ML20235V538

Semiannual Rept Plant Radioactive Effluent Releases, Jul-Dec 1988

ML20235V538
Person / Time
Site:	Hatch
Issue date:	12/31/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML20235V499	List: ML20235V496 ML20235V516 ML20235V538
References
NUDOCS 8903100225
Download: ML20235V538 (100)

Text

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ENCLOSURE 2 GEORGIA POWER COMPANY PLANT E.I. HATCH UNITS NO. 1 & 2 SEMI-ANNUAL REPORT PLANT RADI0 ACTIVE EFFLUENT RELEASES JULY 1, 1988 -- DECEMBER 31, 1988 gojhi321 l

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PLANT E. I. HATCH SEMIANNUAL REPORT RADIOACTIVE EFFLUEW RELEASE REPORT SECTION TITLE PAGE 1.

LIOUID EFFLUEf7TS 1.1 PEGULA'IORY LIMITS

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1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5

1.3 MEASUREMENTS AND APPROXIMATIONS OF 5

TOTAL RADIOACTIVITY 1.4 LIQUID EFFLUENT RELEASE DATA 7

1.5 RADIOLOGICAL IMPACT ON MAN D"E "O

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LIQUID RELEASES 2

GASEOUS EFFLUENTS 22 2.1 REGULA'IORY LIMITS 22 2.2 MEASUREMENTS AND APPROXIMATIONS OF 28 TOTAL RADIOACTIVITY 2.3 GASEOUS EFFLUENT RELEASE DATA 33 2.4 RADIOLOGICAL IMPACT DUE 'IO GASEOUS 3h RELEASES 3

SOLID WASTE 50 3.1 REGULA'IORY SPECIFICATIONS 50 3.2 SOLID WASTE DATA 50 4

THE UNAVAILABILITY OF MILK AT 53 A REMP STATION 5

LA!O USE SURVEY RESULTS 53 6

METEOROLOGY Sh 6.1 METEOROLOGICAL DATA Sh l

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?LANT E. I. HATCH SEMIANNUAL REPORT RADICACI!VE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 3

RADI0 ACTIVE LIQUID EFFLUENT MONI70 RING INSTRUMENTATION 1-2a LIQUID EFFLUENTS - SUMMATION OF lo ALL RELEASES - UNIT 1 1-2b LIQUID EFFLUENTS - SUMMATION OF 11 ALL RELEASES - UNIT 2

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1-2c LIQUID EFFLUENTS - SUMMATIONS OF 12 ALL RELEASES - SITE 1-3a LIQUID EFFLUENTS - UNIT 1 13 1-3b LIOUID EFFLUENTS - UNIT 2 15 1-3c LIQUID EFFLUENTS - SITE 17 1-4a If0IVIDUAL DOSES DUE TO LIQUID RELEASES - UNIT 1 19 1-4b INDIVIDUAL DOSES DUE 70 LIQUID 20 RELEASES - UNIT 2 1-5 IDWER LIMITS OF DETECTION - LIOUID 21 SAMPLE ANALYSES 2-1 TECHNICAL SPECIFICATION TABLE 24 3.14.2-1 RT@IQACTIVE GASEOUS EFFLUENT MONI70 RING INSTRUMENTATION 2-2a GASEOUS EFFLUENTS - SUMMATION OF 35 ALL RELEASES - UNIT 1 2-2b GASEOUS EFFLUENTS - SUMMATION OF 36 ALL RELEASES - UNIT 2 2-2c GASEOUS EFFLUENTS - SDMMATION OF 3T ALL RELEASES - SITE 2-3a GASEDUS EFFLUENTS - ELEVATED 36 RELEASES - UNIT 1 2-3b GASEQUS EFFLUENTS - ELEVATED 39 RELEASES - UNIT 2 2-3c GASEQUS EFFLUENTS - ELEVATED Lo RELEASES - SITE

f TABLES LIST CF TABLES PAGE 2-4a GASEOUS EFFLUENTS - GROUND-L*

LEVEL RELEASES - UNIT 1 2-4b GASEOUS EFFLUENTS - GROUND -

h2 LEVEL RELEASES - UNIT 2 2-4c GASEOUS EFFLUENTS - GROUND -

h3 LEVEL RELEASES - SITE

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2-5 GASEOUS EFFLUENTS - DOSE LL RATES - SITE 2-6a AIR DOSES DUE 20 NOBLE GASES -

L5 UNIT 1 2-6b AIR DOSES DUE 20 tOBLE GASES -

L6 UNIT 2 2-7a INDIVIDUAL DOSES DUE 70 RADIOIODINE, L7 TRITIUM, Ato PARTICULATE IN GASEOUS RELEASES - UNIT 1 2-7b INDIVIDUAL DOSES DUE 70 RADIOIODINE, kB TRITIUM, AND PARTICULATE IN GASEOUS RELEASES - UNIT 2 2-8 IDWER LIMITS OF DETECTION - GASEOUS L9 SAMPLE ANALYSES 3-la,b SOLID WASTE AND IRRADIATED FUEL 51,52 SHIPMENTS

l 1

RADIOACTIVE EFFLUENT RELEASE RERRT 1 LIQUID EFPLUEffrS 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 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 alarm / trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded.

The alarm / trip serpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION mat 0AL (ODOI).

(Technical Specification Table 3.14.1-1 is included in this section as Table 1-1).

3.15.1.1 The concentration of radioactive material released at any time from the site to UfEtES"1RICTED ARFAS (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 dismived or en entrained noble games, the concentration shall be

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limited to 2.0E-04 uCi/ml total activity.

3.15.1.2 The dose or dose cc::aitment '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:

Durino any calendar quarter to less than or equal a.

to 1.5 mrem to the total body and to less than or equal to 5 mrem to any oroan.

b.

During any calendar year to less than or equal to 3 meem 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 described in the ODOt, shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when tha projected doses due to the liquid effluent per Unit from the site (figure 3.15-1) when proWted over the calendar quarter would exceed 0.18 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 having tank overflows and drains connected to the liquid radwaste treatment system.

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 Ci, 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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TABT2 1-1 TECHNICAL SPECIFICATION TABLE 3.'14.1-1 (SHErr 1 of 2)

RADIOACTIVE LIQUID EPPLUENT PONItatIIG IN!rIROMENTATION Minimum Channela 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 Water System Effluent Line 1

(b) 101

3. Flowrate Measure-ment Devices **

Q 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 i

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• • Pap curves may be utilized to estimate flows in such cases, ACTION statement 102 is not required.

(a)

Whenever the radwaste discharge valves are not locked l

closed.

l (b)

Whenever the service water system pressure is below the closed cooling water system pressure or differential pressure ir.dication is not available...

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TABLE 1-1 (CDNTINUED1 TECHNICAL SECIPICATION TABLE 3.14.1-1 (SHEET 1 of 2)

RADIOACTIVE LIGJID EPPLUENT ENI'1GING INS'IRCMENTATION TABLE f0fATIONS AcrION 100 - With the neber of channels OPERABM 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 disenarge valving.

Otherwise, suspend release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstan s shall be included in the next semi-annual effluent release report.

AcrION 101 - With the nebers of channels OPERAB2 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 (l O

Detection of at least 10 'pta or gamma) at a Lower Limit of uCi/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.

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ACTION 102 - With the ntaber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releaser via this pathway may continue, provided l

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 i

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.

i ACTION 103 - With the number of channels OPERABLE less than I

required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system l

nonitor is OPERABLE.

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t-1.2

-1%KIlm PERMISSIBLE CONGNIRATIONS The MPC values used in determining allowable liquid radwaste release rates and concentrations for principal ganea emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10CPR Part 20, Appendix B, Table II, Coluan 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 uti/ml.

Further, for all the above radionuclides or

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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 affluent radiation monitor setpoints is described in Section 1.3 of this report.

1.3 MEASLREMERES AND APPROXIMATIOtG OF TO'DLL 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 l

entrained noble gases by gamma spectrometry.

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

Measurement Frequency Method 1.

Ganna Isotopic Each Batch Ganna spectroscopy with computerized data reduction 2.

Dissolved or Each Batch Gunna spectroscopy Entrained with computerized Noble Gases data reduction - _ _ _ - _ _ - __._.

I Measurement Precuency Method

3. Tritium Monthly Distillation and Composite liquid seinrillation counting

4. Gross Alpha Monthly Gas Flow Proportional Composite counting

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

6. Fe-55 Quarterly Chemical separation and composite low energy photon detector.

Gamne isotopic measurements are performed in-house in the radiochemistry lab using germanium spectrometry.

Three germanium detectors are available: a 25%

efficient and two 15% efficient intrinsic germanium detectors, with 2.0 FWHM resolution and housed in 4 inch-thick lead shields. A one-liter liquid radwaste I

sample is poured into a Marinelli beaker in preparation for a 2000-3000 second count. A peak-anarch 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 q"

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): Mrr-54, F-59, Co-58, Co-60, Zn-65, Mo-99, Ca-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for counting time, decay time, sanple volume, sanple '

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

The radionuclides concentrations determined by gamma spectroscopic analysis of a sanple taken from a tank planned for release and the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90, and Fe-55 are used alors; 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 neximum 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.

A monitor reading'in excess of the calculated Lsetpoint therefore results in an autoestic' termination of the liquid radwaste discharge.

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

Radionuclides concentrations, safety factors, lilution stream flow rate, and liquid effluent radiation monitor calibration factor are entered into the camputer.and a prerelease printout is generated. If the release is not permissible appropriate warnings will be included on the prerelease printout.

If the release is permissible it is approved by the Chemistry Foreman on duty. The pertinent information is transferred manually from the prerelease printout to a one-page release permit which is forwarded to Radeste Operations. When the release is oczpleted the release permit is returned from Radeste Operations with actual release data included. These data are input to the camputer and a postrelease printout is generated.. The postrelease printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

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as 1.4 LIQUID EFFIRENT RELEASE DATA Regulatory Guide. l.21 Tables 2A and 2B'are found 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.

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

1.

Fission and activation products - The total release values (not including tritim, gases, and alpha) are cenprised of the sum of the measured individual radionuclides activities. This sum is for each batch released to the river for the respective

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i

l y,

quarter. Percent of. applicable limit is determined from a mixed nuclide NPC fraction calculation. The average concentration for each nuclide over all released betees is divided by the corresponding individual MPC value. The sum over all nuclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the quarter.

2.

Tritium - The' measured tritium concentrations in the monthly camposite samples are used to' calculate the total release and averbge diluted concentration during each period. Average diluted 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 sanole frca each liquid radwaste batch. The average concentration of dissolved or entrained noble gases for all released batches is divided by the MFC value stated in Metnical specifications 3.15.1.1 and 3.11.1.1 (2.0E-04 tri/ml) to determine the MPC fraction. The result x100 is the percent of applicable limit for noble gases I

in liquid offluent releases during the quarter. Radioisotopes of iodine in any form are also determined during the isotopic analysis for eadi batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not

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provide additional information.

4.

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

-S-

Other data certinent to batch releases of radioactive liculd effluent from both units are as follows:

Number of batch releases:

683 Total time period for batch releases:

96,5?3 minutes Maximum time period for a batch release:

230.0 minutes Averace time period for batch releases:

141.3 minutes Minimum time period for a batch release:

2.0 minutes Averace stream flow durina periods of release of licuid effluent into a flowing stream:

2,498 CFS 1.5 RADIOLOGICAL IMPACT ON MAN DUE M LIQUID RELEASES Doses to an individual, due to radioactivity in licuid effluent, were calculated in accordance

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with Technical Specifications 3/4.15.1.2 (Unit 11 and 3/4.11.1.2 (Unit 2) usina the methodoloav 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 presented in Table 1-4a for Unit 1 and Table 1-4b for Unit 2.

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TABLE 1-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1988 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 3 Quarter 4 Error %

A. Fission &

Activation Products

1. Total release (not includina ci 1.0BE-01 3.69E-01 4.6E+01 H-3, gases, alpha)

2. Average diluted concentration uCi/ml 6.43E-08 1.20E-07 durina period

3. % of applicable 1.02E+00

1. 39E+00 limit B. Tritium 7

1. Total release C1 1.44E+ul 4.36E+00

. 7E+01

2. Averaae diluted uCi/ml 7.99E-06 3.08E-06 concentration during period

3. % of applicable 2.66E-01 1.02E-01 limit C. Dissolved and Entrained Gases

1. Total release Ci 3.04E-02 2.95E-03 1.0E+02

2. Average diluted uCi/ml 1.82E-08 2.09E-09 concentration during period

3. t of applicable 9.10E-03 1.0SE-03 limit D. Gross aloha radioactivity

1. Total release C1

1. 59E-06 2.20E-06 1.2E+02 E. Volume of waste (prior to dilution) liters 7.21E+06 6.39E+06 1.0E+01 F. Volume of dilution water used liters 1.67E+09 1.41E+09 1.6E+02 1 _ _ _ - _ _ _ _.

1 L

TABLE 1-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANtUAL IFFLUENT RELEASE REPORT 1988 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 3 Quarter 4 Error %

A. Fission &

l Activation Products

1. Total release (not including Ci 2.32E-02 1.62E-02 4.7E+ 01 H-3, gases, alpha)

2. Averaae diluted concentration uCi/ml 2.20E-08 1.40E-08 during period

3. % of applicable 5.35E-01 2.31E-01 limit B. Tritium

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1. Total release C1 3.0eE+00 z.e3E+00

.7E+01

2. Averace diluted uCi/ml 2.92E-06 2.43E-06 concentration during period

3. t of applicable 9.74E-02 8.10E-02 limit C. Dissolved and Entrained Gases

1. Total release Ci 1.42E-02 7.71E-03 1.0E+02

2. Average diluted uci/ml 1.35E-08 6.64E-09 concentration during period

3. % of applicable 6.7EE-03 3.32E-03 limit D. Gross alpha radioactivity

1. Total release Ci 2.84E-08 3.53E-08 1.2E+02 f

E. Volume of waste (prior to dilution) liters 3.75E+06 4.27E+06 1.0E+ 01 F. Volume of dilution water used liters 1.05E+09 1.16E+09

1. 6E+ 02

TABLE 1-2c l

E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL EFFLUENT RELEASE REPORT 1988 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total i.

Unit guarter 3 Quarter 4 Error %

A. Fission &

Activation-Products

1. Total release (not includino ci 1.31E-01 1.86E-01 4.7E+ 01 H-3, cases, I

alpha)

2. AveraQe diluted concentration uCi/ml 4.79E-08 7.23E-08 during period

3. % of applicable 8.31E-01 8.64E-01 limit B. Tritium

1. Total release C1 1.64E+01 7.19E+00

.7E+01

2. Average diluted uCi/ml 5.98E-06 2.79E-06 concentration during period

3. t of applicable 1.99E-01 9.29E-02 limit C. Dissolved and Entrained Gases

1. Total release C1 4.47E-02 1.07E-02 1.0E+02

2. Averace diluted uCi/ml 1.64E-08 4.15E-09 concentration durina period

3. t of applicable 8.19E-03 2.08E-03 limit i

D. Gross alpha radioactivity

1. Total release C1 1.62E-06 2.24E-06 1.2E+02 4

E. Volume of waste i

(prior to J

dilution) liters 1.10E+07 1.07E+07 1.0E+01 F. Volume of dilution 1

water used liters 2.73E+09 2.57E+09 1.6E+02 l )

1 1

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i TABLE 1-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL LIQUID EFFLUENIS RELEASE REPORT 1988*

)

Pace 1 of 2 4

Continuous Mode **

Batch Mode Nuclides Released Unit Quarter 3 Ouarter 4 Quarter 3 Ouarter 4 H-3 Ci 1.34E+01 4.36E+00 Na-24 Ci 3.90E-03 1.30E-04 Cr-51 Ci 3.57E-04 1.68E-03 Mn-54 Ci 2.18E-04 3.70E-03 Mn-56 Ci 1.04E-04 1.55E-04 Fe-55 Ci 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 1.52E-04 Co-58 Ci 1.01E-05 1.05E-03 Co-60 Ci 1.79E-03 1.46E-02 Cu-64 Ci 2.78E-03 0.00E+00 Ni-65 Ci 0.00E+00 0.00E+00 Zn-65 Ci 5.08E-03 5.27E-02 As-76 Ci 7.53E-05 0.00E+00 Rb-88 Ci 0.00E+00 0.00E+ 00 Sr-89 Ci 0.00E+00 0.00E+00 St-90 Ci 0.00E+00 0.00E+00 Sr-91 Ci 1.68E-04 7.37E-05 Sr-92 Ci 1.93E-04 2.79E-04 Y-91m Ci 0.00E+00 0.00E+00 Z r-95 Ci 0.00E+00 1.36E-04 Nb-95 Ci

9. 87E-07 2.97E-04 Nb Ci 5.30E-04 6.14E-04 Mo-99 Ci 0.00E+00 0.00E+00 Te-99m Ci 6.49E-04 8.22E-05 Sb-125 Ci 2.90E-03

7. 93E-04 Te-131 Ci 1.73E-05 0.00E+00 I-131 Ci 2.82E-03 3.67E-03 I-132 Ci 4.56E-05 3.56E-05 I-133 Ci 1.70E-03

2. 00E -04 I-134 Ci 8.06E-04 4.29E-04 I-135 Ci 3.56E-04 4.81E-05 Cs-134 Ci 2.47E-02 2.60E-02 Cs-136 Ci 0.00E+00 0.00E+00 Cs-137 Ci 5.40E-02 6.05E-02 Cs-138 Ci

5. 29E-05 2.00E-04 Ba-139 Ci 3.73E-05 1.05E-04 Ba-140 Ci 0.00E+00 0.00E+00 La-140 Ci 2.59E-05 7.01E-05 Ce-141 Ci 0.00E+00 8.88E-05 Ce-144 Ci 0.00E+00 2.04E-04 No-239 Ci 4.26E-03 1.51E-03 l

Totals Ci 1.08E-01 1.69E-01 - _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - - - _ _ - - _ - - - _. _ _.

TABLE 1-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL LIQUID EFFLUENIS RELEASE REPORT 1988*

l Pace 2 of 2 Continuous Mode **

Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1

Kr-85m Ci 0.00E+00 0.00E+00 K r-85 Ci 8.26E-04 1.03E-03 Xe-131m Ci 2.15E-03 0.00E+00 Xe-133 Ci 1.13E-02 1.14E-03 Xe-133m Ci 1.75E-04 0.00E+00 Xe-135m Ci 2.10E-04 0.00E+00 Xe-135 Ci 1.58E-02 7.68E-04 l

A r-41 Ci 0.00E+00 1.02E-05 Totals Ci 3.04E-02 2.95E-03 Gross Alpha Ci 1.59E-06 2.20E-06

• 2 eros in this tacle indicate that no radioac:

1*/1:v was present above detectable levels. See Table 1-5 for tvoical lower limits of detection for liquid sample analyses.

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

1 I

-1h-

. RBLE 1-3b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1988*

.Page 1 of 2 Continuous Mode **

Batch Mode Nuclides peleased' Unit Quarter 3 Quarter 4 Ouarter 3 Quarter 4 l

H-3 Ci 3.08E+00 2.83E+00' l

Na-24 Ci 9.68E-04 6.15E-04 Cr-51 Ci 1.31E-03 9.62E-05 Mn-54 Ci-1.03E-04 1.71E-04 Mn-56 Ci

6. 63E-05 3.65E-05 re-55 Ci 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 Co-58 Ci 7.89E-05 1.13E-04 Co-60 Ci 3.39E-04 8.70E-04 Co-64 Ci 4.5BE-03

.'. 27E-03 Ni-65 Ci-0.00E+00 0.00E+00 Zn-65 Ci 8.16E-04 3.50E-03 As-76 Ci 2.35E-04 4.34E-05 Sr-89 Ci 0.00E+00 0.00E+ 00 Sr-90 Ci 0.00E+00 0.00E+00 Sr-91 Ci 1.26E-04 6.81E-05 Sr-92 Ci 1.01E-04 7.27E-06 Y-91m Ci 0.00E+00 0.00E+00 Zr-95~

Ci 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+ 00 Nb-97 Ci 1.30E-04 0.00E+00 Mo-99 Ci 4.63E-04 0.00E+ 00 Tc-99m Ci 1.00E-03 1.84E-04 Sb-125 Ci 0.00E+00 3.71E-06 I-131

'Ci 4.08E-04 2.11E-04 I-132 Ci 2.91E-04 4.97E-05 I-133 Ci 3.06E-03 1.20E-03 I-134 Ci 3.20E-05 0.00E+00 I-135 Ci 2.49E-03 7.1BE-04 Cs-134 Ci 2.39E-03

2. 48E-03 Cs-136 Ci 0.00E+00 0.00E+00 Cs-137 Ci

3. 49E-03 4.29E-03 Cs-138 Ci

3. 62E-05 0.00E+00 Ba-139 Ci 1.31E-05 0.00E+00 Ba-140 Ci 0.00E+00 8.29E-06 l

La-140 Ci 5.25E-05

.0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 Ce-144 Ci 0.00E+ 00 0.00E+ 00 l

Mp-239 Ci 5.87E-04 3.12E-04 Totals Ci 2.32E-02 1.62E -02

-15__

TABLE 1-3b E.1. HATCH NUCLEAR FLANI' - UNIT 2 SEMIANNUAL LIQUID EFFLUEtCS RELEASE REPORT 1988*

Page 2 of 2 Continuous Mode **

Nuclides Batch Mode Released Unit Quarter 3 Ouarter 4 Quarter 3

')"a rtg Kr-85 Ci 0.00E+00 7.70E-04 K r-85m Ci 0.00E+00 0.00E+00 Kr-87 Ci 5.99E-06 0.00E+00 Xe-131m Ci 8.47E-05 0.00E+00 Xe-133m Ci 2.30E-05 0.00E+00 Xe-133 Ci 1.65E-03 7.11E-04 Xe-135m Ci

2. 4 2E-03 1.04E-03 Xe-135 Ci 1.01E-02 5.20E-03 Ar-41 Ci 3.11E-06 0.00E+00 Totals Ci 1.42E-02 7.71E-03 Gross Aloha Ci 2.84E-08 3.53E-08

• 2 eros in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical lower limits of detection for liquid sanole analyses.

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

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

TABLE 1-3c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL LICUID EFFLUENTS RELEASE REPORT 1988*

Pace 1 of 2 Continuous Mode **

Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 1.64E+01 7.1SE+00 Na-24 Ci 4.87E-03 7.45E-04 Cr-51 Ci 1.67E-03 1.78E-03 Mn-54 Ci 3.21E-04 3.87E-03 Mn-56 Ci 1.70E-04 1.91E-04 Fe-55 Ci 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 1.52E-04 Co-58 Ci

.8.90E-05 1.17E-03 Co-60 Ci 2.13E-03 1.55E-02 Cu-64 Ci 7.36E-03 1.27E-03 Ni-65 Ci 0.00E+00 0.00E+00 Zn-65 Ci 5.89E-03 5.61E-02 As-76 Ci 3.10E-04 4.34E-05 Rb-88 Ci 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 Sr-91 Ci 2.94E-04 1.42E-04 Sr-92 Ci 2.94E-04 2.86E-04 Y-91m Ci 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 1.36E-04 Nty 95 Ci 9.87E-07 2.97E-04 Nb-97 Ci 6.60E-04 6.14E-04 Mo-99 Ci 4.63E-04 0.00E+00 Tc-99m Ci 1.65E-03 2.66E-04 Sb-125 Ci 2.90E-03 7.97E-04 Te-131 C1 1.73E-05 0.00E+00 I-131 Ci 3.23E-03 3.88E-04 I-132 Ci 3.36E-04 8.53E-05 I-133 Ci 4.76E-03 1.40E-03 I-134 Ci 8.38E-04 4.29E-04 I-135 Ci 2.85E-03 7.66E-04 Cs-134 Ci 2.71E-02 2.85E-02 Cs-136 Ci 0.00E+00 0.00E+00 Cs-137 Ci 5.75E-02 6.48E-02 Cs-138 Ci 8.91E-05 2.00E-04 Ba-139 Ci 5.04E-05 1.05E-04 Ba-140 Ci 0.00E+00 8.29E-06 La-140 Ci 7.85E-05 7.01E-05 Ce-141 Ci 0.00E+00 8.88E-05 Ce-144 Ci 0.00E+00 2.04E-04 Np-239 Ci 4.85E-03 1.82E-03 Totals Ci 1.31E-01 1.86E-01 l L-_-______-____________.

TABLE 1-3c E. I. HATCH NUCLEAR PLAtTI - SITE SEMIANNUAL LIQUID EFFLUEfffS RELEASE PEPORT 1988*

Page 2 of 2 Continuous Mode **

Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Ouarter 3 Quarter 4 Kr-85m Ci 0.00E+00 0.00E+00 Kr-85 Ci 8.26E-04 1.80E-03 Kr-87 Ci 5.99E-06 0.00E+00 Xe-131m Ci 2.24E-03 0.00E+00 Xe-133m Ci 1.98E-04 0.00E+00 Xe-133 Ci 1.29E-02 1.85E-03 Xe-135m Ci 2.63E-03 1.04E-03 Xe-135 Ci 2.58E 5.97E-03 Ar-41 Ci 3.11E-06 1.02E-05 Totals Ci 4.47E-02 1.07E-02 Gross Alpha Ci 1.62E-06 2.24E-06

• 2 eros in this table indicate that no radioactivity was cresent above detectable levels. See Table 1-5 for tvoical lower limits of detection for liquid sample analyses.

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

r o.

TABLE 1-4a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1988 INDIVIDUAL DOSES DUE TO LIQUID RELEASES N

J.

i CUMULATIVE DOSES PER QUARTER ORGAN TECH UNIT QUARTER

• OF QUARTER

• OF SPEC 3

TECH 4

TECH LIMIT SPEC SPEC LIMIT LIMIT i

BONE 5.0 MREM 2.45E-01 4.90E+00 2.74E-01 5.48E+00 LIVER 5.0 MREM 4.01E-01 8,02E+00 4.54E-01 9.08E+00 TBODY 1.5 MREM 2.87E-01 1.91E+01 3.21E-01 2.14E+01 THYROID 5.0 MREM 1.62E-02 3.24E-01 1.95E-02 3.90E-01 KIDNEY 5.0 MREM 1.34E-01 2.68E+00 1.57E-01 3.14E+00 LUNG 5.0 MREM 4.43E-02 8.86E-01 4.85E-02 9.70E-01 GI-LLI 5.0 MREM 9.48E-03 1.90E-01 2.68E-02 5.36E-01 CUMULATIVE DOSES PER YEAR ORGAN TECH UNIT QUARTERS

• OF SPEC 1.2.3.4 TECH LIMIT SPEC LIMIT BONE 10.0 MREM 1.40E+00

1. 40E+ 0:1 i

LIVER 10.0 MREM 2.39E+00 2.39E+01 TBODY 3.0 MREM 1.73E+00 5.76E+01 i

THYROID 10.0 MREM 6.77E-02 6.77E-01 l

KIDNEY 10.0 MREM 8.05E-01 8.05E+00 LUNG 10.0 MREM 2.60E-01 2.60E+00 GI-LLI 10.0 MREM 8.32E-02 8.32E-01 l

.-___________-._-_.______.___m_

TABLE 1-4b.

E.

I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1988 INDIVIDUAL DOSES DUE TO LIQUID RELEASES g

1 CUMULATIVE DOSES PER QUARTER ORGAN TECH UNIT QUARTER

• OF QUARTER

% OF 3

SPEC-3 TECH 4

TECH LIMIT SPEC SPEC LIMIT

......................................................... LIMIT BONE 5.0 MREM 3.82E-02 7.64E-01 2.25E-02 4.50E-01 LIVER 5.0 MREM 6.61E 02 1.32E+00 3.87E-02 7.74E-01 TBODY 1.5 MREM 4.79E-02 3.19E+00 2. 78 E- 02 1.85E+00 THYROID 5,0 MREM 4.41E-03 8.82E-02 1.91E-03 3.82E-02 KIDNEY 5.0 MREM 2.25E-02 4.50E-01.1.33E-02 2.66E-01 LUNG 5.0 MREM 7.22E-03 1.44E-01 4.15E - 03 8.30E-02 GI-LLI 5.0 MREM 2.36E-03 4.72E-02 2.01E-03 4.02E-02 CUMULATIVE DOSES PER YEAR ORGAN TECH UNIT QUARTERS

• OF SPEC 1.2.3.4 TECH LIMIT SPEC LIMIT BONE 10.0 MREM 5.71E-01 5.71E+00 LIVER 10.0 MREM 1.03E+00 1.03E+01 TBODY 3.0 MREM 7.60E-01 2.53E+01 THYROID 10.0 MREM 9.06E-02 9.06E-01 KIDNEY 10.0 MREM 3.46E-01 3.46E+00 LUNG 10.0 MREM 1.12E-01 1.12E+00 GI-LLI 10.0 MREM 2.96E-02 2.96E-01 _ _ _ _ _ _ _ _ _ - _ _ _ _ _

/'

TABLE 1-5 IDfER LIMITS OF DETECIION - LIQUID SAMPLE A!RLYSES The values in this table represent apriori lower limits of detecticn (LLD) whien are typically achieved in laboratory analyses of liquid radwaste sanples.

RADIONUCLIDES LLD UNITS Mn-54 T78E-08 uci/ml Fe-59 7.72-08 Co-58 4.67E-08 Co-60 4.72-08 Zn-65 1.31E-07 M>-99 5.12-07*

Co-134 7.18E-08 Co-137 6.02-08 Ce-141 1.41E-07 Ce-144 6.3 2 -07*

=

I - 13 1 6.51E-08 Xe-135 8.4 2 -08 Fe-55 8.00E-07 Sr-89 2.32-08 St-90 7.67E-09 H-3 5.00E-07

• In accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.1 (Unit 2), Table Notation b, the permissible Iower Limit of Detection may be increased inversely proportional to the magnitude of the gansna yield. However, 'the LLD determined in this marmer must not exceed 10 percent of the Maximum Permissible Concentration (MPC) value specified in 10CFR20, Appendix B, Table II (Column 2).

i

i 2 GASEDUS EFFLUENTS 2.1 REGLMORY 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.

1 TECHNICAL SPECIFICATIOfE 3.14.2 The radioactive gaseous effluent monitoring instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarWtrip 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 ODOS. 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 UNRES1RICIED

~

AREAS (figure 3.15-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

The dose rate limit for noble gases shall be less a.

than or equal to 500 mrevyear to the total body and less than or equal to 3000 mrem / year to the skin.

b.

The dose rate limit for I-131, I-133, tritium, and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be less than or equal to 1500 mrem / year to any organ.

3.15.2.2 The air dose in UlRES1RICTED AREAS (figure 3.15-1) due to noble gases released in gaseous effluents from each reactor unit shall be limited to the following:

1 During any calendar quarter, to less than or a.

equal to 5 mrad for gamma radiation and less than or equal to 10 mead for beta radiation.

l b.

During any calendar year, to less than or equal to 10 mrad for ganna radiation and less than or equal to 20 mrad for beta radiation.

i 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 UlRES1RICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the following:

I I*

During any calendar quarter to less than or.

a.

equal to 7.5 mram to any organ.

b.

During any calendar year to less than or.

equal to 15 mram to any organ.

3.15.2.4 The CASEDOS RADNASTE TRFATMFK SYSTEM as i

i described in the ODOI tall be in operation.. (This

(

-htenical Specification applies whenever the main condenser air ejector system is.in operation.)

l 4.15.2.4 CASEDUS RADNASTE 1RFATMFM SY5mlM operability aball 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 MDBER OF T!E PUBLIC due to releases of radioactivity and to radiation -from uranium fuel cycle sources shall be limited to less than or equal to 25 mram to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mram.

(With the calculated doses from the release of radioactive anterials in liquid or gaseous effluents esoseding 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 g

direct tadiation 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 gasma 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 uC1/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 i

I 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 l

t noble gases or 0.02 Ci of radiciodines for gaseous releases.*

_23-

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TABLE 3.14.2-1 (SHEET 3 0F 4)

MDilwiiVE4ASE005,EFFLj]ENTfjg!j[TQ31NGINSTRUMENTATI0tj Table Notations l:

• Monitor i.iust be capable of responding to a Lower Limit of Detect 1cn of I x 10-' pct /ml.

• 0uring releases via this pathway.

""During main condenser offgas treatment system operation.

• • • During operation of the main condenser air ejector.

ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channel.s OPERABLE requirement.

2

.. f r l u. o L relea e3 via thi, pathway md/ ccntinue, provided tne rlowrate is estimated at least cnce 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 explanation of the circumstances shall be incluoad in the next semi-annual effluent release report.

ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab somples are taken daily and analyzed daily for gross

.mtivity 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 monituring system channels OPERABLE less than required by tne Minimum Channels OPERABLE requirement, without delay suscena crywell purge.

If tne numoer 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 106 - With the number of channels OPERABLE less than requir:d by the Mtnimum Channels OPERABLE requirement,

..puration or the main condenser offgas treatment system may continue provided:

(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 sithin thir.:reuing 4 hourt, or lb) U.ing a temporary hydrogen analyzer installed in the of f gas system line cownstrean of the recombiner, h/drogen 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 />.

_26_

I-:-

!AILE 2-1 (::::'d)

TABLE 3.14.2-1 (SHEET 4 0F 4) nAulOMilVE G'5E005 EFFl uEllT f40NITORING INSTRUMENTATION Table Notations (Continueo)

If the numoer of channels OPERABLE remains less snan 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 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this patnway may continue, ;rovided

~'-

samples are continuously collecteo with auxiliary sampling equipment for periods on the order of 7 days ano 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.

It 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; The of fgas system is not bypassed, and a.

b.

The of fgas post-treatment monitor (011-K615) or the main stack monitor (D11-K600) is OPERABLE.

Otherwise, be in at least HOT STANDBY 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.

1 p

2.2 MEAstRatntr AND APPROXIMATIONS OF. 'IUDLL RADIOACTIVITY -

L

\\

Maste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit I reactor building vent Unit 2

. reactor building vent, and the recambiner building vent. Each of these four paths is continuously monitored for gaseous radioactivity. ' Each is equipped with an integrating-type sanple collection device for collecting particulate and iodines. Sample collection is in accordance with Technical Specification Tables 4.15.2-1 (Ubit -1) and 4.11.2-1 (Unit 2). - Unless required more frequently under certain circumstances specified in Table Notations to the above mentioned tables, amaples are collected as follows:

1.

Noble gas sanples are collected by grab sampling monthly.

2.

Tritium sanples are collected by grab aampling monthly.

3.

Radioiodine sasples are collected by pulling the sample stream through a charcoal omrtridge over a 7-day period.

4.

Particulate are collected by pulling the sample stream through a particulate filter Q

over a 7-day period.

5.

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

6.

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

Sample analyses results and release flow rates from the four release points form the basis'for calculating released quantities of.

radionuclides-specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter. and year. This task is normally performed with conmuter assistance.

l-The noble gas grab sample analysis results are used -along with ariana expected release flow rates from eads of the four vents to calculate monitor setpoints for the gaseous effluent monitors serving the four release points, to assure that the limits of Technical 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 0006.

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

Caulative dose results are tabulated along with percent of Mehnical 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 samary of waste gas releases from the four vents is compiled for preparation of the Semiannual' Effluent Release Report required by Mchnical 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 AIS ACTIVATION GAS The radionuclides-specific released radioactivity

.is determined frr. sample ' 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 radiciodines, tritim, and particulate are calculated (with computer assistance).

Calculated dose rates are cospared 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, tritim, and particulate.

Dose rate calculation methodology is presented in the Plant Hatch ODCM.

Beta.and garsna air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are.

calculated for each release period and cumulative totals are kept for each unit' for the current calendar quarter and year. Cumulative air doses are campared to the dose limits specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11. 2. 2 ( Uni t 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 ODCN.

2.

RADIOIODINE, 'lRITIIM, AND PARTICIILATE RELEASES Released quantities of radiciodines are determined from the weekly samples and release flow rates for the four release points.

~-

Radioiodine concentrations are determined by garuna spectroscopy.

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

Gamma spectroscopy is used to quantify concentrations of principal gasma emitters.

After each calendar quarter the particulate filters from each vent are combined, fused, and strontim 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 ra detected, LLD's are calculated.

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

Tritium samles are obtaind monthly from each vent by passirng 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 vapor collection efficiencies. The trititsn sanples are analyzed by an independent laboratory l

l and results are furnished in uCi/ml of water.

The tritium concentration in water is converted I

to trititan concentration in air and this value is l

input into the caposite file of the conputer to be used in release, dose rate, and individual dose calculations. !

l

'L--.___-.----.------.--

^^

l L

Dose rates due to radioiodine,.tritita, and particulate are calculated for a hypothetical child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the hiWiest.

Dose rates are calculated for each release point, for each release period, and the total dose rate from all four release points are mmpared 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 particulate are calculated for the critical receptor, whid for Plant Batch is 'a child exposed to the garden vegetation, inhalation, and gromd 1

9 ane pathways. Individual doses are calculated for each release period and cumulative totals are kept for each unit for the current calendar quarter and ) ear. Cumulative individual doses are compared to the dose limits specified in hchnical Specifications 3.15.2.3 (Ubit 1) and 3.11.2. 3 ( Unit 2).

Current percent of technical specification limits are down on the printout for each release period.

3.

CROSS ALPHA IUILEASE The gross alpha release is computed each month by counting the particulate filters ead week for.

O gross alpha activity in a proportional counter.

I The four or five weeks' numbers are then recorded on a data sheet and the activity is stamed at the end of the month. This concentration is input to the conposite file of the computer and is used for release calculations.

4.

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

-31 _

1 "The total or maximum error associated with the effluent measurement will include the cumulative errors resulting frem the total operation of j

sampling and measuremerit. Because it nay be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested. The objective snould oe to obtain an overall estimate of the error assoc..iated with measurements of radioactive naterials released in liquid and gaseous effluents and solid waste."

Estinated errors are based on errors in counting equipnent calibration, counting statictics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

1 (1) Fission and Activation Total Release was calculated frczn sample analysis results and q

_ release point flow rates.

Statistical Error 60%

Counting Equipnent Calibration 104 Vent Flow Rates 10%

Non-Steady Belease Rates 204 IM

( 2) I-131 Release was calculated from eadi weekly sample:

Statistical Error 604

]

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 ILD concentration 60%

Counting Equipment Calbration 10%

Vent Flow Rates 10 %

Vent Sample Flow Rates 10 %

Non-Steady Release Rates 10 4 1004.

( 4) Total Tritium Release nas dominated by the reactor building vent tritium releases hence, the larger statistical errors of the off-gas vent and reoambiner building vent tritium releases do not affect the error in the total tritium release:

hter Vapor in Sanple Stream Determination 204 Vent Flow Rates 10 %

Cotating Calibration and Statistics 10 %

Non-Steady Release 50%

l

.M 2.3 GASEDtB EFFLUENT RELEASE DATA Regulatory. Guide 1.21 Tables IA,.18, and 1C 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 Regulatory Guide 1.21.

Ib 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 ninber of seconds in the quarter to obtain a release rate in uCi/second for each category.

However, the applicable Itchnical Specification limits are not in terms of release rate in uci/second but in terms of dose rate in area / year, as presented in 7tchnical Specifications 3.15.2.1 (Unit 1) and 3.11.2.1 (Iktit 2).

Noble gases are limited as O

specified in 3.15.2.1.a and 3.11.2.1.a.

The other three categories (tritita, radioiodines, and particulate) are limited as a group 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 radioiodine, tritita, and particulate are presented in Table 2-5 alcng 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. Ctmulative air doses are presented in Tables 2-6a and 2-6b, along with percent of technical specification limits.,

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

2.4 RADIOLOGICAL IMPACT DOE 'IO GASEDUS RN EASES Dose 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 2). Results are presented in Table 2-5.

Dose rates due to radioiodine, trititan, and particulate in gaseous 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 tere 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 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

g results are presented in Tables 2-7a and 2-7b.

Dome rates and doses were calculateo using the methodology presented in the Plant Hatch Offsite Dose Calculation Manual.

-3L-

i TABLE 2-2a E. !. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3

4 Error %

A.

Fission &

Activation Gases

1. Total Ci 8.67E+02 8.29E+01 1.00E+02 Release

2. Averace uCi/see 1.09E+02 1.04E+01 Release Rate For Period

• 3. % of Tech Spec Limit

~-

3.

odines l

1. Total Ci 2.86E-03 7.51E-04 1.10E+ 02 Iodine-131

2. Average uCi/sec 3.60E-04 9.45E-05 Release Rate For Period

• 3. % of Tech Spec Limit C.

Particulate

1. Particulate Ci 2.17E-03 4.95E-04 1.00E+02 with half-lives 8 days

2. Averace uCi/sec 2.73E-04 6.22E-05 Release Rate For Period

• 3. t of Tech Spec Limit

4. Gross Alpha ci 1.32E-06 3.71E-06 Radioactiv-ity D.

Tritium

1. Total Ci 6.10E+00 1.68E+00 9.00E+01 Release

2. Averace uCi/sec 7.67E-01 2.12E-01 Release Rate For Period

• 3. % of Tech Spec Limit

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

_35-

TABLE 2-2b E. I. HATCH WCLEAR PLANT - UNIT 2

- SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 i

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l

E. I. Haten Unit' Quarter Quarter Est. Total Nuclear Plant 3

4 Trror %

A.

Fission &

Activation I

Gases I

1. Total Ci 4.99E+02 2.18E+02 1.00E+02 Release

2. Average uCi/sec

6. 28E+ 01 2.74E+01 Release Rate For Period

• 3. % of Tech Spec Limit B.

Iodines

1. Total Ci 1.31E-03 7.72E-04 1.10E+02 Iodine-131

2. Averaae

-uCi/sec 1.64E-04 9.72E-05 Release Rate For Period

• 3. % of Tech Spec Limit C.

Particulate

>1. Particulate Ci 7.14E-04 1.13E-03 1.00E+02 with half-lives 8 days

2. Averace uCi/sec 8.98E-05 1.42E-04 Release Rate For Period

• 3. % of Tech Spec Limit

4. Gross Alpha ci 3.52E-07 3.12E-06 Radioactiv-ity D.

Tritium

1. Total Ci 1.42E+01 4.27E+00 9.00E+ 01 Release

2. Averace uCi/sec 1.78E+00 5.37E-01 Release Rate For Period

• 3. % of Tech Spec Limit

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

l TABLE 2-2c E. I, HA'ICH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3

4 Error %

A.

Fission &

Activation Gases

1. Total Ci

1. 37E+ 03 3.01E+02 1.00E+02 Release

2. Averace uCi/sec 1.72E+02 3.79E+01 1

Release Rate For Period

• 3. % of Tech Spec Limit B.

Iodines

1. Total Ci 4.17E-03 1.52E-03 1.10E+02 Iodine-131

2. Averace uCi/sec 5.25E-04 1.92E-04 Release Rate For Period

• 3. % of Tech Spec Limit C.

Particulate

1. Particulate Ci 2.89E-03 1.62E-03 1.00E+ 02 with half-lives 8 days

2. Average uCi/sec 3.63E-04 2.04E-04 Release Rate For Period

• 3. % of Tech Spec Limit

4. Gross Alpha Ci 1.67E-06 6.83E-06 Radioactiv-ity D.

Tritium

1. Total Ci 2.03E+01 S.95E+00 9.00E+01 Release

2. Average uCi/sec 2.55E+00 7.49E-01 Release Rate For Period

• 3. % of Tech Spec Limit

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

l 1

TABLE 3-3s E.

I. HATCH HUCLEAR PLANT - UNIT 1 l

SEMI ANNUAL RADIORCT!YE EFFLUENT RELEASE REPORT 1988 i

GASE0US EFFLUENTS - ELEVATED RELERSE*

CONT!HUQUS MODE BRTCH MODE **

HUCLIDES RELEASED UNIT QUARTER 3 QURRTER 4 QUARTER 3 Q

....___....__......._____________...______....__......__UARTER 4 1.

FISSION GRSES KR-05 CI 8.00E+00 0.00E+08 KR-05M CI 1.59E+01 2.73E+08 KR-07 CI 1.49E+80 2.32E-81 KR-80 CI 1.81E+01 2.68E+08 XE-133 CI 2.04E+82 1.33E+08 XE-135 CI 3.10E+00 1.33E+89 XE-135M CI 7.61E+00 3.91E-01 XE-130 CI 2.21E+81 1.51E+98 XE-131M C1 2.35E+81 2.14E-01 XE-133M CI 0.00E+00 0.00E+00 i

XE-137 CI 0.00E+00 0.00E+00 AR-41 CI 1.85E+00 1.30E+08 TOTRL FOR PERIOD C1 2.99E+02 1.18E+01 2.

10 DINES 1-131 CI 5.60E-04 9.40E-05 1-133 CI 8.39E-84 2.63E-84 1-135 CI 6.35E-04 0.13E-05 TOTAL FOR PERIOD C1 2.84E-03 4.39E-04 3.

PARTICU-LRTES CR-51 CI 0.80E+80 0.00E+00 MN-54 CI 8.88E+08 0.00E+80 CO-50 CI 8.80E+80 0.00E+08 CO-60 CI 8.00E+80 4.71E-08 ZH-65 CI 0.08E+00 0.00E+08 SR-09 CI 4.64E-05 6.07E-96 SR-98 CI 3.61E-07 6.'7E-00 NS-95 CI 0.80E+88 0.00E+88-CS-134 CI 9.98E+08 0.00E+08 CS-137 CI 2.10E-06 1.54E-06 BR-140 CI 1.35E-84 1.67E-05 LA-140 CI 2.43E-04 1.09E-05 TOTAL FOR PERIOD CI 4.27E-04 4.34E-05

~

' Zeroes in this table indicate that no radioactivity was present above detectable levels.

See Table 2-8 for typini IcVer limits of detection for gaseous sample anal,yses.

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

38 i

i 1

TABLE 2-3b E.

I. HATCH NUCLEAR PLANT - UNIT 2 SEMI AHHURL RADICRCT!YE EFFLUENT RELEASE REPORT 1900 GASEQUS EFFLUENTF - ELEYRTED RELEASEE CONTINUOUS MODE BATCH MODEe*

HUCLIDES RELENSED UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 1.

FISSION GASES KR-05 CI 0.00E+00 0.00E+00 KR-05M CI 1.72E+01 1.36E+01 KR-07 CI 1.70E+00 0.0?E-01 KR-80 CI 1.11E+01 3.91E+00 XE-133 CI 1.97E+02 1.24E+01 XE-135 C1 3.24E+00 2.63E+00 XE-135M CI 7.47E+00 6.33E+00 XE-130 C1 2.31E+01 2.45E+01 XE-131M CI 2.61E+01 1.05E+01 XE-133M CI 0.00E+00 0.00E+00 XE-137 CI 0.00E+00 0.00E+00 AR-41 C1 1.70E+00 2.01E+00 TOTAL FOR I

PERIOD CI 2.09E+02 7.76E+01 i

l 2.

IODINES 1-131 CI 9.07E-04 3.12E-04 I-133 CI 0.46E-04 7.40E-04 1-135 CI 6.23E-04 6.97E-04 TOTAL FOR PERIOD C1 2.46E-03 1.75E-03 3.

PARTICU-LATES CR-51 CI 0.00E+00 0.00E+00 MN-54 CI 0.00E+00 0.00E+00 CO-50 CI 0.00E+00 0.00E+00 CD-60 CI 0.00E+00 2.31E-07 ZH-65 CI 0.00E+00 0.00E+00 SR-09 CI 5.26E-05 3.76E-05 SR-98 CI 4.09E-07 4.13E-07 NS-95 CI 0.00E+00 0.00E+00 i

CS-134 CI 0.00E+00 0.00E+00 l

CS-137 CI.

1.99E-06 3.90E-06 BR-140 CI te51E-04 1.30E-04 LA-140 CI 2.00E-04 2.15E-04 TOTAL FOR PERIOD CI 4.06E-04 3.96E-04 s.....-_-_-_-_-__.._ _.....____...___.....__..........__...._ --

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

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

E TR3LE 2-3c E.

I. HRTCH NUCLERR PLRNT - $1TE SEMIRHNURL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 l

GASEOUS EFFLUENTS - ELEVATED RELEASE +

CONT!HUQUS MODE 3RTCH MODE *e HUCLIDES RELERSED UNIT QUARTER 3 QUARTER 4 QUARTE

....______________...........__..._____..........R 3

QUARTER 4 1.

FISSICH GRSES KR-05 CI 0.00E+00 0.00E+00 KR-05M CI 3.31E+01 1.64E+01 KR-07 CI 3.10E+00 1.04E+00 KR-80 CI 2.13E+0!

6.59E+00 XE-133 CI 4.01E+02 1.30E+01 XE-135 CI 6.42E+00 3.95E+00 XE-135M CI 1.51E+01 6.72E+00 XE-130 CI 4.52E+01 2.60E+01 XE-131M CI 4.96E+01 1.00E+01 XE-133M CI 0.00E+00 0.00E+00 XE-137 CI 0.00E+00 0.00E+00 RR-41 CI 3.63E+00 4.19E+00 TOTAL FOR PERIOD CI 5.79E+02 0.93E+01 2.

10DIHES 1-131 CI 1.55E-03 4.07E-04 I-133 CI 1.60E-03 1.00E-03 1-135 CI 1.26E-03 7.79E-84 TOTRL FOR PERIOD CI 4.50E-03 2.19E-03 3.

PRRTICU-LRTES CR-51 CI 0.00E+00 0.00E+00 MN-54 CI 0.00E+00 0.00E+00 i

CO-50 CI 0.00E+00 0.00E+00 CO-60 CI 0.00E+00 2.70E-07 ZH-65 C!

8.00E+00 0.00E+00 SR-09 CI 9.91E-05 4.36E-05 SR-98 CI 7.70E-07 4.79E-07 HS-95 CI 0.00E+00 0.00E+00 CS-1Ta CI 0.00E+00 0.00E+00 CS-t * ?

CI 4.09E-06 5.51E-06 3R-140 C1 2.06E-04 1.55E-04 LR-140 CI 3.23E-04 2.34E-04 TOTRL FOR PERIOD CI 9.13E-04 4.39E-04

' Zeroes in thist +=W inditate'that+ wrutibestivity was present above detectable levels. See Table 2 8 for typical lover limits of detection for gaseous sample analyses.

m _ _ _ m _m

TRSLE 2-4a E..I. NATCH NUCLEAR PLANT - UNIT 1 SEMI ANNUAL RADTORCTIVE EFFLUENT RELERGE REPORT 1980 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES CCHTINUOUS MODE BRTCH MODEee HUCLIDES RELERSED UNIT QUARTER 3 QUARTER 4 QUARTER

_.... _________..............._______...... ___.. 3 QUARTER 4 1.

FISS10H GASES t

KR-05 CI 0.00E+00 8.00E+00 KR-85M C1 1.09E-01 1.25E-01 KR-07 CI 1.53E-01 1.23E-81 KR-80 CI 0.88E+08 0.88E+00 XE-133 CI 5.69E+02 6.67E+01 XE-135 CI 5.25E+00 1.22E+90 XE-135M CI 2.89E+98 2.65E+08 XE-130 C1 1.36E-01 8.88E+00 XE-131M 'CI 8.82E-81 8.88E+98 XE-133M CI 8.88E+88 0.88E+88 XE-137 CI 8.88E+88 2.94E-81 RR-41 CI 8.88E+88 8.88E+08 TOTAL FOR PERIOD CI 5.77E+92 7.11E+01 2.

10 DINES 1-131 CI 2.30E-03 6.56E-84 I-133 CI 7.94E-03 2.25E-03 I-135 CI 1.25E-02 3.61E-03 TOTAL FOR PERIOD CI 2.27E-02 6.52E-03 3.

PARTICU-LATES CR-51 CI 4.06E-04 0.00E+00 MN-54 CI 0.00E+00 0.00E+00 CO-50 CI 7.22E-06 0.00E+00 CO-60 CI 5.06E-05 2.02E-05 ZN-65 CI 3.34E-04 5.61E-05 SR-09 CI.

1.06E-04 6.93E-05 SR-98 CI 0.75E-07 3.12E-07 NS-95 CI 0.00E+00 0.00E+00 CS-134 CI 5.39E-06 5.03E-07 CS-137 CI 3.04E-05 6.25E-06 3A-140 CI 2.53E-04 1.00E-04 LA-140 CI 4.64E-04 1.91E-64 TOTAL FOR PERI 0B C1 1.75E-93 4.51E-84 I

' Zeroes in this table indicate that no radioactivity was present above detectable levels.

See Table 2-8 for typical lover limits of detection for gaseous sample analyses.

• • 'Ihere are no batch mode radioactive gaseous release pathways at Plant

' Hatch.

L1-

TR3LE 2-4b E.

1. HRTCH HUCLEAR PLANT - UNIT 2 SEMI ANNUAL RADIOACTIVE EFFLUENT RELERSE REPORT 1999 GRSEOUS EFFLUENTS - GROUND-LEVEL RELERSE*

CONT!HUOUS MODE BRTCH MODE **

NUCLIDES RELERSED UNIT QURATER 3 QUARTER 4 QUARTER 3 Q

.__....____._______..........___........________..___._UARTER 4 1.

FISS!0H GRSES KR-05 CI 0.00E+00 0.00E+00 KR-05M CI 0.00E+00 0.00E+00 KR-07 CI 0.00E+00 0.00E+00 KR-80 CI 0.00E+00 0.00E+00 XE-133 CI 1.99E+02 1.31E+02 XE-135 CI 9.19E+00 9.45E+00 XE-135M CI 2.10E+00 0.00E+00 XE-130 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. 0 0E+ 0 0 AR-41 CI 0.00E+00

0. 00E+ 00 1

1 TOTAL FOR PERIOD C1 2.11E+02 1.40E+02 2.

10DIHES 1-131 CI 3.19E-04 4.60E-04 1-133 CI 6.25E-04 1.97E-03 1-135 CI 3.00E-04

2. 61 E-05 TOTAL FOR PERIOD C1 1.25E-03

2. 4 5E-03 3.

PRRTICU-LATES CR-51 CI 0.00E+00 0.00E+00 RN-54 CI 0.00E+00 0.00E+00 CO-50 CI 0.00E+00 0.00E+00 CD-60 CI 0.00E+00 0.00E+00 ZN-65 CI 8.00E+00

6. 00E-06 SR-09 CI 5.30E-05 1.55E-04 SR-98 CI 2.95E-07

4. 65E-0 7 NS-95 CI 0.00E+00 0.00E+00 CS-134 CI 0.00E+00 0.00E+00 CS-137 CI 2.70E-07 0.00E+00 3R-140 CI 5.03E-05 2.35E-04 LA-140 CI 1.14E-04 3.33E-04 TOTAL FOR PERIOD C1 2.27E-04 7.31E-94

' Zeroes in this table indicate that no radioactivity was present above I

detectable levels.

See Table 2 8 for typical lover limits of detection for gaseous sample analyses.

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

M.

TABLE 8-4c E.

I. HRTCH NUCLEAR PLRHT - SITE SEMIRHNURL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GRSEOUS EFFLUENTS - GROUND-LEVEL RELEASE

• CONTINUOUS MODE BRTCH MODE **

HUCLIDES RELEASED UNIT QUARTER 3 QURRTER 4 QUARTER 3 QUARTER 4 1.

FIS$10H GRSES KR-65 CI 0.00E+08 0.00E+00 KR-85M C1 1.09E-81 1.25E-01 KR-87 CI 1.53E-01 1.23E-01 KR-88 CI 0.88E+00 0.00E+00 XE-133 CI 7.68E+02 1.98E+02 XE-135 C1 1.44E+81 1.07E+01 XE-135M CI 4.28E+00 2.65E+00 XE-138 CI 1.36E-81 0.00E+00 XE-131M CI 8.82E-01 0.00E+00 XE-133M CI 0.90E+00 0.00E+00 XE-137 CI 0.00E+00 2.94E-01 RR-41 CI 0.00E+00 0.00E+00 TOTAL FOR PERIOD CI 7.88E+02 2.12E+02 2.

10 DINES I-131 C1 2.62E-03 1.12E-03 1-133 CI 8.47E-83 4.22E-93 1-135 CI 1.29E-02 3.63E-93 TOTAL FOR PERIOD C1 2.39E-02 8.97E-03 3.

PRRTICU-LATES CR-51 CI 4.86E-04 8.80E+00 MH-54 CI 8.80E+08 0.00E+08 C0-58 CI 7.22E-06 0.00E+00 C0-68 CI 5.06E-05 2.02E-05 ZH-65 CI 3.34E-04 6.38E-85 SR-89 CI 1.68E-84 2.24E-84 SR-98 C1 1.17E-66 7.76E-97 H3-95 CI 8.88E+88 0.00E+00 j

CS-134 CI 5.39E-86 5.83E-87 CS-137 CI 3.87E-85 6.25E-06 3R-148 CI 3.12E-84 3.43E-84 LR-148 CI 5.78E-04 5.24E-84 TOTAL FOR PERIOD CI 1.97E-83 1.18E-03

' Zeroes in this table indicate that no radioactivity was present above detectable levels.

See Table 2 8 for typical lover limits of detection for gaseous sample analyses.

• • There a.re no batch mode radioactive giscous release pathways at Plant Hatch.

,; 3,

TABLE 2-5 E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 i

GASEOUS EFFLUENTS - DOSE PATES Dose Rates Due to Noble Gases Orcan Tech Unit Quarter

% of Quarter

% of Spec 3

Tech 4

Tech Limit Spec Soec Limit Limit TBody 500 mrem /vr 2.91E-01 5.82E-02 9.54E-02 1.91E-02 Skin 3000 mrem /yr

6. 59E-01 2.20E-02 2.14E-01 7.13E-03 Dose Rates Due to Radiciodine, Tritium, and Particulate Organ Tech Unit Quarter

% of Quarter

% of Soec 3

Tech 4

Tech Limit Spec Spec

~-

Limit Limit Bone 1500 mrem /yr 5.88E-04 3.92E-05 3.91E-04 2.61E-05 Liver 1500 mrem /yr 1.82E-02 1.21E-03 7.08E-03 4.72E-04 TBody 1500 mrem /yr 1.80E-02 1.20E-03 7.00E-03 4.67E-04 Thyroid 1500 mrem /yr 9.71E-02 6.47E-03 4.32E-02 2.88E-03 Kidney 1500 mrem /yr 1.83E-02 1.22E-03 7.17E-03 4.78E-04 Luna 1500 mrem /yr 1.96E-02 1.31E-03 8.39E-03 5.59E-04 GI-LLI 1500 mrem /yr 1.80E-02 1.20E-03 7.15E-03 4.77E-04 LL_

TABLE 2-6a E. I HATCH NUCLEAR PLANI - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUEf7f RELEASE REPORT 1988 AIR DOSES DUE 70 tOBLE GAS RELEASES Cumulative Doses Per Quarter Type Tecn Unit Quarter

% of Quarter

% of of Spec 3

Tech 4

Tech Radi-Limit Spec Spec stion Limit Limit Gamma 5.0 mrad 5.96E-02 1.19E+00 9.77E-03 1.95E-01 Beta 10.0 mrad 1.64E-01 :. 64E+ 00 2.13E-02 2.13E-01 Cumulative Doses Per Year Type or Tech Unit Quarters

% of Tech Radiation Spec 1,2,3,&4 Spec Limit Limit Gamra 10.0 mrad 2.91E-01 2.90E+00 Beta 20.0 mrad 5.35E-01 2.68E+00 I

l h5_

TABLE 2-6b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 AIR DOSES DUE 'IO NOBLE GAS RELEASES Cumulative Doses Per Quarter Type-Tech Unit Quarter

% of Quarter

% of of Spec 3

Tech 4

Tech Radi-Limit Spec Spec ation Limit Limit Gamma 5.0 mrad 2.64E-02 5.28E-01 1.79E-02 3.58E-01 Beta 10.0 mrad 6.24E-02 6.24E-01

4. 29E-02 4.29E-01 Cumulative Doses Per Year Type of Tecn Unit Quarters

% of Tech Radiation Spec 1,2,3,&4 Spec Limit Limit i

Gamma 10.0 mrad 2.48E-01 2.48E+00 Beta 20.0 mrad 3.47E-01 1.74E+00 l

l

(

h6-

l l

l l

l TABLE 2-7a E. I. HATCH NUCLEAR PLANT - UNIT 1 i

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 l

INDIVIDUAL DOSES DUE 'IO RADIOIODINE, TRITIUM,

]

AND PARTICULATE IN GASEOUS RELEASES j

j I

Cumulative Dose Per Quarter Organ Tech Unit Quarter

% of Quarter

% of Spec 3

Tech 4

Tech

(

4 Limit Spec Spec I

Limit Limit Bone 7.' 5 mrem 1.33E-03 1.77E-02 4.41E-04 5.88E-03 Liver 7.5 mrem 2.63E-03 3.51E-02 7.59E-04 1.01E-02 Tot. Body 7.5 mrem 2.59E-03 3.45E-02 7.52E-04 1.00E-02 Thyroid 7.5 mrem 1.82E-02 2.43E-01 5.17E-03 6.89E-02 Kidnev 7.5 mrem 2.63E-03 3.51E-02 7.64E-04 1.02E-02 Lune 7.5 mrem 2.67E-03 3.56E-02 7.92E-04 1.06E-02 GI-LLI 7.5 mrem 2.63E-03 3.51E-02 7.82E-04 1.04E-02 Cumulative Dose Per Year Organ Tech Unit Ocarters

% of Tech Spec 1,2,3,&4 Spec Limit Limit Bone 15.0 mrem 1.23E-02 8.18E-02 Liver 15.0 mrem 1.74E-02 1.16E-01 Total Body 15.0 mrem 1.67E-02 1.12E-01 Thyroid 15.0 mrem 9.91E-02 6.60E-01 Kidney 15.0 mrem 1.63E-02 1.09E-01 Lung 15.0 mrem 1.59E-02 1.06E-01 GI-LLI 15.0 mrem 1.56E-02 1.04E-01 1

L7-

I l

l-i TABLE 2-76 E. I. HATCH NUCLEAR PLANr - UNIT 2 i

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 INDIVIDUAL DOSES DUE 'IO RADIOIODINE, TRITIUM, AND PARTICULATE IN GASEOUS RELEASES Cumulative Dose Per Quarter l

Organ Tech Unit Odarter

% of Quarter % of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 1.11E-04 1.48E-03 2.40E-04 3.20E-03 Liver 7.5 mrem 3.38E-03 4.51E-02 1.03E 03 1.37E-02 Tot. Body 7.5 mrem 3.38E-03 4.51E-02 1.04E-J 3 1.39E-02 Thyroid 7.5 mrem 6.05E-03 8.07E-02 4.46E-03 5.95E-02 Kidney 7.5 mrem 3.38E-03 4.51E-02 1.048-03 1.39E-02 Lung 7.5 mrem 3.39E-03 4.52E-02 1.10E-03

1. 47E-02 GI-LLI -

7.5 mrem 3.40E-03 4.53E-02 1.10E-03 1.47E-02 Cumulative Dose Per Year Organ Tech Unit Quarters

% of Tech Spec 1,2,3,&4 Spec Limit Limit Bone 15.0 mrem 9.17E-03 6.11E-02 Liver 15.0 mrem 1.53E-02 1.02E-01 Total Body 15.0 mrem 1.50E-02 1.00E-01 Thyroid 15.0 mrem 6.38E-02 4.25E-01 Kidney 15.0 mrem 1.49E-02 9.95E-02 Lung 15.0 mrem 1.54E-02 1.03E-01 GI-LLI 15.0 mrem 1.51E-02 1.01E-01 t

i I

l I

l 1

!.8

TABIZ 2-8 IDWER LIMITS OF DETECTION - GASEQUS SAMPLE A!RLYSES The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIOf0CLIDE LLD UNITS i

Kr-87 1.31E-07 uCi/ml 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

I-131 4.37E-14 I-133 6.16E-13 Mn-54 2.78E-14 I

Fe-59 4.62E-14 l

Co-SB 2.46E-14 Co-60 2.88E-14 Zn-65 7.51E-14 Mo-99 6.02E-13 Ca-134 3.64E-14 Cs-137 2.88E-14 Ce-141 4.94E-14 Ce-144 2.02E-13 Sr-89 1.17E-14 Sr-90 3.82E-15 83 H-3 5.82E-12

_L9_

3. SOLID WASTE l

3.1 RBGUIKIORY REQUIREMENTS i

The Technical Specifications presented in this section are for Unit 1.

Requirements for Unit 2 are the.same as for Unit It however, the Technical Specification numbers are not the same.

TEQiNIGL SPECIFICATIOtG 3.15.3.1 The solid radwaste system shall be used in i

accordanm with the PROCESS CONIROL PROGUM to provide for the SOLIDIFIGTION 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 CPR Part 20 and of 10 CPR 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 j

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)

Principal radionuclides (specify whether c.

a determined by measurement or estimate) d.

Type of waste, e.g., spent resin, cczupacted dry waste, evaporator bottoms Type of container, e.g., LSA, type A, type B, e.

large quantity f.

Solidification agent, e.g., cement.

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

L t

EFFLUE!C AND WASTE DISPOSAL SEMIANNUAL REPORT 1988 JULY 1,'1988. DECEMBER 31, 1988 SOLID WASTE AND IRRADIATED FUEL' SHIPMENT FOR UNIT I & II TABLE 3-1A I

I I

I l

l

1. Type of waste l

UNIT l 6 monthlEst. Totall I

I I oeriod i ERROR % l

.l

a. Spent resins, filter studges, evaporator l me 1 1.57E 21 l

l bottoms. etc.

I Ci I 6.55E 21 1.00 El

_l l

b. Dry compressible waste, contaminated l

m4_ _ l 1.86E 21 l

.l, eouio. etc' I

Ci I 7.13E-11 2.00 El l

l

c. Irradiated components, control rods, l

m4 I

E I

1 l

etc.

I Ci i

E I

E l

l

d. Other (describe)

[

me i

E I

l.

~l eouio. etc.

I Ci I

E i

E l

2.

Estimate of major nuclide composition (by type of waste) l ISOTOPE I

PERCENT l

CURIES

[

l i

I l

l a.

2n 65 1

51.62 1

338.037 l

l Co 60 1

10.60 1

69.429 l

l Cs-137 I

9.10 1

59.578 -l l

Others 1

28.68 l

187.874

[

l b.

Zn-65 1

50.76 1

0.362 l

-l co-60 1

26.78 1

0.191 1

l cs-137 l

6.70 1

0.0h78 l l

Others i

15.76 1

0.1128 l l

c.

!i/A I

l

[

l l

1 l

l 1

I i

l 1

1 I

I

)

l d.

N/A I

l l

l 4

1 I

l l

l l

l l

1 1

I l

l I

1 3.

Solid Waste Disposition Number of Shionents Mode of Transportation Destination

'28 Cask Barnwell, S.C.

7 Van (Box)

Barnwell B.

IRRADIATED FUEL SHIPMENTS (Disposition)

"'C' e

Number of Shioments Mode of Transportation Destination N/A N/A N/A _ _ _ _ _ _ _ _ _ _ _

.i

EFFLUENT AND h%STE DISPOSAL SEMIANNUAL REPORT 1988 JULY 1,1988 - DECEMBER 31, 1988 SOLID laSTE AND IRRADIATED PUEL SHIPMENT FOR UNIT I & II TABLE 3-1B l

TYPE i CURIE l

PRINCIPLE l

BURIAL l NUMBER OF l VOLUME OF l

TYPE 150LIBIFICATIONI l

0F QUANTITY /l NUCLICES /

I CONTAINER CONTAINERSI EACH CONTAINER ISHIPMENT /'

AENT l

WASTE DETERMINEO! DETERMINATION I DESCRIPTION SHIPPED ICUBIC FEET (ft 3)fCONTAINER I Oevatered 27 51 l 8~

lEesin fEASURED l

'l1h-210 l

l l

I LSA I

~

l

~99.h lTYPEA l NONE CSL 5

I I

I I

I I

i 1

1 I

I I

I I

I I

I i

i l

i l

Ilevateredi 179.00 i Zn-65,Nb-95, j ;C-lh2 1

1 l

_' 3 2. 4 l LSA l

None IResin IEASURED l Ni 63,Co 60, I

' HIC l

l 1 TYPE B l I

i i

l i

l

!=Cs-137 I

I I

I I

l l

l l

l l

==

I 1

I I

I I

I 1

I I

I I

I I

I I

i i

i t

i i

i l

Devatered hh9.k1 Zn-65,Cs-137j :.h-210 l

22 202.1 LSA None l Resin

)EASUREDlCo-60,Cr-51( HIC i

g TYPE A l l

I I

IMEASURED I

l l

l l

l I

I I

I I

I I

I I

I I

i i

I i

i i

Compacte4 0.7153 IZn-65,Co 60, Steel B-25 69 95.0 LSA l

None l DAW ESTIMATEDI Cs-137,Mn-5L.

Icx STC TYPE l

1 1

I I

I I STC I

l

' =Fe-5 5 l

l l

l l

= to 1

1 I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I I

I i

1 i

I i

i l

i l

I I

i I

i I

I I

I I

I I

I I

i l

1 1

I i

I i

l l

I I

I I

I i

1 l

I I

I i

1 I

I I

Notes: STC - Strong tight Container HIC - Hich intecrity container LSA - Low specific activity CSL - Carbon steel liner _

-~

4 7e? UNAVAILABIL*TI OF VP_M AT A PEMP S~'ATION Technical Specification 3.16.1.c reautres, in eart, that if milk samoles frem any of the locations required by Table 3.16.1-1 of the Technical Specifications can no loncer be obtained, efforts will be made to find replacement locations.

The cause of the unavailability and the identification of the

~ ffected locatient s) and of any replacement location (s) shall a

- be sucmitted to tne Commission in the next Semi-Annual Radioactive Effluent Release Reoort.

At the end of the third cuarter of'1988, the coats at Clark's Farm (Station No. 216) went dry and thus milk became unavailable at the only indicator station for the collection of_ milk samoles.

A land use survey was conducted on October 25, but no milk animals were found within five miles of the plant.

The Clarxs exoect that their coats will be oroducinq milk acain in the forthcoming sorino.

5.

LAND USE SURVEY PESULTS Technical Specifications 3.16.2.a reautres that, with a land use survey identifying a location (s) Vieldino a calculated thyroid dose or dose commitment creater than the values currently beino calculated in Specification 4.15.2.3, the new location (s) be submitted to the Commission in the next Semi-Annual Effluent Release Report.

A land use survey was conducted on October 25, 1988 and a follow-up survey conducted in November,1988.

An assessment of the information oathered from these surveys led to the identification of a new contro11ino dose receptor.

A contro11ino receptor is an individual at or beyond the site boundarv expected to receive the createst dose due to the caseous releases of I-131, :-133, tritium and radionuclides in particulate. form with half lives creeter than 8 days.

Doses are calculated in accordance with ODCM Section 2.2.2.b.

The new contro11ino receptor is a child located in the WSW sector at 1.2 miles who receives dose throuch the inhalation, around plane and veaetation oathways.

i L

6.

METEOROLOGY 1

In accordance~with Technical Specification 6.9.1.9,.the annual summary of meteorological data collected at Plant Hatch during 1988 is presented in this section.

6.1 1988 Meteorological Data o.

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

o.

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

o.

Joint Frequency Tables of Wind Speed and Wind Direction 100m vs Delta Temperature 100-10m.

o.

Wind Roses'from 10m (Seasonal and Annual).

o.

Wind Roses from 60m (Seasonal and Annual).

o.

Wind Roses from 100m (Seasonal and Annual).

o.

Percent Data. Recovery by Parameter and for Pertinent Composite Parameters for 1988, o.

Plots of Monthly Averages and Averages of Daily Extremes of Ambient Temperature and Dew Point Temperature, o.

Daily, Monthly and Annual.

Precipitation for the Period of January through December 1988.

o 0.

Descriptive Paragraph Comparing 1988 with Previous years.

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ATTACHMENT 7.

PLANT HATCH METEOROLOGICAL TOWER 1988 DATA RECOVERY l

l Parameter Recovery (Percent)

Wind Speed 10m 98.5 Wind Speed 60m 93.4 Wind Speed 100m 98.0 Wind Direction 10m 99.3 Wind Direction 60m 93.9 Wind Direction 100m 98.2 Delta Temperature 60-10m 98.9 Delta Temperature 100-10m 96.3 Temperature 10m 99.4 Dew Point Temperature 10m 99.4 Rainfall 94.2 Composite Wind Speed and Direction 10m, Delta Temperature 60-10m 97.2 Wind Speed and Direction 60m, Delta Temperature 60-10m 91.3 Wind Speed and Direction 100m, Delta Temperature 100-10m 93.6 5317A022389

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I ATTACHMENT 9.

HATCH DAILY, MONTHLY AND ANNUAL PRECIPITATION DATA FOR 1988 1

1 Month (Inches)

Month (Inches)

January 1 0.01 May 4 0.34 January 2 0.35 May 10 0.09 January 3 0.75 May 13 0.13 January 4 0.02 May 17 0.04 January 7 0.35 TOTAL 0.60 January 17 0.35 January 18 0.71 January 19 0.29 January 20 0.42 January 25 0.31 TOTAL 3.56 February 4 0.21 June 23 0.09 February 5 0.44 June 30 0.57 February 12 0.08 TOTAL 0.66 February 15 0.32 February 18 1.22 February 19 0.62 February 20 1.79 TOTAL 4.68 March July 11 0.15 Bad Data Most July 12 0.20 of the Month July 18 0.57 July 21 0.34 July 22 0.04 July 23 0.10 July 27 0.06 TOTAL 1.46 April 4 0.25 August 3 0.20 April 6 0.88 August 6 0.07 April 11 0.22 August 7 0.08 April 12 0.10 August 8 0.01 April 18 0.42 August 11 0.18 April 19 1.03 August 12 0.06 April 25 1.12 August 13 0.06 April 26 0.09 August 14 0.44 TOTAL 4.11 August 16 0.10 August 19 0.01 August 20 0.04 August 21 0.04 August 23 0.08 August 24 0.09 August 27 0.66 August 30 0.25 August 31 0.23 TOTAL 2.60 5317A022389

ATTACHMENT 9 (Continued)

Month (Inches)

Month (Inches)

September 1 0.12 November 1.

0.02 September 2 0.13 November 4 0.24 September 3 0.11 November 5 0.43 September 4 0.77 November 23 0.10 September 5 0.20 November 28 0.02 September 8 0.69 November 29 0.03 September 9 0.60 TOTAL.

0.84 September 18 0.13 September 24 0.01 September 25 0.04 September 26 0.15 September 29.

0.08 TOTAL 3.03 October 1 0.15 December 9 0.06 October 2 0.02 December 11 0.45 October 3 0.06 December 16 0.28 October 21 0.16 December 31 0.04 October 27 0.04 TOTAL 0.83 October 28 0.03 TOTAL 0.46 1988 Annual Total = 22.83 i

5317A022389

ATTACHMENT 10. HATCH METEOROLOGICAL 1980

SUMMARY

The Plant Hatch 100m treteorological tower marked its fif th year of operation with better data recovery than in any previous year.

For all parameters as shown in Attachment 7, the data recovery averaged above 97%; and for the pertinent parameters of wind speed, direction and delta temperature, the data recovery averaged above 94%. With the exception of the delta temperature, no data from the backup tower was used in 1988.

Most of the data lost in 1988 can be attributed to strip chart problems and short maintenance outages.

The ambient and dew point temperature plots shown in Attachment 8 agree very well with data from the previous year.

In particular, the summer maximum temperatures for 1987 and 1988 were almost identical. The 1988 fall season was somewhat cooler than in previous years. This can be attributed to normal year-to-year climatic variation.

The wind roses in Attachments 4, 5 and 6 show good agreement between levels and with previous years.

As in the past, there are some small differences between the Wm level and the two top levels (60m and 100m) on the tower. The peak u ud direction at all levels is from the northeast. Secondary peaks at the 10m level occur from the south to the southwest.

At the 60m and 100m levels, the secondary peak is from the west.

The most prevalent wind direction does vary somewhat on a seasonal basis with west to northwest winds occurring in the winter months, and south to southwest winds more lik'ely during the summer.

The,

northeast wind is spread more evenly throughout the year.

The joint frequency tables of wind speed and direction versus delta temperature are shown in Attachments 1, 2 and 3.

The table below summarizes the last five years of joint frequency data. The table used the wind speed and direction from the 10m level versus the delta temperature between 60 and 10 meters.

The 1988 data year agrees closely with the 5-year average. There were slightly more stable and unstable hours than occurred in the 5-year average. This is similar to what occurred in 1987 and may mean the long-term average is closer to the 1987 and 1988 percentages. Overall the stability percentages for 1988 are closer to the 5-year average than any other year shown.

5317A022389

Plant Hatch Stability Classification l

Stability Percent Stability Group 1988 1987 1986 1985 1984 5-Year Average 5

A 12.2 15.7 7.8 9.3 8.4 10.8 8

4.0 5.0 3.5 4.7 5.2 4.5 C

3.1 4.0 3.0 5.5 5.8 4.3 D

18.4 16.8 21.4 26.5 19.9 20.6 E

31.8 31.6 37.6 31.8 31.8 33.0 F

15.3 12.3 13.7 11.3 12.4 13.0 F

15.2 14.6 11.0 10.9 16.5 13.8 Total Hours 8541 8162 8037 7860 7928 The precipitation totals (daily, monthly and annual) are shown in.

The total for the year was 22.83 inches which was much below the area normal of about 45 inches. The month of March was considered to be mostly bad data. Therefore, one month is missing out of the total.

However, the overall rainfall total for the second half of the year was only about 9 inches. Therefore, there may have been a problem with the rainfall data that was not apparent on the strip charts.

5317A022389

_ _