriate portions of this system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents vill be kept "as low as is reasonably achievable. " This control implements the requirements of 10 CrK Rev. 8, 1/94 3-15 I ( l

i Hatch ODCM l O 3.2 GASEOUS RADWASTE TREATMENT SYSTEM At Plant Hatch, there are four points where radioactivity normally is released to the atmosphere in gaseous discharges. These four release pathways are the Unit 1 and Unit 2 reactor building vent stacks; the Unit 1 recombiner building vent; and the main stack, which serves both units. In addition, releases r.ay be made from any of the build'.nq exhaust augmented ventilation systems that have been included in Table 3-1, Table 3-2, and Table 3-3. The main stack serves as the discharge point from the following release sources I from each unit: I e Mechanical vacuum pumps; e offgas treatment system (see Figure 3-1); e Gland seal exhaust; and ! e Standby gas treatment system (through which drywell purges are l I l discharged). In addition, the waste gas trcatment building ventilation also discharges through ; the main stack. f l ' I Each reactor building vent stack serves as the discharge point for the following l release sources of its respective unit:

Reactor building; e Refueling floor ventilation;
Turbine building; and e Radwaste building. l The Unit 1 recombiner building vent discharges directly to the atmosphere.

1 l Releases from all of the above discharge points except the main stack are l considered to be ground-level releases; releases from the main stack are considered to be elevated releases. Chapter 8 discusses the calculation of l atmospheric dispersion parameters using the ground-levol and elevated models. All release pathways are considered to be CONTINUOUS (as opposed to BATCH) in ! nature. iG O 1 3-17 Rev. 8, 1/94

l

                                                                       -         . . . .             .. z.

l i Hatch ODCM

m _

l Part 50.36a, General Design Criterion 60 of Appendix A to 10 CTR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CTR Part 50. The the system were specLfied limits governing the use of appropriate portions of s peci f ied as a suitable f raction of the dose design objectives set forth an Section II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. l l This control applies to the release of radioactive materials in gaseous ef fluents f rom each unit at the site. For units with shared radwaste systems, the gaseous ef fluents f rom the shared system are proportioned among the units sharing than system. l 3.1.6 Maior Chances to Caseous Padioactive Waste Treatment Systems l l I Licensee initiated MAJOR CHANGES TO CASEOUS PADICACT!*.'E WASTE TREATMENT S

                                                                                                    "-._1 i

l a. Shall be reported to the Nuclear Regulatory Commission in th Radioactive Effluents Release Report for the period in which the change was implemented, in accordance with section 7.2.2.7. O a* eview Bo dg

b. c revte e-4 Q r : ,

deJ a rev. l by A Nucb B4"$' **7'*- A l l t 1 b Rev. 8, 1/94 3-16

l Hatch ODCM r% U ' l PROM CONDENt2R V

                                                          ,               7 ~!

1ST STAGE EJECTOR 1ST STAGE INTERCONOENSER C t 2ND STAGE ELECTOR 2ND STAGE INTE RCONDENSER .

,J

7) -

3RO STAGE EJECTOR i r OFFGASREMEATER V CATALYTIC RECOMSINE R

                                                                    !!              }        OFF GAS CONDENSER RADIATION MONITOR             h                                WATER SEFAR ATOR a                                                                                     ,

M NOLOUP LINE O COOLER CONOENSER I V

I y i < mumumanse MOISTURE STRIP SEFARATOR MEATER Y CHARCOAL CHARCOAL FILTERS FILTERS (SPLACES) toFLACESI , , , , maggargow

                                                                ',                                                  MONITOR

' V FROM

TANOsv GAS AFTER RAOSATION TREATMENT FILTER MONITOR d SYSTEM l

s STACK H FROM i OLamo s SEAL SYSTEM O l Figure 3-1. Schematic Diagram of the condenser Offgas Treatment System , 3-18 Rev. 8, 1/94 i

l l Hatch ODCE h D 3.3 GASEOUS EFFLUENT MONITOR SETPOINTS 3.3.1 General Provisions Recardinc Noble Gas Monitor Setooints 1 Noble gas radioactivity monitor setpoints calculated in accordance with the methodology presented in this section are intended to ensure that the limits of i Section 3.1.2.a are not exceeded. They will be regarded as upper bounds for the actual high alarm setpoints. That is, a lower high alarm setpoint may be established or retained on the monitor, i* desired. Intermediate level setpoints should be established at an appropriato level to give sufficient warning prior to reaching the high alarm setpoint. l If no release is planned for a given pathway, or if there is no detectable activity '.n the gaseous stream being evaluated for release, the setpoint should be established as close to background as practical to prevent spurious alarms, and yet alarm should a significant inadvertent release occur. As established in Section 3.1.1, gaseous ef fluent monitor setpoints are required only for the noble gas monitors on the release streams listed above. However, Section . 3.3.6 discusses setpoint methodologies for particulate and iodine monitors on an information-only basis. Note Section 3.3.3 is included for section numbering compatibility with the ODCMs of the other Southern Company nuclear power plants. This section is not required by the existing release source and discharge point configuration of Plant Hatch. l l l \ 1D l G 3-19 Rev. 8, 1/94

     .                                                                           Hatch ODCM Table 3-4. Applicability of Gaseous Monitor Setpoint Methodologies i

l Final Release Pathways with no Monitored Source Streams l Setpoint Method Section 3.3.2 Release Type: CONTINUOUS Main Stack Release Elevation: Elevated I Monitor: D11-K600 A and B Maximum Flowrate: 20,000 cfm (9.44 E+06 mL/s) l Unit 1 or Unit 2 Reactor Buildino Vent i Release Elevation: Ground-level Monitor: D11-K619 A and B / 2D11-K636 A and B Maximum Flowrate 300,000 cfm (1.42 E+08 mL/s) Unit 1 Recombiner Buildino Vent Release Elevation Ground-level i Monitor: D11-P003 A and B Maximum Flowrate: 500 cfm (2.36 E+05 mL/s) I Buildino Exhaust Auomented Ventilation The systems in this category are not currently vented to the atmosphere. i 1 l Final Release Pathways with One or More Monitored Source Streams Plant Hatch currently has no release pathways in this category. l (i]D)tb Values for Use in Setpoint Calculations Ground-Level' Releases: 8.37 x 10 4 s/m 3 (ENE Sector) Elevated Releases: 4.10 x 10*8 s/m 3 [ENE Sector) l . ts 3-20 Rev. 8, 1/94

Hatch ODCM p 3.3.2 Setooint for the Final Noble Gas Monitor on Each Release Pathway 3.3.2.1 overview of Method Gaseous ef fluent radioactivity monitors are intended to alarm prior to exceeding the limits of Section 3.1.2.a. Therefore, their alarm setpoints are established to ensure compliance with the following equations c = the lesser of (3*1) AG

SF
X Rg where c= the setpoint, in pCi/mL, of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to release. The setpoint represents a concentration which, if exceeded, could result in dose rates exceeding the limits of Section 3.1.2.a at or beyond the SITE BOUNDARY.

AG = an administrative allocation factor applied to divide the release

 \                   limit among all the gaseous release pathways at the site.

SF = the safety factor selected te compensate for statistical tluctuations and errors of measuremen3. X= the noble gas concentration for the release undar consideration. l the ratio of the dose rate limit for the total body, 500 mrem /y, Rt= to the dose rate to the total body for the conditions of the release under consideration. the ratio of tne dose rate limit for the skin, 3000 mrem /y, to the Rk= dose rate to the skin for the conditions of the release under consideration. Equation (3.1) shows the relationships of the critical parameters that determine the setpoint. However, in order to apply the methodology presented in the equation to a mixture of noble gas radionuclides, radionuclide-specific concentrations and dose factors must be taken into account under conditions of maximum flowrate for the release point and annual average meteorology. L/ 3-21 Rev. 8, 1/94 l I

. _ _ . __.. _ _ .. . _ _ _ _ _ . . _ ._.m _ - _ . _ _ _ . - - . . . . _ - _ ~. __..-_ ______. . l Hatch ODCM . O t The basic setpoint method presented below is applicable to the radioactivity monitor nearest the point of release for tt.e release pathway. For monitors f measuring the radioactivity in source streams that merge with other streams prior - , to subsequent monitoring and release, the modifications presented in Section I 3.3.3 must be applied. 3.3.2.2 Setpoint calculation Steps Sten 1: Determine the concentration, Xjy, of eacn 1,0ble gas radionuclide i in the gaseous stream v being considered for release, in accordance with the sampling and analysis requirements of Section 3.1.2. Then sum these concentrations to determine the total noble gas concentration, I Xiy . l . i Stoo 2: Determine R t , the ratio of the dose rate limit for the total body, 500 mrom/y, to the total body dose rate due to noble gases detected in the release under consideration, as follows, A a. for release pathways for which the release elevation is j ground-level l 500 a, . (X75)vb [ (Ki

O ivj (3.2) i

b. for release pathways for which the release elevation is elevated:

0 Rg [ [Vf

O y) l (3*3)

I where: 500 = the dose rate limit for the total body, 500 mrem /y. I (I76)vb = the highest annual average relative concentration at the SITE BOUNDARY for the discharge point of release pathway v. Table 3-4 includes an indication of what release elevation is applicable to ! each release pathway; release elevation determines the appropriate value of (i]6)vb' 3-22 Rev. 8, 1/94

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

Hatch ODCM lO- Kj = the total-body dose factor due to gamma emissions from noble gas radionuclide i, in (mrem /y)/(yci/m 3), from Tabla 3-5. l

             -Qy i
                   = the release rate of noble gas radionuclide i from the release pathway under consideration, in yCi/s, calculated as the product                                     j of X;y and f,y,     where:                                                                            j X;y  =      the concentration of noble gas radionuclide i for the

( particular release, in yCi/mL. i ; f,y = the maximum anticipated flowrate for release pathway v 3 during the period of the release under consideration, in l l mL/s. [ t 1 Vj = the elevated finite-plume total body dose factor due to gamma ; emissions from noble gas radionuclide i in effluents released from the main stack,_in (mrom/y)/(yci/s), from Table 3-6. I l Stoo 3: Determine R k, the ratio of the dose rate limit. for the skin, 3000 mrom/y, to the skin dose rate due to noble gases detected in the release under consideration, as follows, l' l a. for release pathways for which the release elevation is l ground-level

Rk i (3*0) (T/D)4 [ l ((Li + 1 lN )f

Q v) l t

b. for release pathways for which the release elevation is elevated:

                                 ,     ,                 3000 (3.5)

[, t,Lg (YTC)4 + 1.13f *Qy i wheres

p 8

3000 = the dose rate limit for.the skin, 3000 mrom/y. i 3-23 Rev. 8, 1/94 l -

- . _ . . _ . = - Hatch ODCM Li= the skin dose factor due to betc emissions from noble gas radio-nuclide i, in (mrem /y)/(yci/m 3), from Table 3-5. M; = the air dose factor due to gamma emissions from noble oss radio-nuclide i, in (mrad /y)/(yci/m 3), from Table 3-5. 1.1 = the factor to convert air dose in mrad to skin dose in mrom. Bj = the elevated finite-plume air dose factor due to gamma emissions from noble gas radionuclide i in affluents released from the main stack, in (mrad /y)/(yci/s), from Table 3-6. All other terms were defined previously. l Steo 4: Determine the maximum noble gas radioactivity monitor setpoint con-centration. l Based on the values determined in previous steps, the radioactivity monitor setpoint for the planned release is calculated to ensure that the limits of Section 3.1.2.a will not be exceeded. Because the radioactivity monitor responds primarily to radiation from noble gas radionuclides, the monitor setpoint env I i" pCi/mL) is based on the concentration of all noble gases in the waste stream, as follows: AGy

SF = [ Xgy Rg c nv " the lesser of <

                                                                                          $*E AG y

SF * [ X;y
Rg i

where: c ay = the calculated setpoint, in yci/mL, for the noble gas monitor serving gaseous release pathway v. AG y = the administrative allocation fractor for gaseous release pathway v, applied to divide the release limit among all the gaseous release pathways at the site. The allocation factor may be N assigned any value between 0 and 1, under the condition that the v sum of the allocation factors for all simultaneously-active final release pathways at the entire plant site does not exceed 1. 3-24 Rev. 8, 1/94

Hatch ODCM IO l# i-Alternative methodra - f or determination of AG y are presented in Section 3.3.4. SF = the safety facto selected ~ to compensate for statistical fluctuations and errors of measurement. .The value for the safety factor must be between 0 and 1. A value of 0.5 is reasonable for gaseous releases; a more precise value may be developed if desired. X;y = the measured concentration of noble gas radionuclide i in gaseous ! stream v, as defined in Step 1, in pCi/mL. l The values..of R t and Rk to be used in the calculation are those which were determined in Steps 2 and 3 above. - I ! St.no 5: Determine whether the release is permissible, as follows: l If e nv 2: pXjy, the release is permissible. However, if e nv is within about i 10 percent of p Xiv, it may be impractical to use this value of c,y. 1 This situation indicates that measured concentrations are approaching values which would cause the limits of Section 3.1.2.a-to be exceeded. Therefore, steps should be taken to reduce contributing source terms of gaseous radioactive material, or to adjust the allocation of the limits among the active release points. The setpoint calculations (steps 1-4) must then be repeated with parameters that reflect the modified conditions. i ( If c ny < p X;y, the release may not be made as planned. Consider the 8 l l alternatives discussed in the paragraph above, and calculate a new ( t setpoint based on the results of the actions taken. i 3.3.2.3 Use of the calculated Satpoint 1 The setpoint calculated above is in the units pci/mL. The monitor actually measures a count rate that includes background, so that the calculated setpoint must be converted accordingly: c;, = (cnv ' Ev)

B v ( *U lO whace-3-25 Rev. 8, 1/94

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

f< Hatch ODCM c ny = the monitor setpoint as a count rate. Ey = the monitor calibration factor, in count rate /(pci/mL). Monitor i calibration data for conversion between count rate and concentration may include operational data obtained from I determining the monitor response to ef fluent stream concentrations r l measured by sample analysis. By = the monitor background count rate. In all cases, monitor background must be controlled so that the monitor is capable of ! ! responding to concentrations in the range of the setpoint value. ] Contributions to the monitor background may include any or all of l l . the following f actors: ambient background radiation, plant-related radiation levels at the monitor location (which may change between shutdown and power conditions), .and internal background due to i contamination of the monitor's sar.51e chamber. I j The count rate units for e, , E ,yand B in y equation (3.7) must be the same, cpm j l or cps. 3.3.3 Satooints for Noble Gas Monitors on Effluent Source Streams l l The listing in Table 3-4 shows that Plant Hatch currently has no gaseous release l pathways that meet the following criterlat a setpoint is required for them under the offluent controls of this ODCM; and they are monitored prior to merging with other streams, and passing a final radioactivity monitor. This section, which presents a setpoint methodology for such monitors, is included in the Plant Hatch ODCM for compatibility with the ODCMs of the other Southern Company nuclear power plants. 3.3.3.1 setpoint of the Monitor on the Source Stream sten 1: Determine the concentration X;, of each noble gas radionuclide i in source stream s (in pci/mL) according to the results of its required sample analyses (see section 3.1.2). i Sten 2: Determine r t , the ratio of the dose rate limit for the total body,

500 mram/y, to the total body dose rate due to noble gases detected

;                                             in the source stream under consideration. Use the X;, values and the maximum anticipated source stream flow rate f, in equation 4

3-26 Rev. 8, 1/94 ;

Hatch ODCM r \ (3.2) (or in equation (3.3) if the release is elevated) to determine the total body dose rate for the source stream, substituting r t for R t* The SITE BOUNDARY relative dispersion value used in Steps 2 and 3 for the source stream is the same as the (176)vb that applies to the respective merged stream. This is because the (i/D) value is determined by the meteorology of the plant site and the physical attributes of the release point, and is unaffected by whether or not a given source stream is operating, l i l steo 3: Determine rk, the ratio of the dose rate limit for the skin, 3000 mrem /y, to the skin dose rate due to noble gases detected in the source stream under consideration. Use the X;, values and the maximum anticipated source stream flow rate f as in equation (3.4) (or in equation (3.5) if the release is elevated) to determine the skin dose rate for the source stream, substituting rk f C# E k' I a steo 4: Determine the maximum noble gas radioactivity monitor setpoint con-centration, as follows: AG, ST* [ Xg,*rg c ns

the lesser of

                                                                                    $#**5 AG, = SF * [ X;,

rg j i j where:

c as = the calculated setpoint (in pci/mL) for the noble gas monitor serving gaseous source stream s. AGs = the administrative allocation factor applied to gaseous source stream s. For a given final release point v, the sum of all the AGs values for source streams contributing to the final release point must not exceed the release point's allocation factor AG y. Kj, = the measured concentration of noble gas radionuclide i in gaseous source stream s, as defined in Step 1, in pCi/mL. 3-27 Rev. 8, 1/94

Hatch ODCM l b l V The values of rg and rk to be used in the calculation are those which were determined in Steps 2 and 3 above. The safety factor, SF, was defined previously. 1 l l l Stoo 5: Determine whether the release is permissible, as follows: If e ns at pX;s, the release is permissible. However, if c m is within about I 10 percent of p Xis, it may be impractical to use this value of ens' This situation indicates that measured concentrations are approaching values which would causs the limits of Section 3.1.2.a ! l to be exceeded. Therefore, steps should be taken to reduce j l contributing source terms of gaseous radioactive material, or to j adjust the allocation of the limits among the active release l l l points. The setpoint calculations (steps 1-4) must then be j repeated with parameters that reflect the modified conditions. If ens < pXis, the release may not be made as planned. Consider the a ! alternatives discussed in the paragraph above, and calculate a new ( setpoint based on the results of the actions taken. i 3.3.3.2 Effect on the Setpoint of the Monitor on the Merged ; Stream l Before beginning a release from a monitored source stream, a setpoint must be i I l determined for the source stream monitor as presented in Section 3.3.3.1. In j addition, whether or not the source stream has its own effluent monitor, the l previously-determined maximum allowable setpoint for the downstream final monitor on the merged stream must be redetermined. This is accomplished by repeating the steps of Section 3.3.2, with the following modifications. j Modification 1: The new maximum anticipated flowrate of the merged stream is the sum of the old merged stream maximum flowrate, and the maximum flowrate of the source stream being considered for release. l l (fay),,, = (fay)old + fas (3*') l 1 i Modification 2: The new concentration of noble gas radionuclide i in the merged stream includes both the contribution of the 3-28 Rev. 8, 1/94 ) i c

I l 4 1 l 1 Hatch ODCM i O merged stream without the source stream, and the source stream being considered for release. (fav)old ' (Xiv)old

f as *Xis ,

(Xgy)nsw = (3.10) ) , (fav)new I 4 l 3.3.4 Determination of Allocation Factors, AG 4 When nimultaneous gaseous releases are conducted, an administrative allocation j factor must be applied to divide the release limit among the active gasaous

       .visase pathways. This is to assure that the dose rate limit for areas at and beyond the SITE BOUNDARY (see Section 3.1.2) will not be exceeded by simultaneous releitses. The allocation factor for any pathway may be assigned any value

! between 0 and 1, under the following two conditions:

l. The sum of the allocation factors for all simultaneously-active final 4 release paths at the plant site may not exceed 1.

1 1 2. The sum of the allocation f actors for all simultaneously-active source ! streams merging into a given final release pathway may not exceed the allocation factor of that final release pathway. l 1 Any of the following three methods may be used to assign the allocation f actors to the active gaseous release pathways: ! d

1. For ease of implementation, AGy may be equal for all release pathways:

1 AG y = (3.11) I N where: J N= the number of simultaneously active gaseous release pathways.

2. AG y for a given release pathway may be selected based on an estimate of the portion of the total SITE BOUNDARY dose rate (from all simultaneous releases) that is contributed by the release pathway. During periods when a given building or release pathway is not subject to gaseous radioactive releases, it may be assigned an allocation factor of zero.

p 3. AGy for a given release pathway may be selected based on a calculation of the portion of the total SITE BOUNDARY dose rate that is contributed by the release pathway, as follows, 3-29 Rev. 8, 1/94

   ~ . _. ,               __        . _      ___                                .                _   _ _ . _ - - . m--

I f-Hatch ODCM

a. for ground-level release points:

(M)vb [(Ki I i Ov) AG y = N . (3.12) [ [ (Vi Oi s) + E (x/0)rb E(Ki i r=1 i i Or)

b. for the elevated releaso point (main stack):

E(Vi Qis) AG y = I N , (3.13) E (Vi Ol s) + E (T/D)rb E(KI i Or) i r=1 i I 1 I i where: I (XT)vb = the annual average SITE BOUNDARY relative concentration ! applicable to the gaseous release pathway v for which the 3 l allocation factor is being determined, in s/m , l Kj = the total-body dose factor due to gamma emissions from noble gas radionuclide 1, in (mrem /y)/(pci/m 3), from Table 3-5. l l Qjy = the release rate of noble gas radionuclide i from release pathway v, in pCi/s, calculated as the product of Xjy and f,y, whera: Xjy = the concentration of noble gas radionuclide i applicable j j to the gaseous release pathway v for which the allocation ! factor is being determined, in pCi/mL. l f,y = the discharge flowrate applicable to gaseous release t pathway v for which the allocation factor is being l determined, in mL/s. f Note: As applied in equations (3.12) and (3.13), Q;y is restricted to ground-level release pathways. the elev, d finite-plume total body dose factor due to gamma g Vi= c

emissions from noble gas radionuclide i in affluents released from the main stack, in (mrom/y)/(pci/s), from Table 3-6.

3-30 Rev. 8, 1/94 ! l

                                                                                                     -~. -_-               q; Match ODCM
                       =     the release rate of noble gas radionuclide i f rom the main stack, s               Q,,

in yCi/s, calculated as the product of the X,y and f,y values specific to the main stack. (IOQ)rb

                                =    the annual average SITE BOUNDARY relative concentration                    3 applicable to active gaseous release pathway r, in s/m .

c in uCi/s. Qu = the value of Q,y applicable to active release pathway r, I N= the number of simultaneously active gaseous release pathways (including pathway v that is of interest). HOTE: Although equations (3.11), (3.12), and (3.13) are written to 1 l illustrate the assignment of the allocation factors for final release pathways, they may also be used to assign allocation f actors to the source streams that merge into a given final release l pathway. 3.3.5 Setooints for Noble Gas Monitors with Special Recuirements O Unit 1 Condenser Offcas Pretreatment Monitor Monitor: 1D11-K601 and 1D11-K602 Unit 2 Condenser Offcas Pretreatment Monitor Monitors 2D11-K601 and 2D11-K602 For the purpose of implementing Section 3.1.1, the alarm setpoint level for these 1 noble gas monitors will be calculated as follows. 2.40 x 10 5 (3 l4} e nco , E co *f eo where: ffgas as 2.40 x 105 = the release rate limit for pretreatme

onde '- -'

in T cification 2 15. ." M ,J...t O',, in pCi/s. gg c oco = the reading of the condenser of fgas pretreatment monitor at the r alarm setpoint, in mR/h. I w the calibration factor for the condenser offgas pretreatment Ego = l monitor, in (yci/s) per (cfm mR/h) . Rev. 8, 1/94 3-31 i - _ _ .

                          . - -      . . . - . . - - - . . - . . ~   . ~ - . . ~ . . . ~ ~ .   - - - . . . . . . . , -                  .

Hatch ODCM feo = the condenser offgas flowrate, in efm. 3.3.6 Setooints for Particulate and Iodine Monitors In accordance with Section 5.1.1 of NRC NUREG-0133 (Reference 1), the effluent l controls of section 3.1.1 do not require that the ODCM establish setpoint calculation methods for particulate and iodine monitors. l 1 l 1 l l 4 I f 1 4 3-32 Rev. 8, 1/94

l Hatch ODCM j (/ - 3.4 GASEOUS EFFLUENT COMPLIANCE CALCULATIONS 3.4.1 Dose Rates at and Beyond the Site Boundary Because the dose rate limits for areas at and beycnd the SITE specified in Section 3.1.2 are site limits applicable at any instant in time, the summations extend over all simultaneously active gaseous final release pathways at the plant site. Table 3-4 identifies the gaseous final release pathways at the plant site, and indicates the (17Q)vb ICY (57DIsb) value for each. 1 3.4.1.1 Dose Rates Due to Noble Games i For the purpose of implementing the controls of Section 3.1.2.a, the dose rates due to noble gas radionuclides in areas at or beyond the SITE BOUNDARY, due to releases of gaseous effluents, shall be calculated as follows: For total body dose rates: DR g = {v f(@)vb t b[KI I i Dv) a b (Yi i Di s) (3.15) O For skin dose rates: I DRk bv (X/0)vb b ((Li + 1* 15 )i D iv ' L i (3.16) [ ( (X/0)sb LI + 1.1 B; Ojg

                                             ,I where DRt=    the total body dose rate at the time of the release, in mrom/y.

the skin dose rate at the time of the release, in mrem /y. DRk= ggy = the release rate of noble gas radionuclide i, in pci/s, equal to the product of fty and X;y, wheres ftv = the actual average flowrate for release pathway v during the period of the release, in mL/s. 3-33 Rev. 8, 1/94 i

l J Hatch ODCM 1 I Notes For equations (3.15) and (3.16), the definition of Qjy, !- and the summations over v, are restricted to ground-level release pathways. i l Q;, = the release rate of noble gas radionuclide i from the main stack, in pCi/s, equal to the product of the ftv and X;y val.ses specific to the main stack. ' (This definition applies to both equations (3.15) . ; and-(3.16).) { i f (17D)sb the value of (176)vb for the main stack; that is, the highest annual average relative concentration at the SITE BOUNDARY, for the main stack, in s/m3 . Table 3-4 includes the value of (176)sb' l All other terms were defined previously. 3.4.1.2 Dose Rates Due to Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form with Half-Lives Greater than 8 Days ] l For the purpose of implementing the controls of Section 3.1.2.b, the dose rates due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form i with half-lives greater than 8 days, in areas at or beyond the SITE BOUNDARY, due to releases of gaseous effluents, shall be calculated as follows: 3

(X75)sh [ Pjo Of (3*17) DR, = {v (Y75)v6 [ i Pjo Ojp' where: , DRo = the dose rate to organ o at the time of the release, in mrom/y. Pjo = the site-specific dose factor for radionuclide i and organ o, in (arem/y)/(pC1/m 3). Since the dose rate limits specified in Section l 3.1.2.b apply only to the child age group exposed to the inhalation pathway, the values of P;o may be obtained from Table 3-9, "R,;g for Inhalation Pathway, Child Age Group." l Qjy= the release rate of radionuclide i from gaseous release pathway v, in pCi/s. For the purpose of implementing the controls of Section 3.1.2.b. only I-131, I-133, tritium, and all radionuclides in 3-34 Rev. 8, 1/94

Hatch ODCM l particulate form with half-lives greater than 8 days should be included in this calculation. All other terms were defined previously. ] 3.4.2 Noble Gas Air Dose at or Beyond Site Boundary For the purpose of implementing the controls of Section 3.1.3, air doses in areas at or beyond the SITE BOUNDARY due to releases of noble gases from each unit j shall be calculated as follows (adapted from Reference 1, page 28, by including . only long-term releases): l . i i , , I Dg = 3.17 x 10~8 { ( grg)vb b (Ni

it-) '

l (3.18) l l l (R76)sh E (Ni

d s) i I i

( l % Dy = 3.17 x 10-0 { (xfo)pg { (Mg dfy) ' 1 v , i I (3.19) ,

                                                                         + [ {B;         d f,}

l l l l where: 3.17 x 10~8 = a units conversion f actor: 1 y/(3.15 x 10 7 s). Dg = the air dose due to beta emissions from noble gas radionuclides, in mrad. Dy = the air dose due to gamma emissions from noble gas radionuclides, [ in mrad. t i ~ Nj = the air dose factor due to beta emissions from noble gas radio-nuclide i, in'(mrad /y)/(pci/m 3), from Table 3-5. 3-35 Rev. 8, 1/94

Hatch ODCM

 \ss)         (17D),, = the value of (i7D)vb for the main stack; that is, the highest annual average relative concentration at the SITE BOUNDARY, for the main stack, in s/m3. Table 3-4 includes the value of (17D)sb

M = the air dose factor due to gamma emissions from noble gas radio-nuclide i, in (mrad /y)/(yci/m 3), from Table 3-5.

Bj = the elevated finite-plume air dose factor due to gamma emissions from noble gas radionuclide i in effluents released from the main j stack, in (mrad /y)/(yci/s), from Table 3-6. l 6;y = the cumulative release of noble gas radionuclide i from non-elevated release pathway v. in nci, during the period of intarest. j 6j, = the value of 6jy for the main stack; that is, the cumulative release of noble gas radionuclide i from the main stack, in pCi, during the period of interest. i and all other terms are as defined above. Because the air dose limit is on a per-reactor-unit basis, the summations extend over all gaseous final release pathways (other than the main stack, which has its own term) for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged from the release point may be apportioned to the two units in any reasonable manner, provided that all activity released via the particular shared release pathway is apportioned to one or the other unit. I 1 The gaseous final release pathways at the plant site, and the (27D)vb for each, are identified in Table 3-4. l l

O I

3-36 Rev. 8, 1/94

Hatch ODCM . O N, Table 3-5. Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 4 l i Y - Body (K) $ - Skin (L) y - Air (M) $ - Air (N) I Nuclide (mrem /y) per (mrem /y) per (mrad /y) per (mrad /y) per l ! (pCi/m 3) 3 (pci/m ) (pci/m 3) (pci/m 3) Kr-83m 7.56 E-02 0.00 E+00 1.93 E+01 2.88 E+02 Kr-85m 1.17 E+03 1.46 E+03 1.23 E+03 1.97 E+03 Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 a Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 1.03 E+04 Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 2.93 E+03 Kr-89 1.66 E+04 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 Xe m 9.15 E+01 4.76 E+02 1.56 E+02 1.11 E+03 Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 [T Xe-135m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 Xe-137 1.42 E+03 1.22 E+04 1.51 E+03 1.27 E+04 l Xe-138 8.83 E+03 4.13 E+03 9.21 E+03 4.75 E+03 Ar-41 8.84 E+03 2.69 E+03 9.30 E+03 3.28 E+03 All values in this table were obtained from Reference 3 (Table B-1), with units converted. O 3-37 Rev. 8, 1/94

          .      ..         -           ._.  .-.~

U Hatch 07;fli Table 3-6. Dose Facters for Exposure to Direct Radiation from Noble Gases in an Elevated Finite Plume y - Total Body (V) y - Air (B) Nuclide (mrem /y) per (uci/s) (mrad /y) per (uci/s) Kr-83m 0.00 E-00 0.00 E-OO Kr-85m 8.25 E-05 S.69 E-05 Kr-85 1.26 E-06 1.35 E-06 Kr-87 4.40 E-04 4.59 E-04 Kr-88 1.09 E-03 1.13 E-03 Kr-89 9.44 E-04 9.87 E-04 Kr-90 7.00 E-04 7.38 E-04 Xe-131m . 1.68 E-06 1.76 E-06 Xe-133m 1.29 E-05 1.37 E-05 Xe-133 1.38 E-05 1.43 E-05 Xe-135m 2.42 E-04 2.59 E-04

 /                 Xe-135              1.33 E-04                1.42 E-04

( Xe-137 9.55 E-05 1.02 E-04 Xe-138 6.16 E-04 6.44 E-04 Ar-41 7.34 E-04 7.72 E-04 Values are as reported in Reference 24. They were calculated in accordance' with Reference 1 (Section 5.2.1) and Reference 3 (Appendix F), using the meteorological joint frequency distributions presented in Reference 14. All values in this table are for the site Boundary (1545 m) in the ENE sector. O 3-38 Rev. 8, 1/94

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

l i Hatch ODCM 3.4.3 Dose to a Member of the Public at or Beyond Site Boundary The dose receivod by an individual due to gaseous releases from each reactor l' unit, to areas at or beyond the SITE BOUNDARY, depends on the individual's l location, age group, and exposure pathways. The MEMBER OF THE PUBLIC expected ( to receive the highest dose in the plant vicinity is referred to as the controlling receptor. The dosimetrically-significant attributes of the currently-defined controlling receptor are presented in Table 3-7. Doses to a MEMBER OF THE PUBLIC due to gaseous releases of I-131, I-133, tritium, and all radionuclides in particulate form from each unit shall be calculated as follows (equation adapted from Reference 1, page 29, by considering only long-term releases): Dja = 3.17 x 10~E { { R ap jj [ W yip . dfy' (3.20) p i v

where: Dj, = the dose to organ j of an individual in age group a, due to gaseous releases of I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in mrom. 3.17 x 10-8 = a units conversion factor: 1 y/(3.15 x 107 s). radionuclide i, Raipj = the site-specific dose factor for age group a, exposure pathway p, and organ j. For the purpose of implementing the controls of Section 3.1.4, the exposure pathways applicable to calculating the dose to the currently-defined controlling receptor are included in Table 3-7; values of R aipj for each exposure pathway and radionuclide applicable to calculations of dose to the controlling receptor are listed in Table 3-8 through Table 3-10. A detailed discussion of the methods and parameters used for calculating R,;p; for the plant site is presented in Chaptar 9. That information may be used for recalculating the Raipj V " 1 " *

I f the underlying parameters change, or for calculating Raipj values 3-39 Rev. 8, 1/94

  -..___._._-________._._..___m_                                                                                _ . _ _      -.

l l Hatch ODCM' l'f l\ for special radionuclides and age groups when performing the assessments discussed in Section 3.4.4 below. Wy ;p = . the annual average relative dispersion or deposition at the L location of the controlling receptor, for release pathway v, as , l appropriate to exposure pathway p and radionuclide 1. For all tritium pathways, and for the inhalation of any radio-nuclides Wy ;p is (176)yp, the annual average relative dispersion factor for release pathway v, at the location of the controlling receptor (s/m 3). For the ground-plane exposure' pathway, and for all ingestion-related pathways for radionuclides other than , tritium: Wy ;p is . (576)yp, the annual average relative deposition l factor for release pathway v, at the location of the controlling f receptor (m-2). Values of (176)yp and (575)yp for use -in calculating the dose to the currently-defined controlling receptor f are included in Table 3-7. l l -Qjy= the cumulative release of radionuclide i from release pathway v, during the period of interest (pC1). For the purpose of implementing the controls of Section 3.1.4, only I-131, I-133, ! I tritium, and all radionuclides in particulate form with half-lives greater than 8 days should be included in this calculation. In any dose assessment using the methods of this sub-section, only radio-nuclides detectable above background in their respective samples should be included in the calculation. l' l Because the MF.MBER OF THE PUBLIC dose limit is on a per-unit basis, the t-l summations extend over all gaseous final release pathways for a given unit. For a release pathway discharging materials originating in both reactor units, the activity discharged from the release point may be apportioned between the two units in any reasonable manner, provided that all activity released from the plant site is apportioned to one or the other unit. The gaseous final release pathways at the plant site, and the release elevation for each, are identified in Table 3-4. 4 lO 3-40 Rev. 8, 1/94

l { Hatch ODCM NI. ' ' s Table 3-7. Attributes of the controlling Receptor 4-f The locations of members of the public in the vicinity of the plant site, and the exposure pathways associated with those locations, were determined in the Annual Land Use Census (Reference 12) . Dispersion and deposition values were calculated based on site meteorological data collected for the period 1984 through 1986 (Reference 16). Based on an analysis of this information, the current controlling receptor for the HNP site is described as follows. Sector: Wsw Distance: 1.2 miles Ace Groues Child Exoosure Pathways: Ground plane Inhalation Garden vegetation Discersion Factors (X76)yp: Ground-Level: 3.18 x 10 4 s/m 3 Elevated: 6.53 x 10*8 s/m 3 Denosition Factors ( D76 ) yps Ground-Levels 8.80 x 10~9 m'2 Elevated: 1.37 x 10*9 m -2 Elevated Plume Dose Factore3+ Radionuclide Radionuclide (mrem /y)/(uci/s) (mrem /y)/(uci/s) Kr-85m 6.92 E-05 Xe-133m 1.07 E-05 Kr-85 9.95 E-07 Xe-133 1.23 E-05 Kr-87 3.36 E-04 Xe-133m 1.90 E-04 Kr-88 8.23 E-04 Xe-135 1.09 E-04 Kr-89 7.20 E-04 Xe-137 7.54 E-05 Kr-90 5.39 E-04 Xe-138 4.71 E-04 Xe-131m 1.42 E-06 Ar-41 5.59 E-04 m

                                                     +                               rhese values were calculated using the methods and data described in Reference 29.                                                                                                            They are necessary when performing calculations for the purpose of demonstrating compliance with the limits of Section 5.1.

3-41 Rev. 8, 1/94 i

n. . . _ .

e a :e l ,.

                                                                              ,t, .-      . . . _.

6_._ a Hatch ODCM i ( 3.4.4 Dese Catt"U e r_t Other Pecu;rements

                                /0 U/2, So. 73 Case is         Und    6 ; . . . . . . ; ; a . f . : n . e .- ' 5 ', a radiological impact assess-mer              quir       . su    r av uation of a reportable event.

Dose calculations may be perf ormed using the equations in Section 3.4.3, with the substitution of the dispersion end deposition parameters ((X/Q) and (D/Q)] for the period covered by the report, and using the appropriate pathway dose factors (Raipj) for the receptor of interest. Methods for calculating (X/Q) and (D/Q) from meteorological data are presented in Chapter 8. The values of Rgp j presented in Table 3-8 through Table 3-10 are applicable only to the currently-defined controlling receptor, so that when dose ' calculations must be performed for a different receptor, R ang values applicable to that receptor must first be calculated. Methods and parameters for calculating R,;pj foz radionuclides and age groups other than those required in Section 3.4.3 are presented in Chapter 9. When calculating R,;PJ for evaluation ot en event, pathway and usage factors gm specific to the rriceptor involved in the event may be used in place of the values in Chapter 9, if the specific values are known. Case 2: A dose calculation is required to evaluate the results of the Land Use Census, under the provisions of Section 4.1.2. In the eveat that the Land Use Census reveals that exposure pathways have changed at previously-identified locations, or if new locations are identified, it may be necessary to calculate doses at two or more locations to determine which should be designated as the controlling receptor. Such dose calculations may be performed usir,g the equations in Section 3.4.3, with the substitution of the annual average dispersion and deposition values ((X/D) and (6/Q)) for the locations of interest, and

using the appropriate pathway dose factors (Raig) for the receptors of interest. Methode for calculating (X/Q) and (D/Q) from meteorological data are presented in Chapter 8. The values of Raipj presented in Table 3-8 through Table 3-10 are applicable only to the currently-defined controlling receptor, so that when dose calculations must be performed for a dif ferent

receptor, Raipj values applicable to that receptor must first be calculated. l Methods and parameters for calculating Raipj for radionuclides and age 3-42 Rev. 8, 1/94

Hatch ODCM V Methods and parameters for calculating Rapj j for radionuclides and age groups other than those required in Section 1.4.3 are presented in Chapter 9. Case 3: Under section 5.2, a dose calculation is required to support determination of total dose to a receptor of age group other than that currently defined as the controlling recepter. Dose calculations shall be performed using the equations in Section 3.4.3, using the dispersion and deposition parameters defined in Table 3-7 for { the controlling receptor, but substituting the appropriate pathway dose factors (Raipj) for the receptor age group of interest. The values of Raipj presented in Table 3-8 through Table 3-10 are applicable j only to the currently-defined controlling receptor, so that when dose l calculations must be performed for a different receptor age group, R,jp; values applicable to that receptor must first be calculated. Methods and parameters for calculating R,j pj for radionuclides and age groups other than l those required in section 3.4.3 are presented in chapter 9. 0 l l i l l l l l O 3-43 Rev. 10, 7/95

Hatch 02Cd Table 3-8. Ra jpg for Ground Plane Pathway, All Age Groups Nuclide T. Body Skin H-3 0.00 0.00 C-14 0.00 0.00 P-32 0.00 0.00 Cr-51 4.66E+06 5.51E+06 Mn-54 1.39E+09 1.63E+09 Fe-55 0.00 0.00 Fe-59 2.73E+08 3.21E+08 Co-58 3.79E+08 4.44E+08 co-60 2.15E+10 2.53E+10 Ni-63 0.00 0.00 Zn-65 7.47E+08 8.59E+08 Rb-86 8.99E+06 1.03E+07 Sr-89 2.16E+04 2.51E+04 Sr-90 0.00 0.00 Y-91 1.07E+06 1.21E+06 Zr-95 2.45E+08 2.84E+08 Nb-95 1.37E+08 1.61E+08 g Ru-103 1.09EtCG 1.26E+08 (/ s- Ru-106 4.22E+08 5.07E+08 Ag-110m 3.44E+09 4.01E+09 Sb-124 5.98E+08 6.90E+08 Sb-125 2.34E+09 2.64E+09 Te-125m 1.55E+06 2.13E+06 i Te-127m 9.16E+04 1.08E+05 l Te-129m 1.9BE+07 2.31E+07 ) I-131 1.72E+07 2.09E+07 I I-133 2.45E+06 2.98E+06 Cs-134 6.86E+09 8.00E+09 Cs-136 1.51E+08 1.71E+08 Cs-137 1.03E+10 1.20E+10 Ba-140 2.05E+07 2.35E+07 Ce-141 1.37E+07 1.54E+07 Ce-144 6.95E+07 8.04E+07 Pr-143 0.00 0.00 Nd-147 8.39E+06 1.01E+07

1. Units are m 2-(mrem /yr)/(pci/s).

2. The values in the Total Body column also apply to the Bone, Liver, Thyroid, Kidney, Lung, and CI-LLI organs.

   )           3.         This table also supports the calculations of Section 6.2.          ,

3-44 Rev. 8, 1/94

                                                        .                                             1 Hatch ODCM Table 3-9.      R,jn; for Inhalation Pathway, Child Age Group Nuclide      Bone       Liver     T. Body   Thyroid      Kidney     Lung      GI-LLI H-3         0.00   1.12E+03 1.12E+03 1.12E+03         1.12E+03 1.12E+03 1.12E+03 C-14    3.59E+04    6.73E+03 6.73E+03 6.73E+03         6.73E+03 6.73E+03 6.73E+03 P-32   2.60E+06    1.14E+05 9.88E+04            0.00       0.00      0.00 4.22E+04 Cr-51          0.00        0.00 1.54E+02 8.55E+01       2.43E+01 1.70E+04 1.08E+03          l Mn-54          0.00  4.29E+04 9.51E+03            0.00  1.00E+04 1.58E+06 2.29E+04          j Fe-55   4.74E+04    2.52E+04 7.77E+03            0.00       0.00 1.11E+05 2.87E+03 4

Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00 0.00 1.27E+06 7.07E+04 Co-58 0.00 1.77E+03 3.16E+03 0.00 0.00 1.11E+06 3.44E+04

        ,Co-60           0.00  1.31E+04 2.262+04            0.00       0.00 7.07E+06 9.62E+04 Ni-63   8.21E+05    4.63E+04 2.80E+04            0.00       0.00 2.75E+05 6.33E+03         1 Zn-65   4.26E+04    1.13E+05 7.03E+04            0.00  7.14E+04 9.95E+05 1.63E+04          )

Rb-86 0.00 1.98E+05 1.14E+05 0.00 0.00 0.00 7.99E+03 Sr-89 5.99E+05- 0.00 1.72E+04 0.00 0.00 2.16E+06 1.67E+05 Sr-90 1.01E+08 0.00 6.44E+06 0.00 0.00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00 2.44E+04 0.00 0.00 2.63C+06 1.84E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 0.00 5.96E+04 2.23E+06 6.11E+04 Nb-95 2.35E+04 9.18E+03 6.55E+03 0.00 8.62E+03 6.14Es05 3.70E+04 ) Ru-103 2.79E+03 0.00 1.07E+03 0.00 7.03E+03 6.62E+05 4.48E+04 ) O. Ru-106 1.36E+05 0.00 1.69E+04 Ag-110m 1.69E+04 1.14E+04 9.14E+03 0.00 1.84E+05 1.43E+07 4.29E+05 0.00 2.12E+04 5.48E+06 1.00E+05 l Sb-124 0.00 0.00 0.00 0.00 0.00 0.00 0.00 l Sb-125 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Te-125m 6.73E+03 2.33E+03 9.14E+02 1.92E+01 0.00 4.77E+05 3.38E+04 , Te-127m 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-129m 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 I-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00 5.48E+03 j Cs-134 6.51E+05 1.01E+06 2.25E+05 0.00 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71E+05 1.16E+05 0.00 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 0.00 2.82E+05 1.04E+05 3.62E+03 Ba-140 7.40E+04 6.48E+01 4.33E+03 0.00 2.11E+01 1.74E+06 1.02E+05 Co-141 3.92E+04 1.95E+04 2.90E+03 0.00 8.55E+03 5.44E+05 5.66E+04 Ce-144 6.77E+06 2.12E+06 3.61E+05 0.00 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 0.00 3.00E+03 4.33E+05 9.73E+04 Nd-147 1.08E+04 8.73E+03 6.81E+02 0.00 4.81E+03 3.28E+05 8.21E+04

1. Units are (mrem /yr)/(pci/m3 ) for all radionuclides.

2. This table also supports the calculations of Section 6.2.

( 3-45 Rev. 8, 1/94 i

                                                   .                                       1 1

l Hatch ODCM Table 3 -10. Ra jg for Garden Vegetation Pathway, Child Age Group

   ,Nuclide       Bone       Liver     T. Body    Thyroid    Kidney    Lung      GI-LLI H-3          0.00 4.01E+03    4.01E+03 4.01E+03 4.01E+03 4.L1E+03       4.01E+03 C-14     8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08           1.78E+08 P-32     3.37E+09 1.58E+08 1.30E+08             0.00     0.00      0.00  9.31E+07 Cr-51          0.00        0.00 1.17E+05 6.50S+04 1.78E+04 1.19E+05       6.21E+06 Mn-54          0.00 6.65E+08 1.77E+08            0.00 1.86E+08      0.00  5.58E+08 Fe-55     8.01E+08 4.25E+08 1.32E+08             0.00     0.00 2.40E+08 7.87E+07 Fe-59     3.98E+08 6.43E+08     3.20E+08         0.00     0.00 1.86E+08 6.70E+08 Co-58          0.00 6.44E+07    1.97E+08         0.00     0.00      0.00 3.76E+08 Co-60          0.00 3.78E+08    1.12E+09         0.00     0.00      0.00 2.10E+09 Ni-63     3.95E+10 2.11E+09     1.34E+09         0.00     0.00      0.00 1.42E+08 Zn-65     8.13E+08 2.16E+09     1.35E+09         0.00 1.36E+09      0.00 3.80E+08 Rb-86          0.00 4.52E+08 2.78E+08            0.00     0.00      0.00 2.91E+07 Sr-89     3.60E+10         0.00 1.03E+09         0.00     0.00      0.00 1.39E+09 Sr-90     1.24E+12         0.00 3.lfE+11         0.00     0.00      0.00 1.67E+10 Y-91     1.86E+07         0.00 4.99E+05         0.00     0.00      0.00 2.4RE+09 Zr-95    3.86E+06 6 48E+05 7.55E+05             0.00 1.21E+06      0.00  8.85E+08 Nb-95     4.10E+05 1.60E+05 1.14E+05             0.00 1.50E+05      0.00  2.96E+08 Ru-103     1.53E+07         0.00 5.90E+06         0.00 3.86E+07      0.00  3.97E+08 O     Ru-106 Ag-110m 7.45E+08         0.00 9.30E+07 3.21E+07 2.17E+07 1.73E+07 0.00 1.01E+09 0.00 4.04E+07 0.00 0.00 1.16E+10 2.58E+09 Sb-124          0.00        0.00      0.00        0.00     0.00      0.00       0.00 Sb-125          0.00        0.00      0.00        0.00     0.00      0.00       0.00 Te-125m    3.51E+08    9.50E+07  4.67E+07 9.84E+07         0.00      0.00 3.38E+08 Te-127m    1.32E+09    3.56E+08  1.57E+08 3.16E+08 3.77E+09          0.00 1.07E+09 Te-129m    8.41E+08    2.35E+08  1.31E+08 2.71E+08 2.47E+09          0.00 1.03E+09 I-131    1.43E+08    1.44E+08  8.17E+07 4.75E+10 2.36E+08          0.00 1.28E+07 I-133    3.53E+06    4.37E+06 1.65E+06 8.11E+08 7.28E+06           0.00 1.76E+06 Cs-134     1.60E+10    2.63E+10 5.55E+09          0.00 8.15E+09 2.93E+09   1.42E+08 Cs-136    8.24E+07    2.'27E+08 1.47E+08         0.00 1.21E+08 1.80E+07   7.96E+06 Cs-137    2.39E+10    2.29E+10 3.38E+09          0.00 7.46E+09 2.68E+09   1.43E+08 Ba-140    2.77E+08    2.42E+05 1.61E+07          0.00 7.89E+04 1.45E+05   1.40E+08 Ce-141    6.56E+05    3.27E+05 4.86E+04          0.00 1.43E+05      0.00  4.08E+08 Co-144    1.27E+08    3.98E+07 6.78E+06          0.00 2.21E+07      0.00  1.04E+10 Pr-143    1.46E+05 4.37E+04 7.23E+03             0.00 2.37E+04      0.00 1.57E+08 Nd-147    7.15E+04 5.79E+04 4.48E+03             0.00 3.18E+04      0.00 9.17E+07 Units are (mrem /yr)/(pci/m 3 ) for tritium, and m 2.(mrem /yr)/(pci/s) for all other radionuclides.

O 3-46 Rev. 8, 1/94

l l l Hatch ODCM 3.5 GASEOUS EFFLUENT DOSE PROJECTIONS 3.5.1 Thirty-one Day Dose Proiections Because continuous operation of the gaseous radwaste treatment system is required l (see Section 3.1.5), routine 31-day dose projections are not required for effluent control compliancs at Plant Hatch. However, whenever it is desired to I perform such projections, projected 31-day air doses and doses to individuals due l to gaseous effluents may be determined as follows: For air doses: Dgp

                                                            =              x 31 + Dga 1

(3.21) ), 9 D yp = x 31 + D yg i For individual doses: D,p = x 31 + D, o (3.22) where: Dgp = the projected air dose due to beta emissions from noble gases, for the next 31 days of gaseous releases. Dge = the cumulative air dose due to beta emissions from noble gas releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration. Dg, = the anticipated air dose due to beta emissions from noble gas releases, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that are in addition to routine gaseous ef fluents. If only routine gaseous effluents are anticipated, D#a may be set to zero. l 1

D = the projected air dose due to gamma emissions from noble gases for 9

the next 31 days of gaseous releases. O l l 3-47 Rev. 8, 1/94

Hatch ODCM D ye = the cumulative air dose due to gamma emissions f rom noble gas releases that have occurred in the elapsed portion of the current 1 quarter, plus the' release under consideration. i D,= y the anticipated air dose due to gamma emissions from noble gas releases, contributed by any planned activities during the next f j 31-day period, if those activities will result in gaseous raleases j that are in addition to routine gaseous ef fluents. If only routine gaseous af fluents are anticipated, Dy , may be set to zero. D = the projected dose to the total body or organ o, due to releases 9 of I-131, I-133, tritium, and particulates for the next 31 days of gaseous releases. Doc = the cumulative dose to the total body or organ o, due to releases of I-131, I-133, tritium, and particulates that have occurred in the elapsed portion of the current quarter, plus the release under consideration. D,= o the anticipated dose to the total body or organ o, due to releases of I-131, I-133, tritium, and particulates, contributed by any planned activities during the next 31-day period, if those activities will result in gaseous releases that are in addition to routine gaseous effluents. If only routine gaseous effluents are anticipated, D o, may be set to zero. t= the number of whole or partial days elapsed into the current quarter, including the time to the end of the release under consideration (even if the release continues into the next quarter). 3.5.2 Dose Proinctions for Soecific Releases y Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned release will proceed as anticipated. For air dose and individual dose projections due to gaseous effluent releases, follow the methodolosy of section 3.4, using sample analysis results for the gaseous stream to be released, and parameter values expected to exist during the release period. 3-48 Rev. 8, 1/94 ! I

l Hatch ODCM 3.6 DEFINITIONS OF GASEOUS EFFLUENT TERMS Section of Initial Use l IRIm Definition AG = the administrative allocation factor for gaseous streams, applied to divide the gaseous release limit l l among all the release pathways (unitiess). 3.3.2.1 i I f AG, = the administrative allocation factor- for gaseous. ; source stream s, applied to divide the gaseous release limit among all the release pathways I (uniticss). 3.3.3 AGy = the administrative allocation factor for gaseous l release pathway v, applied to divide the gaseous , release limit among all the release pathways i i (unitiess). 3.3.2.2 Bj = the elevated finite plume air dose factor due to j gamma emissions from noble gas radionuclide i in the ( effluents released from the main stack [(mrad /y)/(pci/s)). 3.3.2.2 l c= the setpoint of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to release [pci/mL). 3.3.2.1 cnm = the reading of the condenser offgas pretreatment monitor at the alarm setpoint (mR/h). 3.3.5 cas = the calculated noble gas effluent monitor setpoint for gaseous source stream s (pci/mL). 3.3.3 c ay = the calculated noble gas effluent monitor setpoint for release pathway v [pci/mL). 3.3.2.2 l l Dj, = the dose to organ j of an individual in age group a, due to gaseous releases of I-131, I-133, tritium, and , radionuclides in particulate form with half-lives l l greater than 8 days [ mrem). 3.4.3 i

i l l 3-49 Rev. 8, 1/94

_ . _ . . . . __..= ._ - _._ .. _ ._ _ m . _ . . ~ . . _ _ _ . . _ _ . _ _ _ . _ . . __ _ I l Hatch ODCM Section of I.RKE Definition Initial Use i D,= o the anticipated dose to organ o due to releases of ) non-noble-gas radionuclides, contributed by any planned activities during the next 31-day period [ mrem). 3.5.1 Doc = the cumulative dose to organ o due releases of non-noble-gas radionuclides that have occurred in the elapsed portion of the current quarter, plus the release under consideration (mrem). 3.5.1 - D op = *he projected dose to organ o due the next 31 days of gaseous releases of non-noble-gas radionuclides (mrem). 3.5.1 , Dg = the air dose due to beta emissions from noble gas radionuclides (mrad). 3.4.2 ; Dg, = the anticipated air dose due to beta emissions from noble gas releases, contributed by any planned ; activities during the next 31-day period (mrad). 3.5.1 { Dge = the cumulative air dose due to beta emissions from noble gas releases that have occurred in the elapsed ) portion of the current quarter, plus the release i under consideration (mrad). 3.5.1 l Dgp = the projected air dose due to beta emissions from noble gases, for the next 31 days of gaseous releases (mrad). 3.5.1 1 I I

     -D    =             the air dose due to gamma emissions from noble gas 7

radionuclides (mrad). 3.4.2 D = the anticipated air dose due to gamma emissions from Ta noble gas releases, contributed by any planned activities during the next 31-day period (mrad). 3.5.1 O 3-50 Rev. 8, 1/94

Hatch ODCM Section of Definition Initial Use IRIm D ye = the cumulative air dose due to gamma emissions from noble gas releases that have occurred in the elapsed portion of the current quarter, plus the release under consideration (mrad). 3.5.1 Op = the projected air dose due to gamma emissions from noble gases, for the next 31 days of gaseous releases j 3.5.1 [ mrad). (D7D)yp = the annual average relative deposition factor for release pathway v, at the location of the controlling receptor, from Table 3-7 (m*2). 3.4.3 DRk= the skin dose rate at the time of the release (mrom/y). 3.4.1.1 DRo = the dose rate to organ o at the time of the release (mrem /y). 3.4.1.2 the total body dose rate at the time of the release i DRt= (mrom/y). 3.4.1.1 E go = the calibration factor for the condenser offgas pretreatment monitor [(pci/s) per (cfm mR/h)). 3.3.5 f,y = the maximum anticipated actual discharge flowrate for release pathway v during the period of the planned release (mL/s). 3.3.2.2 the condenser offgas flowrate (cfm). 3.3.5 ; feo = f,= a the maximum anticipated actual discharge flowrate for gaseous source stream a during the period of the planned release (mL/s). 3.3.3 Kj = the total body dose factor due to gamma emissions from noble gas radionuclide i, from Table 3-5 3 ((arem/y)/(pci/m )). 3.3.2.2 3-51 Rev. 8, 1/94

Hatch ODCM Section of ISKE Definition Initial Use Lj = the skin dose f actor due to beta emissions from noble i gas radionuclide i, from Table 3-5 [(mrom/y)/(pci/m 3

                                                                          ))  .                                                       3.3.2.2 1

Mj = the air dose factor due to gamma emissions from noble gas radionuclide 1, from Table 3-5 [(mrad /y)/(pci/m 3)) . 3.4.2 N= the number of simultaneously active gaseous release l pathways [unitiess). 3.3.4 l l Ng = the air dose factor due to beta emissions from noble gas radionuclide 1, from Table 3-5 [(mrad /y)/(pci/m 3)}. 3.4.2 I Pjo = the site-specific dose factor for radionuclide i , O (I-131, I-133, tritium, and radionuclides in G particulate form with half-lives greater than 8 days) ; and organ o. The values of Pjo are equal to the site- ; specific R,;pj values present ed in Table 3-9 3 3.4.1.2 [(mrom/y)/(pci/m )) . Qjy = the release rate of noble gas radionuclide i from l release pathway v during the period of interest ) [pci/s). 3.3.2.2 Qjy= the release rate of radionuclide 1 (I-131, I-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days) from gaseous release pathway v during the period of interest [yci/s). 3.4.1.2 6;, = the cumulative release of noble gas radionuclide i from the main stack during the period of interest [pci). 3.4.2 6jy = the cumulative release of noble gas radionuclide i ! from release pathway v during the period of interest [pci). 3.4.2 3-52 Rev. 8, 1/94

' Hatch ODCM i Section of ISEE1 Definition Initial Use } t 6ly= the cumulative release of non-noble-gas radionuclide

i from release pathway v, during the period of interest [yCi). 3.4.3 ,

s Rjj= ap the site-specific dose f actor for age group a, radio-i nuclide i, exposure pathway p, and organ j. Values l and units of R,;pj for each exposure pathway, ' age ! group, and radionuclide that may arise in ! ! calculations for implementing Section 3.1.4 are , listed in Table 3-8 through Table 3-10. 3.4.3 l Rk= the ratio of the skin dose rate limit for noble l l gases, to the skin dose rate due to noble gases in , I the release under consideration [unitiess). , 3.3.2.1 i Rt= the ratio of the total body dose rate, limit for noble 1 l 1 j g gases, to the total body dose rate due to noble gases j in the release under consideration [unitiess). 3.3.2.1 l k j rk = the ratio of the skin dose rate limit for noble gases, to the skii dose rate due to noble gases in j the source stream under consideration [unitiess). 3.3.3.1 j rt= the ratio of the total body dose rate limit for noble gases, to the total body dose rate due to noble gases > in the source stream under consideration [unitiess). 3.3.3.1 J SF = the safety factor used in gaseous setpoint calculations to compensate for statistical i J 3 fluctuations and errors of measurement [unitiess). 3.3.2.2 l

l 4

t= the number of whole or partial days elapsed in the current quarter, including the period of the release under consideration. 3.5.1 1 ! l Vg = the elevated finite plume total body dose factor due ] i to gamma emisnions from noble gas radionuclide i in 3-53 Rev. 8, 1/94 l a

Hatch ODCM Section of Term Definition Initial Use the effluents released from the main stack [(mrom/y)/(pci/s)). -3.3.2.2 Wy ;p = the annual average relative dispersion [ (176)yp) or deposition [(67D)yp) at the location of the controlling tsceptor, for release pathway v, as appropriate to exposure pathway p and radio-nuclide 1. 3.4.3 s X= the noble gas concentration for the release under i consideration [pci/mL). 3.3.2.1 Xir = the concentration of radionuclide i applicable to j active gaseous release pathway r [pci/mL). 3.3.4 i X;, = the measured concentration of radionuclide i in gaseous source stream s [pci/mL). 3.3.3 X;y = the measured concentration of radionuclide i in gaseous stream v [pci/mL). 3.3.2.2 (X/Q) = the highest relative concentration at any point at or beyond the SITE BOUNDARY [s/m3 ']. 3.3.2.1 (57D)tb = the annual average SITE BOUNDARY relative concen-tration applicable to active gaseous release pathway r (s/m3 ). 3.3.4 (176)sb = the highest annual average relative concentration at the SITE BOUNDARY for the main stack, from Table 3-4 [s/m3 ). 3.4.2 (176)vb = the highest annual average relative concentration at the SITE BOUNDARY for the discharge point of release pathway v, from Table 3-4 (s/m3 ). 3.3.2.2 3-54 Rev. 8, 1/94

i. Hatch ODCM Section of Is.gg} Definition Initial Use , P (T/D)yp = annual average relative dispersion f actor for release pathway v, at the locetion of the controlling { receptor, from Table 3-7 (s/m 3). 3.4.3 i l t s i t O ! i i i l i I f 3-55 Rev. 8, 1/94

i i Hatch ODCM Section of i IRKE Definition Initial Use (17D)yp = annual average relative dispersion f actor for release pathway v, at the location of the controlling receptor, from Table 3-7 [s/m 3}. 3.4.3 O O i 3-55 Rev. 8, 1/94 A

                                                                                           .-           c     :-

Hatch ODCM CHAPTER 4 l RADIOLOGICAL ENVIPONMENTAL MONI*ORING PPOCRAM 4.1 LIMITS OF OPERATION The following limits are the same for both units at the site. Thus, a single

    . program including monitoring, land use survey, and quality assurance serves both units.

4.1.1 Padiolooical Environmental Monitorina N

      '-      - M*~;         -.-i.
                                -      T.s ;... . . ;  5 y. w . i i . . . . ; .;  i.'"
                                                                                    .  ^b       he    Radiological a          tal          oring                (R           shall        e con                specified in Table 4-1.

4.1.1.1 Applicability ,

                                                                                                       .v This control applies at all times.

4.1.1.2 Actio 3 t,' 4.1.1.2.1 Wi .e REMP no being co du- ed as specified in Table 4-1, submit i to the Nucl ar Regulator Commis on (NRC), in the Annual Radiological Environment

                           "  .;;i'1..
                                     . 5 Re        t,    a description of the reasons for not conducting the                        required and the plans f or preventing a recurrence.

Deviations from the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction, or other just reasons. If deviations are due to equipment malfunction, ef forts shall be made to complete corrective action prior to the end of the next sampling period. 4.1.1.2.2 With the confirmed I measured level of radioactivity as a result of plant effluents in an environmental sampling medium specified in Table 4-1 i exceeding the reporting levels of Table 4-2 when aver . p ...., O days a Special Report to the RC.p r r""* t r * :h;i;;'. he Special Report shall iden e o

        *-ri%.......        ? " 2.

coed nd define the corrective action (s) to be taken to reduce radioactive ef fluents so that the potential annual dose to a MEMBER OF THE PUBLIC I Defined as confirmed by reanalysis of the original sample, or analysis of l( a duplicate or new sample, as appropriate. The results of the confirm-atory analysis shall be completed at the earliest time consistent with the analysis. 4-1 Rev. 8, 1/94

l

                                                                         .,      . ..              -    l u,.        a.......--           l 1

Match ODCM O V is less than the calendar year limits of Sections 2 .1. 3, 3.1. 3, and 3.1.4. The methodology and parameters used to estimate the potent tal annual dose to a MEMBER OF THE PUBLIC shall be indicated in the Special Report. 1 I When more than one of the radionuclides in Table 4-2 are detected in the sampling medium, this report shall be submitted ift concentration (1) , concentration (2) , , , , , 3,n reporting level (1) reporting level (2) When radionuclides other than those in Table 4-2 are detected and are the result of plant effluents, this Special Report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits stated in Sections 2.1.3, 3.1.3, and 3.1.4. This Special Report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event t condition shall be described in the Annual Radiological Environmenta _ _ _ _ .llrrr R et. The levels of naturally-occurring radionuclides which ar not included in he plant's effluent releases need not be reported. g 4. D ) 4.1.1.2.3 If adequate samples of milk, or during the growing season, grass or leafy vegetation, can no longer be obtained from one or more of the sample locations required by T a b '. e 4-1, or if the availability as frequently or persistently wanting, ef forts shall be mades to identify specific locations for obtaining suitable replacement samples; and to add any replacement locations to the REMP given in the CDCM within 30 days. The specific locations from which ples b came unav t ble may be deleted from the REMP. Pursuant to Te ' cal [.S.I Specificatio@-in+b, ocumentation shall be submitted in the ne Aweveo6 oa uent Release Report fo- the change (s) in the ODCM, i revised figure (s) and table (s) reflecting the changes to the location (s), with supporting information identifying the cause of the unavailability of samples and justifying the selection of any new location (s). When the ACTION statement or other requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into an Operational Mode or other specified CONDITION may be made if, as a minimum, the requirements of the ACTION statement are satiefied. 4-2 Rev. 8, 1/94

1

c. . .

l Hatch ODCM G 4.1.1.3 Survetllance Requirements The REMP samples shall be collected pursuant to Table 4-1 from the locations j described in Section 4.2, and shall be analyzed pursuant to the requirements of ! Table 4-1 and Table 4-3. Required detection capabilities f or thermoluminescent dosi.e.eters used for environmental measurements shall be in accordance with the ; recocenendations of Regulatory cuide 4.13. Program changes may be initiated based on operational experience. Analyses shall be performed in such a manner that the stated MINIMUM DETECTABLE CONCENTRATIONS (MDCs) will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may render these , MDCs unachievable. In such cases, the contributing fa will be identified f and described in tb ~ "' adiological Environment _........n- eport. Gen t.' 4.1.1.4 Basis , l The REMP required by this control provides representative measurements of radiation and of radic active materials in those exposure pathways, and for those

   '    radionuclides, which lead to the highest potential radiation exposures of MEMBERS            ,

OF THE PUBLIC resulting from the plant operation. The REMP implements Section f IV.B.2, Appendix I,10 CFR 50, and thereby supplements the radiological ef fluent j mont.oring program by measuring concentrations of radioactive matertals and j levels of radiation, which may then be compared with those expected on the basis l of tne ef fluent measurements and modeling of the envarenmental exposure pathways. j The detection capabilities required by Table 4-3 are within state-of-the-art f or routine environmental measurements in industrial laboratories. (O 4-3 Rev. 8, 1/94

I [,

     ~'                                                                                                                      %j                                            ()

H E Approximate y Exposure Pathway Number of Sampling and Type of Analysis and Frequency A e and/or Sample Sample Collection Frequency Locations" 7 l

1. AIRBORNE w Continuous operation Radiolodine canister. I-131 weekly. S.

Radioiodines and 6 7 of sampler with sample . Particulates collection weekly. Particulate sampler. Analyze for y gross beta radioactivity not less than o 24 hours following filter change and E analyze for I-131 weekly. Perform $ gamma isotopic analysis on affected y sample when gross beta activity is 10 4 times the yearly mean of control samples. Composite (by location) for n gamma isotopic analysis quarterly.

2. DIRECT RADIATION re Quarterly. Gamma dose quarterly. b i Direct Radiation 37 lc

3. INGESTION y r

Gamma isotopic and I-131 analyses bi- g Milk 4b Bi-weekly. n weekly. p Semi-annually. Gamma isotopic analysis on edible e FishC or clams 2 portions semi-annually. .o n Gamma isotopic analysis monthly.d j Grass or Leafy 3 Monthly during growing " Vegetation season. $

4. WATERBORNE 2 Composite' sample Gamma isotopic analysis monthly.

Surface collected monthly. Composite (by location) for tritium analysis quarterly. o Semiannually Gamma isotopic analysis yearly.

 ,4 Sediment               2 Or
 ?

8 C 9

O O O

                                                                                                                                                                             *i Er s

Approximate i Exposure Pathway Number of Sampling and Type of Analysis and Frequency and/or Sample Sample collection Frequency Locations, o

s n

Drinking Water'E I From each of River Water collected I-131 analysis on each sample when bi- S the one to near the' intake will weekly collections are required. three nearest be a composite sample; Gross beta and gamma isotopic analyses water supplies the finished water on each sample; composite (by which could be will be a grab sample. location) for tritium quarterly. , These samples will be e affected by HNP discharge one collected nonthly & 0 sample of river unless the calculated dose due to o water near the

intake and one consumption of the sample of water is greater than y finished water. I mrem / year; then the collections will be m a

bi-weekly. The Q e-8 collection may revert

to monthly should the E
calculated doses g e

become less than 1 mrem / year. S O x o e-o O a a

                                                                                                                                                                            #1 0

4 et L E ? a h 8 C 2

O O H Er TABLE NOTATIONS {

a. Sample locations are shown in Table 4-4, and in Figure 4-1 through Figure 4-5.

b. Up to three sampling locations within 5 miles and in different sectors will be used as -

available. In addition, one or more control locations beyond 10 miles will be used. o 5 Clams will be sampled if a

c. Commercially or recreationally important fish may be sampled. 7 difficulties are encountered in obtaining sufficient fish samples.

d. If gamma isotopic analysis is not sensitive enough to meet the required MINIMUM DETECTABLE CONCENTRATION (MDC), a deparate analysis for I-131 may be performed. :o at intervals not exceeding a a

e. Composite samples shall be collected by collecting an aliquot o few hours.

o 4

f. If it is found that river water downstream of HNP is used for drinking, water samples will n be collected and analyzed as specified herein.

O

g. A survey shall be conducted annually at least 50 river miles downstream of HNP to identify g u

those who use the Altamaha River water for drinking. E kO

e x

o a O a C O O tt t x n = 7 8 C e o e

x%S o8x .O _ oEe IF o $@g:s

ej " m$ Eo. ' oo0eh 9ge%e%e-@m t 5' n g eyS* 0-n i$%e s

y t f ) s t i an eo e Liw x e t 2 3 3

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se i t aVc a p p r ( G r e t a w g

                          )                                                                          n i

kL l / 0

1

2

                                                                                              +      k            .

i i E E E E E n d i e MpC 3 6 7 3 4 r s ( d u o e n b l f y e I a v ) m e t . L L e s / _ w e g 4 4 4 4 4 3 3 i n h , + + + + + + + l C s g p p i i E E E E E E E m t r F /k a 0 O 3 1 3 1 2 1 2 s o i 2 p cp r e f R ( e o t a e _ w u _ r g l o a n v ee ) i k a ntj 1 1 1 n ra e m

                                                                        -     +    +                 i .

ol s/ bu L E E E rd s rc aC iicP 9 1 2 de s t s At ( ru i r o x a f e e _ P b . e y uy a _ l a w am v h t L a

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0E g 4 n _ 3 i _ e k hf n t o i r s se d iu _ i l o s sa n _ y iv l h f _ a 4 7 0 0 Ta I n 4 9 8 0 5 5 5 1 3 3 4 4 A 5 5 5 6 6 9 9 3 1 1 1 1 3 - - - 1 - - - - O H

                                   -   n e o o n 2rZ              b N
                                                                          -    s s a C C B L a

M F C C I . . a b as" g< * "- 3-

I O o/ O . ( H h s Minimum Detectable Concentration (MDC)a i Grass or f Airborne Leafy Particulate Fish Vegetation Sediment Water or casgs (pci/kg, Milk (pci/kg, (pci/kg, g wet) dry) .-- Analysis (pci/L) (PCL/m ) wet) (pci/L) e 8 Gross Beta 4 E+0 1 E-2 es g H-3 2 E+3 b Mn-54 1.5 E+1 1.3 E+2 h e 3 E+1 2.6 E+2 x Fe-59 Co-58, Co-60 1.5 E+1 1.3 E+2 9 2.6 E+2 g Zn-65 3 E+1 E

 ,    Zr-95                  3 E+1                                                                                                                              "

e $ , Nb-95 1.5 E+1 n . 1 E+0c 7 E-2 1 E+0 6 E+1 $ I-131 E 5 E-2 1.3 E+2 1.5 E+*. 6 E+1 1.5 E+2 Cs-134 1.5 E+1 1.8 E+1 6 E-2 1.5 E+2 1.8 E+1 8 E+1 1.8 E+2 Cs-137 6 E+1 6 E+1 % Ba-140 n La-140 1.5 E+1 1.5 E+1 % o

s Other peaks which

a. See the definition of MINIMUM DETECTABLE CONCENTRATION in Section 10.1.

are measurable and identifiable as plant ef fluer.ts, together with the radionuclides in this table, shall be analyzed and reported in accordance with Section 7.1.

n x

 'd b.      If no drinking water pathway exists, a value of 3 E+3 pCi/L may be used.

c. If no drinking water pathway exists, a value of 1.5 E+1 pCi/L may be used. g

 ,m 8

c 9

r ,

                                                                                 -  -s           .     .

Hatch ODCM l(C%j 4.1.2 Land Use Census

              -W
     *. ; ; ; ; .- l.. .u . - . O v

T.........I ^,. c.fic.:.:.- 5_'? 21, and use census shall be conducted and s all t entify e locattens of tn .aowings the nearest MILK l ANIMAI.I and the nearest permanent residence in each of the 16 meteorological sectors within a distance of 5 miles; and all MILK ANIMALS within a distance of 3 miles. 4.1.2.1 Applicability This control applies at all times. 4.1.2.2 Actions 4.1.2.2.1 With a land use census identifying a location (s) whten yields a calculated dose or dose commitment greater than values currently being calc ' ted in eccordance with section 3.4.3, identif y the new location (s) in the ne .dwemrwi Radioactive Ef fluent Release Report. l 1 4.1.2.2.2 With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent d greater than at a location f rem which samples are currently being obtained in , accordance with Section 4.1.1, add the new location (s) to the REMP within 30 days if samples are available. The sampling 'ecatten, excluding centrcl statten location (s), having the lowest calculated dese or dose commitment (via the same

                                                                      '#  new sampling locatior exposure pathway) may be deleted from the REM added.      Pursuant to Technical Specificati -+-M*                mit in the next enewe=1 Radioactive Effluent Release Report any e ange( ) in t e ODCM, including e revised figure (s) and table (s) reflectin any              w locatt n(s) and information supporting the change (s) .                                 5g7                                    l When the ACTION statement or other requirements of this control cannot be met, Entry into steps need not be taken to change the Operational Mode of the unit.

as a minimum, an Operational Mode or other specified CONDITION may be made if, the requirements of the ACTION statement are satisfied. i l V I Defined as a cow or goat that is producing milk for human consumption. Rev. 8, 1/94 4-9

n .

                                                                           ~ .                   a

s '- -- 6_- ._

Hatch ODCM 4.1.2.3 Surveillance Requirements

The land use census shall be conducted annually, using that information which from will provide good results, such as a door-to-door census, a visual census automobile or aircraf t, consultation with local agriculture authorities, or some combination of these methods, as feasible. Results of th Kuse census shall

0. . . . . . A e m. = eport.

be included in the Annual Radiological Environmenta fyr* f*' > 4.1.2.4 Basis This control is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the REMP are made if required by the This census satisfies the requirements of section IV.8.3 results of this census. ! of Appendix I to 10 CTR Part 50. : l I Rev. 8, 1/94 4-10

I Hatch ODCM ! D Interlaberatory Comeartson Procram 4.1.3 e ~

                                                                                                                                   . . ;; ; ' ' _        nal ses shall be performed I-  " :- . d-.... - an iechnical spe c u w a s w..

erlaboratory Comparison on r to Program which has been approved by the NRC. Analyses are required to be perf ormed only in cases in which the sample type and analysis are the same as the sample type and analysis included in Table 4-1. 4.1.3.1 Applicability ) I l This control applies at all times. I 4.1.3.2 Actions ; 1 l With analyses not being performed as required by Section 4.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmenta Cu r ::illM I h qrdMJ When the ACTION s at et er requirements of this control cannot be met, steps need not be taken to change the Operational Mode of the unit. Entry into [ an Operational Mode or other specified CONDITION may be made if, as a minimum, s the re i ements of the ACTION statement are natisfied. 4.1.3.3 Surveillance Requirements g% Either a summary of the r sults obtained as part of the required Interlaboratory Comparison Program shal be included in the Annual Radiological Environmental

                                                                         ^ ~ ' l l . . x % . . ^. ,          participants in the EPA cross-check program shall provide t-                                  est     ' -     r the plant in the Annual Radiological Environment       . _ . . . . _ . . _  Report.
                                                                                                                        ,   Qpgr> W 4.1.3.            as             I The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the l

purposes of Section IV.B.2, Appendix I, 10 CFR 50. l lO 4-11 Rev. 8, 1/94

Hatch ODCM I 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Table 4-4,' and Figure 4-1 through Figure 4-5 specif y the locations at which the l measurements and samples are taken for the REMP required by Section 4.1.1. I l-l l l l l l 1 I' l l l 4-12 Rev. 8, 1/94

Hatch ODCM Table 4-4. Radiological Environmental Monitoring Locations r Descriptive Location Direction f,'g y",",#

T pe 3

064 Roadside park WNW O.8 D 101 Inner ring N 1.9 D 102 Inner ring NNE 2.5 D 103 Inner ring NE 1.8 AD 104 Inner ring ENE 1.6 D 105 Inner ring E 3.7 D 106 Inner ring ESE 1.1 DV 107 Inner ring SE 1.2 AD 108 Inner ring SSE 1.6 D 109 Inner ring S 0.9 D 110 Inner ring SSW 1.0 D 111 Inner ring SW O.9 D 112 Inner ring WSW 1.0 ADV G 113 Inner ring W 1.1 D 114 Inner ring WNW 1.2 D 115 Inner ring NW 1.1 D 116 Inner ring NNW 1.6 AD 170 Upriver WNW ** R 172 Downriver E ** R 201 Outer ring N 5.0 D 202 Outer ring NNE 4.9 D 203 Outer ring NE 5.0 D 204 Outer ring ENE 5.0 D 205 Outer ring E 7.2 D 206 Outer ring ESE 4.8 D 207 Outer ring SE 4.3 D 208 Outer ring SSE 4.8 D 209 Outer ring S 4.4 D 210 Outer ring SSW 4.3 D O 4-13 Rev. 8, 1/94

1

! l l l Haten ODCM

    /   Table 4-4 (contd).         Radiological Environmental Monitoring Locations Location                                                                  Distance                        Sampi,e Descriptive Location         Direction Number                                                                   (miles)                         Type 211       Outer ring                            SW                       4.7                             D 212       Outer ring                           WSW                       4.4                             D 213       Outer ring                             W                       4.3                             D 214       Outer ring                           WNW                       5.4                             D 215       Outer ring                            NW                       4.4                             D 216       Outer ring                           NNW                       4.8                             D           l 301       Toombs Central School                  N                       8.0                             D           l 304       State Prison                         ENE                       11.2                            AD 304       State Prison                         ENE                       10.3                             M 309       Baxley substation                      S                       10.0                            AD 416        Emergency News Center               NNW                       21.0                            DV
 '"

Sample Types:

A - Airborne Radioactivity D - Direct radiation H - Milk R - River (fish or clams, shoreline sediment, and surface water) V - vegetation

           **     Station 170 is located at approximately 0.6 river miles upstream of the intake st ucture for river water, 1.1 river miles for sediment and clams, and 3.5 river miles for fish.

Station 172 is located at approximately 3.0 river miles downstream of the discharge structure f or river water, sediment, and clams, and 1.7 river miles for fish. The location from which river water and sediment may be taken can be rather precisely defined. Often, the sampling locations for clams have to be extended over a wide area to obtain a suf ficient quantity. High water adds to the dif ficulty in obtaining clam samples; high water might also make an otherwise suitable location for sediment sampling unavailable. A stretch of the river on the order of a few miles or so is generally needed to obtain adequate fish samples. The mile locations given above represent approximations of the locations about which the catches are taken. I i l r~s 4-14 Rev. 8, 1/94

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54atch ODCM

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i 1 Match ODCM O I

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i N Figure 4-4. Sampling Location Map seyond Site Periphery, East of Site 4-18 Rev. 8, 1/94

j l Hatch ODCM

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4-19 Rev. 8, 1/94

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                                                                                   . .      .   .r- - . .

Hatch ODCM

   )                                           CHAPTER S lV                                      TOTAL DOSE DETER >4! NATIONS 5.1      LIMIT OF OPERATION                          5,$ 4                                                l l

In accordance with Technical Specification .M:10L th dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar ye , due to releases of radio-activity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. 5.1.1 Aeolicability This limit applies at all times. 5.1.2 Actions With the calculated doses f rom the release of radioactive materials in liquid or gaseous ef fluents exceeding twice the limits of Section 2.1.3, 3.1.3, or 3.1.4, b calculations shall be made according to Section 5.2 methods to determine whether the limits of Section 5.1 have been exceeded. If these limtts have been 1 submit a S pecial eport e Nuclear Regulatory exceeded,

                                                                             '*     itntn 30 days, which         (

Commiss on, ,-r - * *- W '--1 r :, : : : f . : ;. . . . . ! uce bsequent releases to l defines he cor etive a ions to tak prevent recurrence of exceeding the limits of Section 5.1 and includes the schedule for achieving conf ormance with the limits of Section 5.1. This Special Re po rt , as defined in 10 CFR 20.2203, shall also include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from urantum fuel cycle sources (including all ef fluent patnways and direct radiation) for the calendar year that includes the release (s) covered by this report. This Special Report shall also describe the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the limits of Section 5.1, and if the release condition resulting in violation of the provisions of 40 CFR 190 has not already been corrected, the Special Report shall include a request for variance in accordance with the provisions of 40 CFR 190 and including the specified information of 40 CFR 190.ll(b) . Submittal of the report is considered l a timely request, and a variance is granted until staf f action on the request is

complete.

O When the ACTION statement or other requirements of this control cannot be met, I C steps need not be taken to change the operational Mode of the unit. Entry into 5-1 Rev. 8, 1/94

Hatch ODCM an Operational Mode or other specified CONDITION may be made if, as a minimum, (O} the requirements of the ACTION statement are satisfied. i 5.1.3 surveillance P.eeuirements Cumulative dose contributions from liquid and gaseous ef fluents and from direct radiation shall be determined in accordance with Section 5.2. This requirement is applicable only under the conditions set forth above in Section 5.1.2. , 5.1.4 Basis This control is provided to meet the dose limitations and reporting requirements of 40 CFR 190. The control requires the preparation and submittal of a Special j Report whenever the calculated doses from plant radioactive ef fluents exceed the limits of Section 5.1. For sites containing up to 4 reactors, it is highly ) unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the the dose lLmits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the units, such as direct exposure from outside storage tanks, are kept small. The Special l Report will describe a course of action which should result in the limitation of ;

 ~g dose to a MEMBER OF THE PUBLIC for a calendar year to within the 40 CFR 190            )
,,)  limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible with the exception that dose contributions from other uranium fuel         j cycle facilities at the same site or within a radius of 5 miles must be               l considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for variance (provided the release conditions resulting in violation of 40 CFR 190 have not        j already been corrected), in accordance with the provisions of 40 CFR 190.11 and       j 10 CFR 20.2203(a)(4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190 and does not apply in any way to the requirements for dose limitation addressed in other sections of this ODCM. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

O 5-2 Rev. 8, 1/94

l -

                                                    .                                        1 l      .                                                .                                     ;

I l I 1 Hatch ODCM 5.2 DEMONSTRATION OF COMPLIANCE There are no other uranium fuel cycle f acilities within 5 miles of the plant site. Therefore, for the purpose of demenstrating compliance with the limits of Section 5.1, the total dose to a MEMBER OF THE PUBLIC in the vicinity of the l plant site due to uranium fuel cycle sources shall be determined as follows: I Dn=DL+Da+Dp+DN (5.1) where: Dg = the total dose or dose commitment to the total body or organ k, in i mrom. l DL= the dose to the same organ due to radioactivity discharged from the plant site in liquid effluents, calculated in accordance with ) Section 2.4.1, in mram. I DO= the dose to the same organ due to non-noble-gas radionuclides O discharged from the plant site in gaseous ef fluents, calculated for the controlling receptor in accordance with Section 3.4.3, in mrom. 1 l DD= the direct radiation dose to the whole body of an individual at the l controlling receptor location, due to radioactive materials retained within the plant site, in mrom. Values of direct radiation dose may be determined by measurement, calculation, or a combination of the two. Dg = the external whole body dose to an individual at the controlling receptor location, due to gamma ray emissions from noble gas radio-nuclides discharged from the plant site in gaseous effluents, in mrem. Dg is calculated as follows (equation adapted from Reference 1, page 22, by re-casting in cumulative dose form): DN= 3.17 x 10-8 {v (g3,p { [g .g) jy + { [y . g ,) (5.2) i i ' l - l where ! p} >s 5-3 Rev. 8, 1/94 I

Hatch ODCM 3.17 x.lO-8 = a units conversion factor: 1 y/(3.15 x 10 7 s). 6jy = the cumulative release of noble gas radionuclide i from non-elevated release pathway v (yci), during the period of interest. 6; = the value of 6jy for the main. stack; that is, the cumulative release of noble gas radionuclide i from the main stack (pci), during the perLod of interest. Kj = the total-body dose factor due to gamma emissions from noble gas radionuclide 1 (mrom/y)/(pci/m 3), from Table 3-5. V; = the elevated finite-plume total-body dose factor at the controlling receptor location, due to gamma emissions from noble gas radionuclide i in ef fluents relsased from the main stack (mrom/y)/(yci/s), from Table 3-7. (i/Q)yp = annual average relative dispersion factor for release pathway v, at the location of the controlling receptor, from Table 3-7 [s/m3 ). As defined above, DL and Da are for different age groups, while DD and Dg are not age group specific. When a more precise determination of DTk is desired, values of DL and DG may be calculated for all four age groups, and those values used in equation (5.1) to determine age group specific values of DTk; the largest value of DT1 for any age group may then be compared to the limits of Section 5.1. 5-4 Rev. 8, 1/94

f . . l l Hatch ODCM l CHAPTER 6 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 6.1 REQUIREMENT FOR CALCULATION To support the reporting requirements of Section 7.2.2.3, an assessment of the radiation doses from radioactive liquid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 10-1) shall be performed as specified in Section 6.2, at least once per calendar year. 6.2 CALCULATIONAL METHOD For the purpose of performing the calculations required in Section 6.1, the dose to a member of the public inside the SITE BOUNDARY shall be determined at the locations, and for the receptor age groups, defined in Table 6-1. The dose to such a receptor at any one of the defined locations shall be determined as p follows: Dg =[D.+DS+Op) A To (6.1) l where Dg = the total dose to the total body or organ k, in mrem. DA= the dose to the same organ due to inhalation of non-noble-gas radionuclides discharged from the plant site in gaseous ef fluents, calculated in accordance with Section 3.4.3, in mrem. The (176) value to be used is given for each receptor location in Table 6-1; depleted (176) values may be used in calculations for non-noble-gas radionuclides. DS= the dose to the same organ due to around clane deoosition of non-l noble-gas radionuclides discharged from the plant site in gaseous j effluents, calculated in accordance with Section 3.4.3, in mrom. The (D76) value to be used is given for each receptor location in , Table 6-1. 6-1 Rev. 8, 1/94

  . _ . _ . _ _ . _ . -     ,.  . . . . _ _ . _ _ . - . - . . _ _ . . . . _   .m.. _ ._     _.       _      _

Hatch ODCM , f Dp =- the external whole body dose due to gamma ray emissions from noble gas radionuclides discharged from the plant site in gaseous effluents, calculated using equation (5.2), in mrom. The values

of - (X76) and Vi that are to be used are given for each receptor I location in Table 6-1. Fo= the occupancy f actor for the given location, which is the fraction of the year that one individual MEMBER OF THE PUBLIC is assumed to be present at the receptor location (unitless). Values of Fo for each receptor location are included in Table 6-1. l l l l l l l I l-i !O 6-2 Rev. 8, 1/94

1 \

l Hatch ODCM

 \'       Table 6-1.      Attributes of Member of the Public Receptor Locations Inside the SITE BOUNDARY Locations    Roadside Park, WNW at 1182 meters                                            l Ace Grount                   Child Occucancy Factor:            2.28x 10   (based on 2 hours per year)              )

Discersion and Deposition Parameters: i l Parameter Ground-Level Elevated l 1 Undepleted (176), s/m 3 7.83 E-6 2.42 E-8 Depleted (i76), s/m 3 7.00 E-6 2.37 E-8 (676), nc2 2.01 E-8 1.29 E-9 Elevated Plume Dose Factors:+ Yi Yi d Radionuclide (mrom/y)/(uci/s) Radionuclide (mrem /y)/(uci/s) Kr-85m 8.39 E-05 Xe-133m 1.32 E-05 Kr-85 1.31 E-06 Xe-133 1.37 E-05 Kr-87 4.60 E-04 Xe-135m 2.51 E-04 Kr-88 1.14 E-03 Xe-135 1.37 E-04 Kr-89 9.89 E-04 Xe-137 9.91 E-05 Kr-90 7.32 E-04 Xe-138 6.45 E-04 Xe-131m 1.70 E-06 Ar-41 7.69 E-04

Values from Reference 16.

             +    See footnotes to Table 3-6.                                                       i l

l l T

l _ 6-3 Rev. 8, 1/94

I Hatch ODCM

/%

Table 6-1 (contd). Attributes of Member of the Public Receptor Locations (' ') Inside the SITE BOUNDARY j Location: Camping Area, WNW at 1274 meters Ace Grouo Child j occupancy Factor: 5.48 x 10~3 (based on 48 hours per year) Discersion and Deposition Parameters 1 i Parameter Ground-Level Elevated j i Undepleted (i76), s/m 3 7.03 E-6 2.38 E-6 I Depleted (176), s/m3 6.27 E-6 2.33 E-8 I (676) , ac2 1.80 E-8 1.21 E-9 Elevated Plume Dose Factors:+ > 0 Radionuclide Yi (mrem /y)/(uci/s) 1 i Radionuclide Yi (mrem /y)/(uci/s) Kr-85m 7.84 E-05 Xe-133m 1.24 E-05 Kr-85 1.22 E-06 Xe-133 1.28 E-05 Kr-87 4.28 E-04 Xe-135m 2.34 E-04 Kr-88 1.06 E-03 Xe-135 1.27 E-04 Kr-89 9.19 E-04 Xe-137 9.23 E-05 l Kr-90 6.80 E-04 Xe-138 5.99 E-04 Xe-131m 1.59 E-06 Ar-41 7.14 E-04 l 1

Values from Reference 16.

t

             +    See footnotes to Table 3-6.

6-4 Rev. 8, 1/94

1

l Hatch ODCM Table 6-1 (contd). Attributes of Member of the Public Receptor Locations Inside the SITE BOUNDARY l l Location: Recreation Area, SSE at 1030 meters boe Groues Child occupancy Factor 2.37 x 10-2 (based on 208 hours per year) Discersion and Deposition Parameters Parameter Ground-Level Elevated Undepleted (176), s/m3 0.42 E-6 ' . 30 E-8 Depleted (176), s/m 3 5.73 E-6 3.21 u 8 (6/6), m*2 2.36 E-8 1.56 E-9 g Elevated Plume Dose Factors:+ l tr~~~\ i () Radionuclide V; Radionuclide Vj (mrem /y)/(uci/s) (mrem /y)/(uci/s) Kr-85m 7.21 E-05 Xe-133m 1.14 E-05 l Kr-85 1.13 E-06 Xe-133 1.17 E-05 Kr-87 3.99 E-04 Xe-135m 2.17 E-04 Kr-88 9.90 E-04 Xe-135 1.18 E-04 Kr-89 8.57 E-04 Xe-137 8.57 E-05 Kr-90 6.34 E-04 Xe-138 5.58 E-04 Xe-131m 1.46 E-06 Ar-41 6.66 E-04 j i

Values from Reference 16.

           +    See footnotes to Table.3-6.

4 6-5 Rev. 8, 1/94

Hatch ODCM 4 I ( Table 6-1 (contd). Attributes of Member of the Public Receptor Locations Inside the SITE BOUNDARY l Location: Visitors Center, WSW at 694 meters Ace Grouo Child Occuoancy Factors 4.57 x 10 4 (based on 4 hours per year) Dispersion and Deoosition Parameters: Parameter Ground-Level Elevated Undepleted (X7D), s/m3 1.87 E-5 5.00 E-8 Depleted (i~/D) , s/m 3 1.72 E-5 4.97 E-8 1 (67D), m 2 5.47 E-8 2.26 E-9 Elevated Plume Dose Factors + h Radionuclide V; Radionuclide Vi (mrem /y)/(uci/s) (mrem /y)/(uci/s) Kr-85m 1.47 E-04 Xe-133m 2.34 E-05 Kr-85 2.34 E-06 Xe-133 2.36 E-05 Kr-87 8.27 E-04 Xe-135m 4.49 E-04 Kr-88 2.06 E-03 Xe-135 2.42 E-04 Kr-89 1.78 E-03 Xe-137 1.77 E-04 ) 1 Kr-90 1.31 E-03 Xe-138 1.16 E-03 Xe-131m 2.98 E-06 Ar-41 1.38 E-03 l

Values from Reference 16.

          +    See footnotes to Table 3-6.

6-6 Rev. 8, 1/94

l Hatch ODCM CHAPTER - PEPOPTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 7.1.1 Peautrement for Reoort 54 b In accordanc f with me% Technic 1 pecificatio '.0.1.: t Annual Radiological activities during . the Environmen 1 " " - ~ ! 1 1 _.. a R et coverin be submitte _:_::: :% -; each year. (A single previous ca r The m erial provided shall report fulfills the requirements for b h units ) be consistent with the objectives out ined in action 4.1 a d Section 7.1.2 of the ODCM, and in Sections IV.B.2, IV.B. , an IV.C of Appendi I to 10 CFR Part y 1%y /S 7.1.2 Pecort Contents The materials specified in the fol tions shall be included in each 9 -"aii'* - Re t: Annual Radiological Environment rh 7.1.2.1 Data The report shall include sumt.arized and tabulated results of all RE.MP samples required by Table 4-1 taken during the report period, in a f ormat similar to that contained in Table 3 of tne Radiological Assessment Branch Technical Posttien (Reference 18); the results for any additional samples shall also be reported. In the event that some results are not available f or inclusion with the report, the report shall be submitted noting and explatning the reasons for the missing results; the missing data shall be submitted as soon as possible in a supplementary report. The results for naturally-occurring radionuclides not included in plant offluents need not be reported. 7.1.2.2 Evaluations Interpretations and analyses of trends of the results shall be included in the report, including tne following: (as appropriate) comparisons with pre-controls, and previous environmental operational studies, operational surveillance reports; and an assessment of any observed impacts of the plant operation on the environment. If the measured level of radioactivity in an ' environmental sampling medium exceeding the reporting levels of Table 4-2 is not the result of plant of fluents, the condition shall be described as required by l n) section 4.1.1.2.2. Rev. 8, 1/94 7-1

           ..             ~ - - - . ~ . .    .-        . . -    .    . .       .-    .. -     . . .
   .                                                         .                                      I Hatch ODCM 7.1.2.3         Programmatic Information l

Also to be included in each report are the followings a summary description of j l the REMPs a map (s) of all sampling locations keyed to a table giving distances and directions from the main stack; the results of land use censuses required by section 4.1.2; and the results of licensee participation in the Interlaboratory Comparison Program required by Section 4.1.3. [The report shall include either a summary of the results obtained as part of the required Interlaboratory Comparison Program or, for licensees participating in the EPA cross-check , program, the EPA program code designations for the plant.) 7.1.2.4 Descriptions of Program Deviations I Discussions of deviations from the established program must be included in each l report, as follows: 7.1.2.4.1 If the REMP is not conducted as required in Table 4-1, a description of the reasons for not conducting the program as required, and the i ! plans for preventing a recurrence, must be included in the report. i 7.1.2.4.2 If the MDCs required by Table 4-3 are not achieved, the contributing factors must be identified and described in the report. 7.1.2.4.3 If Interlaboratory comparisoo Program analyses are not performed i as required by Section 4.1.3, the corrective actions taken to prevent a recurrence must be included in the report. i l l l 7-2 Rev. 8, 1/94

Hat,e* 4 1.2 ANNUAL RADIOACTIVE EFFLUENT RELE ASE REPORT p Au* p.34 5-Pecuire-ent for Pecort gf4 , 7.2.1 t.^ '

                                                                  *; the h .i          dioactive In accordance with Technical Spec i f icat i Ef fluent Release Report covering the opera ion of the units during t e previous calendar year of operation shall be sub tted -.w.-              n.y .w    usm fa.

However the subm' all single submittal may be made for Units 1 and . nd gas af fluents f rom specify the releases of radioactive material in 1. each unit and solid radioactive waste f rom the site. ) The report shall include a summary of the quantities of radioactive liquid and gaseous ef fluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined throughout this ODCM and the Process Control Program (PCP) and in conformance with 10 CFR Part 50.36a and section IV.B.1 of Appendix I to 10 CFR Part 50. 7.2.2 Report Contents 7.;,werials specified in the following sub-sections snail be included in each

        ' - - '  R dioactive Effluent Release Report 0

5 7.2.2.1 Quantities of Radioactive Materials Released The report shall include a summary of sne quantattes cf radioactive liquid and gaseous effluents and solid waste released f rcm the units as outlined in NRC Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Caseous Ef fluents f rom Light-Water-Cooled Nuclesr Power Plants," Revision 1, June 1974, with liquid and gaseous ef fluent data sumtnarized on a quarterly basis and solid radioactive waste data summarized on a semiannual basis following the format of Appendix 5 thereof. The report shall include documentation of quantities of radioactive materials in unplanned releases of gaseous and liquid ef fluents f rom the site to UNRESTRICTED AREAS, tabulated either by quarter or by event, provided thatt such liquid releases exceeded 1 ci, excluding tritium and dissolved or entrained noble gases; or such gaseous releases exceeded 150 Ci of noble gases or 0.02 Ci of radioiodines. For gamma emitters released in liquid and gaseous effluents, in addition to the principal gamma emitters for which MDCs are l 3-3, other peaks which are f specifically established in Table 2-3 and Table t i measurable and identifiable also shall be identified and reported. I I r 1 7-3 Rev. 8, 1/94

i Hatch ODCM Meteorological 'ata l(O) 7.2.2.2 The report shall include an annual summary of hourly meteorolegical data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wtnd speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of direction, and atmospherte joint f requency distributions of wind spo In lieu of submission with e A, . . . . R dioactive Ef fluent Release stability. ng this summary of required Report, the licensee has the option o A meteorological data on site in a file that shall be provided to the NRC upon request. 7.2.2.3 Dose Assessmente The report shall include an assessment of the radiation deses due to the radioactive liquid and gaseous effltsents released from each unit during the previous calendar year. Historical annual average meteorology or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and This measurement) shall be used for determining the gaseous pathway dese. assessment of radiation doses shall be performed in accordance with Sections 3.1.4, 3.4.2, 3.4.3, 5.1, and 5.2. V 2.1.3, 2.4, 3.1.3, If a determination is required oy Section 5.1.2, tne report snall also snelude an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearoy uranium fuel cycle sources (including l doses from primary ef fluent pathways and direct radiation) for the previous calendar year to show confermance with 40 CFR 190, Environmental Radiation be Protection Standards for Nuclear Power Operation; this dose assessment must

5. The report shall also include an ,

performed in accordance with Chapter assessment of the radiation doses f rom radioactive liquid and gaseous ef fluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE SOUNDARl (Figure 10-1) during the report period; thic assessment must be performed in accordance with Chapter 6. 7.2.2.4 Solid Radwaste Data For each type of solid waste shipped of f site during the report period, the following information shall be included: I

a. Container volume, n Total curie quantity (specify whether determined by measurement of b.

{) ..ttmat.3, Rev. 8, 1/94 7-4 i

r 1

     ~                                                   .

Heten ODCM f

c. Principal radionuclides (specify whethor determined cy reasarerent or estimats),

compacted dry waste, evaporator

d. Type of waste (e.g., spent restn, bottoms),

Type B, Large Quantity), and ! e. Type of container (e.g., LSA, Type A,

f. Solidification agent (e.g., cement, urea formaldehyde.)

l 7.2.2.5 Licensee Initiated Document Changes

e Nuclear Regulatory Licensee initiated changes shall be submitted " - --- ." adioactive Effluent Commission as a part of or concurrent with tt I j de. Such
nges to j Release Report for the period in which any chan r,4 2 This the ODCM shall be submitted pursuant to Technical Specificati n

55. /.

requirement includes: locations in the radiological 7.2.2.5.1 Any changes to the sampling I environmental monitoring program, including any enanges made pursuant to Section 4.1.1.2.3. Documentation of changes made pursuant to Section 4.1.1.2.3 shall include supporting inf ormation identif ying the cause of the unavailability of samples. g 7.2.2.5.2 Any changes to dose calculation locations or pathways, including any changes made pursuant to Section 4.1.2.2.2. 7.2.2.6 Descriptions of Program Deviations Discussions of deviations f rom the established program shall be included in each report, as follows: 7.2.2.6.1 The report shall include deviations from Minimum Detectable concentration (MDC) requirements included in Table 3-3. 7.2.2.6.2 The report shall include deviations from the liquid and gaseous ef fluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, re spectively. The report shall include an explanation as to why monitoring instrumentation l the inoperability of the liquid or gaseous ef fluent was not corrected within the specified time requirement. (This requirement does not include the Service Water System to Closed Cooling Water System Dif ferential Pressure channel.) conten ithin a ' 7 . p awns p inct outside temporary tank exceed the limits of Technical Specification 4.l' L4 (-} u -- = ....I w.i: u.. .=. : . u v ::= te v f, S. W. b.

              ;i 7-5 Rev. 8,  1/94 i

l l Watch ODCM r i 7.2.2.7 Ma)cr Changes to Radicactive Waste Treatment Systems f . _, s ; 1 ' As required by Sections 2.1.5 and 3.1.6, licensee initiated MA.*CR CHANCES TO i and gaseous) shall be reported to the RADIOACTIVE WASTE TREATMENT SYSTEMS

                                                       ._;t P dioactive Ef fluents Felease Repcrt Nuclear Regulatory Commission in t .e "                                                         '

covering the period in which t e change was reviewed and accepted for implementation.I The discussion of each change shall contain:

a. A summary of the eval ation that led to the determination that the 50.59; change could be made in accordance with 10 CFR Part J

b. Sufficient detailed information to totally support the reason f or the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems; An evaluation of the change, which shows the predicted releases of d.

radioactive materials in liquid and gaseous ef fluents that dif f er f rom I those previously predicted in the license application and amendments {,

  / '                    thereto; Nu ]/

e. An evaluation of the change, which shows the expected maximum exposures ,

to a MEMBER OF THE PUBLIC in the UNRESTR CTED AREA and to the general population that dif f er f rom those previously estimated in the license appl .ation and amendments tnereto; in

f. A comparison of the predicted releases of radicactive materials, liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made; g.

An estimate of the exposure to plant operating personnel as a result of the change; and the change was reviewed and found

h. Documentation of the fact that acceptable by the Plant Review Board.

i 1 r ['" dioactive Ef fluents Release Report,

. \s /        I      In lieu of inclusion in t e -A. . - " r ' ed as part of the annual FSAR update.
'                    this same information may 7-6 Rev. 8,  1/94 l

Hatch ODCM

    - 7.3      MONTHLY OPEPATING REPORT This CDCM establishes no requirements pertaining to the Monthly operating Report.

7.4 SPECIAL REPORTS V Special reports shall be submitted to the Nuclear Regulatory Commission sw=

                               .........1!;;;-........'
                                                           $ 9- as required by Sections 2.1.3.2 2 r - . . . ... . w u n
                                   '      3.1.        .    .2. and     . .

2.1. , 3.1. , , . J i 1 l I 4 ., l s 4 4 1 4 i l 1 1 d 't i ) 4 3 Rev. 8, 1/94 7-7 i

                                                                                                     .. i

l l 1 ! Hatch ODCM O CHAPTER 8 METEOROLOGICAL MODELS I The models presented in this chapter are those which were used to compute the j specific values of meteorology-related parameters that are referenced throughout this ODCM. These models should also be used whenever it is necessary to j calculate values of these parameters for new locations of interest. j i 1 Note 1: When calculating values of annual average parameters for new locations, use the joint f requency meteorological data presented in Reference 28. Those are the data which were used to compute the specific values of meteorology-related parameters that are referenced throughout this ODCM. Note 2: Although Plant Hatch has no mixed-mode releases, the sections on mixed-mode calculations (8.1.3 and 8.2.3) are included to preserve section number compatibility with the ODCMs of the other Southern company nuclear power plants. 8.1 ATMOSPHERIC DISPERSION Ip\ V Atmospheric dispersion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations j for each gaseous release point are as indicated in Table 3-4. l 8.1.1 Ground-Level Releases Relative concentration calculations for ground-level releases, or for the ground-level portion of mixed-mode releases, shall be made as follows: l 2.032 6 K r Mjk (X/0)g = { gg,g) N r ,.g UJ E:k where: (X/Q)g = the ground-level secter-averaged relative concentration for a given wind direction (sector) and distance (s/m 3), n 2.032 = (2/n)II2 divided by the width in radians of a 22.5" sector, which is 0.3927 radians. i l l 8-1 Rev. 8, 1/94 I i i

j Hatch'ODCM 6= the plume depletion factor for all radionuclides other than noble 1 gases at a distance r shown in Figure 8-3. For noble gases, the depletion f actor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered. i Kr= the terrain recirculation factor corresponding to a distance r, taken from Figure 8-2. njk = the number of hours that wind of wind speed class j is directed j into the - given sector during the time atmospheric stability ' category k existed. l N= the total hours of valid meteorological data recorded throughout the period of interest for all sectors, wind speed classes, and ! stability categories. uj = the wind speed (mid point of wind speed class j) at ground level (m/s). [3 , V r= the distance from release point to location of interest (m). Id= the vertical standard deviation of the plume concentration t distribution considering the initial dispersion within the building wake, calculated as follows:

                                                                                '2           b2 'l/2

[d 25. 0*O Eg = the lesser of s og O(od) 4 i og = the vertical standard deviation of the plume concentration distribution (m) for a given distance and stability category k as shown in Figure 8-1. The stability category is determined by the l' vertical temperature gradient AT/Az (*c/100 m). l l vr = 3.1416 b= the maximum height of adjacent plant structure (47 m). 8-2 Rev. 8, 1/94 ;

1 l . Hatch ODCM 8.1.2 Elevated Releases

Relative dispersion calculations for elevated releases, or for the elevated l portion of mixed-mode releases, shall be made as follows

1 1

-h

2. 032 K,. 6k Djk exP 2 (s.3) l (X/0)E "

                                       " #      E                   ,2 o,y,

? jk U l J *:k wheres I (X/Q)E = the elevated release sector-avaraged relative concentration for a given wind direction (sector) and distance (s/m )3 . 1 i 6k= the plume depletion factor for all radionuclides other than noble gases at a distance r for elevated releases, as shown in , j Figure 8-4, Figure 8-5, and Figure 8-6. For an elevated release, 'O this f actor is stability dependent. For noble gases, the depletion U factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered. njk = the number of hours that wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed. uj = the wind speed (mid-point of wind speed class j) at the effective release height h (m/s). l

h= the effective height of the release (m), which is calculated as , follows:I i i h=h - y hg (8.4) 1 Effective release height may be further adjusted for plume rise in accordance with Section E.4.3.2 of Appendix E to Reference 7. l l 8-3 Rev. 8, 1/94 , 1 l l

l l Hatch ODCF. A h hy = the height of the release point (m), which is the height of the main stack, 120 m. I ht= the maximum terrain height isotween the release point and the point of interest (m), from Figure 2.3-12 of Reference 8. l 1 All other symbols are as previously defined in section 8.1.1. I 8.1.3 Mixed-Mode Releases Relative dispersion calculations for mixed-mode releases shall be made as follows: (X/0)y = (1 -E) * (X/0)E

E"(X/0)G (8.5) where:

(X/Q)M = the mixed-mode release sector-averaged relative concentration for a given wind direction (sector) and distance (s/m 3).

  ,e E=       the fraction of hours during which releases are considered as ground-level releases, calculated as follows:

W 1.0 for # s 1. 0

")

W# W 2.58 - 1.58 - -. f or 1. 0 < - # 51.5

                                                           ").                        ")

E = ' (8.6) I W# W ' O.3 - 0.06 * -. for 1. 5 < _# s 5. 0

                                                         "}s                          ")

W O for # > 5.0

")

All other symbols are as previously defined. O V 8-4 key. 8, 1/94

   ..           --         ~           .         -       -             .   -.

Hatch ODCM 8.2 RELATIVE DEPOSITION Plume depletion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be ! either at ground-level, elevated, or mixed-mode. Facility release elevations for : each gaseous release points are as indicated in Table 3-4. 8.2.1 Ground-Level Releases Relative deposition calculations for ground-level releases, or for the ground-level portion of mixed-mode releases, shall be made as follow.; 2.55 D g K r (D/0)g = N r {g nk (8.7) where: (D/Q)g - th*: ground-level sector-averaged relative deposition for a given , I wind direction (sector) and distance (m-2), f 2.55 = the inverse of the number of [= (2 n/16)-l). radians in a 22.5* sector Dg = the deposition rate at distance r, taken from Figure 8-7 for ground-level releases (m-I) . nk = the number of hours in which the wind is directed into the sector of interest, and during which stability category k exists. All other symbols are as defined previously in Section 8.1. 8.2.2 Elevated Releases Relative deposition calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows: 2.55 K (D/Q)E " N r b (Uk Dek) (8.8) y O 8-5 Rev. 8, 1/94

r Hatch ODCM (D/Q)E = the elevated-plume sector-averaged relative deposition for a given wind direction (sector) and distance (m-2), Da = the elevated plume deposition rate at distance r, taken from Figure 8-8, Figure 8-9, or Figure 8-10, as appropriate to the plume ef fective release height h defined in Section 8.1.2, for stability class k (m-I) . All other symbols are as defined previously. l 8.2.3 Mixed-Mode Releases Relative deposition calculations for mixed-mode releases shall be made as follows: (D/0)y = (1 -E) * (D/0)E + E * (D/0)G (s.9) where: l (D/Q)M = the mixed-mode release sector-averaged relative deposition for a given wind direction i. sector) and distance (m-2). E= the fraction of hours durin? which releases are considered as ground-level releases, defis.d in Section 8.1.3. All other symbols are as previously defined. i 4 l i l I 8-6 Rev. 8, 1/94

   .                                                          .                                                   1 Hatch ODCM 8.3    ELEVATED PLUME DOSE FACTORS Certain gaseous ef fluent dose calculations require the use of the elevated-plume noble gas dose parameters Bj or Vj, which are first defined in Section 3.4. These parameters are calculated as follows:

A'S " a Eg

Ik ,(r) yI , K { NN t uj (s l0}

rN j.k,e l i Mjk

Act * #8e *E *Ike (r) -( T, d) y5 , 1.1 K [ e , (,,11 l

")

rN ),k.e l l where K= a numerical constant representing the aggregated numerical constants and unit conversions, 2.1 x 10 4. Ag= g the number of photons in energy group e emitted per transformation of radic,nuclide 1 (number / decay) . l y a, = the air energy absorption coefficient for photons in energy group e (m-I). E, = the photon energy assigned to energy group e (MeV). Ike (r) = the (dimensionless) result of integrating the emission and attenuation of photons of energy group e, over the entire spatial activity distribution of a plume that has spread under atmospheric stability classification k, for a dose receptor at downwind distance r (see below for calculational method). 1.1 = the average ratio of the photon energy absorption coef'.icient for tissue to that of air over the energy range of iraterest. This ratio converts air dose (rad) to dose equivalent (rem).

,k 8-7 Rev. 8, 1/94

l . . I 1 l Hatch ODCM l O (j yT, = the tissue energy absorption coefficient for photons in energy l group e (cm 2fg3, d= the tissue <*ansity thickness taken to represent the depth at which j total body dose is received (5.0 g/cm 2). ; l All other symbols are as previously defined. l For a sector-averaged plume model like that described in Section 8.1, the dose l integral Ike (r) is calculated as follows: l oo ao 1 Ig (r) = ffBg(p,, pa,, R) x G( z, k, r) x A(p , R) x L dL dr g (8.12) 2 O z O O where , l i L= the upwind or downwind distance from the differential volume element of the plume to the dose receptor point. I f"'t l z= the vertical distance from the differential volume element of the plume to the dose receptor point. l R= the total distance from the differential volume element of the I plume to the dose receptor points R = L2+z2 l l B g= the air dose buildup factor through a thickness R of air t

                                                                   -ya,)     y, I

B = 1+ (#4 xR 8 p a, l \ l l l p, = the total photon attenuation coefficient in air, for energy group e (m-I). G= the function describing tt2 vertical distribution of activity in a plume that has travelled dcwnwind a distance r from the point of emission, at an ef fective height h, under stability classification f 8-8 Rev. 8, 1/94

Hatch ODCM O G = exp - ( -h)2 + exp -(#*h) 2 2 2 og 2 og I A= the attenuation and geometric loss factor for photons in energy x group c, for the distance R from the differential plume volume l element to the dose receptor point l exp{p,RJ R1 l 1 2tr L dL dz = the volume of the dif ferential plume element. (When the 2n i is factored out into the constants in equations (8.10), (8.11), and (8.12), only L dL dz is left.) l l All other symbols are as previously defined. A derivation of the model describing the gamma dose rate from an elevated finite l I plume is found in Chapter 7 of Reference 19. Numerical methods for evaluating the dose integral are found in Appendix F of Reference 3. Details of the numerical methods used there may be found in Reference 20. i t i 8-9 Rev. 8, 1/94

Hatch ODCM Table 8-1. Terrain Elevation Above Plant Site Grade l l This table intentionally left blank. l l i 1 8-10 Rev. 8, 1/94

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

Hatch ODCM l 1000 - I ' X \ i / J '/I i / /* je s / *

                                                                    /              i/t              ii6 i                      / t         i                     I
                                                                  /                t/ t              t     l l         /          I      i                          -
                                                                /                 /           I I              l /                  I                 /'                              j
                                                             )                /               \              /                               /

l f / \ / l/ I

                                                       /                /                       /

l , - - " 100 A

                                                    /            l
                                                                    /
                                                                                      /                      ,
                                                                                    ,             ,f                ,                ;           ,.

b

                                            /         ,F          ,F                t      j' i              j'                         2" s     t        .c    .     /                    t/             /                            /

g / / 7 A/\ ., - ~ 5 / / / of/\ / / k / (( /h[ A / l l

                        /             / , / , / / ,'

to 1 1

                                        ,/          -

1

                         / /
                             //              /            /                                     ,                                            i I
                                         /           /                                          <
                                                                                                                                                                                        \
                            /         /         /                                               6 l
                               /1 /                                                             l l
                         ' X
                         /

I l

                      ' o.1                                        1.o                                                    to                                           100 PLUME TRAVEL DISTANCE (KILOMETERS)

Range of Vertical Range of Vertical Category Temperature Gradient Temperature Gradient ('C/100 ml ('F/100 ft) A AT/AZ < -1.9 AT/AZ < -1.0 5 -1.9 s AT/AZ < -1.7 -1.0 s AT/AZ < -0.9 , c -1.7 5 AT/AZ < -1.5 -0.9 s AT/AZ < -0.8 D -1.5 s AT/AZ < -0.5 -0.8 s AT/AZ < -0.3 J E -0.5 s AT/AZ < 1.5 -0.3 s AT/AZ < 0.8 i F 1.5 s AT/AZ < 4.0 0.8 s AT/AZ < 2.2 l G 4.0 s AT/AZ 2.2 s AT/AZ O This graph is reproduced from Reference 5 (Figure 1). Figure 8-1. Vertical Standard Deviation of Material in a Plume (og) i 8-11 Rev. 8, 1/94

Hatch ODCM O to

                                                  .          .                   ,     i      ,                   , , , , .
                        .      I      1   I 4 . 4 ll         4          4    1 I it I , $             %           6     jl t i      l      I I i i lin              i         I l 414 lit                  i           i I l I      l I i llI11 \ l                          l l l l llll                  l           l ll g               I       l l l lllll               \I                        l      l           l          l g                                                              N      \

O m % 1 \ l % 1 M e , , , , . . . . . . . , , .,... , , , , .

          $                .      .i            . .i.            .        . . . i,,,                          ,      i..

u i i i i i i Ill I i l i iilil I i i i 1 I I Illli I I I llilli i l i i l I lllll l l lll llll \ ll 0.1 -- ei 1.0 to tes OtBTA8eCE IKILoneETEfts! l O This graph is reproduced from Reference 4. Figure S-2. Terrain Recirculation Factor (Kr) 8-12 Rev. 8, 1/94

_ __ . m .. m _.. .._ _. . _ _ ~ _ _ . _ . . . . . _ _ l...- . . l l l Match ODCM r , l [ t l l IM o.s ! N s i g o.s - ! = i i 's I g z o.71 i l \ N l l . h 2 c.s I I l

                                         '                                      l               h    \

m I l

                                                                                                         ~%
                                                                                                              \

l\ t l" ss

g o.4 o.s o. I' o.1 I 01 1.: ioA 100.0 2004 PLLaME TRAVEL DISTANCE (KILOMETERS) i I i i This graph is reproduced from Reference 5 (Figure 2). Figure 8-3. Plume Depletion Effect for Ground Level Releases 8-13 Rev. 8, 1/94

r . .

e l

l I ! Hatch ODCM

O l

l l j i l ! I 1.0 0.3 NE RA (D E.F,0) w 0.8 E2* - 5 0., I A\a l j 0.0 UNETAsLE (A3,c3 g %g1 i g , i lOA \N,N , ! l l

0.4 '

l 1 OJ NN 1 l 0.2 l l 0.1 0.1 1A 10A 100A' 200A PLUME TRAVEL DISTANCE (KILOMETERS) l l 4 This graph is reproduced from Reference 5 (Figure 3). Figure 8-4. Plume Depletion Effect for 30-Meter Releases 8-14 Rev. 8, 1/94 I

l

i I Hatch ODCM t.o sTASLE ', I I III t%m 'N;% i l i t""

            . o.                                                                        I","of a                   i                                               w w I

h 0.7 UNSTAS N jg o.s (A,Rf4

             !g o.s                                                                                 \\

l

h\

           '$ os
              ' o.:

0.2 0.1 I o.1 1.0 10A 100.0 2tRA PLUME TRAVEL O!aTANCE (KILOMETER 83 i I i l i I ( This graph is reproduced from Reference 5 (Fiy .e 4). Figure 8-5. Plume Depletion Effect for 60-Meter Releases 8-15 Rev. 8, 1/94

l - Match ODCM O () l l l 1 ! 1 I 12

                                                                                % %                                              )

03 l % u NEUTRAL (D) i

                                                                                      % %                                        I f                               w 0.8                                                              \    m

! UNSTABLE \ ! I 0.7 IAM3 A \ ' j STABLE (E.F.Ol' \ l 50.8 NO DEPLETION q \ l 6 h

                               $ 03 (FRACTION REMAINING = 1.01
                                                                                                             \
                                                                                                               \
                                                                                                                      \          l h                                                                                  \              '

gOA \ 03 1

OJ I O.1 l l O1 1.0 102 togy gogg I PLLIME TRAVEL DISTANCE (KILOMETERS) l l l [ I i i o I 1 l

    ,x k                                    This graph is reproduced from Reference 5 (Figure 5).

Figure S-6. Plume Depletion Effect for 100-Meter Releases 8-16 Rev. 8, 1/94 l

Hatch ODCM 104 10-4 \ .m i s e ' ~~ w 2 I \

          $                    I                 (

S %

          $                                           \

5 %

                                                            %g f10-6
                                                                -m E                                                        N s

2 w _ x , Q A w 2 \ S E g

                                                                                    \ %

g m 1 0 - 53 4 10-7 0.1 1A 10.0 100.0 200A PLUME TRAVEL DISTANCE (KILOMETERS) This graph is reproduced from Reference 5 (Figure 6). Figure S-7. Relative Deposition for Ground-Level Releases 8-17 Rev. 8, 1/94

? I Hatch ODCM

O d

103 J 'I J ) UNSTABLE (AA4:1 104 a sN I i 2 m 7 1 r x n r 'w W -g 3

                     ,                               f        &

E I \\ NEUTRAL

E

z / NN

r NEUTRAL (D) '

y g h10-6 L STABLE

                                                                                         'v 4

Of = ,/ m x < s , - m s

- I / vu 5 / r x x

2 / / N %

j N w q [ STABLE (E,F,G) 5 A f I I I

!                                                                             I I

b h i /

10-7: 0.1 1.0 10A 100A 200A
PLUME TRAVEL DISTANCE (KILOMETERS) .

l l r I O This graph is reproduced from Reference 5 (Figure 7). Figure 8-8. Relative Deposition for 30-Meter Releases i l 8-18 Rev. 8, 1/94 ( ! l

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

l 1 Match ODCM O i 104 l l - i _ #% UNSTABLE {AA.C) [ \ ll l w j f '% 10-6 , ,

                                                                                 /         NEUTRAL (D)                          h(
                                                                                                                                 ,m 5                         b                                           f             %

w s i s . < x H I / 6 s NW

                             $                                         /                                          I l                                   \ ^           %       UNSTAPLE
                             $                                        /                                           I l                                         A                 N
                                                                     !                                            I                                  NEUTRAL                               \

3 f N N

                             $104 e                     c i;i 1                                                        .                                                           i e                                l                                                                                                                 l E                                I                                                                                                              )

W f ; E e [ l l m 10-7 STABLE (E F.G) l , . f 1 l j f i e i j i , e i e i l i i t i I i i / II I I / f Id 1 0.1 1.0 10A 100.0 200A PLUME TRAVEL DISTANCE (KILOMETERS) l I t This graph is reproduced from Reference 5 (Figure 8). Figure S-9. Relative Deposition for 60-Meter Releases 8-19 Rev. 8, 1/94

i . . l Hatch ODCM l0 l l l l l l 104 l l l __. _ UNSTABLE (A,B,C)! C

                                                      /                        A N
                                                                                       \

N 10-5 ,

                                           ;                                     f%L
                                          /                                  /            ,
                                                                                                        'b ,a g                           I                                 e i        i ,                                       i

! $ [ ' [NE' UTRAL (D) N g E / I / \ ' N 5 / / N N s B a

                                   /                                /                                                         N Ns 4  ,
                                                                  /

'bl 10-6 ) iQJ ;; l l l

l l E ' '

o / J g / / ! P

4 a l E STABLE (E,F,G) , NO DEPLETION 10-7 ; I i! k I ; I I f I l

                                           /             I 10-8 0.1                                         1.0                                    10A                     100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

O This graph is reproduced from Reference 5 (Figure 9). Figure 8-10. Relative Deposition for 100-Meter (or Greater) Releases 8-20 Rev. 8, 1/94 l _ _ _ _ _

Hatch ODCM CHAPTER 9

                             ' METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUFNT PATHWAY DOSE FACTORS. R aipj 9.1 INHALATION PATHWAY FACTOR 3 -

For the inhalation pathway, Rapj j in (mrom/y) per (yci/m g is calculated as follows (Reference 1, Section 5.3.1.1): R aipj = Kg * (BR)a * (DFA)aij (9*1) I where: Kg = the units conversion factor: 106 pC1/pci. 3 (BR), = the breathing rate of receptor age group a, in m /y, from p Table 9-5. t . (DFA)aij = the inhalation dose factor for receptor age group a, radionuclide 1, and organ j, in mrem /pci, from Table 9-7 through Table 9-10. I l ?

9-1 Rev. 8, 1/94

r

     ~                                                .

Hatch ODCM 9.2 GROUND PLANE PATHWAY FACTOR For the ground plane external exposure pathway, R,;pj in (m *2mrem /y) per (pci/s) is calculated as follows (Reference 1, Section 5.3.1.2):

                                                                                -Af t R aip)

Kg
K2 * (SHF) =

(DFG);; * (9*2) s t s where: i Kg = the units conversion factor: 106 pctypct, Kg = the units conversion factor: 8760 h/y. (SHF) = the shielding factor due to structure (dimensionless). The value used for (SHF) is 0.7, from (Reference 3, Table E-15).

O (DFG)jj = the ground plane dose f actor for radionuclide i and organ j, in (mrem /h) per (pci/m 2), from Table 9-15. Dose factors are the same for all age groups, and those for the total body also apply to all organs other than skin. lj = the radioactive decay constant for radionuclide i, in s -I. Values of 1 used in ef fluent calculations should be based on decay data from a recognized and current source, such as Reference 26. I t= the exposure time, in s. The value used for t is 4.73 x 10 8 m (= 15- y), from (Reference 1, Section 5.3.1.2). 4 L l 9-2 Rev. 8, 1/94

9.3 GARDEN VEGETATION PATHWAY FACTOR For radionuclides other than tritium in the q=rden vegetation consumption pathway, R,j 2 p j in (m = mrem /y) per (pci/s) is calculated as follows (Reference 1, Section 5.3.l.5): R alpj " # Kg * * (DFL)ajj Y v(A+A) l w (9.3)

                                                       'L , gg g g , ~hi 'hv val fL*

where: Kg = the units conversion factor: 106 pCi/pci. r= the fraction of deposited activity retained on the edible parts of garden vegetation (dimensionless). The value used for r is 1.0 for radiciodines and 0.2 for y) particulates, from (Reference 3, Table E-1). Yy = the areal density (agricultural productivity) of growing leafy garden vegetation, in kg/m2 , from Table 9-1. A = the radioactive decay constant for radionuclide i, in s *I. Values of 1; used in ef fluent calculations should be based on decay data from a recognized and current source, > such as Reference 26. Aw= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-I, from Table 9-1. (DFL),jj = the ingestion dose factor for receptor age group a, , 1 radionuclide i, and organ j, in mrem /pci, from Table 9-11 I through Table 9-14. Ug = the consumption rate of fresh leafy garden vegetation by a receptor in age group a, in kg/y, from Table 9-5. v i I 9-3 Rev. 8, 1/94 l 3

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

l i Hatch ODCM Us= a the consumption rate of stored garden vegetation by a receptor in age group a, in kg/y, from Table 9-5. ft= the fraction of the annual intake of fresh leafy garden vegetation that is grown locally (dimensionless), from Table 9-1. f g= the fraction of the annual intake of stored garden vegetation that is grown locally (dimensionless), from l Table 9-1. tt= the average time between harvest of fresh leafy garden vegetation and its consumption, in s, from Table 9-1. l l thy = the average time between harvest of stored garden vegetation and its consumption, in s, from Table 9-1. , I l For tritium in the garden vegetation consumption pathway, Raipj in (mrem /y) per (pci/m3 ) is calculated as follows (Reference 1, Section .5. 3.1. 5 ) , based on the concentration in air rather than deposition onto the grounds Rapjj = Kg

K3 * ( D FL )aij *(Ual fL
UaS fg )
O 'S * (9 4) where: l K3= the units conversion factor: 103 g/kg.

I H= the absolute humidity of atmospheric air, in g/m3 , from Table 9-1. O.75 = the fraction of the mass of total garden vegetation that l is water (dimensionless). 0.5 = the ratio of the specific activity of tritium in garden l vegetatO)n , water to that in atmospheric water (dimensionless). and other parameters are as defined above. 9-4 Rev. 8, 1/94

Hatch ODCM p ( Table 9-1. Miscellaneous Parameters for the Garden Vegetation Pathway The following parameter values are for use in calculating Raipj for the garden vegetation pathway only. The terms themselves are defined in Section 9.3. Parameter Value Reference Yy 2.0 kg/m2 Ref. 3, Table E-15 A,g 5.73 x 10*7 s *I Ref. 1, p&ge 33 (14-day half-life) ft 1.0 Ref. 1, page 36 f 0.76 Ref. 1, page 33 g tt 8.6 x 104 s Ref. 3, Table E-15 (1 day) 5.18 x 106 s ( t hy Ref. 3, Table E-15 (60 days) H 8 g/m 3 Ref. 3 1 i l 9-5 Rev. 8, 1/94 i l

 ~                                              .

Hatch ODCM 9.4 GRASS-COW-MILK PATHWAY FACTOR For radionuclides other than tritium in the grass-cow-milk pathway, ap Rjj in (m2 mrom/y) per (pci/s) is calculated as follows (Reference 1, Section 5.3.1.3): I R aipj " Kg

Oy U ap Emi * (DFL)aij l

(9.5) 4

                                                              ~ l 'hm fp f, + (1 - fpf,) e                e Yp                 Ys j

l where: 1 i Kg = the units conversion factor: 100 pci/pci. r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1). Aj = the radioactive decay constant for radionuclide i, in s ~I. Values of 1 used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 26. 1, = the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-I, from Table 9-2. Qp = the cow's consumption rate of feed, in kg/d, from Table 9-2. l 1 U,p = the consumption rate of cow milk by a receptor in age group a, in L/y, from Table 9-5. l Fg= a the stable element transfer coefficient applicable to radionuclide 1, for cow's milk, in d/L, from Table 9-6. ) l l 9-6 Rev. 8, 1/94 l

Hatch ODCM

                         =    the ingestion dose factor for receptor age group        a, (DFL)aij radionuclide i, and organ j, in mrem /pci, f rom Table 9-11 through Table 9-14.

f p

                    =      the fraction of the year that the cow is on pasture (dimensionless), from Table 9-2.

the fraction of the cow's feed that is pasture grass fs= l while the cow is on pasture (dimensionless), from ! Table 9-2. l l l Y p= the areal density (agricultural productivity) of growing pasture feed grass, in kg/m 2, from Table 9-2. Y, = the areal density (agricultural productivity) of growing t ed , in kg/m 2 , from Table 9-2. storer i l I tg = the transport time from harvest of stored feed to its consumption by the cow, in s, from Table 9-2. g I\ tg = the transport time from consumption of feed by the cow, i to consumption of milk by the receptor, in s, from l Table 9-2. 3 For tritium in the grass-cow-milk pathway, Raipj in (mrem /y) per (yci/m ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the i concentration in air rather than deposition onto the grounds R aipj "K!*K3*OFuap *T mi * (E)aif 0.75 - { 0.5 (9.6) where K3= the units conversion factor: 103 g/kg. H= the absolute humidity of atmospheric air, in g/m3 , from Table 9-2. i 5 97 Rev. 8, 1/94 l I

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

Hatch ODCM 0.75 = the fraction of the mass of total vegetation that is water.(dimensionless). 0.5 = the ratio of the specific activity of tritium in. ! vegetation water to- that in atmospheric water (dimensionless). i and other parameters are as defined above. l I i 1 I l l I h i 1 l 9-8 Rev. 8, 1/94

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

2 f 4 Hatch ODCE i Table 9-2. Miscellaneous Parameters for the Grass-Cow-Milk Pathway I The following parameter values are for use in calculating Rg ;pj for ths grass-cow-milk pathway only. The terms themselves are defined in Section I 9.4. Parameter Value Reference 4 1, 5.73 x 10*7 s *I Ref. 1, page 33 (14-day half-life) Qp 50 kg/d Ref. 3, Table E-3 f p 1.0 Ref. 1, page 33 f, 1.0 Ref. 1, page 33 Yp 0.7 kg/m2 Ref. 3, Table E-15 Y, 2.0 kg/m2 Ref. 3, Table E-15 tg 7.78 x 106 s Ref. 3, Table E-15 (90 days) tg 1.73 x 105 s Ref. 3, Table E-15 (2 days) i H 8 g/m 3 Ref. 3 l 4 i -i i

%)

4 9-9 Rev. 8, 1/94 1

1

       '                                                              ~

i Hatch ODCM O 9.5 GRASS-GOAT-MILK PATHWAY FACTOR i For radionuclides other than tritium in the grass-goat-milk pathway, Raipj in (m2 mram/y) per (uci/s) is calculated as follows (Reference 1, Section l 5.3.1.3): l a.w - x, - ,,; : ,,, o, a.p r1 < m >.u 1 (9.7) i

                                                                                            -Xj tism fp i e -ki  If s+        (1 ~ pf si)*

Yp Ys l

                     -where Kg =

the units conversion factor: 106 pCi/pci. r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless) . The value used'for r is 1.0 for radiciodines and 0.2 for particulates, from (Reference 3, Table E-1). Aj = the radioactive decay constant for radionuclide i, in s -I. Values of 1 used in ef fluent calculations should be based en decay data from a recognized and current source, such as Reference 26. Aw= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-I, from Table 9-3. i Qp = the goat's consumption rate of feed, in kg/d,' from Table 9-3. j U,p = the consumption rate of goat milk by a receptor in age l group'a,'in L/y, from Table 9-5. t the stable element transfer coefficient applicable to j Fini = radionuclide i, for goat's milk, in d/L, from Table 9-6. 9-10 Rev. 8, 1/94

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

      .                                                                                  .                                                                   l l

Hatch ODCM ; l

                                     =      the ingestion dose factor for receptor age group                                                      a, (DFL) aij radionuclide i, and organ j, in mrem /pci, from Table 9-11

! through Table 9-14. ! l l f = the fraction of the year that the goat is on pasture p (dimensionless), from Table 9-3. f, = the fraction of the goat's feed that is pasture grass l while the goat is on pasture (dimensionless), from Table 9-3. I Y = the areal density (agricultural productivity) of growing p l pasture feed grass, in kg/m 2, from Table 9-3. ) 1 l Y, = the areal density (agricultural productivity) of growing l j stored feed, in kg/m 2, from Table 9-3. I i l l tg = the transport time from harvest of stored feed to its consumption by the goat, in s, from Table 9-3. l

    '                                                                                                                                                        l l

l tg = the transport time from consumption of feed by the goat, to consumption of milk by the receptor, in s, from Table 9-3. 3 For tritium in the grass-goat-milk pathway, Raipj in (mrem /y) per (pCi/m ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground: R alp) " Kg

K3*Of*Uap *Fmi * (DFL ) aij
O
T 5 *

(***) i l- i 1 I where: K3= the units conversion factor 103 g/kg.

H= the absolute humidity of atmospheric air, in g/m 3 , from i Table 9-3.

9-11 Rev. 8, 1/94 l

l. . .

l I Hatch ODCM O.75 = the fraction of the mass of total vegetation that is water (dimensionless). , 1 j 0.5 = the ratio of the specific activity of tritium in vegetation water to that in atmospheric water l (dimensionless), and other. parameters are as defined above. l l l r l l t l l i i 1 I l 1 ' l j h a 9-12 Rev. 8, 1/94

~.

Hatch ODCM Table 9-3. Miscellaneous Parameters for the Grass-Coat-Milk Pathway The following parameter values are for use in calculating Raipj for the grass-goat-milk pathway only. The terms themselves are defined in Section 9.5. Parameter . Value Reference 1, 5.73 x 10~7 s"I Ref. 1, page 33 (14-day half-life) Op 6 kg/d Ref. 3, Table E-3 f 1.0 Ref. 1, page 33 p f, 1.0 Ref. 1, page 33 Yp O.7 kg/m1 Ref. 3, Table E-15 Y, 2.0 kg/m2 Ref. 3, Table E-15 tg 7.78 x 106 s Ref. 3, Table E-15 (90 days) tf 1.73 x 105 s Ref. 3, Table E-15 (2 days) H 8 g/m 3 p.g, 3

,i 9-13 Rev. 8, 1/94

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

Hatch ODCM ( 9.6 CRASS-COW-MEAT PATHWAY FACTOR For radionuclides other than tritium in the grass-cow-meat pathway, Raipj in (m 2. mrem /y) per (yCi/s) is calculated as follows (Reference 1, Section 5.3.1.4): i

                                               #                U ap R alp)   = Kg *

Qy
Tp (DFL)aij

( Aj + Aw ) _ I I'* f p f, (1 - fp f,) e , -X; 17 Yp Ys where: r Kg = the units conversion factor 106 peijpeg, r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Refurence 3, Table E-1). Aj = the radioactive decay constant for radionuclide i, in s -I. Values of A; used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 26. A, = the rate constant for removal of activity on leaf and plant surfaces by weathering, in s'I, from Table 9-4. ) Qp = the cow's consumption rate of feed, in kg/d, from Table 9-4. U,p = the consumption rate of meat by a receptor in age group a, in kg/y, from Table 9-5. Fr, = the stable element transfer coefficient applicable to radionuclide i, for meat, in d/kg, from Table 9-6. l l 9-14 Rev. 8, 1/94

I Hatch ODCM (DFL)jj = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem /pci, from Table 9-11 through Table 9-14. ! f p

                      =      the fraction of the year that the cow is on pasture l                             (dimensionless), from Table 9-4.

> 1 f, = the fraction of the cow's feed that is pasture grass I while the cow is on pasture (dimensionless), from l Table 9-4. I Y p= the areal density (agricultural productivity) of growing pasture feed grass, in kg/m 2, from Table 9-4. f I l l Ys = the areal density (agricultural productivity) of growing ! stored feed, in kg/m2 , from Table 9-4. tg = the transpert time from harvest of stored feed to its consumption by the cow, in s, from Table 9-4. tr = the transport time from consumption of feed by the cow, to consumption of meat by the receptor, in s, from Table 9-4. 3 For tritium in the grass-cow-meat pathway, Raipj in (mrom/y) per (yci/m ) is calculated as follows (Reference 1, Section 5.3.1.4), based on the concentration in air rather than deposition onto the grounds R aip) = Kg

K3*Of U ap
Fp * ( DFL ) ajj = 0. 7 5 * ..

(9.10) where K3= the units conversion factor: 103 g/kg. I 3 H= the absolute humidity of atmospheric air, in g/m , from Table 9-4.

d 9-15 Rev. 8, 1/94

i i Hatch ODCM $ O.75 = the fraction of the mass of total vegetation that is , water (dimensionless). i l O.5 = the ratio of the Lpecific activity of tritium in vegetation water to that in atmospheric water ; (dimensionless). and other parameters are as defined above. P 1 l i l . I i l l i 1 l i l i c i i l 4 + h i 9-16 Rev. 8, 1/94

~.

Hatch ODCM l l l Table 9-4. Miscellaneous Parameters for the Grass-Cow-Meat Pathway 1 The following parameter values are,for use in calculating Raipj for the l grass-cow-meat pathway only. The tt rms themselves are defined in Section 9.6. Parameter Value Reference 1, 5.73 x 10~7 s -I Ref. 1, page 33 l (14-day half-life) l l Qp 50 kg/d Ref. 3, Table E-3 f p 1.0 Ref. 1, page 33 l fs 1.0 Ref. 1, page 33 i Y p O.7 kg/m2 Ref. 3, Table E-15 l Yg 2.0 kg/m2 Ref. 3, Table E-15 tyn 7.78 x 106 s Ref. 3, Table E-15 (90 days) tg 1.73 x 106 s Ref. 3, Table E-15 (20 days) l \ H 8 g/m3 Ref. 3 l l 9-17 Rev. 8, 1/94 L

      -                                                                                           j Hatch ODCM Table 9-5.      Individual Usage Factors Receptor Age Group Usage Factor Infant      Child            Teenager    Adult Hilk Consumption Rate, Uap 330        330                400       310 (L/y)

Meat Consumption Rate, Uap o 41 65 110 (kg/y) Fresh Leafy Garden Vegetation Consumption Rate, Ual 0 26 42 64 (kg/y) Stored Garden Vegetation Consumption Rate, UaS O 520 630 520 (kg/y) fs Breathing Rate, (BR), ( ) 1400 3700 8000 8000 N-- (m3 fy) l 1 l 1 All values are from Reference 3, Table E-5. 9-18 Rev. 8, 1/94

l t l l rs Hatch ODCM l Table 9-6. Stable Element Transfer Data 1 l Cow Milk Goat Milk Meat Element Ff (d/kg) Fm (d/L) F m (d/L)+ H 1.0 E-02 1.7 E-01 1.2 E-02 C 1.2 E-02 1.0 E-01 3.1 E-02 Na 4.0 E-02 4.0 E-02 3.0 E-02 P 2.5 E-02 2.5 E-01 4.6 E-02 2.2 E-03 2.2 E-03 2.4 E-03 f Cr Mn 2.5 E-04 2.5 E-04 8.0 E-04 Fe 1.2 E-03 1.3 E-04 4.0 E-02 Co 1.0 E-03 1.0 E-03 1.3 E-02 Ni 6.7 E-03 6.7 E-03 5.3 E-02 Cu 1.4 E-02 1.3 E-02 8.0 E-03 Zn 3.9 E-02 3.9 E-02 3.0 E-02 1 Br 5.0 E-02 5.0 E-02 2.6 E-02 ) Rb 3.0 E-02 3.0 E-02 3.1 E-02 Sr 8.0 E-04 1.4 E-02 6.0 E-04 Y 1.0 E-05 1.0 E-05 4.6 E-03 l Zr 5.0 E-06 5.0 E-06 3.4 E-02 l

   /~'j                       Nb          2.5 E-03       2.5 E-03 7.5 E-03 2.8 E-01 8.0 E-03

(,,/ Mo 7.5 E-03 l l ! Tc 2.5 E-02 2.5 E-02 4.0 E-01 Ru 1.0 E-06 1.0 E-06 4.0 E-01 Rh 1.0 E-02 1.0 E-02 1.5 E-03 Ag 5.0 E-02 5.0 E-02 1.7 E-02 Sb 1.5 E-03 1.5 E-03 4.0 E-03 Te 1.0 E-03 1.0 E-03 7.7 E-02 I 6.0 E-03 6.0 E-02 2.9 E-03 Cs 1.2 E-02 3.0 E-01 4.0 E-03 Ba 4.0 E-04 4.0 E-04 3.2 E-03 La 5.0 E-06 5.0 E-06 2.0 E-04 Ce 1.0 E-04 1.0 E-04 1.2 E-03 Pr 5.0 E-06 5.0 E-06 4.7 E-03 Nd 5.0 E-06 5.0 E-06 3.3 E-03 W 5.0 E-04 5.0 E-04 1.3 E-03 l Np 5.0 E-06 5.0 E-06 2.0 E-04 l

                           * - Values from Reference 3 (Table E-1) except as follov J Reference 2 (Table C-5) for Br and Sb.
                           + - Values from Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I, and Cs in goat milk, and Table E-1 for all r-s                          other elements in cow milk,       except as follows:

i Reference 2 (Table C-5) for Br and Sb in cow milk. I 9-19 Rev. 8, 1/94 l

l

Hatch ODCM Table 9-7. Inhalation Dose Factors for the Infant Age Group t

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.032-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 l Mn-54 No Data 1.81E-05 3. 5E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3.58E-05 h 1307E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-11 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data No Data Br-84 No Data No Data 2.86E-07 No Data No Data No Data No Data Br-85 No Data No Data 1.46E-08 No Data No Data No Data No Data Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 l Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 l Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Dr.ta 8.03E-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 l i All values are in (mrem /pci inhaled). They are obtained from Reference 3 (Table E-10). Neither Reference 2 nor Reference 3 O,- contains data for Rh-105, Sb-124, or Sb-125. l 9-20 Rev. 8, 1/94 l l

~.

P I 1 1 Hatch ODCM i C Table 9-7 (contd). Inhalation Dose Factors for the Infant Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91m 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 , l Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 o 17E-07 6.03E-07 O h Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data j Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.4SE-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 l Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Ta-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05

    ;   Te-131  1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06       5.87E-06 i

9-21 Rev. 8, 1/94

l Hatch ODCM l l (/ Table 9-7 (contd). Inhalation Dose Factors for the Infant Age Group ; Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI l Te-132 2.6fE-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 l l I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 i l I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 l I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-06 l I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 , I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 l l Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 i

     ,p-136    3.45E-05 9.61E-05 3.78E-05   No Data   4.03E-05 8.40E-06  1.02E-06 Cs-137   3.92E-04 4.37E-04 3.25E-05   No Data   1.23E-04 5.09E-05  9.53E-07 Cs-138   3.61E-07 5.58E-07 2.84E-07    No Data  2.93E-07 4.67E-08  6.26E-07 Ba-139   1.06E-09 7.03E-13 3.07E-11   No Data  4.23E-13 4.25E-06  3.64E-05

( Ba-140 4.00E-05 4.00E-OS 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 i Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 l l La-142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Co-143 2.09E-07 1.38E-07 1.5BE-08 No Data 4.03E-08 8.30E-05 3.55E-05 Co-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 1 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 9-22 Rev. 8, 1/94 I l

I Hatch ODCM t (_/ Table 9-8. Inhalation Dose Factors for the Child Age Group Nuglide Bone Liver T. Body Thyroid Kidney Lung GI-LLI )

      == w

! H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4e35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 l P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 l Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 l l Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 l Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 di-63 2.22E-04 1.25E-03 7.56E-06 No Data No Data 7.43E-05 1.71E-06

 /       Ni-65   8.08E-10 7.99E-11 4.44E-11      No Data   No Data   2.21E-06  2.27E-05

'\_/ Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 i Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E-06 Br-83 No Data Fo Data 1.28E-07 No Data No Data No Data No Data l Br-84 No Data No Data 1.48E-07 No Data No Data No Data No Data Br-85 No Data No Data 6.84E-09 No Data No Data No Data No Data l l Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 7 Data No Data No Data 5.11E-10 l Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 All values are in (mrem /pci inhaled). They are obtained from g Reference 3 (Table E-9). Neither Reference 2 nor Reference 3 contains data for Rh-105, sb-124, or Sb-125. 9-23 Rev. 8, 1/94

   .                                              ~,

Hatch ODCM Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91m 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 , l Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 l Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 v 3-24 Rev. 8, 1/94

l l ' l Hatch ODCM l i l Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group l l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI I Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 i I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 l I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 l I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 ( Ba-139 4.98E-10 2.66E-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 ( Ba-140 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 i Ba-142 1.35E-11 9.73E-15 7.34E-13 No Data 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-06 No Data No Data 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 l l Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 l 1 l Co-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 l Co-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 i Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 j l Pr-144 1.61E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 r\ I l 9-25 Rev. 8, 1/94

Hatch ODCM

 \/   Table 9-9.      Inhalation Dose Factors for the Teenager Age Group Nuclide       Bone      Liver     T.Bcdy    Thyroid    Kidney     Lung      GI-LLI H-3      No Data   1.59E-07 1.19E-07 1.59E-07      1.59E-07 1.59E-07    1.59E-07 C-14     3.21E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07           6.09E-07 Na-24     1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06           1.72E-06 l

P-32 2.36E-04 1.37E-08 8.95E-06 No Data No Data No Data 1.16E-05 i i cr-51 No Data Nc Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 I Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 j Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 rh Ni-65 2.73E-10 3.66E-11 1.59E-11 No Data No Data 1.17E-06 4.59E-06 l Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data No Data Br-84 No Data No Data 5.41E-08 No Data No Data No Data No Data Br-85 No Data No Data 2.29E-09 No Data No Data No Data No Data Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21E-06 ! Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 l l Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 i l Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 l Sr-91 1.10E-OB No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 l All values are in (mrem /pci inhaled). They are obtained from O Reference 3 (Table E-8). Neither Reference 2 nor Reference 3 contains data for Rh-105, sb-124, or Sb-125. 9-26 Rev. 8, 1/94

i

        '.                                               ~.

l l Hatch ODCM f s !V Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group i Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 1.19E-09 No Data 5.08E-11 No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 l Y-91m 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 Y-92 1.84E-09 No Data 5.36E-11 No Data No Data 3.35E-06 2.06E-05 l l Y-93 1.09E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 8.42E-06 3.36E-04 1.86E-05 l Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data l Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 l Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 l Mo-99 No Data 2.11E-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 I Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 1.20E-12 1.44E-07 7.66E-07 1 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 O Ru-103 I () 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 ; ! Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 l Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 i Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 ! Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05

,               Te-131   1.97E-12 1.04E-12 6.30E-13      1.55E-12 7.72E-12 2.92E-07     1.89E-09  I 1
   ,O Y.

9-27 Rev. 8, 1/94

    ~
      ~

l l Hatch ODCM f% .k Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group l i l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI 1 l Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07 l I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 1 l I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 l l I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 l 1 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 l l Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 l Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.36E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 p Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.34E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 l La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 l La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 Co-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Co-144 6.11E-04 2.53E-04 3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 1 ! Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 ( Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.11E-06 1.65E-05 {

9-28 Rev. 8, 1/94

           .                                                      .                                           i Hatch ODCM    ,
  '                                                                                                           l
'L                 Table 9-10. Inhalation Dose Factors for the Adult Age Group e

l Nuclide Bone Liver T. Body Thyroid Kidne) Lung GI-LLI ' H-3 No Data 1.5BE-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 l Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 ^ Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 l l 4 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 l i Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 ) i Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 I Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06

    % ,/

Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 1 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 I Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data No Data I Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 i Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 l All values are in (mrem /pCi inhaled). They are obtained from Reference 3 (Table E-7), except as follows: Reference 2 (Table C-1) J for Rh-105, Sb-124, and Sb-125. 1 l 9-29 Rev. 8, 1/94

        .                                              ~.

Hatch ODCM V Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group i Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 i Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 i Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 , i 1 4 Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 1.36E-21 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 t ( Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 No Data 3.89E-11 No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 'No Data 1.67E-05 1.17E-03 1.14E-04 Rh-105 9.24E-10 6.73E-10 4.43E-10 No Data 2.86E-09 2.41E-06 1.09E-05 a Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 i Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 No Data 3.10E-04 5.08E-05 Sb-125 8.26E-06 8.91E-08 1.66E-06 7.34E-09 No Data 2.75E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 l Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-1C 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 0 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 0 . 9-30 Rev. 8, 1/94

l Hatch ODCM Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group i l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI l l Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 l I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 l I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 i I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 l Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1 46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 i l Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Co-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-G5 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 Nc Data 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2,69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 O O 9-31 Rev. 8, 1/94

l . l l l Hatch ODCM

 /O Table 9-11. Ingestion Dose Factors for the Infant Age Group Nuclide       Bone      Liver    T. Body       Thyroid     Kidney     Lung      GI-LLI    )

l l H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 ) C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 No Data No Data No Data 2.30E-05 Cr-51 No Data No Data 1.41E-08 9.20E-09 2.01F-09 1.79E-08 4.11E-07 , I Mn-54 1.99E-05 4.51E-06 No Data No Data 4.41E-06 No Data 7.31E-06 Mn-56 No Data 8.18E-07 1.41E-07 No Data 7.03E-07 No Data 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05 l Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 , 1 ! Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 1 i[] Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 V l Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Data No Data No Data No Data Br-84 , No Data No Data 3.82E-07 No Data No Data No Data No Data Br-85 No Data No Data 1.94E-08 No Data No Data No Data No Data Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07 l Rb-89 No Data 2.86E-07 1.97E-07 No Data No Data No Data 9.74E-08 Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 Sr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04 Sr-91 5.00E-05 No Data 1.81E-06 No Data No Data No Data 5.92E-05 All values are in (mrem /pci ingested). They are obtained from Reference 3 (Table E-14). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-124, or Sb-125. C l 9-32 Rev. 8, 1/94

I l Hatch ODCM Q l d Table 9-11 (contd). Ingestion Dose Factors for the Infant Age Group i Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 1.92E-05 No Data 7.13E-07 No Data No Data No Data 2.07E-04 Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 i Y-91m 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06 Y-91 1.13E-06 No Dats 3.01E-08 No Data No Data No Data 8.10E-05 i i Y-92 7.65E-09 No Data 2.15E-10 No Data No Data No Data 1.46E-04 Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41E-08 No Data 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 No Data 1.24E-08 No Data 1.46E-05 Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 No Data 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05

 %J Ru-105    1.36E-07   No Data  4.5bE-08    No Data  1.00E-06  No Data  5.41E-05 i         Ru-106    2.41E-05   No Data  3.01E-06    No Data  2.85E-05  No Data   1.83E-04 l

Rh-105 No Data No Data No Data No Data No Data No Data No Data l Ag-110m 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data l l Sb-125 No Data No Data No Data No Data No Data No Data No Data l Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 No Data 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.10E-05 I Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05 l Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 , Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.11E-06 O O l 9-33 Rev. 8, 1/94

l i : l Hatch ODCM l (_, I O) Table 9-11 (contd). Ingestion Dose Factors for the Infant Age Group ) I Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81E-05 l I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 No Data 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 No Data 1.51E-06 i I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 No Data 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 No Data 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 No Data 2.62E-06 l 1 Cs-134 3.77E-04 7.03E-04 7.10E-05 No Data 1.81E-04 7.42E-05 1.91E-06 l l l Cs-136 4.59E-05 1.35E-04 5.C4E-05 No Data 5.38E-05 1.10E-05 2.05E-06 j ! Co-137 5.22E-04 6.11E-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 No Data 3.90E-07 6.09E-08 1.25E-06 1 Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05

Ba-140 1.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 ( Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 No Data 8.81E-11 9.26E-11 7.59E-07 i La-140 2.11E-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 No Data No Data No Data 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.48E-08 No Data 2.48E-05 l Ce-143 1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 i l l Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04 l Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 l Pr-144 2.74E-10 1.06E-10 1.38E-11 No Data 3.84E-11 No Data 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05 j Np-239 1.11E-08 9.93E-10 5.61E-10 No Data 1.98E-09 No Data 2.87E-05 9-34 Rev. 8, 1/94

l Hatch ODCM l

   \,_,.f'   Table 9-12.      Ingestion Dose Factors for the Child Age Group Nuclide        Bone      Liver   T. Body   Thyroid    Kidney     Lung     GI-LLI H-3      No Data   2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07        2.03E-07 C-14      1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06         2.42E-06 Na-24      5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06         5.80E-06 l

P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 Cr-51 No Data No Data 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.00E-06 No Data 8.9PE-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05 l Fe-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05 l 1 Co-58 No Data 1.80E-06 5.51E-06 No Data No Data No Data 1.05E-05 l Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06 Ni-65 2.22E-D6 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05 l Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84E-08 No Data 3.99E-06 Br-83 No Data No Data 1.71E-07 No Data No Data No Data No Data Br-84 No Data No Data 1.98E-07 No Data No Data No Data No Data Br-85 No Data No Data 9.12E-09 No Data No Data No Data No Data Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 l Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 l ! Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.11E-05 Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 All values are in (mrem /pci ingested). They are obtained from

p\ Reference 3 (Table E-13). Neither Reference 2 nor Reference 3 6 contains data for Rh-105, S b- 12 4, or Sb-125.

d l 9-35 Rev. 8, 1/94

Hatch ODCM i V' Table 9-12 (contd). Ingestion Doss Factors for the Child Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI J l Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 Y-90 4.11E-08 No Data 1.10E-09 No Datt No Data No Data 1.17E-04 Y-91m 3.82E-10 No Data 1.39E-11 No Data No Data No Data 7.48E-07 Y-91 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-05 Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 No Data 1.45E-09 No Data 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05 i Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.10E-05 l Tc-99m 9.23E-10 1.81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09 O Q Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 5.39E-07 3.64E-07 2.91E-07 No Data 6.78E-07 No Data 4.33E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 9-36 Rev. 8, 1/94

l 1 Hatch ODCM Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group l Nuclide Bone Liver T. Body Thyroid Kidney Lung CI-LLI Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 l I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06 1

I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 l l I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1. "16E-0 3 1.22E-05 No Data 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Co-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 l Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.8BE-09 No Data 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31E-05 l l Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 l Co-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.61E-07 No Data 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 No Data 2.11E-11 No Data 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 V) 9-37 Rev. 8, 1/94

4 1 Hatch ODCM O t I V Table 9-13. Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 Mn-56 No Data 1.58E-07 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 I Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 No Data No Data No Data 1.99E-06

 /            N1-65     7.49E-07 9.57E-08 4.36E-08       No Data   No Data   No Data   5.19E-06 b

Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 Br-83 No Data No Data 5.74E-08 No Data No Data No Data No Data Br-84 No Data No Data 7.22E-08 No Data No Data No Data No Data Br-85 No Data No Data 3.05E-09 No Data No Data No Data No Data Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 l All values are in (mrem /pci ingested) . They are obtained from Reference 3 (Table E-12). Neither Reference 2 nor Reference 3 contains data for Rh-105, sb-124, or sb-125. 9-38 Rev. 8, 1/94 1 I

                                                    .                                          )

l l l Hatch ODCM Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI l Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 l Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04 l l Y-91m 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 i Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 ; I i ! Y-92 1.21E-09 No Data 3.50E-11 No Data No Data No Data 3.32E-05

Y-93 3,P3E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04 ,

l Zr-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91E-08 No Data 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 l Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07 i Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 g Ru-103 2.55E-07 No Data 1.09E-07 No Dat.a 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 Ru-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-06 No Data 1.88E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05 Te-127m 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-129m 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07 Te-131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 l l l O 9-39 Rev. 8, 1/94_

j 1 l ! Hatch ODCM l 0 l b Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group l l f l Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI l l Te-132 3.49E-06 2.21E-06 2.OBE-06 2.33E-06 2.12E-05 No Data 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 l I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-07 i I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 I \ I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 No Data 5.10E-09 l I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 i Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E+?7 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-11 1 p Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-06 J Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 l Ba-141 6.71E-08 5.01E-11 2.24E-09 No Data 4.65E-11 3.43E-11 1.43E-13 l Ba-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-11 1.99E-11 9.18E-20 I La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05 La-142 1.79E-10 7.95E-11 1.9BE-11 No Data No Data No Data 2.42E-06 l l Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05 j i l ! Co-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 l Co-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 I Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 Pr-144 4.30E-11 1.76E-11 2.18E-12 No Data 1.01E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Data 3.6BE-05 l , W-187 1.46E-07 1.19E-07 4.17E-08 No Dat.a No Data No Data 3.22E-05 ! Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 l O l I 9-40 Rev. 8, 1/94 l

Hatch ODCM Table 9-14. Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.05E-07 1.05E-07 1.D5E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.6b2-07 5.68E-07 5.68E-07 5.6BE-07 l Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-Ot' 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 ^ Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 N1-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06

Ni-65 5.2BE-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 !

Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 j Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 i Br-84 No Data No Datn 5.21E-08 No Data No Data No Data 4.09E-13 i Br-85 No Data No Data 2.14E-09 No Data No Data No Data No Data 1 Rb-86 No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16K-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 All values are in (mrem /pci ingested) . They are obtained from Reference 3 (Table E-11), except as follows: Reference 2 (Table g A-3) for Rh-105, Sb-124, and Sb-125. 9-41 Rev. 8, 1/94

  .                                                       .                                           I Hatch ODCM Table 9-14 (contd).      Ingestion Dose Factors for the Adult Age Group w

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 1 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-97 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 , 1 Y-93 2.68F-09 No Data 7.40E-11 No Data No Data No Data 8.50E-05 l Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-09 No Data 4.31E-06 8 . ?.0 E + 0 7 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 ' Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data '6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 f Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41E-05 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05 l Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 '1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Da*.a 2.27E-05 l Te-127 1.1CE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.1EE-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 _ Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2. ',9 E-09 O 9-42 Rev. 8, 1/94

1 Hatch ODCM Table 9-14 (contd). Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-G7 No Data 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63C-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137, 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E*09: 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Co-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Co-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Co-144 4.88E-07 2.04E-07 2.62E-08 No Dhta 1.21E-07 No Data 1.65E-04 Pc-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.C5E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-Os No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 O 9-43 Rev. 8, 1/94

     .                                              ~.

Hatch ODCM V Table 9-15. External Dose Factors for Standing on Contaminated Ground l , I I 1 Nuclide T. Body Skin I Nuclide T. Body Skin H-3 0.00 0.00 Sr-91 7.10E-09 8.30E-09 l l l C-14 0.00 0.00 Sr-92 9.00E-09 1.00E-08 i Na-24 2.50E-08 2.90E-08 Y-90 2.20E-12 2.60E-12 P-32 0.00 0.00 Y-91m 3.80E-09 4.40E-09 Cr-51 2.20E-10 2.60E-10 Y-91 2.40E-11 2.70E-11 I l Mn-54 5.80E-09 6.80E-09 Y-92 1.60E-09 1.90E-09 Mn-56 1.10E-08 1.30E-08 Y-93 5.70E-10 7.80E-10 1 Fe-55 0.00 0.00 Zr-95 5.00E-09 5.80E-09 Fe-59 8.00E-09 9.40E-09 Zr-97 5.50E-09 6.40E-09 Co-58 7.00E-09 8.20E-09 Nb-95 5.10E-09 6.00E-09 Co-60 1.70E-08 2.00E-08 Mo-99 1.90E-09 2.20E-09 , 1 Ni-63 0.00 0.00 Tc-99m 9.60E-10 1.10E-09 l l Ni-65 3.70E-09 4.30E-09 Tc-101 2.70E-09 3.00E-09 l l Cu-64 1.50E-09 1.70E-09 Ru-103 3.60E-09 4.20E-09 l Zn-65 4.00E-09 4.60E-09 Ru-105 4.50E-09 5.10E-09 Zn-69 0.00 0.00 Ru-106 1.50E-09 1.80E-09 Br-83 6.40E-11 9.30E-11 Rh-105 6.60E-10 7.70E-10 l Br-84 1.20E-08 1.40E-08 Ag-110m 1.80E-08 2.10E-08 l Br-85 0.00 0.00 Sb-124 4.30E-08 1.50E-08 Rb-86 6.30E-10 7.20E-10 Sb-125 3.10E-09 3.50E-09 Rb-88 3.50E-09 4.00E-09 Te-125m 3.50E-11 4.80E-11 Rb-89 1.50E-08 1.80E-08 Te-127m 1.10E-12 1.30E-12 Sr-89 5.60E-13 6.50E-13 Te-127 1.00E-11 1.10E-11 Sr-90 0.00 0.00 Te-129m 7.70E-10 9.00E-10 All values are in (mrem /h) per (pci/m 2). They are obtained from j Reference 3 (Table E-6), except as follows: Reference 2 (Table A-7) l l for Rh-105, sb-124, and Sb-125. I 1 D l b l l 9-44 Rev. 8, 1/94 l 1

                    - - . . _ = _ _   - -__           . _         - . -   -  .
     '.                                                        ~.

d i i Hatch ODCM s/ Table 9-15 (contd). External Dose Factors for Standing on Contaminated Ground Nuclide T. Body Skin Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 ) Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 l I-131 2.80E-09 3.40E-09 I-132 1.70E-OB 2.OOE-08 I-133 3.70E-09 4.50E-09 } I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 co-143 2.20E-09 2.50E-09 Co-144 3.20E-10 3.70E-10 Pr-143 0.00 0.00 P7-144 2.OOE-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 9-45 Rev. 8, 1/94

Hatch ODCM CHAPTER 10 DEFINITIONS OF EFFLUENT CONTROL TERMS The terms defined in this chapter are used in the presentation of the above chapters. These terms are shown in all capital letters to indicate that they are specifically defined, 10,1 TERMS SPECIFIC TO THE ODCM The following terms are used in the ODCM, but are not found in the Technical Specifications: ! BATCH RELEASE A BATCH RELEASE is the discharge of wastes of a discrete volume. Prior to sampling for analyses, each liquid batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative san.pling. COMPOSITE SAMPLE A COMPOSITE SAMPLE is cne which contains material from multiple waste releases, in which the quantity of sample is proportional to the quantity of waste discharged, and in which the method of sampling employed results in a specimen that is representative of the wastes released. Prior to analyses, all liquid samples that are to be aliquotted for a COMPOSITE SAMPLE shall be mixed thorooghly, in order for the COMPOSITE SAMPLE to be representative of the affluent release. When assessing the consequences of a waste release at the pre-release or post-release stage, the most recent available COMPOSITE SAMPLE results for the applicable release pathway may be used. CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of wastes of a non-discrete volume, e.g., from a volume within a system that has an input flow during the CONTINUOUS RELEASE. FREQUENCY _HQTATION The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined below, with a maximum allowable extension not to exceed 25% of the surveillance interval. 10-1 Rev. 10, 7/95

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

Hatch ODCM NOTATION FREQUENCY S (Once per shift) At least once per 12 hours. D (Daily) At least once per 24 hoit.ts. W (Weekly) At least once per 7 days. M (Monthly) At least once per 31 days. Q (Quarterly) At least once per 92 days. SA (Semi-annually) At least once per 184 days. R (Refueling) At least once per 18 months. S/U (Startup) Prior to each reactor startup. NA Not applicable. P (Prior) Completed prior to each release. GASEOUS RADWASTE TREATMENT SYSTEM The GASEOUS RADWASTE TREATMENT SYSTEM is the offgas holdup system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. LIOUID RADWASTE TREATMENT SYSTEM A LIQUID RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive materials in liquid aftluents by systematic collection, retention, and processing through filtration, evaporation, separation and/or ion exchange treatment. This system consists of at least one collection tank, one ovaporator or domineralizer system, one post-treatment tank and associsted components providing for treatment flow . and functional control. MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS For the purposes of the ODCM, MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS include the following changes to such systems: (1) Major changes in process equipment, components, structures, or effluent monitoring instrumentation as described in the Final ! Safety Analykis Report (FSAR) or as evaluated in the Nuclear Regulatory Commission staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of domineralizers); , (2) Changes in the design of radwaste treatment systems that could ! significantly increase quantities of effluents released from those previously considered in the FSAR and SER; l l l 10-2" Rev. 10, 7/95

 --r      -                       ---            - , , -                 , , - ,    ,,,,-c   . - - , _                                               _ - , - .         ,.

Hatch ODCM (3) Changes in system design which may invalidate the accident analysis as described in the SER (e.g. , changes in tank capacity that would 3

alter the curies released); or i (4) Changes in system design that could potentially result in a l significant increase in occupational exposure of operating personnel (e.g., use of temporary equipment without adequate j shielding provisions). I j MEMBERf5) OF THE PUBLIC' A MEMBER OF THE PUBLIC shall be an individual in a controlled area or an j UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose. l This category may include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. 1 MILK ANIMAL A MILK ANIMAL is a cow or goat that is producing milk for human consumption. LO j MINIMUM DETECTABLE CONCENTRATION j The MINIMUM DETECTABLE CONCENTRATION (MDC) is defined, for purposes of the l controls in this ODCM, as the smallest concentration of radioactive material in a sample that will yield a not count above system background and that will be detected with 95-percent probability, with only 5-percent l probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation, the MDC for a given radionuclide is determined as follows I (Reference 17):

                                               + 3.29     R,    +

(10.1) g K+V 2. 2 2 x 10' Y e-"

O ' The italicized terms in this definition, which are not otherwise used in this ODCM, shall have the definitions assigned to them by 10 CFR 20.1003.

10-3 Rev. 10., 7/95

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

t=- Haten ODCM O

For gaseous radicactive ef fluents:

Kr-88, Xe- 13 3, Xe-133m, Xe-135,

n noble gas releases, Kr-87, Xe-138; and in particulate Mo- 9 9, Cs- 13 4, Cs- 13 7, rele ases, Mn- 5 4, Fe- 59, Co-58, Cc-60, Zn-65 Co-141, and Co-144.

f

Tor environmental media: The gam.a emitters specifically listed in Table 4-3.

These lista do not mean that only these nuclides are to be considered. o of the above Other gama peaks that are identifiable, together wit adioactive nuclides, shall also be analyzed and reported in e iwesel j the Annual Radiolo a vironmental

                           ~'ilyr"               ease      Report, f

4 I ! _ . . . i i .. .a Re rt, or other applicable report ( s) . i dope +:y O l l l l 1 1 k Rev. 8, 1/94 10-4

Hatch ODCM 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS ( The following terms are defined in the Technical Specifications, Sect on is . Because they are used throughout the Limits of Operation sections of t they are presented here for convenience. In the event of discrepancies between the definitions below and those in the Technical Specifications, the Technical Specification definitions shall take precedence. y CTIONest An ACTION s 11 be that p t of a conte that pres ibes r Unit 1 rem ial meas es required un r designated nditions. ditional requi ents spec ed as or Unit

ACTIONS hall be those 1

Q[ shall be part the contr ts

coMilary sta ements to ach control, a l g

! I \\yND l k ANNEL CALIBRATION adjust nt, as ecessa , of t e CALIB TION sha be th (/ A HANNE such th it re ponds w hin th requir range and i channe outpu , j 1

        -                    acc acy to nown valu            of the arameter hich tb channel onitor . The                {

compass he ent e chann inclu ing th ; NEL IBRATIO shall shall clude e C EL l sensor and alarm and/or

ip func ons, a l _s The NEL C BRATION may be p formed y any rie FUN IONAL TES

such . hat t ent e r o sequenti , overl ping, o total e nnel ste , channel i calibra ed. 4 CHANNEL CHECK CHANNE CHECK sha i be the alitati assessm t of cha nel beh vior d ing ope tion by o ervation. This de rminatio shall in ude, w re th och pos ble, co arison o the chan 1 indica ion and/ status hannels dica ions an or statu derived rom ind endent i trument mo g urin the s paramet . CHANNEL FUNCTIONAL TEST A NEL F CTIONAL EST shall es 4 alog Cha els - the injectio of a s ulated e nal into the channel e close t the pri y senso as prac cable to erify or bot units, larm and r trip OPE ILITY ine dings f etions; a for Unit only, e nnel fa ure trips

Bistab Channels the inj tion of simulate signal in o the sen or to verif OPERABILI includi g alarm an or trip f etions.

 ' /9 V

Rev. 8, 1/94 10-5

Hatch ODCM l

    )              DOSE EOUIVAkfNT I-131                                                  131 (p 1/g) whi h
 %)'      ~

DO EQUIV NT I-13 shall that c centra on of dose e the q antity nd isot pic

,h

k lone wo d producy the s .e thyro' c 134, a I-135 tually present The CN .)

mixtur of I-13 , I-132, -133, snali e thos g - thyr id dose nversio factors used to this ca culati gula ry l ted in T le III f TID-14 44 or t one in T le E-7 of NRC

</

[@ Guide 1. 9, Revi on 1, 1 7. v ' FREOUENCY NOTATION The FREQUENCY NOTATION specified for the performance of surveillance requir sment s shall correspond to the intervals defined below, with a maximum allowable extension net to exceed 25% of the surveillance l i interval. , 1 FREOUENCY NOTATION S (Once per shift) At least once per 12 hours. D (Daily) At least once per 24 hours. ( At least once per 7 days. W (Weekly) M (Monthly) At least once per 31 days. g At least once per 92 days. Q (Quarterly) SA (Semi-annually) At least once per 184 days. At least once per 18 months. l R (Refueling) j y/ \ S/U (Startup) Prior to each reactor startup. f Not applicable. .f NA P (Prior) Completed prior to each release. I MEMBEkfS) OF THE PUBLIC A MEMBER OF THE PUBLIC shall be an individual in a concrolled area or an UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC l during any period in which the individual receives an occupational dose. This category may include persons 'who use portions of the site for recreational, occupational, or other purposes not associated with the plant. MILK ANIMAL A MILK ANIMAL is a cow or goat that is producing milk for human consumption. o Q l The italicized terms in this definition, which are not otherwise used in this ODCM, shall have the definitions assigned to them by 10 CFR 20.1003. A A-_

10-6 Rev. 8, 1/94

                                                                                                                                        . ,  r, Hatch ODCM j

OPERABLE for' OPERABILITY) ( OPERABIL Y exists who a system, sub stem, train, omponent o device a

             \0E                   capable of              rforming i e specified f etion(s), an when all n cessar ttendant in trumentation controls, el ctrical powe                                         cooling o seal g

9 wa er, lubrica on or other uxiliary equi nt that are required to the 4#{\ syst m, subsyste train, com nont or devi to perform to functior. ) I are al o capable o performing air related pport funct n(s). [ V i OPERATIONAL CQNDITION

                                    ";; " !? l'            "': t: n ie i.e; d::! :d.                         ;.. d.finiiivi. e f KO'.0"^3 "^^? :

An OPERATIONAL CONDITION shall be any one inclusive

  ,i h
                                    ?::     "-it        2:

l combination of Mode Switch position and average reactor coolant 3 l M temperature, as defined in !:::ic 1.0 of the Unit 2 Technical i Specifications. M/6 /./-/ f l I l REACTOR MODE l i

                                    ?:: " cit 1; The REACTOR MODE is established by the Mode Switch position.

( The four Mode Switch positions are REFUEL, SHUTDOWN, START & HOT STANDBY, l l and RUN; thus the four possible REACTOR MODES are: Refuel Mode, Shutdown Mode, Start & Hot Standby Mode, and Run Mode. (See "rit i Technical k Specifications Oe.ilei.1.0 for definitions of these terms. ) O re.- :21: 2; Tu- [AblL/,/-l

                                                                                  = .. i..; 2.::::c.             Ox de :1...i;... e: s;;aamaa;.
                                                                                                                                                       \

htal t~ tat MTED THERMAL POWER g g 4 g gg g THERMAL POWER .. C_... M ;^.L__ , 9

                                                                                                                                 ^
                                       ? r "rit 1:          RATED                                                                            ;; ce of l                                       2436 MWt.          This le ein ::: .... Lw . 10 0 y. . . ... . nu,6 7 0^                             A.

l Te. Oi.it *- " _ ' . . , ;; ;;n .T2: ch;ii bc : *^*M ---trr ::x he t ! 4..i.efer ::t: : th; ....Lv. c '..i.; ;f :4;;, h... SITE BOUNDARY V # The SITE BOUNDARY shall be that line beyond which the land is not owned 6

             *o leased or otherwise controlled by Georgia Power Company as shown in Figure 10-1.

19,U.RCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity. I A A \O i 10-7 Rev. 9, 2/94

l I fw INSERT l \

 \
  '~)     ACTIONS ACTIONS shall be that part of a specification that prescribes req 1 red actions to be taken under designated l

Conditions within specified Completion Times. l CHANNEL CALIBRATION CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CRANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the l channel. The CHANNEL CALIBRATION may be performed by means l of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated. CHANNEL CHECK CHANNEL CHECK shall be the qualitative assessment, by

  /,.3           observation, of channel behavior during operation. This
     >           determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels              i measuring the same parameter.

CHANNEL FUNCTIONAL TEST CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify operability, including required alarm, interlock, display, and trip functions, and l channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested. DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) that alone would produce the same thyroid dose as the quantity and isotopic of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, " Calculation of Distance Factors for Power and Test Reactor Sites;" Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977; or ICRP 30, ' (~ ) Supplement to Part 1, page 192-212, Table titled, " Committed k/ Dose Equivalent in Target Organs or Tissue per Intake of Unit Activity."

INSERT (continued! ! (/'"; OPERABLE ter OPERABILITY)

 %-)          A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, i

lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function (s) are also capable of performing their related support function (s). 1 O

 ;    i
 %)

l (3, (_) 1

( . . Hatch ODCM g THERMAL POWER (/ or Uni 1: This term s not defined. For th purpose' of ef uent l c ntrols n the OD M requi 'ng spec'al samp ng in e event f speci ed ! cha ges in THERMAL WER, th defini ion sha be tak n to be t e same that or Un 2.

               -ivs v . . . ;. 2. THERMAL POWER shall be the total reactor core heet transfer t t e reactor coolant.
                                                                              ^

M& RESTRICTED A.REA N V ION The UNRESTRICTED AREA shall be any area access to which is neither limited

ho nor controlled by the licensee, or any area within the SITE BOUNDARY used Q.\ for residential quarters or for industrial, commercial, institutional, and/or u recreational

                                       .            purposes. a (N

Y l l l O 10-8 Rev. 8, 1/94

Hatch ODCM O l l l EU

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1 O Figure 10-1. Site Map for Effluent Controls 10-9 Rev. 9, 2/94

   . _ - - _ - _ _ _ _ _ _ _ .}}

HL-5149, Ei Hatch Nuclear Plant Annual Radioactive Effluent Release Rept for Jan-Dec 1995

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HL-5149, Ei Hatch Nuclear Plant Annual Radioactive Effluent Release Rept for Jan-Dec 1995

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Enclosure:

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