ML20094G725

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991

ML20094G725
Person / Time
Site:	Hatch
Issue date:	12/31/1991
From:	GEORGIA POWER CO.
To:
Shared Package
ML20094G713	List: HL-2059, Forwards Semiannual Radioactive Effluent Release Rept Jul- Dec 1991 & Joint Frequency Tables of Wind Speed & Wind Direction 60m Vs Delta Temp 60-10m for Jan-Dec 1991 ML20094G725 ML20094G736
References
NUDOCS 9203030271
Download: ML20094G725 (58)

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GEORGIA POWER COMPANY PLA*fr E. I. HATCH UNITS to. 1 & 2 SEMIANNUAL RADIOACTIVE EFFLUEtTT RELEASE REPORT July 1, 1991 - December 31, 1991 9203030271 920303 PDR ADOCK 05000321 R PDR

PLAtU E. I. HATCH SEMIANNUAL RADIOACTIVE EFFLUEIR RELEASE REPORT SECTION TITLE PAGE

1. LIOUID EFFLUEtRS 1 1.1 REGULATORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTFATIONS 5 1.3 MEASUREMEtES AND APPROXIMATIONS OF TMAL RADIOACTIVITY 5 1.4 LIQUID EFFLUEIR RELEASE DATA 7 1.5 RADIOLOGICAL IMPACT ON MAN DUE 'IO LIQUID RELEASES -9 2 GASEOUS EFFLUEIRS 19 2.1 REGULA'IORY LIMITS 19 2.2 MEASUREMDES AND APPROXIMATIONS OF

'IMAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUEtC RELEASE DATA 30 2.4 RADIOLOGICAL IMPACT DUE 'IO GASEOUS RELEASES 31 ,

3 SOLID WASTE 47 3.1 REGULATORY REOUIREMDES 47-3.2 . SOLID WASTE DATA 47 4 CHAtGES TO THE PLATE HATCH ODCM 50 AND PCP 5 METEOROLOGY 51 5.1 METEOROLOGICAL DATA- 51

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PLANf E. I. HATCH SEMIAN!K1AL RADIOACTIVE EFFLUEtC PELEASE REPORT TABLE LIST OF TABLES PAGF 1-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORIM 3 INSTRUMENTATION 1-2a LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT 1 10 1-2b LIOUID EFFLUEtES - SUMMATIO1 OF ALL RELEASES - UNIT 2 11 1-2c LIOUID EFFLUEtES - SUMMATIO4S OF ALL RELEASES - SITE 12 1-3a LIOUID EFFLUEtES - UNIT 1 13 1-3b LIOUID EFFLUEtES - UNIT 2 1h 1-3c LIOUID EFFLUEtES - SITE 15 1-4a INDIVIDUAL DOSES DUE 10 LIQUID RELEASES - UNIT 1 16 1-4b INDIVIDUAL DOSES DOE 10 LIOUID RELEASES - UNIT 2 17 1-5 LCHER LIMITS OF DETECTION - LIOUID SAMPLE ANALYSES 18 2-1 TECHNICAL SPECIFICATION TABLE 3.14.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORItG INSTPUMENTATION 21 2-2a GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT 1 32 2-2b GASEOUS EFFLUEPES - SUMMATION OF ALL RELEASES - UNIT 2 33 ,

2-2c GASEOUS EFFLUEtES - SUMMATION OF ALL RELEASES - SITE 3h 2-3a GASEDUS EFFLUENTS - ELEVATED RELEASES - UNIT 1 35 2-3b GASEOUS EFFLUENTS - ELEVATED RELEASES - UNIT 2 36 2-3c GASEOUS EFFLUENTS - ELEVATED PELEASES - SITE 37 l

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TABLES LIST OF TARLES PAGE 7-4a GASEOUS FFFLUENTS - GROUND-LEVEL RELEASES - UNIT 1 38 l 2-4b GASEOUS EFFLUEffTS - GRCUND -

i LEVEL RELEASES - UNIT 2 39 i 2-4C GASEOUS EFFLUEt1TS - GROUND -

LEVEL RELEASES - SITE 40 2-5 GASEOUS EFFLUEt7tS - DOSE I RATES - SITE. 41 l 2-6a AIR DOSES DUE 'IO NOBLE GASES -

UNIT 1- 42

2-6b AIR DOSES DUE 'IO NOBLE GAS 3S -

i UNIT 2 43

2-7a INDIVIDUAL DOSES DUE 'IO RADIOIODINE, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES - UNIT 1 44 2-7b INDIVIDUAL DOSES DUE 'IO RADIOIODINE,

. TRITIUM, AND PARTICULATES IN GASEOUS

) RELEASES - UNIT 2 45 i

j 2-8 LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES 46 3-la,b SOLID WASTE AND IRRADIATED FUEL

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RADIOACTIVE EFFLUEtTT RELEASP REPORT 1 LIQUID EFFLUEtTTS 1.1. REGULATORY LIMITS

1. The Technical Specifications presented in this section are for Unit 1. Requirements for Unit 2 are the same as Unit 1r however, the Technical Specification numbers are not the same.

TECHNICAL SPECIFICATIONS

> 3.14.1 The radioactive liquid effluent monitorina instrumentation channels shown in table 3.14.1-1 shall be OPEPABLE with their alarm / trio setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded. The alarm / trio setooints of these channels shall be determined in accordance with the _OFFSITE DOSE CALCULATION MANUAL (ODCM). (Technical Specification Table 3.14.1-1 is included in this section as Table 1-1).

3.15.1.1 The concer* ration of radioactive material released at any time from the site to UNRESTRICTED AREAS (fiaure 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 cases. For dissolved or entrained noble cases, 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. Durina any calendar cuarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any oraan,

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

3.15.1.3 The liquid redwaste treatment system,'as described in the ODCM, shall be used to reduce-the

, radioactive materials in liquid wastes prior to their discharce when the projected doses due to the liauid effluent per Unit from the site (ficure 3.15-1) when projected over the calendar quarter would_ exceed 0.18 mrem to the total body or 0.62 mrem to any organ.

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i 3.15.1.4(a) The contents within any outside. I

temporary tank shall be limited to less than or equal l l

to 10 curies, excludina tritium and dissolved or entrained noble cases.

(a) An outside temporary tank is not surrounded by ,

liners, dikes, or walls that are capable.of holding the tank contents and not havino tank.

overflows and drains connected to the liouid i radwaste treatment system.

6.9.1.9 states in part: " The Radioactive Effluent Release Report shall include (on a cuarterly basis) uncianned releases from the site to unrestricted areas of radioactive materials in caseous and liquid effluents that were in excess of I Ci, excludina i dissolved and entrained cases and tritium for liquid

! effluents, or those in excess of 150 Ci of noble cases

{ or 0.02 Ci of radiciodines for caseous releases".

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TABLE-1-1 TECHNICAL SPECIFICATION TABLE 3.14,1-1 (SHEET 1 of 2 )

RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMEPTTATION Minimum Channels Instrument OPERABLE Apo11 cab 111ty ACTION

l. 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 Water System Effluent Line 1 (b) 101

3. Flowrate Measure-ment Devices **

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

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

> Cooling Water System Differential Pressure

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

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

(b) Whenever the service water system pressure 1s below

.the closed cooling water system pressure or differential pressure indication is not available.

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TABLE l-1 (COffrINUED)

TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHErr 2 of 2)- ,

PADIOACTIVE LIQUID EFFLUEtTT MONITORItC INSTRUME!7TATION TABLE NCfrATIONS 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 ganca) at a Lower Limit of Detection of at least 10-7 uC1/ml. -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 102 - With the nwnber 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 Gan required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system monitor is OPERABLE.

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t 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC values used in determinina allowable licuid radwaste release rates and concentrations for princioal camma emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10CFR Part 20, Appendix B, Table II, Column 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/nd.

For grosc alpha in liquid radwaste, the MPC is taken f rom 10 CFR Part 20, Appendix B, Note 2.b as 3.0E-08 uCi/ml.

Further, for all the above radionuclides or cateaories 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 MEASUREMDTTS AND APPROXIMATIONS OF 'IOTAL RADIOACTIVITY Prior to release of any tank containinq 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 camma emitters, I-131, and dissolved and entrained noble cases by gamma spectrometry.

Monthly and quarterly comoosites are orecared for analysis by extractina aliquots from each samole taken from tanks which are released. Liquid radwaste samole analyses are performed as follows:

Measurement Frequen:V Method

1. . Garna Isotopic Each Batch Gamma spectroccopy with computerized data reduction

2. Dissolved or Each Batch Gamma spectroscooy Entrained with computerized Noble Gases data reduction

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1 Measurement Prequency Method 4

3. Tritium Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite countina Quarterly Chemical separation and

5. Sr-89 and Sr-90 Composite cas flow proportional counting

6. Fe-55 Quarterly Chemical separation and

' Composite low enercy photon detector.

j Gama isotopic measurements are performed in-house in

the radiochemistry lab usinq cermanium spectrometry.

Three germanium detectors are available: a 20%

efficient and two 15% efficient . intrinsic germanium detectors, with 2.0 FWHM resolution and housed in 4 i inch-thick lead shields. A one-liter liquid radwaste samole is poured into a Marinelli beaker in preparation for a 3000 second count. A peak search of the resulting gama ray spectrum is performed by the i computer system. Enercy and net count data for.all sianificant peaks are determined, and quantitative reduction or LLD calculations are performed for the i nuclides specified in Table Notation e of Technical J Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 21: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for counting time, decay time, sanole volume, sample aeometry, detector efficiency, baseline counts, and branchina 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 spectrum

• where a peak for that radionuclide would be located if present.

4 i The radionuclide concentrations determined by camma spectroscopic analysis of a sample taken from a tank planned for release and the most current sample analysis results available for tritium, cross alpha, Sr-89, Sr-90, and Fe-55 are used alona 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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A monitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid radwaste discharce.

Liquid effluent discharoe is also automatically terminated if the dilution stream flow rate falls below the dilution flow rate used in the setooint calculations and established as a setooint on the dilution stream flow monitor.

Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibration factor are entered into the computer and a prerelease printout is cenerated. If the release is not permissible appropriate warninos will be included on the prerelease orintout. If the release is permissible it is approved by the Chemistry For'.nnan 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 with actual release data included. These data are input to the computer and a post release printout is canerated. The post release printout contains actual release rates, actual release concentrations and quantities, actual diluttor flow, and calculated doses to an individual.

1.4 LIOUID EFFLUEm' RELEASE DATA Regulatory Guide 1.21 Tables 2A and 28 are found in this reoort 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.

The values for the four cateaories of Tables 1-2a and 1-2b, and 1-2c are calculated and the Tables completed as follows:

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

quarter. Percent of apolicable limit is determined from a mixed nuclide MPC fraction calculation. The averaae concentration for each nucitde over all-released batches is divided by the corresoondina-individual VPC value. The sum over all nuclides of the C/MPC ratios times 100 is the percent of aoolicable limit for effluent releases during the quarter.

2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and averace diluted concentration durina each period. Averaae diluted concentration divided by the MPC limit, 3.0E-03 uCi/ml, is converted to percent to oive the percent of apolicable limit.

3. Dissolved and entrained gases -

Concentrations of dissolved and entrained cases in liquid effluents are measured by cermanium spectroscopy on a one liter sample from each liquid radwaste batch. The average concentration of dissolved or entrained noble cases 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/nd ) to determine the MPC fraction. The result x100 is the percent of apolicable limit for noble gases in liquid effluent releases durina the q uarter . Radioisotopes of iodine in any form are also determined durina the isotopic analysis for each batch therefore, a-l separate analysis for possible caseous forms is not performed because it would not provide additional information.

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

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I Other data certinent to batch releases of radioactive liquid effluent frem both units are as follows:

Number of batch releases: 632 Total time period for batch releases: 72,120 minutes Maximum time perlod for a batch release: 221.0 minutes Average time period for batch releases: 114.1 minutes Minimum time period for a batch release: 7.0 minutes Average stream flow during periods of telease of liquid effluent into a flowing stream: 6,917 CFS 1.5 RADIOLOGICAL IMPACP ON MAN DUE 'IO LIOUID RELEASES Doses to an individual, due to radioactivity in licuid effluent, were calculated in accordance with Technical Specifications 3/4.15.1.2 (Unit 1) and 3/4.11.1.2 (Unit 2) using the methodoloay presented in the Plant Edwin I. Hatch Offsite Dose Calculation Manual. As required by the above Technical Specifications, doses were calculated separately for Unit 1 and Unit 2.

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

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TABLE 1-2a '

l E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est. Total Error (%)

A. Fission and activation products

1. Total re1 9ase C1 3.27E-02 3.79E 01 4.70E+01

2. Average diluted concentratton during period uC1/ml 2.59E-08 4.88E-07

3.  % of applicable limit  % 3.19E-01 8.12E-01 B. Tritium

1. Total release C1 4.32E+00 3.56E+00 3.70E+01

2. Average di:.uted concentrat:.on 3.

during per:od

% of applicable uCi/ml 3.43E-06 4.58E-06 limit  % 1.14E-01 1.53E-01 C. Dissolved and entrained gases

1. Total release Ci 1.02E-03 4.12E-04 1.00E+02

2. Average di:.uted concentrat:.on l

during per:.od

3. % of applicable uCi/ml 8.11E-10 5.30E-10

limit  % 4.05E-04 2.65E-04 i

l D. Gross Alpha l radioactivity

1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 E. Volume of waste (prior to dilution) liters 4.79E+06 3.84E+06 1.00E+01 F. Volume of I dilution l water used liters '1.26E+09 7.77E+08 1.60E+02 1

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TABLE 1-2b  !

E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASE 5

_-_--_--_---------_----_---_------_-----_----------_---__--l Unit Quarter 3 Quarter 4 Est. Tota Error (%)

A. Fission and activation products

1. Total re19ase Ci 2.89E-02 6.97E-02 4.70E+01

2. Average diluted concentration during period uCi/ml 3.74E-08 8.35E-08

3. % of applicable limit  % 1.13E-01 1.34E+00 B. Tritium

1. Total release Ci 1.39E+00 3.58E+00 3.70E+01

2. Average di:.uted concentrat:.on during period uC1/ml 1.80E-06 4.29E-06

3. % of applicable limit  % 6.01E-02 1.43E-01 C. Dissolved and entrained gases

1. Total release Ci 3.77E-04 3.95E-03 1.00E+02

2. Average diluted congentration during period

3. % of applicable uCi/ml 4.88E-10 4.73E-09 limit  % 2.44E-04 2.37E-03 D. Gross Alpha radioactivity

1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 l

l E. Volume of waste (prior to dilution)- liters 3.36E+06 3.64E+06 1.00E+01 F. Volume of dilution water used liters 7.73E+08 8.34E+08 1.60E+02

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TABLE 1-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est. Total

........._..___. ___. ...______...____...____.....EEE9E.!!!..

A. Fis ion and act vation pro ucts

1. Total relopse C1 6.16E-02 4.4tE-01 4.70E+01

2. Average di uted conQentrat:,on 3.

durina 'aer:,od

% of sp.311 cable uCi/ml 3.03E-08 2.78E-07 limit  % 2.41E-01 1.09E+00 B. Tritium

1. Total release i 5.71E+00 7.13E+00 3.70E+01

2. Average di:.uted concentratnon during nernod ut /ml 2.81E-06 4.43E-06

3. %of 6ph11 cable limit  % 9.37E-02 1.48E-01 C. Dissolved and entrained gases

1. Total release Ci 1.40E-03 4.36E-03 1.00E+02

2. Average di:uted concentratnon during nernod

%of 6ph11 cable uCi/ml 6.88E-10 2.71E-09 3.

limit  % 3.44E-04 1.35E-03 D. Gross Alpha radioactivity

1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 E. Volume of waste (prior to dilution) liters 8.15E+06 7.48E+06 1.00E+01 F. Volume of x dilution water used liters 2.03E+09 1.61E+09 1.60E+02 4

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TABLE 1-3a*

E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 LIQUID EFFLUENTS Continuous Mode ** Batch Mode  !

1 Huclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 4.32E+00 3.56E+00 Fission and activation productet Na-24 C: 2.02E-03 7.5FE-05 i Cr-51 C: 1.13E-04 1.1141-01 1 Mn-54 C; 3-08E-03 1.74E-02 Fe-55 C: 0,00E+00 1.84E-02 Fe-59 C: C 00E+00 3.99E-03 Co-58 C: 4.73E-04 8.79E-03 Co-60 C: 5.89E-03 7.72E-02 Zn-65 C: 6.78E-03 9.81E-02 As-76 C; 3.92E-05 6.48E-06 Sr-90 C: 4.41E-05 0.00E+00 Sr-92 C: 9.18E-07 A.19E-05 Y-91m C: 2.61E-06 6.79E-06 Zr-95 C: 1.41E-06 8.61E-05 Nb-95 C: 2.76E-06 5.13E-04 Nb-97 C: 1.38E-05 7.64E-04 Ho-99 C: 5.26E-05 0.00E+00 Tc-99m C: 1.84E-04 0.00E+00 Ru-103 C: 0.00E+00 2.28E-04 Sb-125 C: 1.32E-05 2.83E-03 1-131 C; 5.09E-04 0.00E+00-I-132 C: 3.03E-06 0.00E+00 I-133 C: 9.41E-04 5.24E-06 I-134 C: 0.00E+00 6.45E-04 I-135 C: 1.53E-04 0.00E+00 Cs-134 C: 2.16E-03 4.48E-03 Cs-137 C: 1.20E-02 3.39E-02 Ba-140 C: 5.80E-05 0.00E+00 La-140 C: 9.34E-05 0.00E+00 Ce-141 C: 1.01E-05 1.06E-05 Ce-144 C: 0.00E+00 5.19E-04 Total C:- 3.27E-02 3.79E-01 Dissolved and entrained gases Kr-88 C: 0.00E+00 1.28E-05 Xe-131m C 0.00E+00 7.21E-05 Xe-133 C: 1.30E-04 3.29E-05 Xe-135m C: 4.06E-05 0.00E+00 Xe-135 C: 8.49E-04 2.81E-04 Ar-41 C: 1.49E-06 1.30E-05 Total C: 1.02E-03 4.12E-04

! Gr-Alpha Ci 0.00E+00 0.00E+00

• Zeroes in this table indicata that no radioactivity was c ee Table 1-5 for t resent above detectab'e levele Sowerlimitsofdetectionfor11guYdsampleanalyses.ypical

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

TABLE 1-3bo 1 E. f. HATCH NUCLEAR PLANT - UNIT 2 .

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 LIQUID EFFLUENTS Continuous Mode ** Batch Mode Nuclides Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Released

..............................__..........___..... ___.__.... i H-3 C1 1.39E+00 3.58E+00 Fission and activation products Na-J4 C: 1.47E-03 1.37E-02 Cr-51 C: 1.15E-03 5.33E-03 Mn-54 C: 3.96E-04 3.37E-04 Fe-55 C: 1.75E-02 0.00E+00 Co-58 C 9.35E-05 8.82E-04 Co-60 C 2.45E-03 2.22E-03 Zn-65 C: 1.30E-03 5.15E-03 As-76 C; 4.47E-04 5.22E-03 Sr-92 C 0.00E+00 1.99E-06 Y-91m C; 2.67E-05 1.13E-03 Nb-97 C; 5.59E-06 1.74E-04 Mo-99 C: 0.00E+00 2.89E-04 Tc-99m C: 1.67E-04 1.78E-03 Ru-103 C; 0.00E+00 6.93E-05 Sb-125 C: 8.33E-06 0.00E+00 I-131 C:, 3.11E-05 2.1SE-03 I-132 C: 1.38E-06 7.42E-06 I-133 C 3.56E-04 2.38E-03 I-135 C: 0.00E+00 2.80E-04 Cs-134 C: 6.39E-04 8.01E-04 Cs-137 C: 2.91E-03 3.64E-03 Ba-140 C 0.00E+00 1.66E-05 La-140 C: 0.00E+00 4.25E-05 Co-141 C: 1.55E-06 1.41E-06 Zn-69m C:. 0.00E+00 5.77E-06 Np-239 C: 0.00E+00 2.18E-0?

Co-57 C; 0.00E+00 2.45E-04 Br-82 C 0.00E+00 3.98E-04 Sb-124 C 0.00E+00 1.64E-03 Total C: 2.89E-02 6.97E-02 Dissolved and entrained gases:

Xe-133 C. 2.14E-05 6.76E-04 Xe-135m C: 4.76E-06 8.57E-04 Xe-135 C; 3.51E-04 2.41E-03 Total C, 3.77E-04 3.95E-03 Gr-Alpha ci 0.00E+00 0.00E+00

! *5Nrobb 5 Eh5b E$ bib ~5nb5ckES~th$E no"~$h5o$cE5v5Ey~w$~~~~~~ r resentaovedstectabbe levelu See Table 1-5 for t cal Sowerlimtsofdetect:,onforliquidsampleanalyses.yp$

i

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

_1L_

TABLE 1-3c8 E. 7. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE -EFFLUENT HELEASE REPORT 1991 LIQUID EFFLUENTS Continuous Mode ** Batch Mode Nu lidos Re eased Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 5.71E+00- 7.13E+00 Fission and activation productst Na-24 C; 3.49E-03 1.38E-02 Cr-51 C: 1.27E-03 1.16E-01 Mn-54 C; 1.47E-03 1.77E-02 Fe-55 C: 1.75E-02 1.84E-02 Fe-59 C; 0.00E+00 3.99E-03 Co-58 C:. 5.66E-04 9.68E-03 Co-60 C: 8.35E 7.94E-02 Zn-65 C: 8.08E-03 1.03E-01 As-76 C: 4.86E-04 5.23E-03 Sr-90 C; 4.41E-05 0.00E+00 Sr-92 C: 9.18E-07 8.39E-05 Y-91m C: 2.93E-05 1.14E-03 Zr-95 C: 1.41E-06 8.61E Nb-95 C; 2.76E-06 5.13E-04 Nb-97 C: 1.94E-05 9.39E-04 Mo-99 C: 5.26E-05 2.895-04 Tc-99m C; 3.51E-04 1.78E-03 Ru-103 C: 0.00E+00 2.97E-04 Sb-125 C: 2.16E-05 2.83E-03 I-131 C: 5.40E-04 2.18E-03 I-132 C:, 1.04E-05 7.42E-06 I-133 C: 1.30E-03 2.38E-03 1-134 C:. 0.00E+00 6.15E-04 I-135 C: 1.53E-04 2.80E-04 Cs-134 C:. 2.80E-03 5.28E-03 Cs-137 C: 1.50E-02 3.75E-02 Ba-140 CL 5.80E-05 1.66E-05 La-140 Ch 9.34E-05 4.25E-05 Co-141 C: 1.16E-05 1.20E-05 Ce-144 C: 0.00E+00 5.19E-04 Zn-69m C 0.00E+00 5.77E Np-239 C: 0.00E+00- 2.18E-02 Co-57 C: 0.00E+00 2.45E-04 Br-82 C; 0.00E+00 3.98E-04 Sb-124 C: 0.00E+00 1.64E-03 Total Ch 6.16E-02 4.49E-01 Dissolved and entrained gases:

Kr-88 C: 0.00E+00 1.28E-05 Xe-131m C: 0.00E+00 7.21E-05 Xe-133 C: 1.52E 7.09E-04 Xe-135m C:. 4.53E-05 8.57E-04 Xe-135 C: -

-1.20E-03 2.69E Ar-41 C:. -

1.49E-06 1. 3 0E-0 5 --

Total Ch 1.40E-03 4.36E-03 Gr-Alpha Ci 0.00E+00 0.00E+00

• Zeroes in this table indicate that no radioactivity wa -

resen gowergagovedetectab{elevelstsofdetectonfor11gu{eeTabge1-5fortypcal-d samp e analyses re{herearenocontinuousmoderadioactiveliquid ease pathways at Plant Hate

TABLE 1-4a E. I. HATCH 11UCLEAR PLANT - Unit 1 SEMI All!JUAL RADIOACTIVE EFTLUEllT RELEASE REPORT 1991 IllDIVIDUAL DOSES DUE TO LIQUID RELEASES Cumulative Doses per Quarter organ Tech Unit Quarter 3  % of Quarter 4  % of Spec Tech Tech Limit Spec Spec Limit Limit B no 5.0 nrem 4.16E-02 8.32E-01 1.63E-01 3.26E+00 L ver 5.0 mrem 6.33E-02 1.27E+00 2.61E-01 5.22E+00 TBody 1.5 mrom 4.32E-02 2.88E+00 1.73E-01 1.15E+01 Thyroid 5.0 mrom 2.75E-03 5.49E-02 3.06E-05 6.12E-04 Kianey 5.0 mrem 2.19E-02 4.38E-01 9.94E-02 1.99E+00 Lung 5.0 mrem 6.87E-03 1.37E-01 2.48E-02 4.96E-01 GILLI 5.0 mrem 5.23E-03 1.05E 01 7.71E-02 1.54E+00 Cumulative Doses This Year . . . -----.. . --. _____ . .. _ .---

Organ Tech Unit uarters  % of Spec ,2,3,& 4 Tech Limit Speg

. Limit Bone 10.0 mrem 2.60E-01 2.60E+00 Liver 10.0 mrom 4.10E-01 4.10E+00 TBody 3.0 mrem 2.74E-01 9.14E+00 Thyrbid 10.0 mrom 2.67E-02 2.67E-01 Kianey 10.0 mrem 2.51E-01 1.51E+00 Lung 10.0 mrem 4.09E-02 4.09E-01 GILLI 10.0 mrom 9.10E-02 9.10E-01

TABLE 1-4b E. I. HATCH NUCLEAR PLANT - Unit 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 INDIVIDUAL DOSES DUE To LIQUID RELEASES Cumulative Doses per Quarter Organ Tech Unit Quarter 3  % of Quarter 4  % of Spec Tech Tech Limit Spec Spec Limit Limit Done 5.0 mrom 1.47E-02 2.94E-01 1.90E-02 3.81E-01 Liver 5.0 mrem 2.27E-02 4.55E-01 3.01E-02 6.01E-01 TDody 1.5 mrem 1.57E-02 1.05E+00 2.04E-02 1.36E+00 Thyroid 5.0 mrem 4.69E-04 9.38E-03 1.655-02 3.30E-01 Kianey 5.0 mrom 7.79E-03 1.56E-01 1.09E-02 2.18E-01 Lung 5.0 mrem 2.48E-03 4.97E-02 3.17E-03 6.33E-02 GILLI 5.0 mrem 2.42E-03 4.84E-02 3.91E-03 7.82E-02 Cumulative Doses This Year organ Tech Unit uarters  % of Speg ,2,3,& 4 Tech Limit Speg Limit Bone 10.0 mrem 1.10E-01 1.10E+00 Liver 10.0 mrem 1.78E-01 1.78E+00 TDodv 3.0 mrom 1.22E-01 4.05E+00 Thyrbid 10.0 mrem 1.83E-02 1.83E-01 Kianey 10.0 mrom 6.51E-02 6.51E-01 Lung 10.0 mrem 1.78E-02 1.78E-01 GILLI 10.0 mram 4.72E

--...-__......____..--....._-02 4.72E-01

1 TABLE 1-5 LOWETt LIMITS OF DETECTKX4 - LIQUID SAMPLE ANALYSES The values in this table represent aorlori Iower limits of datection (LLD) which are typically achieved in laboratory analyces of 11guld radwaste samples.

HADIONUCLIDE LLD tRJITS Pn-54 5.38E-08 uci/mi Fe-59 7.7BE-08 Co-58 4.67E-08 Co-60 4.78E-08 Zn-65 1.31E-07 Mo-99 5.10E-07*

Cs-134 7.18E-08 Cs-137 6.05E-08 Ce-141 -1.41E-07 Ce-144 6.30E-07*

I-131 6.51E-08 Xe-135 8.45E-08 Fe-55 2.00E-06 Sr-89 5.00E-08 St-90 5.00E-08 H-3 1.00E-05

• In accordance with Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2), Table Notation b, the permissible Lower Limit of Detection may be increased inversely proportional to the magnitude of the carra yield. However, the LLD determined in this manner must not exceed 10 percent vf the Maximum Permissible concentration (MPC) value coecified in 10 CFR20, Appendix B, Table II (Column 2).

t 2 CASfDUS EFFLUEffrS 2.1 RfTULA'IORY LIMITS The Technical Specifications presented in this rection are for Unit 1. Requirenents for Unit 2 are the same ao for Unit 11 however, the Technical Srecification nunbers are not the same.

TECHNICAL SPEC;'ICATIONS 3.14.2 The radioactive caseous ef fluent monitorina instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.2.1 (a) are not exceeded.

The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM. (Technical Specification Table 3.14.2-1 is included in this section as Table 2-1),

3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (floure 3.15-1) due to radioactive materials released in asseous effluents from the site shall be limited to the following values:

a. The cose rate limit for noble cases shall be less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin,

b. The dose rate limit for I-121, I-133, tritium, and for all radioactive noterials in particulate form and radionuclides other than noble cates with half-lives creater than 8 days shall be less 7

than or equal to 1500 mrem / year to any oroan.

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

a. Durina any calendar quarter, to less than or olual to 5 mrad for gamma radiation and less than ,

or equal to 10 mrad for beta radiation.

b. During any ca19ndar year, to less than or equal to 10 mrad for aamra radiation and less than or equal to 20 mrad for beta radiatitx1, 3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLIC f rom I-131, I-133, tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents teleased to UNRES'IRICTED AREAS (flaure 3.15-1) from each reactor unit shall be limited to the follesing:

a. Durino any calendar quarter to less than or equal to 7.5 mrem to any oraan,

b. Durina any cilendar year to lecs than or equal to 15 mrem to any oraan.

3.15.2.4 The GASEQUS RADWASTE TREATMDR 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 GASD00S RADWASTE TREATMDC SYSTEM operability shall be demonstrated by administrative cont *als 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 75 mrem.

(With the calculated doses from the release of radioactive materials in liquid or caseous 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 storace 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 reconbiners in the min condenser offaas treatment system shall be limited to less than or equal to 4 perzent by volume.

3.15.2.7 The cross aamm 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 pretreatment monitor station shall be limited to less than or ewal 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 sterials in caseous and liquid effluents that were in excess of 1 Ci, excludina dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble cases or 0.02 C1 of radiciodines for caseous releases."

i l

i i

1 1ABLE 3.las.2-1 ( Stil t i l of ts)

HADIOACilVE GASEOUS Li f i tit HT Mo*Ilj.Ott i ttG INST RUME NT Ai tcM ,

.i

• Mi si s atic Cisanfie I s I AP2jjcab i i i e y Ps remate r ACTfOM instrtiment O_tLMAetE J

1. M.e in Condense r Or rqa s i r+ra tmerit System [* plosive Cas Monitoring I System

• • % flydrogen 106 ttydrogen Moni tur (I)

2. Reactor fluilding Vent Stack f4onitorisig Systese i

'I

• Madioactivity Rate 105

s. Moble cas Activity Monstor (t)

Mea ste rement + D M

M lodisse Sampler Cartridge (1)

• Verify Presence or 107 4

e y

b. Cartridge 7 g

i s

Partictilate Sampler F ilter (1)

• Ver fy Presence of 107 c.

Filter ,

d. E r r iesesit System F lowrate

• Hem ste remenet Device (1) System flowrote 1 04:

Measterement ,

i

e. Samp t er F t owra +e Measurement (I)

• Sampler i f ewrote 10te Device Mea ste remen t

3. Itecombisestr Usei tding Vesit ilation 3 Monitoriseg System t

s. Noble Cas Activity Monitor (1)

• Radioactivity Rate to$

Measierement + l I

Bodiste Sampler Ca rtridge {1)

- Verify Presence or 107  !

b. i Ca rt ridge (I)

• Verify Presence of' for

c. F,a rt e cia l a t o Sampler f i l ter Filter a 1

d. Sammpler F 8uwrate Meastoresreset (1)

" Sampler Flowrote lose Device Mea surement

• i -

. ggdfti n yas ,ooj e

'". 2 N

O *y T 7 a 4 8 I 0 0 , 0 t0 0 0 T 1 1 1 1 1 1 C

A e f r e 6 t o o t a e a R e e e t R c c t a r y y+ n n o r

t e e w t it s s wt ot it N vn e e on l n vn O r ie re r l Fm e fe ie I e tm Pg P m tm T t ce d yr e re ce A e ar yi mr er ar T m ou fr fe it eu psu ts l ou is N a is it E r da rr rl sa ye ae ma da M a ae ea ei ae U P RM VC VF SM SM RM R

T S

)

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r i v

r m

a mc ei t

a P r

y o t e S tv r t t c l se w s i i

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c e e

in i

c eru a l ee c r s a l t l s pi o a t b d r ra mv sr G S o o a re ae no t N t P EM SD et te n n di e i nn s t m a . . . . . oo o r

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TABLE 3.14.2-1 (SHEET 3 0F 4)

RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations

+ Monitor must be capable of responding to a Lower Limit of Detection of 1 x 10-* uC1/ml.

• 0uring releases via this pathway.

"During main condenser of fgas treatment system operation.

l

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

ACTION 104 - With the number of channels OPERABLE less than reouired 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 />.

If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an expl3 nation of the circumstances shall be included in the next emi-annual effluent release report.

ACTION 105 - With the number of channels OPERABLE less than recuired by the Minimum Channels OPERABLE requirement, l

effluent releases via this pathway may continue, provided grab samples are taken daily and analyzed daily for gross activity within 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 mor'itoring system channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay suspend drywell purge.

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.

l ACTION 106 - With the number of channels CPERABLE less than required by the M kimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided:

1 (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 l

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) Using a temporary hydrogen analyzer installed in the offgas system line downs,trean of the recombiner, -

hydrogen concentration readings are taken and logged-every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

TAILE 2-1 (COST'b)

TABLE 3.14.2-1 (SHEET 4 0F 4) ,

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTA Table Notations (Continued)

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.

ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided 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 /> after the end of the sampling period.

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 ef fluent release report, ACTION 108 - With the number of channels OPERABLE less than 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 system is not bypassed, and

b. The of fgas post-treatment monitor (011-K615) .or the main -

stack monitor (011-K600) is OPERABLE.

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

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.

2L.

2.2 MEASUPEMEffT AND APPROXIMATICt1S OP 'IOTAL RADIOACTIVITY Waste cas release at Plant Hatch is confined to four oaths: main stack (also called the offaas vent), Unit I reactor buildina vent t Unit 2 /

reactor buildina vent, and the recombiner (

buildina vent. Each of these four paths is continuously monitored for gaseous radioactivity. Each is equipped with an integratino-type sample collection device for collectina particulates and todines. 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 frequentiv under certain circunstances specified in Table Notations to the above mentioned tables, samples are collected as follows:

1. Noble gas sanples are collected by arab sampling monthly.

2. Tritium samples are collected by grab samoling monthlv.

3. Radiciodine sanples are collected by pulling the sample stream throuah a charcoal cartridge over a 7-day period.

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

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

6 Quarterly composite samoles are prepared '

from the particulate filters collected over the previous quarter and the quarterly catposite sample is analyzed for Sr-89 and Sr-90.

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

-2),-

~ ______ - _ _ - _ _ A

The noble cas 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 servina the four release points, to assure that the limits of Technical Spectfications 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 eacn 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.? 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.

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

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

1. PISS 70N AND ACTIVATION GAS The radionuclide-specific released radioactivity is determined from sample analyses results collected as described above and averaae release flow rates over the period represented by the collected sample.

Instantaneous dose rates due to noble gases and due to radiciodines, tritium, and particulates are calculated (with computer assistance).

Calculated dose rates are canpared to the dose rate limits specified in 3.15.2.1.a (Unit 1) and 3.11.2.1.a (Unit 2) for noble cases and 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2) for radiciodine, tritium, and Darticulates. Dose rate calculation methodolocy is presented-in the Plant Hatch ODCM.

1

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

Deta and game air doses due to noble cases are calculated for the location in the unrestricted area with the potential for the hiahest exposure due to gasoous 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 are can' oared to the dose limits specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2). Current percent of technical specification limits are shown on the printout for each release period. Air dose calculation methodolocy is presented in the Plant Hatch ODCM.

2. RADIOIODINE, 'IRITIUM, AND PAirrICULATE RELEASES Released quantities of radiotodines are determined from the weekly samples and release flow rates for the four release points.

Radiciodine concentrations are determined by cama spectroscopy.

Released quantities of particulates are determined from the weekly (filter) samples and release flow rates for the four release points.

Gama spectroscooy is used to quantify concentrations of principal aanm3 emitters.

After each calendar quarter the particulate filters frm each vent are combined, fused, and strontium separation is performed. Since sample flows and vent flows are almost constant over each quarterly period the filters from each vent can be dissolved together. Decay corrections are made back to the middle of the quarterly collection period. Where significant Sr-89 or Sr-90 is not detected, LLD's are calculated, i

Strontium concentrations are input to the i

composite file of the computer to be used in release, dose rate and individual dose calculations.

Tritium samples are obtained monthly from each

! vent by oassing the sample stream throuah a cold --

l trap. The grams of water vapor / cubic foot cas is j neasured upstream of the cold trap in order to j

alleviate the difficulties in determining water j

vapor collection efficiencies. The tritium t

sanples are analyzed by an independent laboratory L and results are furnished in uCi/ml of water.

The tritium concentration in water is converted

, to tritium concentration in air and this value is l input into the composite file of the computer to

! be used in release, dose rate, and individual dose calculations.

-2 l-

Dose rates due to radiciodine, tritium, and particulates are calculated for a hyoothetical child, expoced 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 rate from all four release points are compared to the dose rate limits specified in Technical Specifications 3.15.2.1.b (Unit 1) or 3.11.2.1.b (Unit 2).

Individual doses due to radiciodine, tritium, and particulates are calculated for the critical receptor, which is described in the Plant Hatch ODCM. Individual doses are calculated for each release period and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative individual doses 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 aross alpha release is computed each month by counting the particulate filters each week for cross alpha activity in a aas flow proportional counter. The four or five weeks' nunbers 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 to 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 fission and activation cas release, total I-131 release, total particulates with half-lives greater than 8-day release, and total tritium release.

_ _ - - - - - . - - - - -- J

"The total or maximum error associated with the effluent nessurecent will include the cumulative errors resulting from the total operation of samplina and neasurement. Because it nay be very dif ficult to assion error terms for each parameter af fectina 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 materials released in liquid and gaseous effluents and solid waste."

Estimated errors are based on errors in countina equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sacole losses for such items an charcoal cartridges.

(1) Fission and Activation Total Release was calculated from sample analysis results and release point flow rates.

Statistical Error 60%

Counting Equipment Calibration 10%

Vent Flow Rates 10%

Non-Steady Release Rates 20%

1001 (2) 1-131 Release was calculated from each weekly sample:

Statistical Error 60%

Counting Equipnent Calibration 10%

Vent Flow Rates 10%

Vent Samole Flow Rates 10%

Non-Steady Release Rates 10%

Losses From Charcoal Cartridge 10%

110%

(3) Particulates with half-lives areater than 8 days release was calculated from samole analysis results and release point flow rates.

Statistical Error at LLD concentration 60%

Counting Equioment Calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

100s

_ _ _____ -- -_. - 1

(4) Total Tritium Release was dominsted by the r ctor building vent tritium releases hence, the larcer statistical errors of the off-aas vent and recombiner buildina vent tritium releaces do not affect the error in the total tritium release:

Water Vapor in Sanole Stream Determination 20%

Vent Flow Rates 10%

Counting Calibration and Statistics 10%

Non-Steady Release 50%

90%

2.3 GASEOUS EFFLUEtTT RELEASE DATA Reculatory Guide 1.21 Tables 1A, 1B, and IC are found in this report as Tables 2-2a-c, 2-3a-c, and 2-4a-c. ,

Data are presented on a quarterly basis as required by i Regulatory Guide 1.21.

To complete Tables 2-2a-c, total release for each of the four categories (fission and activation gases iodiness particulates 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 terns of release rate in uCi/second but in terns of dose rate in mrem / sear, as presented in Technical Specifications 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2). Noble cases are linited as specified in 3.15.2.1.a and 3.11.2.1.a. The other three categories (tritium, radiciodines, and particulates) are limited as a greco as specified in 3.15.2.1.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 particulates are cresented in Table 2-5 along with percent of technical specification limits.

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 are unit limits. Cumulative air doses are presented in Tables 2-6a and 2-6b, alona with percent of ,

technical specification limits.

w wg --y--e w.q-. - - - - .5 -s.9.,w ,,-9,. .- ,m. y- w .- - - - - , # y y- y,-- w-ey- ,.--=y rg-

Limits for cumulative individual doses, due to radiciodine, tritium, and mrticulates, 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 Tables 2-7a and 2-7b, with percent of technical specification limits.

2.4 RADIOLOGICAL IMPACT DUE 'IO GASDOUS PELEASES Doce rates due to noble gas releases were calculated for the site in accordance with Technical Specifications 3/4.15.2.1.a (Unit 1) and 3/4.11.2.1.a (Unit ?). Results are presented in Table 2-5. Doce '

rates dua to radiolodine, tritium, and particulates in caseous releases were calculated in'accordance with 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. ,

Cumulative air doses due to noble gas releases were calculated for each unit in 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 2-6b.

cumulative doses to an individual due to radiciodine, tritium , and particulates 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 results are presented in Tables 2-7a and 2-76.

Dose rates and doses were calculated using the

methodology presented in the Plant Hatch Offsite Dose Calculation Manual.

l l

TABLE 2-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est. E Total

__________________________________________________ EE?E_!'!__

A. Fission and Activation Gases 1.66E+01

1. Total Ci 5.63E+01 1.00E+02 Release

2. Average uC1/sec 7.16E+00 2.11E+00 Release Rate For Period

• 3. % of Tech  %

Spec Limit B. Iodines Ci 6.82E-04 5.24E-05 1.10E+02

1. Total Iodine-131

2. Average uCi/sec 8.67E-05 6.66E-06 Release Rate For Period

• 3.  % of Tech  %

Spec Limit C. Particulates

1. Particulates Ci 3.51E-04 4.51E-05 1.00E+02 wnth half-Invas > P days

2. Average uCi/sec 4.46E-05 5.74E-06 Release Rate For Period

• 3. % of Tech  %

Spec Limit

4. Gross Alpha Ci 6.77E-07 8.50E-07 Radioactivity I

D. Tritium

1. Total Ci 7.61E+00 4.07E-01 9.00E+01

2. Averace uCi/sec 9.68E-01 5.18E-02 Release Rate For i Period

• 3. % of Tech  %

Spec Limit

• Technical Specification limits are in terms of dose rate See Tables 2-5, 2-6a, 2-6b, fmrom/grg

-7a, and 2-7bdose (mrem).

l i

i

-w--m- - p y y,. y, ,-+.w.. e --y- en

TABLE 2-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est. Total

__________________________________________________EEEoE_!*l__

A. Fis ion and Act$vation Gases

1. Total Ci 4.70E+01 4.16E+01 1.00E+02 Release

2. Average uC1/sec 5.98E+00 5.29E+00 Release Rate For Period

• 3. % of Tech  %

Spec Limit B. Todines

1. Total Ci 7.46E-04 1.10E-04 1.10E+02 Iodine-131

2. Average uCi/sec 9.49E-05 1.40E-05 Release Rate For Period

• 3. % of Tech  %

Spec Limit C. Particulates

1. Particulates Ci 5.82E-05 4.58E-05 1.00E+02 with half-lives > 8 days

2. Average uCi/sec 7.40E-06 5.82E-06 Release Rate For Period

• 3. % of Tech  %

Spec Limit

4. Gross Aloha Ci 5.72E-07 7.59E-07 Radioactivity D. Tritium

1. Total Ci 5.34E+00 4.90E+00 9.00E+01

2. Average uCi/sec 6.80E-01 6.23E-01 Release Rate For Period

• 3. % of Tech  %

Spec Limit

• TechnicalSgecificationlimitsareintermsofdoserate dose (mrem). See Tables 2-5, 2-6a, 2-6b, jmrem/grg gn q

TABLE 2-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est. Total Error (%)

A.

Fis$vationion and Act Gases 5.82E+01

1. Total Ci 1.03E+02 1.00E+02 Release

2. Average uCi/sec 1.31E+01 7.40E+00 Release Rate For Period

• 3.  % of Tech  %

Spec Limit B. Iodines 1.43E-03 1.10E402

1. Tetal Ci 1.62E-04 Iodine-131

2. Averace uCi/sec 1.82E-04 2.07E-05 Relea6e For Rat!od Per

• 3.  % of Tech  %

Spec Limit C. Particulates 1.00E+02

1. Particulates Ci 4.09E-04 9.09E-05 w:.th half-1.ves > 8 days

2. Average uCi/sec 5.20E-05 1.16E-05 Release Rate For Period

• 3.  % of Tech  %

Spec Limit

4. Gross Aloha Ci 1.2SE-06 1.61E-06 Radioactivity D. Tritium

1. Total Ci 1.30E+01 5.30E+00 9.00E+01

2. Average uCi/sec 1.65E+00 6.74E-01 Release Rate For Period

• 3. % of Tech  %

Spec Limit

• Technical Sgecification dose (mrem). limits are in terms See Tables of dose 2-5, 2-6a, rate 2-6b, fmrem/grggn

-3h-

TABLE 2-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - ELEVATED RELEASES

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Kr-85m C: 1.65E-01 4.25E-01 Kr-87 C: 0.00E+00 7.65E-02 Xe-133 C: 3.14E+00 0.00E+00 Xe-135m C: 1.26E+01 6.88E-01 Xe-135 C: 1.34E+01 7.08E-01 Xe-138 C: 3.45E+00 2.86E+00 Ar-41 C: 9.34E-02 5.74E-01 Tot 1 For Per od C1 3.29E+01 5.33Et00

2. Iodines -----_-----_-_ -----------

---

_------_-------------__5E-05 I-131 C: 5.68E-04 2.9 I-133 CL 6.69E-04 1.04E-04 <

I-135 Ca 1.77E _____ - 1.44E 04

--- .... _--_----...---_-_-03 ___-_.-_-_---___-----.- .. j Tot 1 For j C1 3.01E ..._--_.-_ 2.77E ____---..-__----__--- ..

_-04 Per od.........--_.---_. _----_-03

3. Particulates Cr-51 C: 0.00E+00 9.53E-08 Mn-54 C:. 5.78E-08 5.12E-08 Co-58 C: 0.00E+00 2.77E-08 Co-60 C: 3.45E-08 6.92E-07 Zn-65 C: 8.85E-08 5.18E-07 Sr-89 C: 2.79E-06 6.84E-07 Sr-90 CL 3.10E-08 4.29E-09 Ba-140 C: 1.29E-05 4.02E-06 La-140 Cn 2.37E-05 7.20E-06 I-131 Ca 2.65E-07 0.00E+00 Total For Period Ci 3.98E-05 1.33E-05

• Zeroes in- this table ind:Leate that no radioactivity way See Table 2-8 for ty present above detectable :,evels. lower limits of detection for gaseous sample analyses.pic

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

[

- e-- ,mr,r --

p - di. mv

TABLE 2-3b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS -

ELEVATED RELEASES

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Kr-85m C: 2.60E-01 1.12E+00 Kr-87 C; 0.00E+00 1.20E+00 Xe-133 C: 3.14E+00 2.41E+00 Xc-135m C: 1.37E+01 7.35E+00 Xe-135 C: 1.37E+01 3.35E+00 '

Xe-138 C: 6.02E+00 1.62E+01 Ar-41 C. 9.34E-02 8.81E-01 Tot For Per d Ci 3.70E+01 3.25E+01

2. Iodines I-131 CL 7.04E-04 4.16E-05 I-133 CL 7.10E-04 1.60E-04 I-135 CL 1.80E-03 2.10E-04 Total For Period Ci 3.23E-03 4.11E-04

3. Particulates Cr-51 C: 0.00E+00 8.57E-07 Mn-54 C: 5.78E-08 4.89E-07 Co-58 CL 0.00E+00 2.49E-07 Co-60 C: 3.45E-08 6.31E-06 Zn-65 C: 2.65E-07 4.66E-06 Sr-89 C: 3.76E-06 3.27E-06 Sr-90 C: 4.18E-08 2.05E-08

. Cs-137 C; 0.00E+00 3.05E-08 l Ba-140 C: 1.56E-05 8.97E-06 I La-140 C: 2.88E-05 1.29E-05 I 131 C: 3.42E-07 0.00E+00 Total For Period Ci 4.90E-05 3.78E-05

• Zeroes in this table indicate that no radioactivity was Dresent above See Table 2-8 for ty lower limits of detectable detection for levels.

gaseous sample analyses.pical

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

l i

I l

l i

-36

TABLE 2-3c E. I. HATCH NUCLEAR PLANT - SITE SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - ELEVATED RELEASES

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases

~~~~~kr~85~~~~~C5~~~i~25E~b5~~~5I555 Ob~~~~~~~~~~~~~~~~~~~~~~

Kr-87 C: 0.00E+00 1.28E+00 Xe-133 CL 6.28E+00 2.41E+00 Xe-135m C:. 2.64E+01 8.04E+00 Xe-135 C:. 2.71E+01 4.06E+00 Xe-138 CL 9.46E+00 1.90E+01 Ar-41 Ca 1.87E-01 1.46E+00 Tota For Peri d Ci 6.99E+01 3.78E+01 2.

Iodines _---- .......__ -__- ...--_-.._ .........._____

I-131 C:, 1.27E-03 7.11E-05 I-133 C:, 1.38E-03 2.63E-04 I 135 Ca 3.58E-03 3.54E-04 Total For Period Ci 6.23E-03 6.89E-04

3. Particulates Cr-51 C: 0.00E+00 9.53E Mn-54 C:. 1.16E-07 5.40E-07 Co-58 CL O.00E+00- 2.77E-07 Co-60 - C: 6.91E-08 7.00E-06 Zn-65 C: 3.53E-07 5.18E-06 Sr-89 C: 6.56E-06 3.95E-06 Sr-90 C: 7.29E-08 2.48E-08 Cs-137 CL 0.00E+00 3.05E-08 Ba-140 CL 2.85E-05 1.30E-05 La-140 C: 5.25E-05 2.01E-05 I 131 C: 6.07E-07 0.00E+00 Tot 1 For Per od Ci 8.88E-05 5.11E

_....---_-05 _---_..--- .......... _.-

• Zeroes in this table indicate that no radioactivity was resent above detectable levels.- See Table 2-8 for ty Sowerlimitsofdetectionforgaseoussampleanalyses.pical

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

37 - - - - - - - - -

_b

TABLE 2-4a E. I. HATCH NUCLEAR PLANT - Uh1T 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Kr-85 Ca 1.03E+01 0.00E+00 Xo-133 C; 3.02E-02 6.15E-02 Xe-135 C: 1.31E+01 1.12E+01 Total For 1.13E+01 Period Ci 2.35E+01

2. Iodines I-131 C: 1.14E-04 2.29E-05 1-133 C: 4.73E-03 4.88E-05 I-135 Ca 3.06E-03 0.00E+00 Tot 1 For Per Ci 7.90E-03 7.17E-05

... od ...........--............ ... ..............-- .....-- --

3. Particulates Mn-54 C: 6.91E-06 4.07E-07 Co-58 C: 7.68E-06 0.00E+00 Co-60 C: 3.18E-05 1.47E-05 Zn-65 C: 1.73E-04 8.56E-06 Sr-89 C: 4.29E-06 9.30E-07 Sr-90 C: 8.72E-08 0.00E+00 Mo-99 C: 0.00E+00 5.04E-06 Cs-137 C: 8.52E-05 9.46E-07 Ba-140 C 2.03E-06 0.00E+00 I-131 C:, 0.00E+00 1.30E-06 Tot 1 For Per od C1 3.11E-04 3.18E-05

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

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

i' 38-

TABLE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

• Continuous Mode Datch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4

1. Fission Gases Xe-135 Ci 1.00E+01 9.08E+00 Total For Period Ci 1.00E+01 9.08E+00

2. Iodines I-131 C: 4.19E-05 6.85E-05 I-133 C: 2.06E-04 1.34E-04 I-135 CL 0.00E+00 0.00E+00 Total For Period Ci 2.48E-04 2.02E-04

3. Particulates Co-58 Ci 1.53E-06 0.00E+00 Co-60 C: 2.65E-06 0.00E+00 Zn-65 C: 0.00E+00 9.27E-07 Sr-89 C: 5.02E-06 3.32E-06 I-131 C: 0.00E+00 3.78E-06 Tot 41 For Ci 9.20E 8.03E-06 Period ._-06

• zeroes in this table indicate that no radioactivity was resent above detectablo levels. See Table 2-8 for ty Sowerlimitsofdetectionforgaseoussampleanalyses.pical

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

)

l l

l

TABLE 2-4c E. I. HATCH NUCLEAR Pu?UT - SITE SMI ANNUAL RADIOACTIVE EFFLUENT RCLEASE REPORT 1991 GASEOUS EFFLUENTS - GROUND-LE'v3L RELEASES *

)

Continuous Mode Batch Mode **

Nuclides '

Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 f

1. Fission Gases

____________....______ ._____________________________________ i Kr-85 C: 1.03E+01 0.00E+00 Xe-133 C: 3.02E-02 6.15E-02 Xe-135 C: 2.31E+01 2.03E+01 Tot 1 For Per od Ci 3.35E+01 2.03E+01

2. Iodines I-131 C:. 1.56E-04 9.14E-05 I-133 C:. 4.94E-03 1.83E-04 I 135 Ca 3.06E 03 0.00E+00 Total For Period Ci 8.15E 2.74E 04 i

_________________________-03 __ .____________________..__________

3. Particulates Mn-54 Cj 6.91E-06 4.07E-07 Co-58 C:. 9.21E-06 0.00E+00 Co-60 C: 3.44E-05 1.47E-05 Zn-65 C: 1.73E-04 9.49E-06 Sr-89 C: 9.30E-06 4.25E-06 Sr-90 C: 8.72E-08 0.00E+00 Mo-99 C: 0.00E+00 5.04E-06 Cs-137 C:. 8.52E-05 9.46E-07 Ba-140 C: 2.03E-06 0.00E+00 I 131 Ca 0.00E+00 5.09E

.___________________________________-06 ________________ ________

Total For Period Ci 3.20E 04 3.99E 05

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

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

s LO-

Table 2-5 E. I. MATCH NUCLEAR PLANT - SITE SEMI ANNUAL RADIOACTIVE- EFFLUENT RELEASE REPORT 1991 GASEOUS EFFLLENTS - DOSE RATES Dose Rates Due to Noble Gases ------

---

4'of Organ Tech Unit -Quarter 3- Tech  % of Quarter 4 Tech Speg Spec Limit Spec i Limit L1mit TD y 500 mrem / r 4.68E-02 9.36E-03 4.11E 8.22E-03 Sk 3000 mrem / r .1.16E-01 '3.86E-03 -8.87E-02 2.96E-03 Dose Rates Due to Radiciodine, Tritium, and Particulates Organ Tech Unit Quarter 3  % of Tech Quarter 4  % of

-Tech Spec Limit Speg Spec L1mit Limit B ne 1500 mrem r 2.01E-04 1.34E-05 1.20E-05 8.02E-07 L ver 1500 mrem r 1.51E-02 1.01E-03 6.12E-03 4.08E-04 TBody 1500 mre r 1.50E-02 1.00E-03 6.12E-03 4.08E-04 Thyroid 1500 mrem r 3.80E-02 2.53E-03 8.45E-03 5.63E-04 Kianey 1500 mrem r 1.52E 1.01E-03 6.13E-03 4.08E-04 Lung 1500 mrem r 1.54E-02 1.03E-03 6.24E-03 4.16E-04 GILLI 1500 mrem yr 1.50E-02 9.98E-04 6.12r 03 -4.08E-04

_ =.

41-

b TABLE 2-6a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 AIR DOSES DUE TO NOBLE GAS RELEASES Cumulative Doses per Quarter ____________ . . __ . ____ _

Type Tech Unit Quarter 3  % of Quarter 4  % of Tech of Speg Tech Radi- Limit Spec Soeg ation L1mit Limit j Gamma 5.0 mrad 6.96E-03 1.39E-01 5.79E-03 1.16E-01 Beta 10.0 mrad 1.40E 1.40E 01 7.35E 03 7.35E-02

____ __ .. ____ .___ ____-02 __ ____

Cumulative Doses This Year wpe Tech Unit uarters  % of of Speg ,2,3,& 4 Tech Radi- Limit Spec Limit ation ____ . __ . __ . ________ . .

Gamma 10.0 mrad 1.92E-02 1.92E-01 Beta 20.0 mrad____ ___.4.28E 02 __ . 2.14E 01 1

h2-

{

1

___g

TABLE 2-6b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 AIR DOSES DUE TO NOBLE GAS RELEASES ,

Cumulative Doses per Quarter T pe Tech Unit Quarter 3  % of Quarter 4  % of o Spec Tech Tech Radi- Limit Spec Socc ation Limit Limit '

Gamma 5.0 mrad 5.41E-03 1.08E-01 5.07E-03 1.01E-01 Beta 10.0 mrad ______-03 6.65E ________ 6.65E__-02 6.07E-03 6.07E 02 Cumulative Doses This Year Wpe Tech Unit uarters  % of of Spec ,2,3,& 4 Tech Radi- Limit Spec ation Limit Gamma 10.0 mrad 1.91E-02 1.91E-01 Beta 20.0 mrad 2.37E 02 1.19E

_____________________________________-01 _____________________ ..

_L3-

. _ _ _ . _ _ _ _ _ _a

TABLE 2-7a E. I. HATCH NUCLEAR PLANT - Unit 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 INDIVIDUAL DOSES DUE TO RADIOIODINE TRITIUM, AND PARTICULATES IN GASEOUS RELkASES Cumulative Doses per Quarter

-Organ Tech Unit Quarter 3  % of Quarter 4  % of Spec Tech Tech i L1mit Spec Spec Limit Limit

---

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

Bone 7.5 mrem 1.35E-03 1.80E-02 1.28E-04 1.71E-03 Liver 7.5 mram 5.14E 6.85E-02 3.01E-04 4.02E-03 TBody 7.5 mrem 4.57E-03 6.09E-02 2.96E-04 3.95E-03 Thyroid 7.5 mram 1.05E-02 1.40E-01 7.63E-04 '1.02E-02 Kianey 7.5 mrem 4.69E-03 6.25E-02 2.94E-04 3.92E-03 Lung 7.5 mrem 4.49E-03 5.98E-02 2.98E-04 3.97E-03 GILLI 7.5 mrem 4.43E-03 5.90E-02 2.97E-04 3.96E-03 Cumulative Doses This Year Organ Tech Unit Quarters  % of Spec 1,2,3,& 4 Tech L1mit Spec-Limit

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

Bone 15.0 mrem 1.97E-03 1.31E-02 Liver 15.0 mrem 7.86E-03 5.24E-02 TBody 15.0 mrem 7.25E-03 4.83E-02  ;

Thyroid 15.0 mrem 1.94E-02 -1.30E-01 Kianey 15.0 mrem 7.36E-03 4.91E-02 Lung 15.0 mrem 7.12E-03 4.75E GILLI 15.0 mrem 7.07E-03 4.72E-02 Lh-

t TABLE 2-7b E. I. H \TCH NUCLEAR PLANT - Unit 2 SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991 INDIVIDUAL DCSES DUE TO RADIOIODINE TRITIUM, AND PARTICULATES IN GASEOUS REL$ASES Cumulative Doses per Quarter Organ Tech Unit Quarter 3  % of Quarter 4  % of Spec Tech Tech L1mit SpeQ Spec Limit Limit Bone 7.5 mrem 9.19E-05 1.22E-03 5.54E-05 7.39E-04 Liver 7.5 mrem 2.65E-03 3.54E-02 2.47E-03 3.30E-02 TBody 7.5 mrem 2.65E-03 3.54E-02 2.47E-03 3.30E-02 Thyroid 7.5 mrem 4.98E-03 6.64E-02 3.78E-03 5.04E-02 Ki8ney 7.5 mrem 2.66E-03 3.54E-02 2.48E-03 3.30E-02 Lung 7.5 mrem 2.65E-03 3.53E-02 2.47E-03 3.29E-02 GILLI 7.5 mrem 2.65E 3.53E 02 2.47E 03 3.30E 02

____________________________-03 __________ ______..______________ _

Cumulative Doses This Year Organ Tech Unit Quarters  % of Spec 1,2,3,& 4 Tech L1mit Speg Limit Bone 15.0 mrem 3.78E-04 2.52E-03 Liver 15.0 mrem 1.10E-02 7.35E-02 TBody 15.0 mrem 1.10E-02 7.34E-02 Thyroid 15.0 mrem 2.95E-02 1.96E-01 Ki8ney 15.0 mrem 1.11E-02 7.38E-02 Lung 15.0 mrem 1.10E-02 7.31E-02 GILLI 15.0 mrom 1.10E 7.32E 02

___________________________-02 _______. _________________________

\

_L5-

TABLE 2-8 LOWER LIMITS OF DETECTION - GASEDUS SAMP',E ANALYSES The values in this table represent aoriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of caseaus radwaste samples.

RADIOt0CLIDE LLD UNITS Kr-87 1.31E-07 uCi/ml Kt-88 2.10E-07 Xe-133 1.62E-07 Xe-133m 6.07E-0 8 X e-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 2n-65 7.51E-14 MO-99 6.02E-13 Cs-134 3.64E-14 Cs-137 2.88E-14 Ce-141 4.94E-14 Ce-144 2.02E-13 Sr-89 1.00E-11 Sr-90 1.00E-11 H-3 1.00E-06 h6-

3. SOLID WARTE 3.1 RFI;ULA70RY RECOIREMENTS The Technical Specifications presented in this section are for Unit 1. Requirements for Unit 2 are the same as for Unit 1r however, the Technical Specification nunbers are not the same.

TECHNICAL SPECIFICATIONS 3.15.3.1 The solid radwaste system shall be used in accordanca with the PROCESS OCNTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATICN 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 the following infornation for each type of solid waste shipped offsite during the report oeriod:

a. Container volume

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

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

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

e. Type of container, e.g., LSA, type A, type B, large quantity

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

3.2 SOLID WASTE DATA Reculatory guide 1.21 Table 3 is found in this report as Table 3-la, and 3-lb.

hT-

. .. .. __ - _ . ._ 1

EFFLUEtTI AND WASTE DISNSAL SEMTAhNUAL REPORT 1991 July 1,1991 - Decerber 31, 1991 SOLID WASTE AND IFRADIATED FUEL SHIPME!frS FOR UNITS I AND II TABLE 3-1A PERIOD COVERED: FROM 7 / 1/ 91 TO 12 / 31/ 91 FOR UNIT 1& 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiat'ed fuel) t

1. Type of waste UNIT 6 month Est. Total neriod ranong

a. Spent resins, filter sludges, evaporator a 3 1 35m2 bottoms. etc. c1 1 D3 3 1.0 m 01

b. Dry compressible waste, contaminated a 3 1.75m2 eaulo. etc. c1 1.4 0 a 0 1.0 sol

c. Irradiated components, control rods, a 3 0 .00 m o el- 0 .00 m 0 2.0 noi

d. Control Rod Drive Filters __.,p 3 1 .59 E O c.. 2.53E1 2.0 El

e. Ot.her (describe) a h 1 11E1 eauin. etc. Vendor to Barnwell (DAV) c1 1 .072.'-l 2.0 E01

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

I SOff0PR PERCENT CURIES

a. Zn-65 3.38E+01 3.48E+02 re-55 2.52E+01 2.60E+02

~

Co-60 2.07E+01 2.13E+02 Cn-137 2.20E+00 2.27E+01 OT!iER 1.81E+01 1.86E+02

h. 2n-65 4.38E+01 6.13E-01 re-55 8.59E+00 1.20E-01 co-60 3.17E+01 4.44E-01 cm-137 5.92E+00 8.29E-02 OTHER 1.00E+01 1_dE-01

c. 2n-65 0.00E+00 0.00E+00 Fe-55 0.00E+00 0.00E+00 co-60 0.00E+00 0.00E+00 cm-137 0.00E+00- 0.00E+00 OTHER 0.00E+00 0.00E4 00

d. 2n 6.4BE+00 1.64E+00 Fa-55 2.37E+01 5.90E+00 cn-60 3.75E+01 9.49E+00 cm-137 0.00E+00 0.00E+00 OTHFR 3.23E+01 9.17E+00

e. 2n-A; 4.2BE+01 4.69E-02 Fa-;; R.59E+00 9.19E-03' cn-K0 - 3 ' 17E+ 01- 3.39E-02 cm-137 5.92E+00 6.33E-03 nTHER 1.00E+01 1.07E-02

3. Solid Maste Dispositica Mi=her of th1 manta Mode of Transportation Destination 34 Tractor Trailer Barnwell e B. ISRADIATED FUBL SHIPMENTS (Disposities)

Ni=her of thi_ manta Mode of Trananortation k tinatlam N/A N/A N/A.

LS-l

_ _ _ _ A

EFFLUEffT AND WASTE DISIOSAL SEMIANNUAL REPORT 1991 July 1, 1991 - December 31, 1991 SOLID WASTE AND IRFADI ATED FUFL SHIPMEVTS FOR UNITS I AND II TABLE 3-18 TYPE CUtts PRINCIP!J SUt!AL IO4BER OF VOLIME OF TYPE SOLIDIFICATION Or QUAart!TY / WUCLIDes / COstTAINER CQrtaturas EACE CCErTAllrER SRIFleir! / AC DIT wi m brTravtwrn nrivauTu m fm nati n t Ptt fEf RETPPED rifaff Ftf? fft il EQrratwen Dswatered 646.7 En65,Co60 Itigh Integrity 4 132.4 Type B n/a Rasins measured Cs137 Fe55 Container Cask Measured 10-142 Dewatered 378.72 . In65,Co60 High Integrity 20 202.1 Type A n/a Rasins measured Cs137, Fe55 Container Cask ha u r ed

..e..s14-210 Torus 4.58 In65,Co60 High Integrity 1 202.1 Type A n/a Cleanup measured: Cs137,Fe55 Container Cask Filters Measured 14-210 DAW 1.40 Zn65,Co60 Strong Tight- 67 92 Strong n/a (ORY) measured Cs137,Fe55 Container Tight (ACTIVE) Measure B-25 Boxes (WASTE)

CRD 25.3 Zn65,Co60 High Integrity 2 28.07 Type B- n/a Filters measured Fe55 Container Catk measure 10-142 Vendor .107 In65, Co60 Strong unknown unknown strong n/a to measured Cs137, Fe55 -tight tight Barnwell measured container L9

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

4 CHAtCFS 'IO THE PIAN 1'- HATCH ODCM AND PCP There were no chances for this period.

i I

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S. METEDROIDGY l l

In accordance with Technical Soocification 6.9.1.9, the annual summary ef meteoroloaical data collected at Plant Hatch over 1991 is presented in this section.

5.1 1991 Meteoroloaical Data Attachment 1 Joint Frequency Tables of Wind Speed and Wind Direction 10m vs Delta Temperature 60-10m.

Attachment 2 Joint Frequency Tables of Wind Speed and Wind Direction 60m vs Delta Temperature 60-10m.

Attachment 3 Joint Frecuency Tables of Wind Soeed and Wind Direction 100m vs Delta Temperature 100-10m.

Attachment 4 Wind Roses from 10m (Seasonal and Annual).

Attachment 5 Wind Roses from 60m (Seasonal and Annual).

Attachment 6 Wind Roses from 100m (Seasonal and Annual).

Attachment 7 Wind Roses from 23m Backup (Seasonal and Annual).

Attachment 8 Percent Data Recovery by Parameter and for Pertinent Comoosite Parameters for 1991.

Attachment 9 Plots of Monthly Averaces and Averages of Daily Extremes of Ambient Temperature and Dew Point Temoeratuce, l

Attachment 10- Daily, Monthly, and Annual Precipitation for the Period of January throuch December-1991.

Attachment 11 Descriptive Paragraoh Comparina 1991 with Previous Years.

{

l- - - - . - , , . . , . - - .

1 1 of 8 'j AliACHMENT 1. JOINT FREQUENCY TABLES OF WIND SPEED AND WIND DIRECTION 10m l VS DELTA TEMPERATURE 60-10m JANUARY 1, 1991 THROUGH DECEMBER 31, 1991 4

SITE: PLANT HATCH . - _- - .- -. - . -

HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60-UIND SPEED (MPH)

UIND >24 TOTAL DIRECTION 1-3 4-7 8-12 13-18 19-24 ___ _____

4 34 2 0 0 0 40 N 0 51 8 41 2 0 0 NNE 0 144 4 122 18 0 0 NE 0 102 5 88 9 0 0 ENE r 47 5 41 1 0 0 0 E.

5 35 6 0 0 0 46 ESE 41 10- 23 8 0 0 0 SE 10 23 10 0 0 0 43 SSE 7 40 17 0 0 0 64 S

11 58 19 0 0 0 88 SSU l11 ' 80 10 0 0 0 101 SU 11 62 9 0 0 -0 82 USU 7 104 10 0 0 0 121 U

13 83 16 0 0 0 112 UNU 11 78- 16 0 0 0 105 NU 1

(

6 38 10 0 9 0 54 NNU 128 950 163 0 0 0 1241 TOTAL

________J_____________________________________________________

PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 483 HOURS OF MISSING DATA: 68

W . -.

ATTACHMENT 1 (continued) 2 of 8 SITE: PLANT HATCH - - - - . . . _ _ . _ .

HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91123124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:D160-UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 2 13 2- 1 0 0 18 N

6 10 0 0 0 0 16 NNE NE 3 33 1 0 0 0 37 2 38 1 0 0- 0 41 ENE 4 11 0 0 0 0 15 E

4 11 1 0 0 0 16 ESE 9E O 10 1 0 0 0 11 6 8 2 0 0 0 16 ss2 S 6 19 2 0 0 0 27 SSU 5 '20 3 0 0 0 28 SU 5 1'4 0 1 0 0 20 ,

14 26 0 0 0 41 LSU 1 U 7 29 1 0 0 0 37 3

[

UNU '

S 32 3 1 0 0 41 NU 8 39 6- 0 0 0 53 NNU 11 11 3 0 0 0 25 PERIODS'OF CALM (HOURS): 0 UARIABLE. DIRECTION 251 HOURS OF MISSING DATA: 68

ATT ACHMENT I (continued) 3 of 8 SITE: PLANT HATCH - - - - . - - .-

HOURS AT EACH UIND SPEED AND DIRECTION PER'0D DE RECORD = 91010101-91123124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60-

~

UIND SPEED (MPH)

UIND 1-3 4-7 8-12 13-18 19-24 >24 TOTAL DIRECTION ____ _____ _____ ___ _____

8 17 1 0 0 0 26 N

5 .8 0 0- 0 0 13 NNE 6- 42 3 0 0 0 51 NE j.

4 27 0 0 0 0 31 ENE 4 9 0 0 0 0 13 E

7 10 0 0 0 0 17 ESE

-SE 11 14 0 0 0 0 25 SSE 3 6 1 0 0 0 10' S 4- 18 5 1 0 0 28 SSU 5 18 4 0 0 0 27 0 0 31 SU 9 19 3 0 USU J 10 13 0 0 0 0 23 U 7 13 2 0 0 0 22 UNU 9 22 3 1 0 0 35 NU 7 17 1 0 0 0 25 NNU 8 13 0 0 0 0 21 l TOTAL 107 266 23 2 0 0 398 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 260 HOURS OF I MISSING DATA:

68

ATTACHMENT 1 (continued) 4 of 8 SITE: PLANT HATCH _ . _ _ _ _ _ _ - _ .

HOURS AT EACH UI'iD SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91123124 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60-WIND SPEED (MPH)

UIND DIRECTION 1-3 4 8-12 13-18 19-24 >24 TOTAL N 33 42 .17 0 0 0 92 NNE 39 59 -1 0 0 0 99 NE 77 271 15 0 0 0 363 ENE 62 164 5 0 0 0 231 E 52 68 3 0 0 0 .123 ESE 50 56 2 0 0 0 108 SE 39 54 9 0 0 0 102 SSE 21 57 3 0 0 0 81 S 38 90 20 1 0 0 149 ,

SSU '48 69 11 8 0 0 136 SU 51 67 9 0 0 0 127 USU 42 41 9 0 0 0 92 j' U. 51 49 19 0 0 0 119 UNU 38 54 14 .1 0 0 107 NU 31- 76 17 0 0 0 124 NNU 23 69 9 0 0 0 101 TOTAL 695 1286 163 10 0 0 2154 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION .1340 HOURS OF MISSING DATA: 68 l

. . - . = - _ _ .

ATTACHMENT I (continued) 5 of 8 SITE: PLANT HATCH _ _ _ _ _

HOURS AT EACH UIND SPEED AND DIRECTION

.PERIGD OF-RECORD =- 91010101-91123124 STABILITY CLASS: E DT/DZ SPE D:SPD10M DIRECTION:DIR10M LAPSE:DT60-

}

l ELEVATION:

WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 ' TOTAL.

31 .36 8 'O O O 75 N 0 64 31 33 0 0 0 NNE 0 339 141 196 2 0 0 NE 176 109 66 1 0 0 0 ENE 94 78 15 '1 0 0 0 E

.99 33 1 0 -0 0 133 ESE 144 91 2- 0 0 0 237 SE 102 64- 6 0 0 0 172 SSE

'131 86 2 0- 0 0 219 S

'138 66 6 0 0 0 210 SSU 211 62 4 0- 0 0 2??  !

l SU 130 37 0 0 0 0 167 USU

.95 54 1 0 0 0 150 U

75 73 16 2 0 6 166 UNU )

41 81 .10 0 0 0 132 NU

'30 50- 1 0 0 0 81 NNU TOTAL 1586 1043 61 2 0 0 2692

~~ -- ~~ - -~~~~~ -~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

iiid55 5 C5 J 55Eii 5 UARIABLE-DIRECTION 1757 HOURS OF MISSING DATAi 68

ATTACHMENT 1 (continued) 6 of 8 l

j SITE: PLANT HATCH HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 91010181-91123124 STABILITY CLASS: F D UDZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60-UIND SPEED (MPH)

UIND 1-3 4-7 8-12 13-18 19-24 >24 TOTAL DIRECTION ____ _____ _____ ___ _____

21 3 1 0 0 0 25 N

1G 4 0 0 0 0 20 NNE 63 29 0 0 0 0 92 NE 51 11 0 0 0 0 62 ENE 21 0 0 0 0 0 21 E

ESE 24 1 0 0 0 0 25 41 2 1 0 0 0 44 SE 38 1 0 0 0 0 39 SSE 60 12 0 0 0 0 72 S

SSU 81 4 0 0 0 0 85 SU 73 3 0 0 0 0 76 USU 99 1 0 0 0 0 100 W 60 8 'O O O O 68 UNU 48 12 0 0 0 0 60 NU 27 15 0 0 0 0 42 NNU 17 5 1 0 0 0 23 TOTAL 740 111 3 0 0 0 854 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 520 HOURS OF MISSING DATA: 68 i

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ATTACHMENT 1 (centinued) 8 cf 8 SITE: PLANT HATCH _ . _ _ _ .

-HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 91010101-91123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60-WIND SPEED (MPH)

, WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

~

N 106 145 31 1 0 0 283 NNE' 114 155 3 0 0 0 272 NE 312 696 39 0 0 0 1047 ENE 253 395 16 0 0 0 664

. E 179 145 5 0 0 0 329 ESE 198 146 10 0 0 0 354 SE 277 195 21 0 0~ 0 493 SSE 206 159 22 0 0 0 387 i

S 292 268 46 2 0 0 608 SSU 422 237 43 8 0 0 710 SU.- 530 246 26 1 0 0 803 USU 494 182 '19 0 0 0 695 U '348 266 33 0 0 0 647 UNU 231 280 52 5 0 0 568 NU 146 309 50 0 0 0 505 NNU 116 187 24 0 0 0 327 TOTAL 4224 4011 440 17 0 0 8692

, PERIODS OF CALM (HOURS): 0

VARIABLE DIRECTION 4975 HOURS OF MISSING DATA: 68

_ _ _ _ - _ _ - _ _ _ _ _ _ . _ -