ML20237H720

Semiannual Rept,Radioactive Effluent Release Rept, for Jan-June 1987

ML20237H720
Person / Time
Site:	Hatch
Issue date:	06/30/1987
From:	Gucwa L GEORGIA POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SL-3127, NUDOCS 8709030370
Download: ML20237H720 (59)

Text

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6 'o GEORGIA NWER COMPAfE PLAffr E. I. HATCH UNITS fD.1 & 2 SEMI-ANNUAL REMRT RADIOACTIVE EFFLUEf7f RELEASE REPORT January 1, 1987 - June 30, 1987 l

I 8709030370 070630 PDR ADOCK 05000321 4-R PDR jb S

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PLANT E. I. HATCH GEMIANNUAL REPORT

. RADIOACTIVE EFFLUENT RELEASE REPORT -

,, SECTION TITLE PAGE-

1.- LIWID EFFLUENTS 1-1.1 REGULATORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5 1.3 MEASUREMENTS AND APPROXIMATILE OF TOTAL RADIOACTIVITY :5 1.4 LI@ID EFFLUENT RELEASE DATA 7 1.5 RADIODDGICAL IMPACT ON MAN DUE TO LI WID RELEASES 9 2 GASEOUS EFFLUENTS 22 2.1 REGULATORY LIMITS 22 2.2 MEASUREMENTS AND APPROXIMATIONS OF TUTAL RADIOACTIVITY 28 3

2.3 GASEOUS EFFLUENT RELEASE DATA 33 2.4 RADICII)GICAL IMPACT DUE 'IO GASEOUS RELEASES 34' 3 SOLID WASTE 50 3.1 REGULATORY SPECIFICATIONS 50 3.2- SOLID WASTE DATA 50 l 4 CHANGES 'IO THE PLANT ' HATCH RADIO-LOGICAL ENVIRONMENTAL MONITORING PROGRAM 53 1

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PLAtC E. I. HATCH SEMIANNUAL REPORT RADIOACTIVE EFFLUEtE RELEASE REPORT TABLE LIST OF TABLES PAGE l-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 RADIOACTIVE LIQUID EFFLUENT MONI'IORIBC IBGTRUMElEATION 3 1-2a LIQUID EFFLUEtES - SUMMATION OF ALL RELEASES - UNIT 1 10 1-2b LIQUID EFFLUEtES - SUMMATION OF ALL RELEASES - UNIT 2 11 1-2c LIQUID EFFLUENTS - SUMMATIOBE OF ALL RELEASES - SITE 12 1-3a LIQUID EFFLUEtTPS - UNIT 1 13 1-3b LIQUID EFFLUEtES - UNIT 2 15 1-3c LIQUID EFFLUEtTIS - SITE 17 1-4a INDIVIDUAL DOSES DUE 'IO LIQUID RELEASES - UNIT 1 19 l-4b INDIVIDUAL DOSES DUE 'IO LIQUID RELEASES - UNIT 2 20 1-5 wWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES 21 2-1 TECHNICAL SPECIFIC 7. TION TABLE 3.14.2-1 RADIOACTIVE GASEOUS EFFLUEtE IONI'IORItG INSTRUMENTATION 24 2-23 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT 1 35 2-2b GASEOUS EFFLUEtES - SUMMATION OF ALL RELEASES - UNIT 2 36 2-2c GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - SITE 37 2-3a GASEOUS EFFLUEtTPS - ELEVATED RELEASES - UNIT 1 38 l

2-3b GASSOUS EFFLUEtTIS - ELEVATED RELEASES - UNIT 2 39 2-3c GASD30S EFFLUEtTPS - ELEVATED RELEASES - SITE 40

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i b l TABLES LIST OF TABLES PAGE 2-4a GASECUS EFFLUEtES - GROUND-LEVEL RELEASES - UNIT 1 41 $

l 2-4b GASEOUS EFFLUEBTES - GROUto -

LEVEL RELEASES - UNIT 2 42 2-4c GASEOUS EFFLUEIRS - GROUFO -

LEVEL RELEASES - SITE 43 2-5 GASEOUS EFFLUENTS - DOSE RATES - SITE 44  ;

1 2-6a AIR DOSES DUE TO ?OBLE GASES - i UNIT 1 45 2-6b AIR DOSES DUE 'IO 10BLE GASES -

UNIT 2 46 2-7a INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM, AND PARTICULATE IN GASEOUS RELEASES - UNIT 1 47 2-7b INDIVIDUAL DCGES DUE 'IO RADIOIODINE, TRITIUM, AND PARTICULATE IN GASEOUS RELEASES - UNIT 2 48 2-8 IDWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES 49 3-la,b SOLID WASTE AND IRRADIATED FUEL I SHIPMEtES 51,52 I

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I. ;D PADIOACI'IVE EFFLUENT RELEASE. REPORT l' LIQUID EFFLUENTS ,

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.1.1. REGULA'IORY LIMITS i

1. TheITechnical Specifications presented in this section are for Unit 1. Requirements for Unit 2

,- are the same as Unit 1; however, the Technical

[ Specification numbers are' not the same.

TECHNICAL SPECIFICATIONS

[ 3.14.1 The radioactive liquid effluent monitoring -

instrumentation channels shown in. table 3.14.1-1 shall be OPERABLE With their alarWtrip setpoints set to ensure .that the limits of Specification 3.15.1 are .not exceeded. The alarW trip setpoints of'these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). (Technical Specification Tab]e 3.J4.1-1 is included in this section as Table I l-1).

3.15.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (figure 3.15-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II (column 2) for radionuclides other than dissolved or.' entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 uCi/ml total activity.-

3.15.1.2 The dose or dose commitment to a MEMBER OF

. THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site (figure 3.15-1) shall be limited to:

a. During any calendar quarter to less than or equal to 1.5 mrem .to the tota) body and to less than or equal to 5 mrem to any organ.

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 mrem to any organ.

3.15.1.3 The liquid radwaste treatment system, as j described in the ODCM, shall be used to reduce the j radioactive materials in. liquid wastes prior to their  ;

discharge when the projected doses due to the liquid ,

effluent per Unit from the site (figure 3.15-1) when 1 projected over the calendar quarter would exceed 0.18 i mrem to the total body or 0.62 mrem to any organ. )

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3.15.1.4(a) The contents within any outside temporary tank shall be limited to less than or equal '

to 10 curies, excluding tritium and dissolved or entrained noble gases.

'(a) .An outside temporary tank is not surrounded by liners,' dikes, or walls that are capable of holding the tank contents and not naving tank i

overflows and drains connected to the liquid l radwaste treatment system.

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~6.9.1.9 states in part: "The Radioactive Effluent Release Report shall include'(on a. quarterly basis) unplanned releases frce the site to unrestricted areas of radioactive materials in gaseous and liquid ,

effluents that were in excess of 1 C1, excluding  ;

dissolved and entrained gases and tritium for liquid effluents,.or those in excess of 150 Ci of noble gases l- or 0.02 Ci of radioiodines for gaseous releases".

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, o TABLE 1-1 1 TECIDJICAL SPECIFICATION l TABLE 3.14.1-1 (SHEET 1 of 2)

RADIOACTIVE LIQUID EFFLUE?TP MONI'IORING INSTRUMENTATION Minimum Channels Instrument OPERABLE Applicability ACTION

1. Gross Radioactivity Monitors Providing Automatic Termina-tion of Release Liquid Radwaste Effluent Line 1 (a) 100  :

2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Nater System Effluent Line 1 (b) 101

3. Flowrate Measure-ment Devices **

l Liquid Radwaste Effluent Line 1 (a) 102 Discharge Canal 1 (b) (a) 102

4. Service Water 1 At all times 103 System to Closed l q

Cooling Water System Differential l Pressure {

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• • Pump curves may be utilized to estimate flow; in such cases, 3 ACTION statement 102 is not required.

l (a) Whenever the radwaste discharge valves are not locked closed.

( b) Whenever the service water system pressure is below the closed cooling water system pressure or o P indication is not available.

TABLE 1-1 (COBEINUED)

TECHNICAL SPECIFICATION i TABLE 3.14.1-1 (SHEET 1 of 2)

RADIOACTIVE LIQUID EFFLUE?E MONITORItG IFETRUMEBEATION TABLE BUPATIOtB

. ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be continued, provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4.15.1.1.1.

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

Otherwise, suspend release of radioactive effluents via  !

this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 101 - With the numbers of channels OPERABLE less than ,

required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that once per shift grab samples are collected and analyzed for gross radioactivity (beta or gamna) at a Lower Limit of j Detection of at least 10-7 uCi/ml. If the channel j remains inoperable for over 30 days, an explanation of the i circumstances shall be included in the next semi-annual i 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 the flowrate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system monitor is OPERABLE.

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. r 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC values used in determining allowable liquid radwaste release rates and concentrations for principal gaama emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10CFR Part 20, I.ppendix B, Table II, Colunn 2.

For dissolved or entrained noble gases in liquid radwaste, the MPC is taken from Technical Specification 3.15.1.1 (Unit 1) and 3.11.1.1 (Unit

2) as 2.0E-04 uCi/ml.

For gross alpha in liquid radwaste, the MPC is taken from 10CFR Part 20, Appendix B, Note 2.b as 3.0E-08 uci/ml.

Further, for all the above radionuclides or categories of radioactivity, the overall MPC fraction is determined in accordance with 10 CFR Part 20, Appendix B, Note 1.

The method whereby the MPC fraction is used to determine release rates and liquid radwaste effluent radiation monitor setpoints is described in Section 1.3 of this report.

1.3 MEASUREMENTS AND APPROXIMATIONS OF 'IOTAL RADIOACTIVITY Prior to release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2) . A sample from each tank planned for release is analyzed for principal gamma emitters, I-131, and dissolved and entrained noble gases by gama spectrometry.

Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from tanks which are released. Liquid radwaste sample analyses are performed as follows:

Measurement Frecuency Method

1. Gama Isotopic Each Batch Ganma spectroscopy with computerized data reduction

2. Dissolved or Each Batch Gamna spectroscopy Entrained with computerized Noble Gases data reduction J. :o

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Measuretrent Frequency . Method I

3. Tritita Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha - Monthly Gas Flow Proportional Composite counting

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5. St-89 and Sr-90 Quarterly Chemical separation and Composite gas flow proportional counting

6. Fe Quarterly Chemical separation and Composite low energy photon detector.

Gamma isotopic measurements are performed irehouse in the radiochemistry lab using germanium spectrometry.

Three germanita detectors are available: a 10%

efficient Ge(Li) detector and two 15% efficient i intrinsic germanium detectors, with 2.0 FWHM

' resolution and housed in 4 inch-thick lead shields. A I one-liter liquid radwaste sample is poured into a Marinelli beaker in preparation for a 2000-3000 second i

count. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for. all significant peaks are determined, and quantitative reduction or LLD .  !

calculations are performed for the nuclides specified in Table Notation e of Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2): Mrr54, F-59,

' Co.-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for counting time, decay tims, sarrple volume, sample geometry, detector efficiency, baseline counts, and branching ratio. LLD calculations, including the above corrections, are made based on the counts in two standard deviations of the baseline count at the location on the spectrtn where a peak for that radionuclides would be located if present. l The radionuclides concentrations determined by gamma  !

spectroscopic analysis of a sample taken from a tank .l planned for release and the most current sample  ;

I analysis results available for tritium, gross alpha, Sr-89, Sr-90, and Fe-55 are used along with the corresponding MPC values to determine an MPC fraction for the tank planned for release. This MPC fraction is then used, with appropriate safety factors, along with the expected dilution stream flow to calculate a maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of Technical Specifications 3.15.1.1 (Unit 1) or 3.11.1.1 (Unit 2) are not exceeded.

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• G 'g- termination of the liquid radwaste discharge.

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['s . % , ,terminated if the dilution stream flow rate falls

/, I Liquid. effluent discharge is also automatically 4

.% below the dilution flow rate' used in the setpoint '

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calculations and established as_a setpoint on the

,. dilution stream flow monitor.

e Radionuclides concentrations, safety factors, P ' di!)ubion stream flow rate,cand liquid effluent

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radiation monitor calibration factor are entered into the computer and.a prerelease printout is i

. generated. If_the release is not permissible

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appropriate warnings will be included on the prerelease printout. If the release is ,

i' 1 permissible it is approved by the Chemistry

. . Foreman on duty. The pertinent information is

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W transferred manually ft w the prerelease printout to a ohe-page release permit which is forwarded

. to Radwaste Operations. When the release is 4y. i.

completed the release permit is returned from

(% 'Radwaste Operations with actual release data 4

included. These data are input to the computer 1

y and a postrelease printout is generated. The

g. postrelease printout contains actual release 1

yz. rates, actual release concentrations and  !

o .. /, quantities, actual dilution flow, and calculated

[b - doses to an individual.

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q9' 1.4 LIQUID EFFLUENT RELEASE DATA

/ }~j 0 Regulatory Guide 1.21 Tables 2A and.2B are found v in this report as Table 1-2a for Unit 1, Table 1-2b for Unit 2 and Table 1-2c for the site; and Table 1-3a for Unit 1,-1-3b for Unit 2, and Table 1-3c for the site.

/ Ihe values for the four categories of Tables 1-2a and 1-2b, and 1-2c are calculated and the Tables p completed as follows:

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1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the

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measured individual radionuclides activities. This sum is for each batch released to the river for the respective 1

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quarter.. Percent of applicable limit is determined from a mixed nuclide MPC fraction

• l calculation. The average concentration for- ,

each nuclide over all released batches.is divided by the corresponding individual MPC l value. The sum over all nuclides of the 1 Ci/MPCi ratioa times 100 is the percent of.

applicable limit for effluent releases  !

during the quarter.

I 2.- Tritium - The measured tritium -

l concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration

-during each period. Average diluted j concentration divided by the MPC limit,  !

3.0E-03 uCi/ml, is converted to percent to  !

give the percent of applicable limit. '

3. Dissolved and entrained gases'-

. Concentrations of dissolved and entrained gases in liquid effluents are measured by.

germanium spectroscopy on a one liter sample fran each liquid. radwaste batch. The- 1 '

average concentration 'of dissolved or entrained noble gases for all released batches is divided by the MPC value stated .

in Technical Specifications 3.15.1.1 and  !

3.11.1.1 (2.0E-04 uCi/ml) to determine the ,

MPC fraction. The result x100 is the t percent of applicable limit for-noble gases  !

in liquid. effluent releases during the  ?

quarter. Radioisotopes of iodine in any 'i

. form are also determined during the isotopic  !

analysis for each batch; therefore, a j separate analysis for possible gaseous forms is not performed because it would not  :

provide additional-information.

4. Gross alpha radioactivity - The measured I gross alpha concentrations in the monthly 1 composite sanples are used to calculate the total release of alpha radioactivity.

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L Other data pertinent to batch releases of radioactive liquid effluent frcun both units are as follows:

' Number of batch releases: 902 Total time period for ' batch releases: 119,992 minutes L

Maximtan time' period for a L

batch release: 343.0 minutes

( Average time period for batch p' releases: 133.0 minutes l

. Minimum time period for a' batch

[> release:

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17.0 ' minutes -

t I Average stream flow during periods of release of. liquid effluent into a flowing stream: 17,263 CFS

1. 5 RADIOIDGICAL IMPACT ON MAN DUE 'IO LIQUID RELEASES Doses; to an individual, due to radioactivity in i,

. liquid effluent, were calculated in accordance L

'with Technical Specifications 3/4.15.1.2 (Unit 1)

- and 3/4.11.1.2 (Unit 2) using the methodology l'

' presented:.in the Plant Edwin I. Hatch Offsite Dose Calculation Manual.. As required by the=

s above Technical. Specifications, doses were

'. calculated separately for Unit 1 and Unit 2.

Results are presented in Table 1-4a .for Unit I and Table 1-4b for Unit 2.

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TABLE 1-2a E. I. HATCH NUCLEAR PLANI - UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1987 LIQUID EFFLUENIS - SUMMATION OF ALL RELEASES i

Est. Total Unit Quarter 1 Quarter-2 Error %

A. Flssion &

Activation eroducts

1. Total release (not including Ci 4.29E-02 3.70E-01 4.6E+01 H-3, gases, alpha)

2. Average diluted concentration uCi/ml 3.67E-08 2.47E-07 during period

3. % of applicable  % 4.01E+00 6.56E+00 limit B. Tritium

1. Total release ci 5.83E+00 3.14E+00 3.7E+01

2. Average diluted uCi/ml 4.98E-06 2.09E-06 concentration during period

3. % of applicable  % 1.66E-01 6.98E-02 limit C. Dissolved and Entrained Gases

1. Total release ci 3.23E-02 2.39E-02 1.0E+02

2. Average diluted uCi/ml 2.76E-08 1.59E-08 concentration during period

3. 9 of applicable  % 1.38E-02 7,97E-03 l limit 3 1

D. Gross alpha l radioactivity )

1. Total release C1 1.78E-08 4.49E-06 1. 2E+02 E. Volume of waste (prior to dilution) liters 5.53E+06 7.38E+06 1. 0E+ 01 l

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F. Volume of dilution '

water used liters 1.17E+09 1.50E+09 1.6E+02 l

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TABLE 1-2b E.- I.' HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1987

' LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total  !

Unit. Quarter 1 -Quarter 2 Error %

A. Fission in Activation Products

1. Total. releam

, (not' including Ci 2.14E-02 5.72E-02 4.7E+ 01 H-3, gases ~,

alpha)

2. Average' diluted.

concentration uCi/ml 1.49E-08 4.16E-08 during period- l

3. % of applicable  % 1.41E-01 5.74E+ 00

- ' limit '

B. Tritium l'

1. Total releam C1 3.63E+00 2.76E+00- 3. 7E+01 -

2. Average diluted uCi/mi .2.10E-06 2.01E-06 concentration during period

3. 4 of applicable  % 7.01E-02 6.72E-02 limit e

C.-Dissolved and' Entrained Gases

1. Total release Ci 6.38E-03 3.53E-02 1.0E+02  !

2. Average diluted uCi/ml 4.43E-09 3.58E-08 concentration during period

3. % of applicable

% 2.22E-03 1. 29E-02 limit- ]

i D. Gross alpha radioactivity

1. Total release. Ci 7.76E-08 3.09E-07 1. 2E+0 2

.E. Volume of waste I (prior to dilution) liters 6.13E+ 06 5.75E+06 1.0E+01 F. Volume of diluticn water used liters 1.44E+09 1. 37E+ 09 1.6E+02  !

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i TABLE 1-2c l E. I. HATCH NUCLEAR PLANT - SITE SEMIANt0AL EFFLUENT RELEASE REPORT 587 LIQUID EFFLUEITIS - SUMMATION OF ALL RE,i. EASES Est. Total Unit Quarter 1 Quarter 2 Error %

A. Fission &

Activation j Products ]

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1. Total release (not including Ci 6.43E-02 4.27E-01 4.78+01 l H-3, gases, alpha)

2. Average diluted j concentration uCi/ml 2.46E-08 1.49E-07 1 during period  !

3. % of applicable  % 1.88E+00 6.17E+00 limit B. Tritium

1. Total release C1 8.86E+00 5.90E+00 3.7E+01

2. Average diluted uci/ml 3.39E-06 2.06E-06 concentration during period-  ;

3. % of applicable  % 1.13E-01 6.85E-02 i limit l C. Dissolved and Entrained Gases l

1. Total release Ci 3.87E-02 5.92E-02 1.0E+02

2. Average di. luted uCi/ml 1.48E-06 2.06E-08  ;

concentration i during period

3. % of applicable  % 7.41E-03 1.03E-02  !

limit l

D. Gross alpha radioactivity

1. Total release Ci 9.54E-08 4.80E-06 1.2E+02 E. Volume of waste (prior to dilution) liters 1.17EF07 1.31E+07 1,0E+01 F. Volume of dilution water used liters 2.61E+09 2.87E+09 1.6E+02 1

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' TABLE 1-3a E. I. HATCH NUCLEAR PLAM' - UNIT 1 i

SEMIANNUAL LIQUID EFFLUENIS RELEASE REIORT 1987*

Page'1 of 2 l i

l Continuous Mode ** Batch Mode Nuclides  ;

Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 5. 83E+ 00 3.14E+00 Na-24 C1 1.04E-03 1.84E-03 Cr-51 C1 1. 50E-03 1. 93E-02 Mn-54 Ci 6.12E-04 5.93E-03 Mn-56 C1 2. 99E-05 1. 38E-05 Fe-55 Ci 0.00E+00 Fe-59 3.42E-03 Ci 0 00E+00 9.65E-04 Co-58 C1 2.93E-04 2.36E-03 Co-60 Ci 2.45E-03 1. 92E-02 Cu-64 Ci 8.06E-04 1.45E-03 Ni-65 Ci 0. 00E+00 6.30E-06 Zn-65 C1 4.11E-03 As-76 7.02E-02 Ci 3.67E-05 6. 55E-05 Sr-89 Ci 0.00E+00 0.00E+00 Sr-90 Ci 0. 00E+ 00 0. 00E+00 i

St-91 Ci 0.00E+00 0.00E+00 Sr-92 C1 1.13E-05 Y-91m

7. 93E-05 C1 1.04E-04 Z r-95 5.71E-05 Ci 0. 00E+ 00 1. 98E-04 Nb-95 Ci 9.58E-06 5.20E-04 Nb-97 C1 2.77E-04 8.75E-04 j It-99m Ci 9.40E-04 1.08E-03 '

I- 131 C1 1.19E-02 2.21E-02 I-132 Ci 2. 29E-04 6.16E-04 I-133 Ci 5.48E-03 6.51E-03 1

i I- 134 Ci 4.15E-05 5. 4 9E-04 I-135 C1 1. 07E-03 2. 26E-03 i

Co-134 Ci 4.03E-03 9.15E-02 Cs-136 C1 1. 83E-04 3.52E-03 {'

co-137 Ci 7.23E-03 1.14E-01 Ba-139 Ci 6.6 7E-05 4. 2 3E-04 Ba-140 Ci La-140 Ci 0.00E+00 0 00E+00 0.00E+00

1. 55E-0 5 f '

Np-239 Ci ' 10E-06 9.51E-04 Totals Ci ,2 9E-02 3.70E-01 i

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TABLE 1-3a E. I. HATCH NUCLEAR PLANT - UNIT 1

.v- SEMIANNUAL. LIQUID EFFLUENTS RELEASE REPORT 1987* '

Page 2 of 2- --

'I Continuous Mode ** Batch Mode Nuclides.

Released- Unit Quarter 1 Quarter 2 - Quarter 1 Quarter 2 Kr-85m Ci 0.00E+00 Kr-85 .1.928-05 Ci 7.91E-04 ~ 0.00E+00 Xe-131m C1 1. 26E-04 Xe-133 3.23E-03 Ci' 1.09E-02 5.88E-03 Xe.-133m C1 1. 77E-04 0.00E+00 Xe-135m Ci 3. 39E-03 8.42E-03 Xe-135 C1 1. 69E-02 6.31E-03

-Ar-41 Ci 0.00E+00 Totals 1.41E-05  !

C1 3.23E-02 2.39E-02 '

Gross Alpha Ci. 1.78E-08 4.49E-06

• Zeros in this table indicate that no radioactivity was present I above detectable levels. See Table 1-5'for. typical lower

' limits of detection for liquid sample analyses.

• • There are no continuous mode radioactive liquid release

. pathways at Plant Hatch.-

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TABLE 1-3b L

E. I. HATCH NUCLEAR PLANT - UNIT 2 ,

SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987*-  !

Page 1 of 2 l

Continuous Mode ** Batch Mode EMc11 des .

g Released- Unit: Quarter 1 Quarter 2 Quarter 1 Quarter 2 1 1

H-3 Ci 3. 03E+00 2. 76E+00

.Na-24 Ci Cr-51 4.67E-04 9.23E-05 C1 Mn-54

1. 20E-04 3.46E-04 Ci 5.05E-04 Mn-56 C1 4.19E-04 Fe-55 3.20E-05 0.00E+00 Ci 1.18E-02 i

Fe-59 C1 4.12E-03 co-58 0.00E+00 0. 00E+00 Ci 1.02E-04 i

Co-60 Ci - 1.07E-04 Cu-64 1. 80E-03 1.24E-03 Ci 0.00E+00 Ni-65 Ci- 0.00E+00 Zn-65 0. 00E+00 0. 00E+00 Ci- 9.97E-04

,Aa-76 3.40E-03 Cs 2.27E-05 S t-89 1.70E-05 Ci 0.00E+00 0.00E+ 00 l

- St-90 Ci 0. 00E+00 0. 00E+00 St-91 Ci St-92 4.36E-06 9.04E-06

- Ci 1.91E-05 ,1. 27E-06 Y-91m Ci Z r-95 2.66E-05 1.78E-05 Ci 0. 00E+00 Nb-95 Ci' 0. 00E+00 .

Nb-97 O.00E+00 6.43E-06 Ci 0. 00E+ 00 Mo Ci 0. 00E+00  ;

Tc-99m 0.00E+00 0.00E+00 Ci

3. 49E-05 1.81E-04

.I- 13 1 C1 I-132 3.83E-04 2.08E-02 C1

2. 4 9E-05 2.91E-04

.I- 133 Ci I- 134 2. 81E-04 7.46E-03 Ci 0. 00E+ 00 I- 135 Ci 0.00E+00 Co-134 1.09E-04 2.23E-03 Ci 1.70E-03 Cs-136 Ci 6.61E-03

1. 28E-05 1.91E-04 Cs-137 Ci Co-138 2.70E-03 9.61E-03 Ci 0.00E+00 Ba-139 Ci 0.00E+00

5. 03E-06 0. 00E+00 Ba-140 Ci Ce-141 0.00E+00 0.00E+00 C1

3. 00E+00 0.00E+00 Ce-144 Ci Np-239 0.00E+00 1.23E-05 C1  !

Totals 2.13E-04 0. 00E+00 Ci 2.14E-02 5.72E-02 l

i

)

h TABLE 1-3b E. -I. . HATCH NUCLEAR PLANP - UNIT 2 '

SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987*

Page 2 of.2.

1 Continuous Mode ** Batch Mode .l lI , Nuclides  !

j:,

. Released Unit - Quarter 1 Quarter 2 Quarter 1 Quarter 2 l Kr-85 Ci 6.19E-04 0.00E+00  !

Kr-85m Ci 0.00E+00 0.00E+00 l 4.17E-05 8.13E-05 i, Xe-131m- Ci

.Xe-133m Ci 3.21E-06 3.16E-04 Xe-133 .Ci 7.96E-04 1.04E-02 Xe-135m -Ci 5.63E-04 8.09E-03  :

Xe-135 Ci 4. 36E-03 1.64E-02 l Ar-41 Ci 0.00E+00 4. 39E-06 Totals Ci 6.38E-03 3.53E-02  !

i Gross Alpha Ci' 7.76E-08 3.09E 'l l

.* Zeros in this table indicate that no radioactivity was present ,

above detectable levels. ' See Table 1-5 for typical lower -!

limits of detection for liquid sample analyses.  !

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

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4 TABLE.1-3c j E. I. HATCH NUCLEAR PLANI - SITE 3 l

SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987*

Page 1 of 2' Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 , Quarter ' 1 Quarter 2 <

H-3 Ci 8.86E+00 5.90E+00

]

Na-24 Ci 1.51E-03 1.93E Cr-51 Ci 1. 62E-03 1.96E-02 4 Mn-54 Ci 1.12E-03 6.35E-03 Mn-56 Ci 6.19E-05 1.38E-05 i Pe-55 'Ci 1.18E-02 7.54E-03 i Fe-59 Ci 0. 00E+00 9.65E-04 ,

Co-58 Ci 3.95E-04 2.47E-03 Co-60 Ci 4.25E-03 2.04E-02 C u-64 ' -Ci 8.06E-04 1.45E-03 Ni-65 Ci 0. 00E+00 6.30E-06 l n-65 Ci 5.12E-03 7.36E-02 i' As-76 Ci 5. 94E-05 8. 25E-0 5 j Sr-89 Ci 0.00E+00 0.00E+ 00 Sr-90 . ci . 0. 00E+00 0. 00E+00 Sr-91 Ci 4.36E-06 9.04E-06 ,

S r-92 Ci 3. 04E-05 8.06E-05 j Y-91m Ci 1.31E-04 7. 49E-05 .;

Z r-95 Ci 0. 00E+00 - 1.98E-04 l Nb-95 Ci 9.58E-06 5.26E-04 l Nb-97 Ci 2.77E-04 8.75E-04  !

Mo-99 Ci 0.00E+00 0.00E+00 i To-99m Ci 9. 75E-04 1.26E-03 l I- 131 C1 1.23E-02 4. 29E-02 j I-132 Ci 2. 54E-04 9.07E-04 1 I- 133 Ci 6. 26E-03 1.40E-02 f '

I- 134 Ci 4.15E-05 5.4 9E-04 I- 135 C1 1.18E-03 4. 49E-03 Cs-134 Ci 5.73E-03 9.81E-02 Ce-136' Ci 2.04E-04 3.71E-03 Cs-137 Ci 9. 93E-03 1.24E-01 Ba-139 Ci 7.17E-05 4. 23E-04 Ba-140 Ci 0. 00E+00 0.00E+00 La-140 Ci 0.00E+ 00 0.00E+00 Ce-141 Ci 0.00E+00 0. 00E+00 Ce-144 Ci 0.00E+00 1. 23E-05 Np-239. C1 2.16E-04 9.51E-04 Totals Ci 6.43E-02 4. 27E-01 l

l l

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, . 1 l

E. I. HATCH PLANI - SITE -

SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987*

Page 2 of 2 I continuous Mode ** Batch Mode 4

'Nuclides  !

Released ' Unit Quarter 1 Quarter 2 - Quarter 1 Quarter 2  ;

Kr-85m Ci 0.00E+00 1. 92E-0 5 .

Kr-85 C1. '1.41E-03 0.00E+00.  !

Xe-131m Ci '1.68E-04 3.31E-03 Xe-133m C1 1.80E-04 3.16E-04  ;

Xe-133 C1 1.17E-02 1.63E-02

. Xe-135m C1 3.95E-03 1.65E-02 Xe-135 C1 2.13E-02 2. 27E-02 .!

Ar-41 Ci- 0.00E+00 1.85E-05 l Totals ci 3.87E-02 5.92E-02 i l \l l Gross Alpha Ci 9.54E-08 4.80E l' l

• Zeros in this table indicate that no radioactivity was present  :

above detectable levels. See Table 1-5 for typical lower  ;

limits of detection for liquid sample analyses. i 1

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

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TABLE 1-4a q E. I. HATCH NUCLEAR PLANP UNIT 1 i SEMIANNUAL EFFLUENT RELEASE REPORT 1987 l INDIVIDUAL DCEES DUE TO LIQUID RELEASES ~

]

1 Cumulative Dose Per' Quarter

/

t . organ Tech Units Quarter '% of Quarter  % of I Spec -1 Tech 2 Tech Limit Spec. Spec Limit Limit Bone' 5.0 mreWqtr 3.98E-02 7.96E-01 7. 36E-01 1. 4 7E+01 '

Liver'. 5.0 mreWqtr 6.75E-02 "1.35E+00 1.31E+00- 2.62E+01 e T. Body 1.5 . mreWqtr 4.86E-02 3.24E+00 9.60E-01 6.4 0E+01 Thyroid 5.0 mreWqtr -7.46E-02 1.49E+ 00 -1.52E-01 3.04E+00 Kidney 5.0- mreWqtr 2.34E-02 4.68E-01' 4.44E-01' 8.88E+00 Lung 5.0 mreWgtr 7.37E-03 1.47E-01 1.41E-01 2.82E+00 GI-LLI. 5.0 mreWqtr 3. 92E-03 -7.84E-02 5.41E-02 1.08E+00

-l Cumulative Dose Per Year  !

Organ Tech ' Unit Quarters  % of Tech spec ' l and 2 Spec Limit Limit' ,

Bone 10.0 mreWyr 7.76E-01 7.76E+00- -

Liver 10.0 mreWyr - 1. 3 8E+ 00. 1.38E+01  ;

Total Body 3.0 mrevyr 1.01E+00 .3.36E+01  !

Thyroid 10.0- mreWyr 2. 27E-01 2.27E+00  !

Kidney 10.0 .mreWyr 4.67E-01 ' 4. 67E+ 00 -l Lung 10.0 meeWyr 1.48E-01 1.48E+00 i

'GI-LLI 10' 0

. mreWyr 5.80E-02 5.80E-01 l i

i i

1

t i

TABLE l-4b

!.- E. I. HATCH NUCLEAR PLANf UNIT 2 L SEMIANNUAL EFFLUENT RELEASE REPORT 1987 INDIVIDUAL DOSES DUE TO LIQUID RELEASES j l

Cumulative Dose Per Quarter Organ Tech _ Units Quarter  % of Quartar  % of i Spec Tech 1 2 Tech Limit Spec Spec Limit Limit Bone 5.0 meeWqtr l'. 66E-02 3.32E-01 6.40E-02 1. 28E+ 00 !

Liver 5.0 mreWqtr 2.85E-02 5.70E-01 1.11E-01 2.22E+00 i T. Body 1.5 mreWqtr 2.08E-02 1. 39E+ 00 8.09E-02 5.39E+00 l Thyroid 5.0 mreWqtr 2.72E-03 5.44E-02 1.43E-01 2.86E+00 {

Kidney 5.0 mreWqtr 9.62E-03 1.92E-01 3.79E-02 7.58E-01 J Lung 5.0 mreWqtr 3.11E-03 6. 22E-02 1.20E-02 2.40E-01 GI-LLI 5.0 mreW qtr- 1.94E-03 3.88E-02 3.94E-03 7.88E-02 Cumulative Dose Per Year Organ Tech Unit Quarters  % of Tech Spec 1 and 2 Spec Limit Limit Bone 10.0 mrevyr 8.06E-02 0.06E-01 Livu 10.0 mreWyr 1.40E-01 1.40E+00 Total Body 3.0 mreWyr 1.02E-01 3.40E+00 Thyroid 10.0 mrevyr 1.46E-01 1.46E+00 Kidney 10.0 mreWyr 4.75E-02 4.75E-01 Lung 10.0 mreWyr 1.51E-02 1.51E-01 GI-LLI 10.0 mrem /yr 5.88E-03 5. 88E-02 )

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.~ :,  ! 8 TABLE 1 IMER LIMITS OF DETECTION - LICOID SAMPLE ANALYSES l- , _ The values in this table represent apriori lower limits -

l. of detection (LLD) which are typically achieved in laboratory analyses of liquid radwaste sanples.  !

RADIONUCLIDES LLD UNITS - I Mn-54 U8E-08 uCi/ml q Fe-59 7.78E-08 -

-Co-58 4.67E-08 -j l- Co-60 4.78E l 2n-65 1.31E-07 ,

Mo-99 5.10E-07*

Cs-134 7.18E-08 Co-137 6.05E-08 .,

. Ce-141 1.41E-07  !

Ce-144 6.30E-07*

I- 13 1 6.51E-08 I l Xe-135 8.45E-08 l

! Fe-55 8.00E-07 '

l Sr-89 2.30E-08 Sr-90 7.67E-09 H-3 -

5.00E-07 j

• In accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.1 (Unit 2), Table Notation b, the permissible Lower Limit of ~'

Detection may be increased inversely proportional to the magnitude of the gamma yield. However, the LLD determined in this manner must not exceed

. 10 percent of the Maximum Permissible Concentration (MPC) value _specified

- in 10CFR20, Appendix B, Table II'(Column 2).

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2 GASEOUS EFFLUENTS 2.1 REGULAERY LIMITS The Technical Specifications presented in this section are for Unit '1. Requirements for. Unit 2 are the same as for Unit 1; however, the Technical Specification numbers are not the same.

TECHNICAL SPECIFICATIONS 3.14.2 The radioactive gaseous effluent monitoring -l instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarW trip setpoints set to ensure that the limits of Specification 3.15.2.1(a) are not exceeded.

The alarWtrip setpoints of these channels shall be determined in accordance.with the ODCM.- Technical i Specification Table 3.14.2-1 is included in this section as' I Table 2-1. ) 'l 3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.15-1) .due to radioactive materials released in gaseous effluents from the site .shall be limited to the-following values:

a. The dose rate limit for noble gases shall be less than or equal to 500 mrevyear to the total body and less than or equal to 3000 mre vyear to the j skin. '

b. The dose rate -limit for I-131, I-133, tritium,.

and for all radioactive materials in particulate 1 form and radionuclides other than noble gases -

with half-lives greater than 8 days shall be less than or equal to 1500 mreW year to any organ.

3.15.2.2 The air dose in UNRESTRICTED AREAS (figure i 3.15-1) due to noble gases released in gaseous effluents from each reactor unit'.shall be limited to the following: i

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

b. During any calendar year, to less than or equal l- to 10 mrad for gama radiation and less than or L equal to 20 mrad for beta radiation.

p l 3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLIC

! from I-131, I-133, tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to UNRESTRICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the  !

following: '

l I

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a. During any calendar quarter to less than or equal to 7.5 mrem to any organ.

b. During any calendar year to less than or equal to 15 mrem to any organ.

3.15.2.4 The GASECUS RADWASTE TREATMEtE SYSTEM as described in the ODCM shall be in operation. (This Technical Specification applies whenever the main '

condenser air ejector system is in operation.)

4.15.2.4 GASEOUS RADWASTE TREATMEtR SYSTEM operability shall be demonstrated by administrative controls which assure that the offgas treatment system is not bypassed.

3.15.2.5 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 7S mrem.

(With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.1.2(a), 3.15.1.2(b),

3.15. 2. 2. ( a ) , 3.15. 2. 2( b) , 3.15. 2. 3 ( a ) , or 3.15.2.3(b), calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.15.2.5 have been exceeded. ,

3.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to less than or equal to 4 percent by volume.

3.15.2.7 The gross gamma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation system retreatment monitor station shall be limited to less than or equal to 240,000 uci/second.

6.9.1.9 states in part:

"The Radioactive Effluent Release Report shall include (on a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents that were in excess of 1 C1, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radiciodines for gaseous releases."

_ _ _ _ _ _ _ _ _ _ _ _ _ _ )

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, )

TABLE 3.14.2-1 (SHEET 3 0F 4)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENT Table Notations i i

/ ~

+Detection Monitor mustof I xbe capable 10-' of responding to a lower Limit of pCf/ml.

i l *0uring relea~ses via this pathway.

I  !

• • 0uring main condenser offgas treatment system operation, i

! ***0uring operation of the main condenser air ejector.  !

ACTION 104 - With' the number of channels OPERABLE less than '

required by the Minimum Channels 0PERABLE requirement, effluent releases via this pathway may continue, provided i

the flowrate is-estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.  !

If the number of channels OPERABLE remains less than i required by the Minimum Channels OPERABLE requireme'nt' for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. n

((

ACTION'105 - With the number of channels OPERABLE less than '

required by the Minimum Channels' 0PERABLE requirement, ,

effluent releases via this pathway may continue, provided  !

grab sampler activity within are taken daily and analyzed daily for gross 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

With the number of main stack  ;

monitoring system channels OPERABLE less than required by the Minimum suspend drywellChannels purge. OPERABLE requirement, without delay i; 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 shall be included in the next semi-annual effluent release report. $

i )

ACTION 106 - With the number of channels OPERA 8LE less than required by the Mi.nimum Channels OPERABLE requirement, i

continue provided: operation of the main condenser offgas treatment system may {

(a)

Gas samples are collected once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed  :

within the ensuing 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or $

(b) i Using a temporary hydrogen analyzer installed in the i of fgas system line downstream. of the recombiner, .

l hydrogen every concentration readings are taken and logged _

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

I

_26.

TABLE 2-1 (Cont'd) 1-TABLE 3.14.2-1 (SHEET 4 0F 4) i' f

RADIOACTIVE GASEOUS EFFLUENT ENITORING INSTRUMENTATION

\,

Table ~ Nota tions (Continued)"

(

If the number of channels OPERABLE remains less than (

required by the Minimum Channels. OPERA 8LE requirement.for

[..

' over 30 days, an explanation of the circumstances shall be l' i

included in the next semi-annual effluent release report.  ;

(  !

ACTION 107.- With the' number of channels OPERA 8LE less than -

I required by the Minimum Channels OPERABLE requirement,  ;

effluent releases via this pathway may continue, provided i

) samples are continuously collected with auxiliary sampling .

equipment for periods on the order of 7 days and analyzed within.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter the end of the sampling period.

If the number of channels OPERABLE remains less-than l

required by the Minimum Channels OPERABLE requirement for over 30 days, .an explanation of the circumstances shall be -

included in the' next, semi-annual effluent release report.

s ACTION 108 - With the number of channels OPERABLE less than y ('

required by the Minimum Channels OPERABLE requirement, release to the environment may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided: ( [

a,

'The offgas syst'em is not bypassed, and

b. The offgas po'st-treatment monitor (011-K615) or the main i stack monitor (011-K600).is OPERABLE. -

'l Otherwise, be in at least HOT STAND 8Y within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

If. the n' umber of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report, i

i

)

..n . . .

2.2 MEASUREMEtTr AND APPROXIMATIOtB OF TOTAL RADIOACTIVITY Wa ste gas release at Plant Hatch is confined to L

four paths: main stack (also called the offgas vent), Unit I 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 particulate and iodines. Sample collection is in accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2). Unless required more frequently under certain circumstances specified in Table Notations to the above mentioned tables, samples are collected as follows:

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

2. Tritium samples are collected by grab sampling monthly.

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

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

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

6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly 1 composite sample is analyzed for Sr-89 and St-90. l j

Sample analyses results and release flow rates j frm the four release points form the basis for calculating released quantities of radionuclides-specific radioactivity, dose rates associated with gaseous releases, and cumulative 4 doses for the current quarter and year. This i task is normally performed with computer ]

assistance. j i

l l

1 l

l

i l

. . 1 I

l

)

The noble gas grab sample analysis results are used along with maximum expected release flow i rates from each of the four vents to calculate monitor setpoints for the gaseous effluent monitors serving the four release points, to j

assure that the limits of Technjcal j specifications 3.15.2.1.a (Unit 1) or 3.11.2.1.a  !

(Unit 2) are not exceeded. Calculation of monitor setpoints is described in the Plant Hatch ODCM.

With each release period released radioactivity, dose rates, and cumulative doses are calculated.

Cumulative dose results are tabulated along with percent of Technical Specification limits (3.15.2.2 and 3.15.2.3 (Unit 1); 3.11.2.2 and 3.11.2.3 (Unit 2) for each release, for the current quarter and year.

After each calendar quarter (13 weeks) a summary of waste gas releases from the four vents is compiled for preparation of the Semiannual Effluent Release Report required by Technical Specifications 6.9.1.8 and 6.9.1.9 and described in IRC Regulatory Guide 1.21.

The methods for determining released quantities of radioactivity, dose rates and cumulative doses are as follows:

1. FISSION AND ACTIVATION GAS The radionuclides-specific released radioactivity is determined from saqple analyses results collected as described above and average release flow rates over the period represented by the collected sample.

Instantaneous dose rates due to noble gases and due to radioiodines, tritium, and particulate are calculated (with computer assistance). {

Calculated dose rates are compared to the dose  !

rate limits specified in 3.15.2.1.a (Unit 1) and 3.11. 2.1.a (Unit 2) for noble gases; and 3.15.2.1 b (Unit 1) and 3.11.2.1.b (Unit 2) for radiciodine, t ~. tium, and particulate. Dose rate calculation methodology is presented in the Plant Hatch ODCM.

'I

(

Beta and gansna air doses due to noble gases are

- calculated for the location in the unrestricted area with the potential for the highest exposure l due to gaseous releases. Air doses are calculated for each release period and cumulative  ;

totals are kept for each unit for the current calendar-quarter and year. Cumulative air doses j

are compared to the dose limits specified in  ;

Technical Specifications 3.15.2.2 (Unit 1) and j 3.11.2.2 (Unit 2) . - Current percent of technical  :

specification limits are shown on the printout for each release period. Air dose calculation methodology is presented in the Plant Hatch ODCM.

2. RADIOIODINE, TRITIUM, AND PARTICULATE RELEASES i

Released quantities of radioiodines are determined from the weekly samples and release flow rates for the four release points.

Radioiodine concentrations are determined by gama spectroscopy.

Released quantities of particulate are determined from the wekly (filter) samples and release flow rates for the four release points, j Gamma spectroscopy is used to quantify i concentrations of principal ganina emitters.

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

flows and vent flows are almost constant over each quarterly period the filters fran each vent can be dissolved together. Decay corrections are ,

made back to the middle of the quarterly l collection period. Where significant Sr-89 or Sr-90 is not detected, LLD's are calculated. l Strontium concentrations are input to the q j

composite file of the computer to be used in release, dose rate and individual dose calculations. j Tritium samples are obtained monthly from each \

vent by passing the sample stream through a cold trap. The grams of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water L vapor collection efficiencies. The tritium j; samples are analyzed by an independent laboratory l j

and results are furnished in uCi/ml of water, j The tritium concentration in water is converted to tritium concentration in air and this value is input into the composite file of the computer to be used in release, dose rate, and individual dose calculations.

l 1

1 l L

~ ;. . j

' j ';

1 Dose rates due to radioiodine, tritium, and particulate are calculated for a hypothetical child, exposed to the inhalation pathey, 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 rate from all four release points are conpared to the dose rate limits specified in Technical Specifications 3.15.2.1.b (Unit 1) or 3.11.2.1.b (Unit 2) . j Individual doses due to radiciodine, tritium, and .!

particulate are calculated for the critical receptor, which for Plant Hatch is an infant .j f

exposed to the grass-cow-milk, inhalation, and ground-plane pathways. ' Individual doses are calculated for each release period and cumulative totals are kept for each unit for the current calendar quarter and War. Cumulative individual .

doses are compared to the dose limits specified in Technical Specifications 3.15.2.3 (Unit 1) and 3.11.2. 3 (Unit 2) . Current percent of technical specification limits are shown on the printout for each release period.

3. GROSS ALPHA RELEASE The gross alpha release is computed each month by counting the particulate filters 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 sunnled at the end of the month. This concentration is input to i the composite file of the computer and is used '

for release calculations.

4. ERROR ESTIMATES Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported, These estimates are required for the total '

s fission and activatico gas release, total I-131 release, total particulate with half-lives greater than 8-day release, and total tritium release. ,

I i

i

.J, O

"The total or maximum error associated with the-effluent. measurement will include the cumulative errors resulting from the total operation of-sampling and measurement. Because.it may be very difficult to assign error terms for each l' parameter' affecting the final measurement, detailed. statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive naterials 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 sanple losses for such items as charcoal cartridges, ,

(1) Fission and Activaticn Total Release was i l

calculated from sample analysis results and release point flow rates. i Statistical Error 60%

Counting Equipment Calibration 10%  ;

Vent Flow Rates 10%

. Non-Steady Release Rates _20%

100%

( 2) I-131 Release was calculated from each weekly i sanple:

Statistical Error- 60%

Counting Equipment Calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

)

Losses From Charcoal Cartridge 10% )

110%

' ( 3) Particulate with half-lives greater than 8 days release was calculated from sanple analysis results and release point flow rates.

Statistical Error at LLD concentration 60%

Counting Equipment Calbration 10%

Vent Flow Rates 10%

j Vent Sample Flow Rates 10 %

Non-Steady Release Rates 10% i 100%

l (4) : Total Tritityn Release was dominated by the reactor building vent tritium release; hence, the larger statistical errors of the off-gas vent and j recombiner building vent tritium releases do not '

affect the error in- the total tritium release:

l

~ Water Vapor in Sanple Stream Determination 20%

Vent Flow Rates 10%

' Counting Calibration and Statistics 10 %

Non-Steady Release 50%

90 % !

2.3 GASEDUS EFFLUENP RELEASE DATA Regulatory Guide 1.21 Tables 1A,18, and 1C are found in this report as Tables 2-2a-c, 2-3a-c, and 2-4a-c. I Data 'are presented on a quarterly basis as required by Regulatory Guide 1.21.

To complete Tables 2-2a-c, total release for each of

. the four categories (fission and activation gases; iodines; particulate; and tritium) was divided by the number of-seconds in the quarter to obtain a release rate in uCi/second for each category. -

However, the applicable Technical Specification limits are not.in terms of release rate in uCi/second but in ' I terms of dose rate in mrenVWar, as presented in Technical Specifications 3.15.2.1 (Unit 1) and 3.11. 2.1 ( Unit 2) . Noble gases are limited as specified in 3.15.2.1.a and 3.11.2.1.a. The other three categories (tritium, radioiodines, and parheulates) are limited as a group as specified in 3.1L 2.1.b and 3.11. 2.1.b. Further the limits specified in Technical Specifications 3.15.2.1 and 3.11.2.1 are site limits, not unit limits. Dose rates due to noble gas releases and due to radiciodine, tritium, and particulate are presented in Table 2-5 I along with percent of technical specification limits. l Gross alpha radioactivity is reported in Tables 2-2a, 2-2b, and 2-2c as curies released in each quarter.

Limits for cumulative beta and gamma air doses, due to noble gases, are specified in Technical Specifications

! 3.15.2.2 (Unit 1) and 3.11. 2. 2 ( Unit 2). These limits L

are unit limits. Cumulative air doses are presented

' in Tables 2-6a and 2-66, along with percent of j technical specification limits. 1 i

1

. .. a 1

)

Limits for cumulative ' individual doses, due to i radiciodine, tritium, and particulate, are specified in Technical Specifications 3.15.2.3 (Unit '1) and 3.11.2.3 (Unit 2). These limits are also unit limits.' Cumulative individual doses are presented in L Tables 2-7a and 2-7b, with percent of technical specification limits.,

L 2.4 RADIOWGICAL . IMPACT DUE TO GASEDUS RELEASES i

l L Dose rates &e to noble gas releases were calculated i for the site in accordance with Technical Specifications 3/4,15.2.1.a (Unit 1) and 3/4.11.2.1.a j (Unit 2). Results are presented in Table 2-5. Dose l l

' rates &e to radiciodine, trititzn, and particulate in ]

gaseous releases were calculated in accordance with i Technical Specifications 3/4.15.2.1.b (Unit 1) and 3/4.11.2.1.b (Unit 2) . These results are also in  ;

Table 2-5.

l Cumulative air doses due to noble gas releases were calculated for each unitiin accordance with Technical Specification 3/4.15.2.2 (Unit' 1) and 3/4.11.2.2 (Unit 2). These results are presented in Tables 2-6a and-2-66.

Cumulative doses to an individual due to radioiodine, tritium , and particulate were calculated for each unit in accordance with Technical Specifications '

3/4.15.2.3 (Unit 1) and 3/4.11.2.3 (Unit 2). These I results are presented in Tables 2-7a and 2-7b.

l Dose rates and doses were calculated using the methocblogy presented in the Plant Hatch Offsite Dose  !

Calculation Manual. I l

I

! ,r 7 1, o 4

TABLE 2-2a '

x E.^I. HATOi NUCLEAR PLANT - UNIT ~1 l]/'

'm N"

. f.n~

SEMIANNUAL. RADIOACTIVE EFFLUENT RELEASE REIORT 1987-GASB00S! EFFLUENTS - SLNMATION OF ALL RELEASES

/ ) 1.

E. I. Hatch , Unit -Quarter Quarter -Est. Total Nuclear Plant 1 2 Error %

4 .- A. Fission &

?.h- Activation t .-

Gases

-( 1.' Total 4 -Ci

2. 63E+ 02 7.99E+ 02 1.00E+ 02 4 ) Release I

2. Averaga l' uCi/sec '3. 38E+ 01 1.02E+02 l Release 4t' 1. ,

Rate For

I .'Per'iod 4 *3.  %

of %ch  %

' Spec Limit.

g> ' . B. lodinek .

a l'. Total. Ci 9.53E-03 1.92E-02 1.10E+ 02.

Iodine-131

-2. Average uCi/sec 1.23E-03 2.44E-03 Release-

' Rate For Period

, *3. % of n ch  %

{' .

Spec Limit C. Particulate I

1. Particulate .Ci 1.11E-03 2.168-03 1.00E+ 02

.d' with half-

/./ / lives 8 3 F

o / days

2. Average i; y

uCi/ rec 1.43E-04 .2.75E-04 Release Rate Fori' I fl .

Period

--

• 3. % of Tech  %

Spec Limit. I

4. Gross Alpha C.j' 1.55E-06 7.09E-06 Radioactiv- -

i

' i ty g D. Tritium '

1. Total Release C1 2.44E+00 5.84E+00 9.00E+ 01 )

2. Average uCi/sec 3.14E-01 Release 7.43E-01

)

Rate For-Period

• 3. % of Tech  %

Spec Limit -

,i

'L  ; ?l ,

l

• Technical Specification limits are in terms of dose rate ]

(mrem /yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, j 2-7a, and 2-7b. _ _ - _ _ _ a

.u.

t' P

TABLE ' 2-2b E. I. HATCH NUGEAR PLANI - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENI F".Gd REPORT 1987 GASEQUS EFFLUENTS - SIM4ATr.4 CF ALL RELEASES ' 't

l. l l l L B. I. Hatch' Unit Quarter Quarter Est. Total' 1

!- ' Nuclear Plant ~ 1- 2 Error % )

1 ,

I- A.. Fission ti Activation Gases k l' 1.-Total- Ci' 3.01E+02 ' 4. 29E+ 03 1.COE+02 l ,

1

.iRelease. ..,

2.TAverage . uCi/sec ' 3.87E+01 - 5.46E+02 Release- I Rate ' For <

Period .

• 3. % of 'Mch li,  !

Spec Limit B. Iodines

1. 'Ibtal'- Ci 8. 39E-04 2.31E-02 1.10E+ 02 Iodine-131

2. Average ~ uCi/sec 1.0 88-04 2.94E-03

.1 Release 7 ate For Period

• 3. % of Tech- .% '

Spec Limit C. Particulate '

1. Particulate Ci 2.1/E-04 -1.198-03 1.00E+ 02 l with half- ,

lives 8

> - days

2. Average uCi/sec 2.75E-05 1.51E-04 Release.

Rate For Peried

• 3. % of Tech  % 1 Spec Limit

4. Gross Alpha ci 1.07E-06 4.433-06 Radioactiv-ity D. Tritium i

1. Total Ci 5. 28E+ 00 . 2. 39E+01 9 .0 0E+ 0.'.

Release  !

2. Average uCi/sec 6.79E-01 3.04E+00 Release Rate hit Period

• 3. % of Tech  %

Spec Limit

• Techn'ical Specification limits are in terms of done rate (mredyr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b.

t

.1 TABLE 2-2c l- E. I. HATCH NUCLEAR PLANr - SITE l SENIANNUAL RADIOACTIVE EFFLUENT RELEASE REEORT 1987 GASEOUS EFFLUENTS.- SINMATION OF ALL RELEASES

. E. I. Hatch ' Unit Quarter Quarter Est. Total Nuclear Plant 'l 2 Error %

1' A. Fission &

Activation Gases

1. Total Ci 5.64E+02 5.09E+03 1.00E+ 02 Release I

r .- '2. Average uCi/sec 7. 25E+ 01 6. 47E+ 02 I' Release Rate For 1 Period l

• 3. %'of Tech  %

Spec Limit i B.- Iodines- 1

1. Total. C1 1.04E-02 4.22E-02 1.10E+02 Iodine-131

2. Average uCi/sec 1. 34E-03 5.37E-03

)

Release .

^

Rate For Period I

• 3. % of 'Dech  %

Spec Limit C. Particulate i

1. Particulate C1 1.32E-03 3.34E-03 1.00E+ 02 .!

with half-lives 8 chys

'2. Average (C1/sec 1.70E-04 4. 25E-04  !

Release Rate For Period

• 3. % of Tech  %

Spec Limit

4. Gross Alpha ci 2.62E-06 1.15E-05 Radioactiv-ity' i D. Tritium

1. Total Ci 7.72E+ 00 2.97E+01 9.00E+ 01 Release

2. Average uCi/sec 9.93E-01 3.78E+00 Release Rate For Period

• 3. % of Tech  %

Spec Limit

• Techtiical Specification limits are in terms of dose rate (mreWyr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b.

TABLE 2-3a E. I. HATCH NUCLEAR PLATE - UNIT 1 SENIAtUUAL RADIOACTIVE EFFLUEfC RELEASE REIVRT 1987 GASDOUS EFFLUEBES - ELEVATED RELEASE

• Continuous Mode Batch Mode ** '

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fissicti Gases Kr-85 Ci 0. 00E+00 0. 00E+00 Kr-85m C1 1. 21E+ 01 2.02E+00 K r-87 Ci 1.18E+00 1.12E+ 00 j K r-88 Ci 0.00E+00 0.00E+00 Xe-133 C1 1.88E+02 4.16E+01 Xe-135 Ci 1.22E+01 3.02E+ 00 Xe-135m Ci 4.33E+00 6.372+00 Xe-138 Ci 0. 00E+ 00 0.00E+00 Xe-131m Ci 0.00E+00 0. 00E+00 Xe-133m Ci 0.00E+ 00 1.00E+00 Xe-137 Ci 0.00E+00 0. 00E+ 00 A r-41 Ci 0.00E+00 0.00E+00 IUTAL FOR PERIOD Ci 2.18E+ 02 5.42E+01

2. Iodines I- 13 1 Ci 5.91E-04 2.42E-04 I-133 Ci 1.29E-04 4. 94E-05 I- 135 C1 1.56E-05 7. 38E-06 1UTAL FOR PERIOD Ci 7.35E-04 2.98E-04

3. Particu-lates C r-51 Ci 0.00E+00 0. 00E+ 00 Mn- 54 Ci 0.00E+00 0.00E+ 00 Co.-58 Ci 0. 00Et00 0. 00E+ 00 l Co-60 Ci 0. 00E+ 00 0.00E+00 Zn-65 Ci 0. 00E+ 00 0. 00E+ 00 Sr-89 Ci 4.43E-05 9.21E-06 S r- 90 Ci 1.16E-06 1. 44E-0 7 tb-95 Ci 0.00E+ 00 0.00E+00 Ce-134 Ci 0.00E+00 0. 00E+00 Co-137 Ci 1.15E-07 0.00E+00 Ba-140 Ci 1. 78E-06 6. 62E-06 La- 140 Ci 8.81E-07 3.60E-06 1 DIAL FOR PERIOD Ci 4.82E-05 1.96E-05

• Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

• • There are no batch noch radioactive gaseous release pathways at Plant Hatch. - _ _ - _ _ _ _

\  ;

L TABLE 2-3b E. I. HATCH 10 CLEAR PLA17f - UNIT 2  !

SEMIANt0AL RADIOACTIVE EFFLUEtTP RELEASE REPORT 1987 j GASEOUS EFFLUENTS - ELEVATED RELEASE

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 !

1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m C1 1.21E+01 6. 29E+ 01 Kr-87 Ci 1.18E+00 4.77E+01 Kr-88 Ci 0.00E+00 3.36E+01 Xe-133 C1 1.88E+02 1.12E+03 Xe-135 C1 1.22E+01 8.36E+02 .

Xe-135m Ci 4.33E+00 5.05E+02 l Xe-138 Ci 0.00E+00 2.88E+02 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 2.59E+01 Xe-107 Ci 0.00E+00 0.00E+00 A r-41 Ci 0.00E+00 0.00E+00  :

'IUrAL FOR PERIOD Ci 2.18E+ 02 2.92E+03 1

2. Iodines '

I- 131 Ci 5.91E-04 6.55E-03 I-133 C1 1.29E-04 1.61E-03 I-135 C1 1.56E-05 2.72E-04 TOTAL FOR l PERIOD Ci 7.35E-04 8.44E-03

3. Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn- 54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Z n-65 Ci 0.00E+00 0. 00E+00 l St-89 Ci 4.43E-05 5.41E-05 Sr-90 C1 1.16E-06 8. 46E-07 Nb-95 Ci 0.00E+ 00 5.71E-07 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 1.15E-07 3.39E-06 Ba-140 C1 1.78E-06 1.25E-24 La-140 Ci 8.81E-07 8.34E-05 ~

'IUrAL FOR i PERIOD C1 4.28E-05 2. 68E-04

• Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

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

s TABLE 2-3c E. I. HATCH NUCLEAR PLANI - SITE

-SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 GASCOUS EFFLUENIS - ELEVATED RELEASE

• Continuous Mode Batch Mode ** 1

, Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. ' Fission Gades Kr-85 Ci 0.00E+00 0.00E+00' Kr-85m -Ci 2. 41E+ 01 6.49E+ 01 Kr-87 C1 2.35E+00 4.88E+01 i Kr-88 Ci 0.00E+00! 3. 36E+ 01 ~ i Xe-133 Ci 3.76E+02 1.16E+03 Xe-135 C1 2.43E+01 8. 39E+ 02 Xe-135m Ci 8. 66E+ 00 5.12E+02 Xe-138 Ci 0.00E+00 2.88E+02 Xe-131m Ci 0.00E+00- 0.00E+00 Xe-133m ' Ci 0.00E+00 2.59E+ 01 i Xe-137 Ci 0.00E+00 0.00E+00 A r-41 Ci 0.00E+00 0.00E+00

'ICIAL FOR PERIOD Ci 4.36E+02 2. 97E+ 03

2. Iodines I-131 C1 1.18E-03 6.79E-03 I-133- Ci 2.57E-04 1. 66E-03 I- 135 Ci- 3.13E-05 2.79E-04

'IUIAL FOR PERIOD C1 1.47E-03 8.74E-03

3. Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 7o-58 Ci 0.00E+00 0. 00E+00 Co-60 Ci 0.00E+00 0.00E+00  ;

7.n-65 Ci 0.00E+00

~

0.00E+00 Sr-89 Ci 8.85E-05 6.33E-05 Sr-90 Ci 2.32E-06 9.90E-07 Nb-95 Ci 0.00E+00 5.71E-07 Cs-134 Ci 0.00E+00 0.00E+00 '

Cs-137 Ci 2.30E-07 3.39E-06 Ba-140 Ci 3.57E-06 1.32E-04 ra-140 C1 1.76E-06 8.70E-05 i

'IDIAL FOR PERIOD Ci 9.64E-05 2.87E-04

• Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

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

4 TABLE 2-4c E. I. HATCH NUCLEAR PLAUF - SITE SEMIANIRAL RADIOACTIVE EFFLUEllr RELEASE REEORT 1987 GASEOW EFFLUENTS - GROUND-LEVEL RELEASES

• Continuous Mode Batch Mode **

FMc11 des Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Kr-85 Ci 0.00E+00 0. 00E+00 Kr-85m Ci 7.60E+00- 1. 63E+ 01 Kr-87 Ci 0. 00E+ 00 5.75E+01 Kr-88 Ci 0.00E+00 4.21E+01 Xe-133 Ci 4. 29E+01 7. 2 4E+02 Xe-135 Ci 7.82E+01 7.73E+ 02 Xe-135m Ci 0. 00E+00 4. 2 9E+02 Xe-138 Ci 0.00E+00 7.66E+01 Xe-131m Ci 0. 00E+00 0. 00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 0. 00E+ 00 0. 00E+ 00 A r-41 Ci 0.00E+00 0.00E+ 00 IUfAL EVR PERIOD C1 1. 29E+ 02 2.12E+ 03

2. Iodines I- 13 1 Ci 9.19E-03 3.54E-02 I-133 C1 1. 54E-03 1. 83E-02 I- 135 Ci 2. 47E-04 5. 37E-03 20TAL FOR PERIOD Ci 1.10E-02 5.91E-02

3. Particu-lates Cr-51 Ci 2. 4 7E-04 0. 00E+00 Mn-54 C1 1.43E-06 5.04E-06 Co-58 Ci 1.3 7E-05 1.GlL-06 Co-60 Ci 4.05E-05 2.71E-05 ta-65 Ci 3.7 6E-04 1. 2 4E-04 Sr-89 Ci 2.31E-04 2.50E-03 St-90 Ci 1. 3 6E-06 2.01E-06 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 1.41E-04 1. 2 7E-05 Cs-137 C1 1.72E-04 4.0 9E-05 Ba-140 Ci 0. 0 0E+00 1.85E-04 La-140 Ci 0.00E+00 1. 58E-04 TOTAL FOR PERIOD Ci 1.22E-03 3.06E-03 l

• 2eroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

l l **There are no batch mode radioactive gaseous release pathways at I l Plant Hatch. _3,,

~

_________________ _ ____ l

TA3LE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REIORT 1987 GASEDUS EFFLUENTS - GROUND-LEVEL RELEASES

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases Kr-85 Ci 0. 00E+00 0. 00E+00 Kr-85m Ci 7.31E+00 1.63E+01 K r-87 Ci 0.00E+00 l 5.75E+01 Kr-88 Ci i 0.00E+00 4.21E+01 Xe-133 Ci 2.71E+01 2.85E+02 i Xe-135 Ci 4.92E+01 4.87E+02 '

Xe-135m Ci 0.0 0E+00 4.10E+02 Xe-138 Ci 0.00E+00 7.66E+01 Xe-131m Ci 0. 0 0E+00 0. 00E+00 he-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 0. 00E+ 00 0. 00E+00 A r-41 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 8.36E+01 1. 37E+ 03

2. Iodines I- 13 1 C1 2. 4 8E-04 1.65E-02 I I- 133 C1 1.19E-04 8.19E-03 I- 13 5 Ci 6.61E-06 2.67E-03 TOTAL FOR PERIOD Ci 3.74E-04 2.73E-02

3. Particu-lates Cr-51 Ci 0. 0 0E+ 00 0. 00E+00 Mn-54 Ci 0.00E+00 5.04E-06 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 1.56E-06 Zn-65 Ci 0.00 +00 6. 82E-06 Sr-89 Ci 1.65E-04 '.32E-04 i

Sr-90 Ci 0.00E+00 1.30E-06 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 8.12E-07 C s-137 Ci 0.00E+00 4.88E-06 Ba-140 Ci 0.00E+00 8.092-05 La-140 Ci 0.00E+00 8.45E-05 TOTAL FOR '

PERIOD C1 1.65E-04 9.18E-04

• Zeroes in this table indicate that no radioactivity was present '

above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.

• • There are no batch mcb radioactive gaseous release pathways at Plant Ha'_ch.

I

TABLE 2-4a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADICACfIVE EFFLUEtTf RELEASE REIORT 1987 GASECUS EFFLUENfS - GROJND-LEVEL RELEASES * .

Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fissicn Gases Kr-85 Ci 0.00E+00 0. 00E+ 00 Kr-85m C1 2.89E-01 0.00E+00 Kr-87 Ci 0. 00E+00 0. 00E+ 00 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133 C1 1.58E+01 4.40E+02 Xe-135 C1 2.90E+01 2.86E+02 Xe-135m Ci 0.00E+00 1. 95E+01 Xe-13 8 Ci 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 0. 00E+00 0.00E+00 A r-41 Ci 0.00E+00 0.00E+00

'IUfAL FOR PERIOD Ci 4.51E+01 7.45E+02

2. Iodines I- 131 Ci 8.94E-03 1.90E-02 {

I-133 C1 1. 42E-03 1.01E-02 I-135 Ci 2.41E-04 2.70E-03

'IOrAL EDR PERIOD C1 1.06E-02 3.18E-02

(

3. Particu-1ates {

Cr-51 Ci 2.47E-04 0.00E+00 l Mn~ 54 C1 1.43E-06 0.00E+00 Co-58 Ci l 1.37E-05 1.81E-06 l Co-60 Ci 4.05E-05 2.55E-05 Zrr65 Ci 3.76E-04 1.17E-04 I St-89 Ci 6.51E-05 1.77E-03 Sr-90 C1 1.36E-06 7.12E-07 Nb-95 Ci 0.00E+00 0.00E+00 Co-134 C1 1.41E-04 1.19E-0 5 Cs-137 C1 1.72E-04 3.60E-05 Ba-140 Ci 0. 00E+00 1.04E-04 La- 140 Ci 0.00E+00 7.36E-05

'IUTAL FOR PERIOD Ci 1.06E-03 2.14E-03 1

• Zeroes in this table indicate that no radioactivity was present l l above detectable levels. See Table 2-8 for typical lower limits of I detection for gaseous sample analyses.

• • There are no batch moch radioactive gaseous release patheys at Plant Hatch.

{ ,

t_-_---__-------------

]

TABLE 2-5 ' <

E. I. HATCH NUCLEAR PLAlq,. ,JITE l a

SEMIANNUAL RADI0 ACTIVE EFFLUENT ItELEASE REMRT 1987 GASEOUS EFFLUEtTIS - DOSE RATES Dose Rates Due to Noble Gases I Organ Tech Unit Quarter  % of Quarter  % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Total 500 mreWyr 1.44E-01 2.88E-02 4.04E+00 8.08E-01 Body Skin 3000 mreWyr 3.21E-01 1.07E-02 7.34E+00 2.44E-01 Dose Rates Due to Radiciodine, Tritium, and Particulate Organ Tech Unit Quarter  % of Quarter  % of f Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 1500 mreWyr 8.85E-04 5.90E-05 3.278-03 2.18E-04 Liver 1500 mreW yr 8.23E-03 5.49E-04 3.07E-02 2.05E-03 Total 1500 mreWyr Body 7.84E-03 5.23E-04 2.998-02 1.99E-03 Thyroid 1500 mreWyr 1.43E-01 9.538-03 5.89E-01 3.932-02 Kidney 1500 mreWyr 8.31E-03 5.54E-04 3.18E-02 2.12E-03 Long 1500 mreWyr 8.61E-03 5.74E-04 3.42E-02 2.28E-03 ,

GI-LLI 1500 mrenvyr 7.60E-03 5.07E-04 2.94E-02 1.96E-03 1

1 l

TABLE 2-6a E. I. liATO! FCCLEAR PLAfE - UNIT 1 SEMIA!RUAL RADIOACTIVE EFFLUEfC RELEASE REEORT 1987 AIR DOSES DUE 10 tOBLE GAS REL2ASES Cumulative Doses Per Quarter Type Tech Unit Quarter  % of Quarter  % of of Spec 1 Tech 2 Tech Radi- Limit Spec Spec aticn Limit Limit Gantna 5.0 mead 1.35E-02 2.68E-01 1.66E-01 3.32E+00

_ Beta 10.0 mrad 1.99E-02 1. 98E-01 2. 55E-01 2.55E+00 Cumulative Doses Per Year Type of Tuch Unit Quarters  % of Tech Radiation Spec 1 and 2 Spec Limit Limit Gamma 10.0 mrad 1.79E-01 1.79E+ 00 Beta 20.0 mrad 2.75E-01 1. 3 88+00 1

l 1

i l

i

. TABLE 2-6b B. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REIORT 1987 AIR DCEES DUE 'IO NOBLE GAS RELEASES '

1 Cumulative Doses'Per Quarter 4 Type 'Iech Unit Quarter.  % of Quarter  % of I of Spec l' Tech 2 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 ' mrad. 2. 46E-02 4.92E-01' 9.05E-01 1.81E+01 Beta 10.0 mrad 3.62E-02 3.62E-01 6.46E-01 6.46E+ 00 Cumulative Doses Per Year Type of Tech Unit Quarters  % of Tech Radiation- Spec 1 and 2. Spec Limit Limit-Gamma 10.0 ' mrad 9.30E-01 9.30E+00 Beta 20.0 mrad 6.82E-01 3.41E+00 I

J 1

l l

i

TABLE 2-7a E. I, HATCH NUCLEAR PLATE - UNIT 1 SEMIAta.UAL RADIOACTIVE EFFLUEbc RELEASE REIORT 1987 INDIVIDUAL DOSES DUE 'IO RADIOIODIBE, TRITIUM, i J AND PARTICJLATES IN GASEDUS RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter  % of Quarter  % of Spec 1 Tech 2 Tech Limit Spec Spec l Limit Limit Bone 7.5 mrem 2.78E-03 3.71E-02 4.81E-03 6.41E-02 Liver 7.5 mrem 3. 81E-03 5.08E-02 4. 49E-03 5.99E-02 Tot. Body 7.5 mrem 1. 4 8E-03 1.9 72-02 2.19E-03 2.92E-02 Thyroid 7.5 mrem 5.85E-01 7.80E+ 00 2.23E+00 1.64E+ 01 Kidney 7.5 mrem 3.00E-03 4.00E-02 4.91E-03 6.55E-02 Lung 7.5 mrem 5. 27E-04 7.03E-03 5.25E-04 7.00E-03 GI-LLI 7.5 mrem 8.21E-04 1.09E-02 7.12E-04 9.4 9E-03 Cumulative Dose Per Year Organ Tech Unit Quarters  % of Tech Spec 1 and 2 Spec Limit Limit Bone 15.0 mrem 7.59E-03 5.06E-02 Liver 15.0 mrem 8.30E-03 5.53E-02 Total Body 15.0 mrem 3. 67E-03 2.45E-02 Thyroid 15.0 mrem 1. 82E+ 00 1.21E+01 Kidney 15.0 mrem 7.91E-03 5. 27E-02 Lung 15.0 mrem 1.058-03 7.01E-03 GI-LLI 15.0 mrem 1.53E-03 1.02E-02 _

l

• TABLE 2-7b E. I. HATCH NUCLEAR PLANP - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REEORT 1987 If0IVIDUAL DOSES DUE 'IO RADI0 IODINE, TRITIUM, AND PARTICULATE IN GASEDUS RELEASES Cumulative Dose Per Quarter Organ 'Nch Unit Quarter  % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 2.20E-04 2.93E-03 3.78E-03 5.04E-02 Liver 7.5 mrem 3.98E-04 5.31E-03 5.15E-03 6.87E-02 Tot. Body 7.5 mrem 3.53E-04 4.71E-03 3. 07E-03 4.0 9E-02 Thyroid 7.5 mrem 2.998-02 3.99E-01 1.21E+00 1.61E+ 01 Kidney 7.5 mrem 4.13E-04 5.51E-03 5. 76E-03 7.68E-02 Lung 7.5 mrem 3.15E-04 4.20E-03 1.46E-03 1.95E-02 GI-LLI 7.5 mrem 3.15E-04 4.20E-03 1.582-03 2.11E-02 Cumulative Dose Per Year Organ Tech Unit Quarters  % of Tech Spec 1 and 2 Spec Limit Limit Bone 15.0 mrem 4. 00E-03 2.67E-02 Liver 15.0 mrem 5.55E-03 3.70E-02 Total Body 15.0 mrem 3.428-03 2.28E-02 Thyroid 15.0 mrem 1.24E+00 8.27E+00 l Kidney 15.0 mrem 6.17E-03 4.11E-02 l

Lung 15.0 mrem 1. 78E-03 1.198-02 GI-LLI 15.0 mrem 1.90E-03 1. 27E-02 l

l

! l

l l TABLE 2-8 LOWER LIMITS OF DETECTION - GASEQUS SAMPLE ANALYSES l Tte values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of gaseous radwaste sanples.

_ RADIONUCLIDES LLD UNITS l Kr-87 1.31E-07 uC1/nd l Kr-88 2.10E-07 Xe-133 1. 62E-07 Xe-133m 6.07E-08 Xe-135 5. 77E-08 Xe-138 2.85E-06 I- 131 4. 37E-14 I- 133 6.16E-13 Mn-54 2. 78E-14 Fe-59 4.62E-14 Co-58 2. 46E-14 Co-60 2. 88E-14 Zn-65 7.51E-14 Mo-99 6.02E-13 Ce-134 3. 64E-14 Cs-137 2.88E-14 Ce-141 4.948-14 Ce-144 2.02E-13 Sr-89 1.17E-14 S r-90 3.82E-15 H-3 5. 82E-12

(

i

3. ' _S OLID WASTE 3.1 REGULATORY REQUIRDiENTS The Technical Specifications presented in this section are for Unit-1. Requirements for Unit-2 are the same as for Unit 1; however, the <

Technical Specification numbers are not the sam.

TECHNICAL SPECIFICATIONS 3.15.3.1 The solid radwaste system shall be used in i accordance with the PROCESS COtTIROL PROGRAM to provide i for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

6.9.1.9 states in part:

The Radioactive Effluent Release Report shall include I the following information for each type of solid waste shipped offsite during the report period:

a. Container volume

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

c. Principal radionuclides (specify whether determined by masurement or estimte)

d. Type of waste, e.g., -spent resin, compacted dry waste, evaporator bottoms

e. Typ! of container, e.g., [SA, type A, type B,

~1arge quantity

f. Solidification agent, e.g., cement.

3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-la. and 3-lb. i l

l

, . l

** ' ~ ^

. Table 3-la EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) January-June,1987  ;

SOLIO WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I & II SOL 10 WASTE SHIPPE0 0FFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel). .

I I I I I l 1. Type of waste l

l UNIT l 6 month lEst. Totall l l period i ERROR % l l a. Spent resins, filter studges, evaporator l mJ l 1. 58E+2l l l- bottoms'. etc. I Ci 1 7. O sE +21 1. O E -1 l l

b. Dry compressible waste, contaminated l mJ l R. 69E +11 l equio. etc.

Ci 4. o hn 7. 0 E -1

c. Irradiated components, control rods, mJ n. E- o etc. Ci i

I n. E I a E l j l d. Other (describe) l mJ l n. E n l l eaulo. etc. I Ci l n. E n. E l

2. Estimate of major nuclide composition (by type of waste) l IS0 TOPE I PERCENT l CURIES l l l l

a. Zn-63 34.26 Cs-137 1 l 241.55 l l

l 12.80 l 90.24 l Cr-51 11.62-

.I l 81.95 l All others

b. Zn-65 1 41 31 l 291.26 l l l 52.89 l 2.13 Co-60 l l l 28.06 l 1.13 Cs-137 -

l l I 6.95 1 0.28 All others l l l 12,17 1 0,49 l

, l c. l l l l 1 1 1 l l 1 l l- 1 I l  ;

l d. 1 I

• l l -

1 I l 1 I I I )

l- 1 l l

l l l

3. Solid Waste Disposition ,

,e -

Number of Shioments Mode of Transportation Oestina' tion ,

29 Cask Barnwe.11 4 Van Barnwell

4. IRRA0!ATED FUEL SHIPMENTS (Disposition)

Number of Shioments Mode of Transportal fo'n Destination 0 N/A N/A 1

l l

l

_ _ _ _ - _ _ _ _ _ _ 1

a EFFLUENT AND WASTE DISPOSAL' SEMIANNUAL REPORT (YEAR) 1987 ->

SOLID WASTE AND IRRADIATED FUEL SHIPMENT i

FOR UNIT I AND II - .

,' TABLE 3-lh l JANUARY-~ JUNE 1987

. t l l

CURIE PRINCIPLE BURIAL NUMBER OF iYFE I VOLUME OF .

l QUANTITY / NUCLIDES I ' CONTAINER CONTAINERS EACH CONTAINER SHIPPIN6 TYPE OF WASTE SETERMINED GETERMINA!!0N DESCRIPi!0N SHIPPED CUllC FEET Ht3) CONTAINER l

OEWATERED' 26.00 IN-65,CO-60,MN-54, CARBON STEEL 5 206- LSA RESIN HEASURED CS 134,CS-137' LINER TYPE A

!. MEASURED -

. 1 l

DEWATERED l'06.26 IN-65,CO-60,MM 54,- CARBON STEEL 16 199 LSA l RESIN MEASURED CS-134,CS-137 . LINER. TYPE A J MEASURED l

OEWATERED 33.92 IN-65,00-60,MM-54, HIGH j RES!N. MEASURED CS-134,CS-137 (NTE6RITY 2 193 LSA MEASURED CONTAINER TYPE A

m. .9 k

DEWATERED 328.62 ZN-65,C0-60,MN-54, HIGH RESIN MEASURED CS-134,CS 137 INTEGRITY 2 132 LSA j MEASURED CONTAINER TYPE B l

) 1 DEWATERED 164.87 IN-65,C0-60,MM-54, HIGH RESIN MEASURED CS-134,CS 137 INTEGRITY l 119 LSA  :

MEASURED CONTAINER TYPE B CEWATE9ED 45.37 ZN-65,00-60,MN-54, HIGH RESIN MEASURED CS-134,CS-137 [NTEGRITY 3 202 LSA MEASURED CONTAINER TYPE A

~ .

COMPACTED 4.03' IN-65,C0-60,MN-54, B-25 801 ORY ACTIVE ESTIMATED CS-134,CS 137 STEEL 33 93 88 LSA WASTE MEASURED STRONG IIE4li )

CONTAINER ti AVERAGE FT3 DUE 10 BUL61NG BOIES FROM NEW COMPAC10R j

l j

S38s3383 3333333338333

.. u I

4. CHANGES IN THE RADIOIfGICAL EtWIR0tNENTAL MONITORItG PROGRAM '

Technical Specification 3.16.1.c requires in part that 1 in the event environmental samples become unavailable, the cause of the unavailability and identification of the affected locations and the locations (if any) for q obtaining repla ment sanples shall be submitted to j the Commission in the next semi-annual radioactive {

effluent release report. Achnical Specification j

' 3.16.1.c further states that the locations frcm which  !

sartples become unavailable may be deleted from the j radiological environmental monitoring program.

In plant Hatch's Semiannual Radioactive Effluent Release Report for the second half of 1986, it was reported pursuant to Technical Specification-3.16.1.c that milk samples had become unavailable at two locations and that in spite of efforts, only one replacement location had be~en found; no milk animal had been found to replace Williamson's cows which had been located in the NNE sector at 3.2 miles. During the first quarter of.1987, a land use survey was. t conducted, and as a consequence, milk goats were found )

at Clark's farm which is located in the NtM sector at [

4.8 miles; this location was added to the program for i milk sanpling, j 1

l

____-__-___________-__a

< . Georgia' Power Company I,

, f 1 333 P;edmont Avenue

'A' ' Atlanta. Georgia 30308 Telephone 404 5266526 Ma, ling Address.

Pbst off>ce Box 4545 Attanta, Georgia 30302 Georgia Power -

L. T. Gucwa tlc sauthern +ixttc system Managet NJc}6at Safeh amt Licensing SL-3127 1638C X7GJ17-H530 l

August 31, 1987

'U. S. Nuclear Regulatory Commis:f on ATTN: Document. Control Desk Hashington, D. C. 20555 l

1 PLANT HATCH - UNITS 1, 2 ,

NRC 00CKETS 50-321, 50-366  ;

OPERATING LICENSES DPR-57, NPF-5 SEMI-ANNUAL EFFLUENT REPORT Gentlemen: l Pursuant to the Plant' Hatch Units 1 and 2. Technical Specifications  !

6.9.1.8 and 6.9.1.9, please find enclosed six copies of the Semi-Annual l Radioactive ' Effluent Release Report for January 1,1987, through June 30, '

1987:

If you have any questions in this regard, please contact 'this office at any. time.

Sincerely, y Q ._ -

L. T. Gucwa GKM/lc 'I

Enclosure:

Semi-Annual Effluent Report c: (see next page)

)

16-48 1638C L ll g L - a

l Georgia Power di U. S. Nuclear Regulatory Commission August 31, 1987 Page Two c: Georgia Power Comoany Mr. J. P. O'Reilly, Sr. Vice President - Nuclear Operations (w/o enclosure)

Mr. J. T. Beckham, Jr., Vice President - Plant Hatch GO-NORMS U. S. Nuclear Reaulatory Commission. Hashinaton. D. C.

Mr L. P. Crocker, Licensing Project Manager - Hatch U. S. Nuclear Regulatory Commission. Reaion II Dr. J. N. Grace, Regional Administrator (2 copies)

Mr. P. Holmes-Ray, Senior Resident Inspector - Hatch American Nuclear Insurers Mr. L. Cross State of Georgia Mr. J. Setser, DNR l

1638C 700775

.