ML20205D984

Semiannual Rept,Plant Radioactive Effluent Releases,Jul- Dec 1985

ML20205D984
Person / Time
Site:	Hatch
Issue date:	12/31/1985
From:	Nix H GEORGIA POWER CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
LG-MGR-106-0286, LG-MGR-106-286, LG-MGR-107-0286, LG-MGR-107-286, NUDOCS 8608180220
Download: ML20205D984 (106)

Text

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GEORGIA POWER COMPANY PLANT E.I. HATCH SEMI-ANNUAL REPORT l

PLANT RADI0 ACTIVE EFFLUENT RELEASES JULY 1 THE0 UGH DECEMBER 31,1.J85 i

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Georgia P:w:r C:rnpiny Post Offica B:x 439 B:xt:y, Georgia 31513 Telephone 912 367-7781 912 537-9444 k s' Georgia Pbwer Edwin 1. Hatch Nucteer Plant February 26, 1986 LR-MGR-106-0286 PLANT E.

I.

HATCH Semi-Annual Radioactive Effluent Release Report Dr.

J.

Nelson Grace U.

S.

Nuclear Regulatory Commission Office of Inspection and Enforcement Region II, Suite 3100 101 Marietta Street Atlanta, Georgia 30303

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Dear Dr. Grace:

%d Pursuant to Technical S p ec i f ic a t io n s,

6.9.1.8 and 6.9.1.9.,

of the Plant Edwin I.

Hatch Operating Licenses, please find enclosed the Semi-Annual Radioactive Effluent Release Report, July 1,

1985,through December 31, 1985.

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Georgia Power Comp:ny Post Offica B:x 439 B xlIy, Georgin 31513 Telephone 912 367-7781 912 537-9444

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Edwin 1. Hatch Nuclear Plant February 26, 1986 LR-!!GR-107-0286 PLANT E.

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HATCH Semi-Annual Radioactive Effluent Release Report Director of Inspection and Enforcement

% Distribution Services Branch U.

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Nuclear Regulatory Commission Washington, D.

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1 Gentlemen:

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Pursuant to Technical Specifications, t>. 9.1. 8 and 6.9.1.9.,

of the Plant Edwin I.

Hatch Operating. Licenses, please find enclosed the Semi-Annual' Radioactive Effluent Release Report, July 1,

1985 through December 31,'1985.

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l GEORGIA POWER COMPANY PLANT E.

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HATCH UNITS NO.

1 & 2 SEMI-ANNUAL REPORT RADIOACTIVE EFFLUENT RELEASE REPORT July 1,

1985 - December 31, 1985

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PLANT E.

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HATCH

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SEMIANNUAL REPORT N_/

r RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE 1.

LIQUID EFFLUENTS 1

1.1 REGULATORY LIMITS 1

1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5

1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 5

1.4 LIQUID EFFLUENT RELEASE DATA 7

1.5 RADIOLOGICAL IMPAC? ON MAN DUE TO LIQUID RELEASES 9

1.6 ABNORMAL RELEASES 9

2 GASEOUS EFFLUENTS 17 2.1 REGULATORY LIMITS 17

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2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 23 2.3 GASEOUS EFFLUENT RELEASE DATA 28 2.4 RADIOLOGICAL IMPACT DUE TO GASEOUS RELEASES 29 3

SOLID WASTE 45 1

3.1 REGULATORY SPECIFICATIONS 45 3.2 SOLID WASTE DATA 45 4

CHANGES TO THE PLANT HATCH ODCM 48 5

METEOROLOGY 49 5.1 Meteorological Data 49 l

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/~'s SEMIANNUAL REPORT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE l-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3

1-2a LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT I 10 1-2b LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT II 11 1-3a LIQUID EFFLUENTS - UNIT I 12 1-3b LIQUID EFFLUENTS - UNIT II 13 1-4a INDIVIDUAL DOSES DUE TO LIQUID RELEASES - UNIT I 14 1-4b INDIVIDUAL DOSES DUE TO' LIQUID g

RELEASES - UNIT II

.15 1-5 LOWER LIMITS OF DETECTION LIQUID SAMPLE ANALYSES 16 2-1 TECHNICAL SPECIFICATION TABLE 3.14.2-1. RADIOACTIVE GASEOUS EFFLUENT MONITok1NG INSTRUMENTATION 19 2-2a GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT 1 30 2-2b GASEOUS EFFLUENTS - SUMMATION OF 31 ALL RELEASES - UNIT 2 2-2c GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - SITE 32 2-3a GASEOUS EFFLUENTS ELEVATED UNIT 1 33 RELEASES 2-3b GASEOUS EFFLUENTS - ELEVATED RELEASES - UNIT 2 34 2-3c GASEOUS EFFLUENTS - ELEVATED RELEASES - SITE 35 O

TABLES LIST OF TABLES PAGE

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2-4a GASEOUS EFFLUENTS - GROUND-

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UNIT 1 36 LEVEL RELEASES 2-4b GASEOUS EFFLUENTS GROUND -

LEVEL RELEAS AS - UNIT 2 37 2-4c GASEOUS EI"FLUENTS GROUND -

1 LEVEL RELEASES - SITE 38 2-5 GASEOUS EFFLUENTS - DOSE RATES - SITE 39 2-6a AIR DOSES DUE TO NOBLE GASES -

UNIT 1 40 2-6b AIR DOSES DUE TO NOBLE GASES -

UNIT 2 41 I

2-7a INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM, AND PARTICULATES IN GASEOUS

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RELEASES - UNIT 1 42 l

2-7b INDIVIDUAL DvSES DUE TO RADIOIODINE, 1

TRITIUM, AND PARTICULATES IN GASEOUS RELEASES - UNIT 2 43 2-8 LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES 44 f

3-la,b SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 46,47 i

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. V RADIOACTIVE EFFLUENT RELEASE REPORT 1

LIQUID EFFLUENTS 1.1.

REGULATORY LIMITS 2

1.

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

Requirements for Unit II are the same as Unit I; 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 setpointe set to ensure that the limits of Specification 3.15.1 are not exceeded.

The alarm / trip setpoints 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 concentration of radioactive material

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released at any time from the site to UNRESTRICTED

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AREAS (figure 3.15-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B,

Table II (column 2) for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04.uci/mi 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 tot a.

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

b.

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

3.15.1.3 The liquid radwaste treatment system, as described in the ODCM, shall be used to reduce the l

radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid

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effluent per Unit from the site (figure 3.15-1) when

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projected over the calendar quarter would exceed 0.18 l

mrem to the total body or 0.62 mrem to any organ, i l

l 3.15.1.4(a)

The contents within any outside gS temporary tank shall be limited to 10 curies,

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excluding tritium and dissolved or entrained noble g&Ses.

(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 radioiodines for gaseous releases".

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TABLE l-1 TECHNICAL SPECIFICATION rN TABLE 3.14.1-1 (SHEET 1 of 2)

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Channels Instrument OPERABLE Applicability ACTION 1.

Gross Radioactivity MoniLota 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

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Flowrate Measure-ment Devices **

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Liquid Radwaste Effluent Line 1

(a) 102 Discharge Canal 1

(b)

(a) 102 i

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Service Water 1

At all times 103 System to closed Cooling Water System Differential Pressure

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• • Pump 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 is below the closed cooling water system pressure or AP indication is not available.

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TABLE l-1 (CONTINUED)

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

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RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS 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, suspended 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 o

t that once per shift grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a Lower Limit of A

Detection of at least 10-7 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.

ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

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

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

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1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS A) i\\_/

The MPC values used in. determining allowable liquid radwaste release rates and concentrations for principal gamma emitters, I-131, tritium, St-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 I) and 3.11.1.1 (Unit' II) as 2.0E-04 uCi/ml.

For gross alpha in liquid radwaste, the MPC is taken from 10CFR Part 20, Appendix B,

Note 2.b as 3.0E-08 uCi/ml.

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

Note 1.

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

l.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL 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 I) and 4.11.1-1 (Unit II).

A sample from each tank planned for release is analyzed for principal gamma emitters, I-131, and dissolved and entrained noble gases by gamma spectrometry.

Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from tanks which are released.

Liquid radwaste sample analyses are performed as follows:

1 Measurement Frequency Method 1.

Gamma Isotopic Each Batch Gamma spectroscopy with computerized data reduction i

2.

Dissolved o r' Each Batch Gamma spectroscopy i

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Entrained with computerized Noble Cases data reduction

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Measurement Frequency Method 3.

Tritium Monthly Distillation and

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Composite liquid scintillation 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.

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

Three germanium detectors are available a 10%

efficient Ge(Li) detector 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 sample is poured into a Marinelli beaker in preparation for a 2000-3000 second count.

A peak search of the resulting gamma ray Q(,)

spectrum is performed by the computer system.

Energy and net count data for all significant peaks are determined, and quantitative reduction or LLD calculations are performed for the nuclides specified in Table Notation e of Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2) :

Mn-54, F-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, sample volume, sample geometry, detector efficiency, baseline counts, and branching ratio.

LLD calculations, including the above corrections, are made based on the L

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.

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The radionuclide concentrations determined by gamma spectroscopic analysis of a sample 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 along with the corresponding MPC values to determino an MPC fraction for the tank planned for release.

This MFC fraction i

is then used, with appropriate safety factors, along l

with the expected dilution stream flow to calculate a l

maximum permissible release rate and a liquid effluent

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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 nonitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid radwaste discharge.

Liquid effluent discharge is also automatically

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terminated if the dilution stream flow rate falls

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below the dilution flow rate used in the setpoint calculations and established as a setpoint on the j

dilution stream flow monitor.

J 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 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 Radwaste Operations.

When the release is completed the release permit is returned from Radwaste Operations with actual release data included.

This data is input to the computer 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.

l l.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-2a for Unit 1 and Table 1-2b for Unit 2; and Table 1-3a for Unit 1 and 1-3b for Unit 2.

The values for the four categories of Tables 1-2a l

and 1-2b are calculated and the Tables completed as follows:

1.

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

This sum is for each batch released to the river for the respective t..

quartor.

Porcont of cpplicablo limit is datorminod froo a nixod nuclido MPC fraction calculation.

The average concentration for each nuclide over all released batches is I

divided by the corresponding individual MPC j-s)

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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 composite samples are used to calculate the total release and average 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 on each batch by germanium spectroscopy on a one liter sample from each liquid radwaste batch.

The average concentration of dissolved or entrained nobles gases for all released batches is divided by the MPC value stated in Technical Specifications 3.15.1.1 and 3.11.1.1 (2.0E-04 uCi/ml) to determine the MPC fraction.

The result x100 is the pe,rcent of applicable limit for noble gases N

in liquid effluent releases during the quarter.

Iodine radionuclides in any form are also determined during the isotopic analysis for each batch, therefore a separate analysis for possible gaseous forms is not performed because it would not provide additional information.

4.

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

Other data pertinent to batch releases of radioactive liquid effluent from both units is as follows:

Number of batch releases:

805 Total time period for batch releases:

87,722 minutes Maximum time period for a batch release:

293 minutes 2

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Avorogo time poried for botch j

.roloccos:

109 cinutoo Minimum time period for a batch release:

1.0 minute

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Average stream flow during periods

(_,S) of release of liquid effluent into a flowing stream:

5400 CFS 1.5 RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID RELEASES

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Doses to an individual, due to radioactivity in liquid 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 methodology 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.

1.6 ABNORMAL RELEASES Technical Specifications 3.15.1.1 (Unit 1) and 3.11.1.1 (Unit 2) state in part that if concentration of radioactive material in liquid effluents released from the site to unrestricted areas exceeds the concentration limits stated within, notification, including a discussion of causes and corrective actions taken, must be f) provided to the Commission in the next

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Semi-annual Effluent Release Report.

Further, Regulatory Guide 1.21 states that the total curies of radioactive materials released as a result of abormal releases should be included.

On November,3, 1985, during the release of Chemical Waste Sample Tank B (Unit 2) to the Altamaha River, the concentration of radioactive material entering the river exceeded Technical Specification 3.11.1.1 limits for a period of one minute.

A total of 58 gallons of liquid containing 70.6 microcuries was released.

The cause of the abnormal release was personnel error in that the chemistry technician and the lab foreman who approved the discharge permit prior to release failed to recognize that the specified tank discharge rate was greater than i

the maximum permissible discharge rate calculated for the planned release.

The liquid radwaste i

effluent radiation monitor tripped after one j

minute of discharge and terminated the release.

Additional training was given to the chemistry staff concerning liquid radwaste discharge i s,)

permits and the significance of information contained in the permits.

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TA2LE 1-2c E.

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HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1985 b[~N SUMMATION OF ALL RELEASES LIQUID EFFLUENTS Est. Total Unit Quarter 3 Quarter 4 Error t A.

Fission &

Activati'on Products 1.

Total release (not including Ci 3.59E-2 1.41E-1 4.6E+1 H-3,

gases, alpha) 2.

Average diluted concentration uCi/ml 4.02E-8 1.02E-7 during period 3.

4 of applicable t

6.73E-1 7.00E-1 limit B. Tritium 1.

Total release Ci 5.48E+0 9.55E+0 3.7E+1 2.

Average diluted uCi/ml 6.13E-6 6.92E-6 concentration during period 3.

t of applicable 1

2.04E-1 2.31E-1 limit

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Dissolved and Entrained Gases 1.

Total release Ci 6.65E-4 2.15E-3 1.0E+2 2.

Average diluted uCi/mi 7.44E-10 1.56E-9 concentration during period 3.

t of applicable t

3.72E-4 7.79E-4 limit D.

Gross alpha radioactivity 1.

Total release ci 8.67E-7 4.73E-6 1.2E+2 4

E.

Volume of waste (prior to dilution) liters 3.94E+6 6.97E+6 1.0E+1 F.

Volume of dilution water used liters 8.94E+8 1.38E+9 1.6E+2 0

TABLE l-2b E.

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HATCH NUCLEAR PLANT UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1985

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LIQUID EFFLUENTS SUMMATION OF ALL RELEASES N,

Est. Total Unit Quarter 3 Quarter 4 Error %

A.

Fission &

Activation Products 1.

Total release (not including Ci 3.38E-2 6.57E-2 4.7E+1 H-3,

gases, alpha) 2.

Averags diluted concentration uCi/ml 2.97E-8 5.14E-8 during period 3.

% of applicable 4

2.09E-1 3.42E-0 limit B. Tritium 1.

Total release Ci 4.24E+0 4.81E+0 3.7E+1 2.

Average diluted uCi/mi 3.73E-6 3.76E-6 concentration during period 3.

4 of applicable 1.25E-1 1.25E-1 limit

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C.

Dissolved and

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Entrained Cases 1.

Total release Ci 5.33E-4 8.23E-2 1.0E+2 2.

Average diluted uCi/ml 4.67E-10 6.44E-8 concentration during period 3.

% of applicable,

2.34E-4 3.22E-2 limit D.

Gross alpha radioactivity 1.

Total release ci 2.26E-6 3.41E-7 1.2E+2 E.

Volume of waste (prior to d ilu t io n) liters 4.93E+6 5.31E+6 1.0E+1 F.

Volume of dilution water used liters 1.14E+9 1.28E+9 1.6E+2 O

TABLE l-3o E.

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HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1985*

O Continuous Mode **

Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 5.48E+0 9.55E+0 Na-24 Ci 1.29E-2 9.56E-3 Cr-51 Ci 2.54E-4 6.13E-3 Mn-54 Ci 3.74E-4 6.90E-3 Mn-56 Ci 1.90E-6 0.00E+0 Fe-55 Ci 2.02E-3 3.14E-3 Fe-59 Ci 0.00E+0 2.95E-5 Co-58 Ci 2.79E-4 5.13E-3 Co-60 Ci 2.52E-3 1.93E-2 Zn-65 Ci 2.41E-3 5.2SE-2 St-89 Ci 9.38E-4 0.00E+0 Sr-91 Ci 0.00E+0 2.60E-4 Sr-92 Ci 0.00E+0 3.02E-4 Y-91m Ci 0.00E+0 2.23E-4 Zr-95 Ci 0.00E+0 2.79E-6 Nb-95 C1 3.54E-6 3.13E-5 Tc-99m Ci 9.79E-5 7.44E-4 I-131 Ci 1.20E-3 1.49E-3 I-130 Ci 0.00E+0 1.30E-5

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I-133 Ci 2.93E-4 6.44E-4 I-134 Ci 0.00E+0 4.20E-3 Cs-134 Ci 3.88E-3 1.09E-2 Cs-136 Ci 0.00E+0 3.30E-5 Cs-137 Ci 8.67E-3 1.98E-2 Ba-140 Ci 0.00E+0 3.71E-5 Np-239 Ci 1.81E-5 0.00E+0 Totals Ci 3.59E-2 1.41E-1 Xe-133 Ci 1.27E-4 5.55E-4 Xe-135m Ci 0.00E+0 5.82E-6 Xa-135 Ci 5.38E-4 1.57E-3 Ar-41 Ci 0.00E+0 1.86E-5 Totals Ci 6.65E-4 2.15E-3 Gross Alpha Ci 8.67E-7 4.73E-6

• Zeros in this table indicate that no radioactivity was present above detectable levels.

See Table 1-5 for typical lower limits of detection for liquid sample analyses.

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

TABLE l-3b E.

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HATCH NUCLEAR PLANT - UNIT 2 7-SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1985*

Continuous Mode **

Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 4.24E+0 4.81E+0 Na-24 Ci 4.12E-3 5.11E-3 Cr-51 Ci 0.00E+0 2.45E-3 Mn-54 Ci 2.68E-4 1.25E-4 Mn-56 Ci 1.78E-5 2.14E-4 Fe-55 Ci 2.29E-3 3.58E-3 Co-58 Ci 1.38E-4 1.15E-4 Co-60 Ci 3.37E-3 1.31E-3 Cu-64 Ci 0.00E+0 3.28E-3 Zn-65 Ci 1.87E-3 3.68E-3 Sr-89 Ci 1.17E-3 0.00E+0 Y-91m Ci 0.00E+0 9.59E-4 Zr-95 Ci 6.99E-5 7.80E-6 Nb-95 Ci 8.60E-5 1.67E-5 Tc-99m Ci 2.21E-5 8.65E-4 I-131 Ci 6.45E-5 1.04E-2 I-132 Ci 0.00E+0 3.68E-4 I-133 Ci 7.50E-5 6.40E-3 s

I-134 Ci 0.00E+0 2.15E-4 I-135 Ci 0.00E+0 7.92E-4 Cs-134 Ci 6.66E-3 8.37E-3 Cs-135 Ci 0.00E+0 1.94E-4 Cs-137 C1 1.36E-2 1.66E-2 Ba-139 Ci 0.00E+0 6.81E-4 Ba-140 Ci 0.00E+0 1.83E-5 Totals Ci 3.38E-2 6.57E-2 Kr-85 Ci 0.00E+0 5.38E-3 Kr-87 Ci 5.71E-6 0.00E+0 Xe-131m Ci 2.27E-5 3.55E-3 Xe-133m Ci C.00E+0 1.80E-3 Xe-133 Ci 4.25E-5 5.77E-2 Xe-135m Ci 0.00E+0 4.57E-4 Xe-135 Ci 4.62E-4 1.34E-2 Totals ci 5.33E-4 8.23E-2 Gross Alpha CL 2.26E-6 3.41E-7

• Zeros in this table indicate that no radioactivity was nresent above detectable levels.

See Table 1-5 for typical lower limits of detection for liquid sample analyses.

(

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

TABLE l-40 E.

'I. HATCH NUCLEAR PLANT UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1985 INDIVIDUAL DOSES DUE TO LIQUID RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter 4 of Quarter

% of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Bone 5.0 mrem /qtr 4.43E-2 0.89 1.18E-1 2.36 Liver 5.0 meem/qtr 7.25E-2 1.45 2.07E-1 4.14 Tot. Body 1.5 mrem /qtr 5.18E-2 3.45 1.45E-1 9.67 Thyroid 5.0 mrem /qte 6.74E-3 0.13 1.18E-2 0.24 Kidney 5.0 mrem /qtr 2.46E-2 0.49 7.51E-2 1.50 Lung 5.0 mrem /qtr 8.07E-3 0.16 2.07E-2 0.41 GI-LLI 5.0 mrem /qtr 4.07E-3 0.08 2.88E-2 0.58 Cumulative,"use Per Year Organ Tech Unit Quarters

% of Tech Spec 3 & 4 Spec Limit Limit Bone 10.0 mrem /yr 1.62E-1 1.62 Liver 10.0 mrem /yr 2.79E-1 2.79 Total Body 3.0 mrem /yr 1.97E-1 6.57

\\

Thyroid 10.0 mrem /yr 1.85E-2 0.19 Kidney 10.0 mrem /yr 9.98E-2 1.00 Lung 10.0 mrem /yr 2.88E-2 0.29 GI-LLI 10.0 mrem /yr 3.28E-2 0.33 I

I i

l l

l -_

TABLE l-4b E.

I.

HATCH NUCLEAR PLANT UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1985 INDIVIDUAL DOSES DUE TO LIQUID RELEASES f%

Cumulative Dose Per Quarter Organ Tech Unit Quarter t of Quarter t of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Bone 5.0 mrem /qte 7.24E-2 1.45 1.33E-1 2.7 Liver 5.0 mrem /qtr 1.20E-1 2.40 1.40E-1 2.8 Tot. Body 1.5 mrem /qtr 8.61E-2 5.74 1.00E-1 6.7 Thyroid 5.0 meem/qtr_

5.08E-4 0.01 6.35E-2 1.3 Kidney 5.0 mrem /qtr 4.01E-2 0.80 4.63E-2 0.9 Lung 5.0 mrem /qtr 1.32E-2 0.26 1.50E-2 0.3 GI-LLI 5.0 mrem /qtr 4.67E-3 0.09 1.10E-2 2.2 Cumulative Dose Per Year Organ Tech Unit Quarters

% of Tech Spec 3 & 4 Spec Limit Limit Bone 10.0 mrem /yr 2.05E-1 2.1 Liver 10.0 meem/yr 2.60E-1 2.6 Total Body 3.0 mrem /yr 1.86E-1 6.2 O

Thyroid 10.0 mrem /yr 6.40E-2 0.6 Kidney 10.0 mrem /yr 8.64E-2 0.9 Lung 10.0 mrem /yr 2.82E-2 0.3 GI-LLI 10.0 mrem /yr 1.57E-2 0.2 O

- - _ -. __ =

{

TABLE l-5 LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES The values in this table represents apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE LLD UNIT Mn-54 5.38E-08 uCi/ml i

Fe-59 7.78E-08 j

Co-58 4.67E-08 1

Co-60 4.78E-08 l

Zn-65 1.31E-07 l

Mo-99 5.10E-07 Cs-134 7.18E-08 l

Cs-137 6.05E-08 i

Ce-141 1.41E-07 Ce-144 6.30E-07 I-131 6.51E-08 Xe-135 8.45E-08 i

Fe-55 8.00E-07 Sr-89 2.30E-08

)

St-90 7.67E-09 4

H-3 5.00E-07 1

l0 i

t I

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1 k

t 5

l i

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f i.....

e-2 GASEGUS EFFLUESTS 2.1 REGULATORY LIMITS

[~N The Technical Specifications presented in this (m,)

section are for Unit 1.

Requirements for Unit 2 are the same as for Unit 1; however, the Technical Specification numbers are not the same.

TECHNICAL SPECIFICATIONS 3.14.2 The radioactive gaseous effluent monitoring 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 (figure 3.15-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values a.

The dose rate limit for noble gases shall be 6 500 mrem / year to the total body and 6 3000 mrem / year to the skin.

g-w b.

The dose rate limit for I-131, I-133,

( j tritium, and for all radioactive materials in particulate form and radionuclides other than noble gaser with half-lives greater than 8 days shall be A 1500 mrem / year to any organ.

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

During any calendar quarter, to i 5 mead for gamma radiation and 6 10 mrad for beta radiation.

b.

During any calendar year, to 4 10 mrad for gamma radiation and 1 20 mead for beta radiation.

3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLIC from I-131, I-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to UNRESTRICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the following a.

During any calendar quarter to n 7.5 mrem to any organ.

I\\/

b.

During any calendar year to n 15 mrem to,any organ.

3.15.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM as d.escribed in the ODCM shall be in operation.

(This Technical Specification applies whenever the main condenser air ejector system is in operation.)

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

3.15.2.5 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 meem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 meem.

(With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of O

Specifications 3.15.1.2(a), 3.15.1. 2 ( b),

3.15.2.2.(a), 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 ce ntributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 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 i 4 percent by volume.

3.15.2.7 The gross gamma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation system pretreatment monitor station shall be limited to 6.

240,000 uCi/second.

6.9.1.9 states in part:

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

liquid effluents, or those in excess of 150 Ci of nobio gases or 0.02 Ci of radioiodines for gaseous releases."

O C

O TABLE 2-1 TABLE 3.14.2-1 (SHEET 1 OP 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minieue ChanneIs enstrument OPERA 8tE AnolicabiIity Pa rame te r ACT 1001 1.

Main Condenser Orrgas Treatment System Explosive Gas Monitoring System stydrogen Monstor (1)

T, Hydrogen 106 2.

Reactor Building Vent Stack Monitoring Systee Radioactivity Rate 105 a.

Isotte Gas Activity Monitor (1)

Measurement +

b.

Iodine Sampler Cartridge (1)

Verify Presence of 107 Ca rt ridge h

Verify Presence of 107 c.

Particulate Sampler Fi tter (1) y)

Filter I

d.

Effluent System Flowrate steasurement Device (1)

System flowrate 1 01s Measurement e.

Sampler Flowrate Measurteent Sampler Flowrate 104 Device (1)

Measurement 3.

Recombiner Building venti tation Monitoring System Radioactivity Rate 105 a.

stotle Gas Activity Monitor (1) feessurement +

b.

todine Sampler Cartridge (1)

Verify Presence of 107 Ca rt ridge c.

Particulate Sampler Filter (1)

Verify Presence of 107 Filter Sampler Flowrate 104 d.

Sampler Flowrate Measurement (1)

Devece Measurement A

h q

sj s

TABLE 2-1 TABLE 3.14.2-1 SHEET (2 OF 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimus ChanneIs Instrument OPEft4SL E Aeolicability Pa ramete r ACTIOes 4.

lesin Stack Monitoring System a.

seoble Gas Activity Monitor (1)

Radioactivity Rate 105 Measurement +

Verify Presence of 107 b.

todine Sampler Cartridge (1)

Ca rt ridge Verify fresence or 107 c.

Particu' ate Sampler Filter (1)

Filter d.

Effluent Systes Flowrote Systes Flowrate 1 04 stessuring Devices (1)

Measurement I

Sampler Flowrate 104 w

e.

Sampler Flowrate leessuring (1) o Devsce Mea surement t

5.

Condenser Offgas Pretreatment stoni tor noese Cas Activity Monitor (s)

Radioactivity Rate 108 Mea surement

TABLE 2-1 TABLE 3.14.2-1 (SHEET 3 OF 4)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations l

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

i

• During releases via this pathway.

i j

• • 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 Channels OPERABLE requirement, j

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 />.

1 If the number of channels OPERABLE remains less than

]

required by the Minimum Channels OPERABLE requirement for l

over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

l ACTION 105 - With the number of channels OPERABLE less than i

j required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided s'

grab samples are taken daily and analyzed daily for gross l

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 monitoring system channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay l

t 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 i

included in the next semi-annual effluent release report.

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

3 l

(a)

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

(b)

Using a temporary hydrogen analyzer installed in the i

offgas system line downstream of the recombiner, i

hydrogen concentration readings are taken and logged i

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

l 1

I i i

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

TABLE 2-1 TABLE 3.14.2-1 (SHEET 4 OF 4)

-s PADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 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 and 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 effluent release report.

ACTION 108 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, 0,

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 offgas system is not bypassed, and a.

b.

The offgas post-treatment monitor (Dil-K615) or the main stack monitor (Dil-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.

f

n s_-

1 a 1

-__-m.

gS 2.2 MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY n

\\

l Waste gas release at Plant Hatch is confined to four paths:

main stack (also called the offgas vent), Unit 1 reactor building vent; Unit 2 reactor building vent, and the recombiner building vent.

Each of these four paths is continuously monitored for gaseous radioactivity.

Each is equipped with an integrating-type sample collection device for collecting particulates and iodines.

Sample collection is in accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2).

Unless required more frequently under certain circumstances specified in Table Notations to the abovementioned tables,-

samples are collected as follows:

1.

Noble gas samples are collected by grab sampling monthly.

2.

Tritium samples are collected by grab sampling monthly.

3.

Radioiodine samples are collected by pulling the sample stream through a charcoal

'j

)

cartridge over a 7-day period.

4.

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

5.

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

6.

Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly i

composite sample is analyzed for Sr-89 and i

Sr-90.

Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year.

This task is normally performed with computer assistance.

O 4

The noblo goo greb neaplo analycio results are used along with, maximum expected release flow rates from each of the four vents to calculate

(~}/

monitor setpoints for the gaseous effluent

(,

monitors serving the four release points, to assure that the limits of Technical Specifications 3.15.2.1.a (Unit 1) or 3.11.2.1.6 (Unit 2) are not exceeded.

Calculation of monitor setpoints is described in the Plant Hatch.

ODCM.

With each release pe$1od released radioactivity, dose rates, and cunulative doses are calculated.

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

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

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

l.

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

Instantaneous dose rates are calculated (with 3

computer assistance) due to noble gases and due to radioiodines, tritium, and particulates.

Calculated dose rates are compared to the dose-l 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 radioiodine, tritium, and particulates.

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

O l (

l

' s,3 I( A (4,

Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted y,_ '

f area with the potential for the highest exposure t

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 compared to the dose limits specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2).

Current percent of tech spec limits are shown on the printout for each release period.

Air dose calculation methodology is presented in the Plant Hatch ODCM.

2.

RADIOIODINE, TRITIUM, AND PARTICULATE RELEASES Released quantities of radioiodines are determined from the weekly samples and release flow rates for the four release points.

Radioiodine concentrations are determined by gamma spectroscopy.

Released quantities of particulates 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 gamma emitters.

(\\)

After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is made.

Since sample flows and vent flows are almost constant over each monthly 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 St-90 is not detected, LLD's are calculated.

Strontium concentrations are input to the 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 passing the sample stream from a cold trap immersed in a liquid nitrogen or an acetone and ice mixture.

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 tritium samples are analyzed by an independent laboratory 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 input into the composite C) file of the computer to be used in release, dose rate, and individual dose calculations.

s.

Dose rates due to radioiodine, tritium, and fs particulates are calculated for a hypothetical

.( )

child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the highest.

Dose rates are calculated for each release point, for each release period, and the total dose 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 radioiodine, tritium, and particulates are calculated for the critical receptor, which for Plant Hatch is an infant exposed to tne grass-cow-milk, inhalation, and ground-plane pathways.

Individual doses are calculated for each release pericd 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 tech spec limits are shown on the printout for each release period.

[ T 3.

GROSS ALPHA RELEASE

.V

's computed each month by i

The gross alpha release counting the particulate filters each week for gross alpha activity in a proportional counter.

The four or five weeks numbers are then recorded i

on a data sheet and the activity is summed at the end of the month.

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

l l

l l. - _ _ _.

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

("N sampling and measurement.

Because it may be very

(,)

difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested.

The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste."

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

(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%

100%

(2)

I-131 Release was calculated from each weekly

(

sample:

Statistical Error 60%

Counting Equipment Calibration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

Losses From Charcoal Cartridge 10%

110%

(3)

Particulates with half = lives greater than 8 days release was calculated from sample analysis results and release point flow rates.

Statistical Error at LLD concentration 60%

Counting Equipment Calbration 10%

Vent Flow Rates 10%

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10%

100%

O - - -

(4)

Total Tritium Ralease was dominated by the reactor building vent tritium release, hence, the larger statistical errors of the off-gas vent and

N recombiner building vent tritium releases do not

,)

affect the error in the total tritium release:

Water Vapor in Sample Stream Determination 20%

Vent Flow Rates 10%

Counting Calibration and Statistics 10%

Non-Steady Release 50%

90%

1 2.3 GASEOUS EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables lA, 1B, 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.

To complete Vables 2-2a-c, total release for each of the four categories (fission and activation gases; iodines; 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 terms of release rate in uCi/second but in terms of done rate in mrem / year, as presented in g3

(

)

Technical Specifications 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2).

Noble gases are limited as specified in 3.15.2.1.a and 3.ll.2.1.a.

The other three categories (tritium, radioiodines, and particulates) 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, tritium, and particulates are presented 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, along with percent of technical specification limits.

O _ -.. _ _

Limits for cumulative individual doses, due to radiolodine, tritium, and particulates, are specified

~

\\ ')

in Technical Specifications 3.15.2.3 (Unit 1) and i

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 TO GASEOUS RELEASES 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, tritium, and particulates 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 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 radioiodine,

. '\\-

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 2-7b.

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

O

TABLE 2-2a E.

I.

HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 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 4.38E+02 9.00E+03 1.00E+02 Release 2.

Average uCi/sec 5.51E+01 1.13E+03 Release Rate For Period

• 3.

% of Tech Spec Limit B.

Iodines 1.

Total Ci 1.94E-04 2.44E-03 1.10E+02 Iodine-131 2.

Average uCi/sec 2.44E-05 3.07E-04 Release Rate For Period

• 3.

% of Tech

.O Spec Limit I

C.

Particulates 1.

Particulates Ci 3.05E-02 2.10E-03 1.00E+02 l

with half-lives 8

days 2.

Average uCi/sec 3.84E-03 2.64E-04 Release Rate For l

Period 3.

% of Tech l

Spec Limit 4.

Gross Alpha Ci 5.21E-06 3.63E-06 Radioactiv-ity D.

Tritium 1.

Total Ci 3.48E+00 2.73E+00 9.00E+01 l

Release l

2.

Average uCi/sec 4.38E-01 3.43E-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 2-76..... -.

TABLE 2-2b E.

I.

HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES E.

I.

Hatch Unit Quarter Quart ar Est. Total Nuclear Plant 3

4 Error %

A.

Fission &

Activation Gases 1.

Total Ci 2.62E+02 2.01E+03 1.00E+02 Release 2.

Average uCi/sec 3.30E+01 2.53E+02 Release Rate For Period

• 3.

% of Tech Spec Limit B.

Iodines 1.

Total Ci 7.14E-05 2.79E-03 1.10E+02 Iodine-131 2.

Average uCi/sec 8.98E-06 3.51E-04 Release Rate For Period

• 3.

% of Tech D

Spec Limit j

C.

Particulates 1.

Particulates Ci 2.91E-02 6.37E-04 1.00E+02 l

with half-lives 8

days 2.

Average uCi/sec 3.66E-03 8.01E-05 Release Rate Por Period

• 3.

% of Tech Spec Limit 4.

Gross Alpha ci 2.05E-06 2.18E-06 Radioactiv-ity D.

Tritium 1.

Total Ci 7.65E+00 1.21E+00 9.00E+01 Release 2.

Average uCi/sec 9.62E-01 1.52E-01 Release Rate For Period

• 3.

% of Tech

/ )

Spec Limit l

x_/

l l

• 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. -

TABLE 2-2c E.

I.

HATCH NUCLEAR PLANT - SITE SE :I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985

[d')

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 7.00E+02 1.10E+04 1.00E+02 Release 2.

Average uCi/sec 8.81E+01 1.3dE+03 Release Rate For Period

• 3.

% of Tech Spec Limit B.

Iodines 1.

Total Ci 2.65E-04 5.23E-03 1.10E+02 Iodine-131 2.

Average uCi/sec 3.33E-05 6.58E-04 Release Rate For Period g

• 3.

% of Tech

,(

)

Spec Limit C.

Particulates 1.

Particulates Ci 5.96E-02 2.74E-03 1.00E+02 with half-lives 8

days 2.

Average uCi/sec 7.50E-03 3.45E-04 Release Rate For Period

• 3.

% of Tech Spec Limit 4.

Gross Alpha Ci 7.26E-06 5.81E-06 Radioactiv-ity D.

Tritium 1.

Total Ci 1.llE+01 3.94E+00 9.00E+01 Release 2.

Average uCi/sec 1.40E+00 4.96E-01 Release Rate For Period

• 3.

% of Tech O(T Spec Limit i

• 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..

TABLE 2-3a E.

I.

HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GASEOUS EFFLUENTS - ELEVATED RELEASE

• Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.

Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 2.78E+01 2.61E+01 Kr-87 Ci 1.52E+00 1.33E+01 Kr-88 Ci 3.14E+01 2.31E+01 Xe-133 Ci 1.58E+02 6.70E+02 Xe-135 Ci 2.97E+01 2.09E+02 Xe-135m Ci 1.93E+00 8.90E+00 Xe-138 Ci 1.06E+00 1.66E+01 Xe-131m Ci 0.00E+00 2.94E+00 Xe-133m Ci 0.00E+00 1.09E+01 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 9.05E+00 7.65E+00 TOTAL FOR PERIOD Ci 2.60E+02 9.88E+02 2.

Iodines I-131 Ci 7.00E-05 2.14E-03 s.

I-133 Ci 1.34E-04 5.35E-04 I-135 Ci 2.63E-05 4.74E-05 TOTAL FOR PERIOD Ci 2.30E-04 2.72E-03 3.

Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 2.85E-08 1.10E-07 Sr-89 Ci 3.33E-04 4.63E-04 Sr-90 Ci 0.00E+00 4.94E-07 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 1.65E-08 9.00E-07 Ba-140 Ci 1.36E-05 1.52E-05 La-140 Ci 3.71E-06 9.10E-06 TOTAL POR PER'OD Ci 3.50E-04 4.89E-04

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

See Table 2-8 for tfpical lower limits of detection for gaseous sample analyses.

• • The're are no batch mode radioactive gaseous release pathways at Plant Hatch. - - -.

TABLE 2-3b E.

I.

HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GASEOUS EFFLUENTS - ELEVATED RELEASE *

()

Continuous Mode Batch Mode **

Nuclides Released Unit Guarter 3 Quarter 4 Quarter 3 Quarter 4 1.

Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 2.78E+01 2.61E+01 Kr-87 Ci 1.52E+00 1.33E+01 Kr-88 Ci 3.14E+01 2.31E+01 Xe-133 Ci 1.58E+02 6.70E+02 Xe-135 Ci 2.97E+01 2.09E+02 Xe-135m Ci 1.93E+00 8.90E+00 Xe-138 Ci 1.06E+00 1.66E+01 Xc-131m Ci 0.00E+00 2.94E+00 Xe-133m Ci 0.00E+00 1.09E+01 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 9.05E+00 7.65E+00 TOTAL FOR PERIOD Ci 2.60E+02 9.88E+02 2.

Iodines I-131 Ci 7.00E-05 2.14E-03 I-133 Ci 1.34E-04 5.35E-04 I-135 Ci 2.63E-05 4.74E-05 TOTAL FOR PERIOD Ci 2.30E-04 2.72E-03 3.

Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 2.85E-08 1.10E-07 St-89 Ci 3.33E-04 4.63E-04 Sr-90 Ci 0.00E+00 4.94E-07 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 1.65E-08 9.00E-07 Ba-140 Ci 1.36E-05 1.52E-05 La-140 Ci 3.71E-06 9.10E-06 TOTAL FOR PERIOD Ci 3.50E-04 4.89E-04

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

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

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

TABLE 2-3c E.

I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GASEOUS EFFLUENTS - ELEVATED RELEASE *

,~

\\msl Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.

Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 5.55E+01 5.22E+01 Kr-87 Ci 3.03E+00 2.66E+01 Kr-88 Ci 6.27E+01 4.61E+01 Xe-133 Ci 3.16E+02 1.34E+03 Xe-135 Ci 5.93E+01 4.17E+02 Xe-135m Ci 3.85E+00 1.77E+01 Xe-138 Ci 2.llE+00 3.32E+01 Xt-131m Ci 0.00E+00 5.88E+00 Xe-133m Ci 0.00E+00 2.17E+01 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 1.81E+01 1.53E+01 TOTAL FOR PERIOD Ci 5.21E+02 1.98E+03 2.

Iodines n

(

)

I-131 Ci 1.39E-04 4.28E-03 I-133 Ci 2.67E-04 1.07E-03 I-135 Ci 5.26E-05 9.48E-05 TOTAL FOR PERIOD Ci 4.59E-04 5.44E-03 3.

Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 5.70E-08 2.20E-07 l

Sr-89 Ci 6.65E-04 9.26E-04 l

Sr-90 Ci 0.00E+00 9.88E-07 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 3.29E-08 1.80E-06 Ba-140 Ci 2.72E-05 3.03E-05 La-140 Ci 7.41E-06 1.81E-05 TOTAL FOR l

PERIOD Ci 7.00E-04 9.77E-04 f' )

• Zeroes in this table indicate that no radioactivity was present

'N /

above detectable levels.

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

I

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

TABLE 2-4a E.

I.

HATCH NUCLEAR' PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 4

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 Ci 1.71E+02 0.00E+00 Kr-85m Ci 1.55E-02 0.00E+00 Kr-87 Ci 9.73E-02 0.00E+00 Kr-88 Ci 5.70E-02 0.00E+00 Xe-133 Ci 1.68E+00 7.98E+03 Xe-135 Ci 2.27E+00 3.15E+01 Xe-135m Ci 9.79E-02 0.00E+00 Xe-138 Ci 4.85E-01 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 9.85E-01 0.00E+00 l

Ar-41 Ci 2.79E-02 0.00E+00 TOTAL FOR PERIOD Ci 1.77E+02 7.98E+03 i

2.

Iodines

)

I-131 Ci 1.24E-04 2.95E-04 I-133 Ci 5.91E-05 8.39E-05 I-135 Ci 0.00E+00 0.00E+00 l

TOTAL FOR PERIOD Ci 1.83E-04 3.79E-04 i

3.

Particu-lates Cr-51 Ci 2.54E-04 2.85E-04 Mn-54 Ci 5.60E-06 4.32E-05 Co-58 Ci' l.86E-05 4.14E-05 Co-60 Ci 2.62E-04 1.09E-04 Zn-65 Ci 2.82E-04 8.09E-04 Sr-89 Ci 2.23E-04 2.54E-04 Sr-90 Ci 0.00E+00 1.10E-06 Nb-95 Ci 0.00E+00 2.43E-06 Cs-134 Ci 3.85E-05 9.92E-06 Cs-137 Ci 4.66E-04

'5.00E-05 Ba-140 Ci 0.00E+00 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.55E-03 1.61E-03 O

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

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

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

-..-- ~

TADLE 2-4b UNIT 2 E.

I.

HATCH NUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GROUND-LEVEL RELEASES

• GASEOUS EFFLUENTS

/~s Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 1.

Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133 Ci 0.00E+00 9.79E+02 Xe-135 Ci 1.37E+00 4.36E+01 Xe-135m Ci 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.37E+00 2.00E+03 2.

Iodines

[

j.\\-)

I-131 Ci 1.93E-06 6.46E-04 I-133 Ci 8.25E-06 1.90E-04 i

I-135 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.02E-05 8.36E-04 3.

Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 0.00E+00 0.00E+00 Sr-89 Ci 1.03E-04 1.45E-04 Sr-90 Ci 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 l

Cs-134 Ci 0.00E+00 0.00E+00 I

Cs-137 Ci 0.00E+00 3.04E-06 Ba-140 Ci 6.23E-07 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.04E-04 1.48E-04

)

• Zeroer in this table indicate that no radioactivity was present above detectable levels.

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

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

l L

-~

TABLE 2-4c E.

I.

HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES *

(]

\\

Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 4

1.

Fission Gases Kr-85 Ci 1.71E+02 0.00E+00 Kr-85m Ci 1.55E-02 0.00E+00 Kr-87 Ci 9.73E-02 0.00E+00 Kr-88 Ci 5.70E-02 0.00E+00 i

Xe-133 Ci 1.68E+00 8.96E+03 Xe-135 Ci 3.64E+00 7.51E+01 Xe-135m Ci 9.79E-02 0.00E+00 Xe-138 Ci 4.85E-01 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 9.85E-01 0.00E+00 Ar-41 Ci 2.79E-02 0.00E+00 TOTAL FOR PERIOD Ci 1.78E+02 9.04E+03 2.

Iodines I p)

I-131 Ci 1.26E-04 9 41E-04

,(,

I-133 Ci 6.74E-05 2.74E-04 I-135 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.93E-04 1.21E-03 I

3.

Particu-lates Cr-51 Ci 5.13E-04 2.85E-04 Mn-54 Ci 1.63E-05 4.32E-05 Co-58 Ci 4.04E-05 4.14E-05 Co-60 Ci 1.59E-04 1.09E-04 Zn-65 Ci 4.61E-04 8.09E-04 Sr-89 Ci 2.23E-04 3.99E-04 Sr-90 Ci 0.00E+00 1.10E-06 Nb-95 Ci 0.00E+00 2.43E-06 Cs-134 Ci 3.08E-05 9.92E-06 Cs-137 Ci 2.24E-04 5.30E-05 Ba-140 Ci 6.23E-07 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 1.67E-03 1.75E-03 O

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

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

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

TABLE 2-5

<~

E.

I.

HATCH NUCLEAR PLANT - SITE (g)

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 GASEOUS EFFLUENTS DOSE RATES Dose Rates Due to Noble Gases Organ Tech Unit Quarter

% of Quarter

% of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Total 500 mrem /yr 2.57E-02 5.14E-03 2.39E+00 4.78E-01 Body Skin 3000 mrem /yr 2.52E-01 8.40E-03 5.62E+00 1.87E-01 Dose Rates Due to Radioiodine, Tritium, and Particulates Organ Tech Unit Quarter

% of Quarter

% of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Bone 1500 mrem /yr 3.33E-04 2.22E-05 4.29E-04 2.86E-05 O

~ Total 1500 mrem /yr 1.02E-02 6.80E-04 3.55E-03 2.37E-04 T,iver 1500 mram/yr 1.04E-02 6.93E-04 3.62E-0.3 2.41E-04 Body Thyroid 1500 mrem /yr 1.21E-02 8.07E-04 1.84E-02 1.23E-03 Kidney 1500 mrem /yr 1.02E-02 6.80E-04 3.59E-03 2.39E-04 Lung 1500 mrem /yr 1.20E-02 8.00E-04 5.68E-03 3.79E-04 GI-LLI 1500 mrem /yr 1.02E-02 6.80E-04 3.54E-03 2.36E-04 i

{

llO l

1 _ _ _ _

-....-.n

TABLE 2-6a UNIT 1 E.

I.

HATCH AUCLEAR PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 AIR DOSES DUE TO NOBLE GAS RELEASES

-1 V Cumulative Doses Per Quarter Type Tech Unit Quarter

% of Quarter

% of of Spec 3

Tech 4

Tech Radi-Limit Spec Spec ation Limit Limit t

Gamma 5.0 mrad 4.85E-03 9.70E-02 6.22E-01 1.24E+01 Beta 10.0 mead 8.32E-02 8.32E-01 1.83E+00 1.83E+01 Cumulative Doses Per Year Type of Tech Unit Quarters

% of Tech Radiation Spec 3 & 4 Spec Limit Limit Gamma 10.0 mrad 6.27E-01 6.27E+00 Beta 20.0 mrad 1.91E+00 9.55E+00 I

h f

\\

TABLE 2-6b E.

I.

HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 i

AIR DOSES DUE TO NOBLE GAS RELEASES l-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 1.98E-03 3.96E-02 9.50E-02 1.90E+00 Beta 10.0 mead 2.llE-03 2.11E-02 2.50E-01 2.50E+00 Cumulative Doses Per Year Type of Tech Unit Quarters

% of Tech Radiation Spec 3 & 4 Spec Limit Limit Gamma 10.0 mrad 9.70E-02 9.70E-01 Beta 20.0 mrad 2.52E-01 1.26E+00

.4

,i l

O

..~--

TABLE 2-7a E.

I.

HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 fm.

INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM,

(

AND PARTICULATES IN GASEOUS RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter

% of Quarter

% of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 2.56E-03 3.41E-02 1.llE-03 1.46E-02 Liver 7.5 mrem 3.06E-03 4.08E-02 1.73E-03 2.31E-02 Tot. Body 7.5 mrem 1.15E-03 1.53E-02 9.20E-04 1.23E-02 Thyroid 7.5 mrem 1.05E-02 1.40E-01 6.89E-02 9.19E-01 Kidney 7.5 mrem 1.53E-03 2.04E-02 1.12E-03 1.49E-02 Lung 7.5 mrem 1.08E-03 1.44E-02 4.26E-04 5.68E-03 GI-LLI 7.5 mrem 1.13E-03 1.51E-02 1.17E-03 1.56E-02 4

Cumulative Dose Per Year Organ Tech Unit Quarters

% of Tech Spec 3 & 4 Spec Limit Limit Bone 15.0 mrem 3.67E-03 2.45E-02 1.

Liver 15.0 mrem 4.79E-03 3.19E-02 i

Total Body 15.0 mrem 2.07E-03 1.38E-02 Thyroid 15.0 mrem 7.94E-02 5.29E-01 Kidney 15.0 mrem 2.65E-03 1.77E-02 Lung 15.0 mrem 1.51E-03 1.00E-02 GI-LLI 15.0 mrem 2.30E-03 1.53E-02 l

i l

l L

l l

l

!o i

TABLE 2-7b E.

I.

HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1985 INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM, c3 AND PARTICULATES IN GASEOUS RELEASES Cumulative Dose Per Quarter

~

Organ Tech Unit Quarter

% of Quarter

% of Spec 3

Tech 4

Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 1.77E-04 2.36E-03 4.93E-04 6.57E-03 Liver 7.5 mrem 4.37E-04 5.83E-03 3.55E-04 4.73E-03 Tot. Body 7.5 mrem 4.38E-04 5.84E-03 2.08E-04 2.77E-03 Thyroid 7.5 mrem 2.21E-03 2.95E-02 9.llE-02 1.21E+00 Kidney 7.5 mrem 4.37E-04 5.83E-03 1.77E-03 2.36E-02 Lung 7.5 mrem 4.36E-04 5.81E-03 7.30E-05 9.73E-04 GI-LLI 7.5 mrem 4.35E-04 5.80E-03 8.01E-05 1.07E-03 Cumulative Dose Per Year Organ Tech Unit Quarters

% of Tech Spec 3 & 4 Spec Limit Limit C

Bone 15.0 mrem 6.70E-04 4.47E-03 Liver 15.0 mrem 7.92E-04 5.28E-03 Total Body 15.0 mrem 6.49E-04 4.33E-03 Thyroid 15.0 mrem 9.33E-02 6.22E-01 Kidney 15.0 mrem 2.21E-03 1.47E-02 Lung 15.0 mrem 5.09E-04 3.39E-03 GI-LLI 15.0 mrem 5.15E-04 3.43E-03 i

O

. -... ~.. _ _

TABLE 2-8 j

LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES The values in this table represents apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of gaseous radwaste samples.

~

RADIONUCLIDE LLD UNIT d

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-131 4.37E-14 I-133 6.16E-13 Mn-54 2.78E-14 Fe-59 4.62E-14 Co-58 2.46E-14 Co-60 2.88E-14 Zn-65 7.51E-14 Mo-99 6.02E-13 Cs-134 3.64E-14 Cs-137 2.88E-14 Ce-141 4.94E-14 Ce-144 2.02E-13 l*

Sr-89 1.17E-14 Sr-90 3.82E-15 H-3 5.82E-12 l

l O 1

3.

SOLID WASTE 77

\\s-3.1 REGULATORY REQUIREMENTS The Technical Specifications presented in this section are for Unit 1.

Requirements for Unit 2 are the same as for Unit 1; however, the Technical Specification numbers are not the same.

TECHNICAL SPECIFICATIONS 3.15.3.1 The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure 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 Effluents Release Report shall include the following information for each type of solid waste shipped offsite during the report period:

a.

Container volume

)

b.

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

(

c.

Principal radionuclides (specify whether determined by measurement or estimate)

I 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.

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

O l

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TABLE 3-la July 1 December 31

/~N EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1985 lh SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I & II SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) l l

l l

l l

1. Type of waste l

UNIT l 6 month lEst. Totall l

l I Deriod l ERROR % l l

a. Spent resins, filter studges, evaporator l m3 12.53E+2l l

~

l bottoms etc.

I Ci il.32EtJi1.00 E+1l l

b. Dry compressible waste, contaminated l

m3 17.84E+2 l

l eQlli D. etc.

l Ci il.48E+1 2.00 E+1l l

c. Irradiated components, control rods, l

m3 l.48E0 l l

l e tt;.

I Ci 7. 9 7 E + 12. 0 0 E+l l

d. Other solidified oil, oil trash; m3 1.03E+2l l

eGuiD.

ispeedy dry mix & CRD' Filters Ci I 3.29E01 2.00 E+1 2.

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

l 1

l a.

Zn-65 42.74 l

l Cr-51 21.89 l

l Co-60 12.48 l

l All others 22.89 l

)

l b.

Co-60 42.13

_l U

l Zn-65 26.07 l

l Cs-137 12.88 l

l All others 18.92 l

l c.

Co-60 52.52 l

l Fe-55 41.76 l

l Mn-54 2.89 l

l All others 2.83 l

l d.

Co-60 64.98 l

l Zn-65 25.09 l

l Ni-63 3.71 l

l Cs-137 0.83 l

l All others 5.39 l

3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination 47 Cask Barnwell,S.C.

27 Van Barnwell,S.C.

5 Van Hanford, Wash.

l 4.

Irradiated Fuel Shipments (Disposition) p Number of Shipments Mode of Transportation Destination 0

NA NA l

,z ~3 f

/

I

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JULY 1 - DECEMBER 31 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENT-FOR UNIT I a 11 TABLE 3-1B TYPE OF CURIE PRINCIPLE BURIAL NUMBER OF VOLUME OF TYPE WASTE

@JWTI1N NUCLIDES CONTAINgR CONTAINERS EACH CON-SHIPPING DETuptINATR24 DETERMINATION DESCRIPTION SNIPPED TAINER Ft3 CONTAINER DEWATERED MEASURED MEASURED CARBON STEEL 33 200 LSA, TYPE A RESIN LINER DEWATERED MEASURED MEASURED HIGH INTEGRITY 9

195 LSA, TYPE A

, RESIN CONTAINER (Poly)

DEWATERED MEASURED MEASURED HICH INTEGRITY 4

121 LSA, TYPE 8 RESIN CONTAINER (Poly)

DEWATERED MEASURED MEASURED FIBERGLASS 4

19 LSA. TYPE A RESIN REINFORCED VESSEL DRY ACTIVE ESTIMATED ESTIMATED B-25 Som 136 92 LSA, STRONG WASTE (DAW)

(Steel)

TICHT CONTAINER DAW ESTIMATED ESTEMATED S-25 Bou 81 90 LSA,STC (Steel)

DAW ESTEMATED ESTEMATED s-25 1

137 LS A, STC OVERPACE(Steel)

DAW ESTIMATED ESTIMATED S-25 4

134 LSA,STC OVERPACE(Steel)

I DAW ESTIMATED ESTIMATED B-25 9

112 LSA.STC 4.

OVERPACE(Steel)

'd DAW ESTIMATED ESTIMATED B-25 1

126 LSA.STC I

OVERPRCE(Steel)

DAW ESTEMATED ESTIMATED B-144 4

248 LSA,STC BOX (Steel)

DAW ESTIMATED ESTIMATED S-88 6

100 LSA.STC BOX (Steel)

DAW ESTEMATED ESTIMATED S-85 6

109 LS A, S TC BOX (Steel)

DAW ESTIMATED ESTIMATED S-87-6 2

118 LS A STC SOX (Steel)

DAW ESTIMATED ESTEMATED BOE STRONG TIGHT 2

115 LS A, S TC CONTAINER (Steel)

DAW ESTIMATED ESTIMATED OVERPACE 10 222 LSA.STC CONTAINER (Steel)

DAW ESTEMATED ESTIMATED OVERPACE 1

375 LSA,STC CONTAINER (Steel)

DAW ESTIMATED ESTIMATED DRUM (NIC) 2 1/2*

40.2 LSA,STC OVERPACE(Poly)

• CRD ESTIMATED ESTIMATED DRUM (NIC) 1/2*

40.2 LS A, T Y P E A FILTERS OVERPACE(Poly)

IRRADIATED ESTIMATED MEASURED CARBON STEEL 2

26.2 FSV-1 TYPE B COM PON E NTS LINER CONTAINER

• • OTHER ESTIMAT&D ESTIMATED DOT 17 H(Steel) 452 7.5 LS A, 7A (Ostp DRUM TYPE A

• SulaJatied wath cement

• • Oa! was either solidified with cement or absorbent material.

_ =-

4.

CHANGES TO THE PLANT HATCH ODCM Technical Specification 6.9.1.8 requires in part that changes to the Plant Hatch Offsite Dose Calculation j d Manual (ODCM) be reported to the Commission in the next Semiannual Effluent Release Report.

On November 8,

1985, the Plant Hatch ODCM was reissued in a revised format.

The contents of the ODCM were j

not changed.

The Plant Hatch ODCM in the revised format will be furnished to the Commission under separate cover.

i s

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5.

METEOROLOGY In accordance with Technical Specification 6.9.1.9, the annual summary of meteorological data collected at Plant Hatch over 1985 is presented in this section.

5.1 REVIEW OF 1985 DATA The second year of Plant Hatch meteorological data was collected on the new level primary tower during 1985.

The wind speed and direction data of all three levels (10m, 60m, 100m) are shown in Attachments 5-4 through 5-6.

The wind roses agree quite well between levels.

They all have a predominant wind direction of northeast with a secondary peak of a westerly wind direction.

This agreement is prevalent in the quarterly wind roses as well, particularly during the third and fourth qu6rters with a high percentage of northeast winds.

The wind directions generally agree with previous years when the west and northeast winds have been dominant.

However, in 1984 the winds were more from the southwest.

This slight shift is due to normal year to year climatic variations in wind direction.

The high percentage of northeast winds may have caused by the large number of storms moving up the east coast during the fall.

The ambient and dew point temperature date (10m level) for 1985 are shown in Attachment 5-7.

The temperatures were normal when compared with previous years.

They reflect the fact that the temperatures were well above average for the month of June.

As with the 1984 data, the summertime temperatures are a few degrees lower than the average for the early 1980's.

Since data collection began on the new meteorological tower in 1982, this has occurred each year.

The joint frequency tables of wind speed and direction versus delta temperature (Attachments 5-1 through 5-3) continue to show some differences with previous years tables.

The elevation difference between the new and old meteorological towers 164 feet versus 117 feet is responsible for the shift from unstable toward neutral conditions. l

J The following table shows the latest 5 year stability classifications.

Plant Hatch Stability Classification Stability

% Stability Group Year 1985 1984 1983 1982 1981 5-year Average A

9.3 8.4 14.7 16.7 c1.7 14.2 8

4.7 5.2 5.2 3.8 5

4.7 C

5.5 5.8 3.8 2.3 2.0 3.9 D

26.5 19.9 21.9 20.8 19.0 21.6 E

31.8 31.8 33.8 34.3 29.1 32.2 F

11.3 12.4 11.3 14.8 11.7 12.3 G

10.9 16.5 9.3 7.8 11.9 11.3 Total Hours 7860 7928 7468 7725 7944 l

i The total precipitation for 1985 was about 28 inches.

As in the past, this is well below local climatic averages of about 45 inches. The 28 inches is close to the Hatch average precipitation totals of previous j

years.

O 1

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

" Joint Frequency Tables of Wind Speed and Wind Direction 60m vs. Delta Temperature 60-10m. Joint Frequency Tables of Wind Speed and Wind Direction 100m vs. Delta Temperature 100-10m. Wind Roses from 10m (seasonal and annual).

' Wind Roses from 60m (seasonal and annual). Wind Roses from 100m (seasonal and annual). Plots of Monthly Averages and Averages of Daily Extremes of Ambient Temperature and Dew Point l

Temperature. Monthly and Annual Precipitation for 1985.

. Daily Precipitation for the Period of January through December 1985.

s M

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()

ATTACHMENT 5-1 i

PlantHatchJointFrequencyTabiesofWindSpeedand Wind Direction 10m versus Delta Temperature 60-10m 1/1/85 - 12/31/85 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

8S010101-85123124 STABILITY CLASS:

A DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

1 7

3 0

0 0

11 i

NNE O

20 9

0 0

0 29 NE 1

62 44 0

0 0

107 ENE 3

30 10 0

0 0

43

_)

E 2

15 4

0 0

0 21 ESE 2

19 8

0 0

0 29 SE 2

25 9

0 0

0 36 SSE 3

17 9

0 0

0 29 S

0 14 18 1

0 0

33 SSU 1

29 23 7

0 0

60 SU 0

36 26 0

0 0

62 USU 1

36 39 1

0 0

77 U

1 31 42 2

0 0

76 UNU 0

22 27 3

0 0

S2 NU 2

24 22 3

0 0

S1 NNU 1

9 5

3 0

0 18

_______________________________.4-_..

TOTAL 20 396 29 20 0

0 734 PERIODS OF CALM (HOURS):

0 UARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 0.

ATTACHMENT 5-la r

s(

l HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

8S010101-85123124 STABILITY CLASS:

B DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 UIND SPEED (MPH)

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

>24 TOTAL N

1 6

2 0

0 0

9 NNE O

13 1

0 0

0 14 NE 2

33 13 0

0 0

48 l

ENE O

10 5

0 0

0 15 E

O 15 3

0 0

0 18 ESC 2

10 3

0 0

0 15 l

SE O

10 3

0 0

0 13 SSE O

9 3

0 0

0 12 l

S 1

9 10 0

0 0

20 L?

SSU 0

15 8

0 0

0 23 1-SU 1

20 14 0

0 0

35 l

USU 1

22 13 1

0 0

37 l

U 3

17 10 2

0 0

32 UNU 2

14 17 0

0 0

33 NU 3

18 6

0 0

0 27 NNU 1

17 0

0 0

0 18 TOTAL 17 238 111 3

0 0

369 PERIOD 5 OF CALM (HOURS):

0 l

VARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 0

ATTACHMENT 5-lb Ob HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

C DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

1 9

1 0

0 0

11 NNE 1

13 2

0 0

0 16 NE 5

30 8

0 0

0 43 ENE 2

20 4

0 0

0 26 E

2 9

3 0

0 0

14 ESE O

19 2

0 0

0 21 SE 2

7 1

0 0

0 10 l

SSE 2

12 4

0 0

0 18 S

5 20 7

0 0

0 32 SSU 1

18 11 1

0 0

31 SU 3

27 10 1

0 0

41 USU 0

18 7

1 0

0 26 U

1 25 19 2

0 0

47 UNU 0

23 16 1

0 0

40 NU 2

19 5

1 0

0 27 NNU 4

19 4

0 0

0 27 TOTAL 31 288 104 7

0 0

430 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 l

ATTACHMENT 5-1c O

HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

D DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

10 51 6

0 0

0 67 NNE 10 63 7

0 0

0 80 NE 29 129 71 0

0 0

229 ENE 24 124 14 0

0 0

162 E

19 54 11 0

0 0

84 ESE 23 53 8

0 0

0 84 O~

SE 20 63 15 1

0 0

99 SSE 21 42 13 0

0 0

76 S

14 68 26 1

0 0

109 SSU 15 94 38 3

0 0

150 SU 21 102 35 1

0 0

159 l

USU 18 99 19 0

0 0

136 l

U 20 113 43 5

0 0

181 UNU 13 106 57 0

0 0

176 NU 18 102 40 2

0 0

162 NNU 15 87 24 1

0 0

127 TOTAL 290 1350 427 14 0

0 2081 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 0.--

()

ATTACHMENT 5-1d HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 l

STABILITY CLASS:

E DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

14 31 1

0 0

0 46 NNE 25 35 1

0 0

0 61 NE 64 203 31 0

0 0

298 ENE 65 102 12 0

0 0

179 E

68 62 5

0 0

0 135 ESE 76 67 10 2

0 0

155 SE 75 123 14 0

0 0

212

.s SSE 55 109 11 0

1 0

176 S

52 130 10 1

1 0

194 SSU 39 133 21 1

0 0

194 SU 45 137 26 1

0 0

209 USU 34 73 14 0

0 0

121 U

33 106 26 1

0 0

166 UNU 28 64 22 1

0 0

115 NW 21 96 24 0

0 0

141 NNU 16 67 15 0

0 0

98 TOTAL 710 1538 243 7

2 0

2500 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 0.

ATTACHMENT 5-le HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

F DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

10 4

0 0

0 0

14 NNE 10 15 0

0 0

0 25 NE 32 62 5

0 0

0 99 ENE 47 22 0

0 0

0 69 E

57 13 0

0 0

0 70 ESE 35 9

1 0

0 0

45 SE 29 14 1

0 0

0 44

\\-

SSE 32 22 0

0 0

0 54 S

32 42 1

0 0

0 75 SSU 28 36 7

0 0

0 71 SU 33 40 8

0 0

0 81 USU 43 41 1

0 0

0 85 W

32 20 4

0 0

0 56 UNU 20 19 1

0 0

0 40 NU 13 24 1

0 0

0 38 NNU 9

12 0

0 0

0 21 TOTAL 462 395 30 0

0 0

887 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 O

(}

ATTACHMENT 5-lf HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

G DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

15 6

0 1

0 0

22 NNE 10 1

0 0

0 0

11 NE 20 15 2

0 0

0 37 ENE 25 14 1

0 0

0 40 E

33 3

1 0

0 0

37 ESE 16 10 0

0 0

0 26 4 '()

SE 25 6

0 0

0 0

31 SSE 25 7

0 0

0 0

32 S

39 19 1

0 0

0 59 SSU 82 50 4

0 0

0 136 l

SU 97 40 3

0 0

0 140 USU 92 27 1

0 0

0 120 W

82 18 0

0 0

0 100 UNU 19 11 0

0 0

0 30 NU 12 10 1

0 0

0 23 NNU 10 5

0 0

0 0

15 TOTAL 602 242 14 1

0 0

859 PERIODS OF CALM (HOURS):

0 UARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 I

O.--.

O

~

ATTACHMENT 5-1g HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

ALL DT/DZ ELEVATION:

' SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT60 WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

52 114 13 1

0 0

180 NNE 56 160 20 0

0 0

236 NE 153 534 174 0

0 0

861 ENE 166 322 46 0

0 0

534 E

181 171 27 0

0 0

379 O

ESE 154 187 32 2

0 0

'375 SE 153 248 43 1

0 0

445 SSE 138 218 40 0

1 0

397 S

143 302 73 3

1 0

522 SSU 166 375 112 12 0

0 665 SW 200 402 122 3

0 0

727 USU 189 316 94 3

0 0

602 U

172 330 144 12 0

0 658 UNU 82 259 140 5

0 0

486 NU 71 293 99 6

0 0

469 NNU 56 216 48 4

0 0

324 TOTAL 2132 4447 1227 52 2

0 7860 E-i6656-CEE~i66iiii-~~~~5-~~~~~~~~~~~~~~~~~~~~~~~~~~~~

VARIABLE DIRECTION O

HOURS OF MISSING DATA:

900 l

l O

U ATTACHMENT 5-2 i

Plant Hatch Joint Frequency Tables of Wind Speed and Wind Direction 60m versus Delta Temperature 60-10m 1/1/85 - 12/31/85 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

8S010181-85123124 STABILITY CLASS:

A DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

O 2

4 1

0 0

7 NNE 3

3 6

5 0

0 17 NE O

16 52 29 2

0 99 ENE O

17 36 5

1 0

59 E

1 7

21 4

0 0

33 ESE O

8 14 5

0 0

27 SE O

8 10 1

0 0

19 SSE O

9 18 1

0 0

28 S

0 12 13 11 1

0 37 SSU 0

2 21 21 7

6 51 SU 0

5 29 22 4

0 60 USU 0

1 29 35 4

0 69 U

0 3

33 37 11 1

85 UNU 0

5 23 16 7

8 51 NU 1

5 18 9

2 0

35 NNU 0

4 4

4 0

0 12 TOTAL 5

107 331 206 39 1

689 1

PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOUR 5 0F MISSING DATA:

1339

!O l --

. - ~

O ATTACHMENT 5-2a 1

HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

8S010101-8S123124 STABILITY CLASS:

B DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 UIND SPEED (MPH)

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

>24 TOTAL N

O 6

3 0

0 0

9 NNE 1

3 1

1 0

0 6

NE O

7 21 7

0 0

35 ENE O

6 17 4

0 0

27 E

O 7

6 3

0 0

16

(~'

ESE O

7 11 2

0 0

20

.\\

SE O

4 4

2 0

0 10 SSE O

3 7

1 0

0 11 S

0 5

9 5

0 0

19 SSU 0

6 11 7

1 0

25 SU 0

8 10 8

0 0

26 USU 0

6 18 10 5

2 41 U

1 7

16 9

4 2

39 UNU 1

7 16 7

0 0

31 NU 0

6 12 3

0 0

21 NNU 1

6 7

1 0

0 15 TOTAL 4

94 169 70 10 4

351 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1339

2 ATTACHMENT 5-2b HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010181-85123124 STABILITY CLASS:

C DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

1 5

3 1

0 0

10 NNE O

5 3

0 0

0 8

NE O

16 24 4

0 0

44 ENE 1

15 18 0

0 0

34 E

O 3

13 3

0 0

19 ESE O

8 8

1 0

0 17 SE 1

6 3

0 0

0 10 SSE O

12 7

2 0

0 21 O

S 1

12 15 1

1 0

30 SSU 0

6 10 12 2

0 30 SU 0

3 10 10 0

0 23 USU 2

9 19 4

0 1

35 U

0 9

20 13 4

3 49 UNU 0

16 16 6

0 0

38 NU 1

12 9

0 0

0 22 TOTAL 7

147 183 59 7

4 407 PERIODS OF CALM (HOURS):

0 l

UARIABLE DIRECTION O

HOURS OF MISSING DATA:

1339

.O l

l._

i

%)

ATTACHMENT 5-2c HOUR 5 AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

D DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 UIND SPEED (MPH)

WIND i

DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

2 38 29 13 1

0 83 1

NNE 3

27 10 2

0 0

42 NE 5

42 107 50 9

0 213 i

ENE 3

69 58 20 1

0 151 l

E 5

45 54 15 1

0 120 ESE 4

33 40 13 0

0 90 SE 5

29 24 7

0 0

65 l

SSE 3

26 32 7

0 0

68 S

3 36 48 23 2

0 112 SSU 7

47 54 32 3

1 144 SU 3

48 61 34 5

0 151 USU 3

49 62 20 6

5 145 U

7 47 74 32 14 2

176 UNU 9

42 80 45 6

0 182 NU 6

57 40 16 5

0 124 NNU 4

45 50 2

1 0

102 TOTAL 72 680 823 331 54 8

1968 Eiii55i5ECEEsis55iii?-~~~~5-~~~~~~~~~~~~~~~~~~~~~~~~~

VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1339 O. -.--

O ATTACHMENT 5-2d HOUR 5 AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

E DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 WIND SPEED (MPH)

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

>24 TOTAL N

1 19 16 5

1 0

42 NNE 5

14 23 15 4

0 61 NE 7

33 108 71 0

0 219 O

ENE 3

48 98 29 2

0 180 E

8 36 88 13 0

0 145 ESE 18 35 84 13 6

2 158 SE 4

53 130 8

0 0

195 SSE O

33 105 18 1

1 158 S

9 50 112 22 2

1 196 SSU 4

27 112 38 3

1 185 SU 6

26 97 33 1

0 163 USU 2

27 70 31 1

0 131 W

3 24 80 70 1

1 179 UNU 2

26 48 25 3

0 104 NU 2

15 67 30 0

0 114 NNU 1

8 54 11 0

0 74 1

TOTAL 75 474 1292 432 25 6

2304 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

l HOURS OF MISSING DATA:

1339 O _ -.

l O

ATTACHMENT 5-2e HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

8S010101-85123124 STABILITY CLASS:

F DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 UIND SPEED (MPH)

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

>24 TOTAL N

2 5

3 1

0 0

11 NNE O

9 6

8 4

0 27 NE A

9 25 25 4

0 63 ENE 1

11 32 4

0 0

54 E

1 9

44 8

0 0

62

's ESE 4

21 48 1

0 0

74 SE 1

25 29 2

0 0

57 SSE O

15 26 7

0 0

48 S

4 16 60 5

0 0

85 SSU 1

10 43 11 0

0 65 SW 1

8 41 9

0 0

59 USU 0

8 46 21 0

0 75 W

0 9

43 20 0

0 72 UNU 1

3 25 4

1 0

34 NU 1

9 26 5

0 0

41 NNU 0

4 14 3

0 0

21 TOTAL 17 171 517 134 9

0 848 PkRkbbSbFbkLMkHbbRb5 b

VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1339 i

O I

3(G ATTACHMENT 5-2f HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

8S010101-8S123124 STABILITY CLASS:

G DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

2 11 10 3

0 0

26 NNE 4

8 8

2 0

0 22 NE 4

12 19 7

1 0

43 ENE 2

12 20 12 0

0 46 E

5 12 15 7

0 0

39 O

ESE 3

24 10 3

0 0

40 SE 6

30 20 1

0 0

S?

SSE 1

20 19 4

0 0

44 S

5 23 20 10 0

0 58 SSU 2

13 18 7

0 0

40 SU 3

12 45 20 0

0 80 USU 1

11 67 25 0

0 104 U

1 18 45 10 0

0 74 UNU 1

13 39 13 1

0 67 i

NU 9

14 37 6

0 0

66 NNU 5

20 20 3

0 0

48 TOTAL 54 253 412 133 2

0 854 l

PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1339 i

lO

, l

I l

ATTACHMENT 5-2g HOURS RT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

ALL DT/DZ ELEVATION:

SPEED:SPD 60 DIRECTION:DIR 60 LAPSE:DT60 WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

8 86 68 24 2

0 188 NNE 16 69 57 33 8

0 183 NE 16 135 3S6 193 16 0

716 ENE 10 178 285 74 4

0 551 E

20 119 241 53 1

0 434 ESE 29 136 215 38 6

2 426 SE 17 155 220 21 0

0 413 O

SSE 4

118 214 40 1

1 378 S

22 154 277 77 6

1 537 SSU 14 111 269 128 16 2

540 SU 13 110 293 136 10 0

562 USU 8

111 311 146 16 8

600 U

12 117 311 191 34 9

674 UNU 14 112 247 116 18 6

507 NU 20 118 209 69 7

0 423 NNU 11 97 154 26 1

0 289 TDTAL 234 1926 3727 1365 146 23 7421 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1339 1

0... _. _ _. _

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

ATTACHMENT 5-3 Plant Hatch Joint Frequency Tables of Wind Speed and Wind Direction 100m versus Delta Temperature 100-10m 1/1/85 - 12/31/85 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

A DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-WIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

0 O

4 0

0 0

4

/~

NNE O

O 3

0 0

0 3

NE O

2 17 15 3

0 37 ENE O

5 6

9 1

1 22 E

O 2

13 3

0 0

18 ESE O

6 8

4 1

0 19 SE 1

1 3

0 0

0 5

SSE O

3 7

5 0

0 15 S

0 0

8 11 3

1 23 SSU 0

3 3

3 1

0 10 SU 0

1 10 1

2 0

14 USU 0

2 10 18 5

1 36 U

0 3

15 17 11 3

49 UNU 1

3 17 14 3

0 38 NU 0

1 19 17 1

0 38 NNU 0

0 2

3 1

0 6

i TOTAL 2

32 145 120 32 6

337 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1684 I

l V - -

O ATTACHMENT 5-3a

't HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

B DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

0 O

O 1

0 0

1 NNE O

1 1

2 1

0 5

NE O

5 11 9

3 0

28 ENE 1

3 13 2

0 0

19 E

O 3

6 2

0 0

11 O

ESE O

1 4

1 0

0 6

SE O

4 1

0

'O O

5 SSE O

4 4

2 0

0 10 i

S 1

3 5

4 3

0 16 SSU 1

2 4

2 1

0 10 SU 0

1 7

6 0

1 15 i

USU 0

2 9

6 4

1 22 U

0 4

7 14 3

0 28 UNU 0

1 4

15 2

0 22 NU 0

3 8

0 1

0 12 j

NNU 0

1 1

3 0

0 5

j TOTAL 3

38 85 69 18 2

215 PERkbbbbhbhLMkHbbkS5I b

UARIABLE DIRECTION 0

HOURS OF MISSING DATA:

1684

' O

(,

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

,,._______,_____L____.__,,_.__..,__,.,.._,,

Ob ATTACHMENT 5-3b HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

C DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-UIND SPEEDCMPH)

UIND i

DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL i

N O

3 3

1 1

0 8

NNE 1

0 3

2 0

0 6

NE O

6 18 13 4

0 41

• O ENE O

2 8

1 1

0 12 E

O 5

5 2

0 0

12 ESE O

1 5

1 0

0 7

l SE O

4 0

0 0

0 4

l SSE O

1 3

1 0

0 5

l S

0 3

7 2

2 0

14 SSU 0

2 3

5 0

1 11 l

SU 0

5 6

11 2

0 24 USU 0

4 14 9

3 0

30 i

U 0

3 12 5

4 0

24 UNU 0

1 10 4

1 0

16 NU 1

3 4

4 0

0 12 NNU 1

4 5

4 0

0 14 l

TOTAL 3

47 106 65 18 1

240 PERIODS OF CALM (HOURS):

0 UARIABLE DIRECTION O

HOURS OF MISSING DATA:

1684 O

! i-

ATTACHMENT 5-3c HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

D DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-i UIND SPEED (MPH)

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

>24 TOTAL N

9 35 32 15 4

0 95 NNE 5

25 26 21 3

0 80 NE 7

47 125 109 33 6

327 ENE 6

58 82 51 5

4 206 E

4 24 65 32 9

0 134 ESE 6'

24 42 17 1

0 90 SE 7

36 40 14 1

0 98 SSE 7

33 36 12 3

0 91 S

8 31 53 47 7

2 148 SSU 4

41 40 53 9

2 149 '

SU 4

37 65 53 10 1

170 i

USU 11 38 81 42 21 2

195 U

8 41 76 58 27 2

212 UNU 5

44 81 56 26 1

213 NU 5

52 52 31 13 2

155 NNU 6

48 54 18 1

0 127 TOTAL 102 614 950 629 173 22 2490 PERIODS OF CALM (HOURS):

0 UARIABLE DIRECTION O

HOURS OF MISSING DATA:

1684 O

1 _ _ _ _ _ _

f^(

ATTACHMENT 5-3d HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

E DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

4 6

18 15 10 0

53 NNE 5

12 20 34 19 5

95 NE 3

29 70 119 51 1

273 ENE 6

18 65 73 24 1

187 E

3 17 58 55 6

0 139 ESE 7

23 69 46 7

2 154 SE 3

37 75 47 5

0 167 SSE 3

15 59 74 2

1 154 S

1 22 86 81 7

2 199 SSU 1

12 58 88 12 0

171 SW 2

20 53 67 10 2

154 USU 2

8 41 86 14 1

152 U

4 11 37 80 20 0

152 UNU 2

9 28 43 10 0

92 NU 2

9 42 54 5

0 112 NNU 1

17 29 17 4

1 69 TOTAL 49 265 808 979 206 16 2323 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1684 0

l.

ATTACHMENT 5-3e HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

F DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-UIND SPEED (PPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

0 3

6 3

1 0

13 NNE O

11 12 8

7 2

40 NE O

12 28 18 23 2

83 ENE 1

10 20 25 4

0 60 O

E 3

8 20 20 6

0 57 ESE 5

9 26 25 0

0 65 SE 7

15 21 10 0

0 53 SSE 2

5 32 16 2

1 58 S

2 14 26 29 3

0 74 SSU 1

6 25 28 10 0

70 SU 2

6 25 26 14 0

73 USU 1

10 32 35 17 8

95 U

2 9

31 31 11 0

84 UNU 1

7 22 19 3

0 52 NU 1

3 14 22 3

0 43 I

NNU 1

11 18 11 0

0 41 1

TOTAL 29 139 358 326 104 5

961 PERIODS OF CALM (HOURS):

0

(

UARIABLE DIRECTION O

I HOURS OF MISSING DATA:

1684

O ATTACHMENT 5-3f HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

G DT/DZ ELEVATION:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-UIND SPEED (MPH)

UIND DIRECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

1 9

5 10 1

0 26 NNE 2

10 8

5 2

0 27 NE 2

2 5

2 5

2 18 ENE 4

8 8

6 7

0 33

( -)

E 1

4 3

7 1

0 16

'~

ESE 3

5 8

6 0

0 22 SE 3

8 16 8

1 0

36 SSE 1

9 8

5 4

0 27 S

0 7

8 6

5 0

26 SSU 0

7 14 3

3 0

27 SU 0

6 10 11 11 0

38 USU 2

9 21 20 5

0 57 U

1 11 11 7

3 0

33 UNU 1

9 17 12 2

0 41 NU 3

10 11 20 5

0 49 NNU 4

5 11 10 4

0 34 TOTAL 28 119 164 138 59 2

510 PERIODS OF CALM (HOURS):

0 VARIABLE DIRECTION 0

HOURS OF MISSING DATA:

1684 O J

ATTACHMENT 5-39 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD =

85010101-85123124 STABILITY CLASS:

ALL DT/DZ ELEVATIGN:

SPEED:SPD 10 DIRECTION:DIR 10 LAPSE:DT100-WIND SPEED (MPH)

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

>24 TOTAL N

14 56 68 45 17 0

200 NNE 13 59 73 72 32 7

256 NE 12 103 274 285 122 11 807 ENE 18 104 202 167 42 6

539 O

E 11 63 170 121 22 0

387 ESE 21 69 162 100 9

2 363 SE 21 105 156 79 7

0 368 SSE 13 70 149 115 11 2

360 S

12 80 193 180 30 5

500 SSU 7

73 147 182 36 3

448 SU 8

76 176 175 49 4

488 USU 16 73 208 216 69 5

587 U

15 82 189 212 79 5

582 UNU 10 74 179 163 47 1

474 NU 12 81 150 148 28 2

421 NNU 13 86 120 66 10 1

296 TOTAL 216 1254 2616 2326 610 54 7076 PkkkbbbbFbALMiHbbRb5:

b~

VARIABLE DIRECTION O

HOURS OF MISSING DATA:

1684 O u

ATTACHMENT 5-4 Plant Hatch Meteorological Tower 10m Wind Annual - 1/1/85 - 12/31/85 t

s I

s I ::

~

WND ROSE

^

(WNDg FRon) o t

n l

r

.WND SPEED LESS THAM 3.5 f1PH

+WND SPEED LESS THAH7.5 NPH xWND SPEED LESS THANf 2.5 HPH s.a rt NE0'ngAS SPEED LESS TNANO.5) ca WND SPEED GREATER THAtt 12.5 NPH (CALMS 4 -. _ _

(a ATTACHMENT 5-4a Plant Hatch Meteorological Tower 10m Wind Rose First Quarter - 1/1/85 - 3/31/85 12 2 g

2 i

2 o

,=p,

=

=

o n

aWIND SPEED LESS THAN3.5 NPH-

, WIND SPEED LESS THAN7.5 NPH fd!LMS kkNNkhk SPEED LESS THANO.5)

T T t} l NPH...

m

1 ATTACHMENT S-4b Plant Hatch Meteorological Tower 10m Wind Rose i

Second Quarter - 4/1/85 - 6/30/85

[

l t E i

s M,. R S 1

(MH0gFRON) u l

4MND SPEED LESS THAH3.5 ftH

, WIND SPEED LESS THAN7.5 NPN e eP catHs xWIND SPEED LESS THAN12.5 NPH (dAL NED AS SPEED LESS THANS.5)

, Wits SPEED GREATER THAN f 2.5 ffN lO 1

i '

O ATTACHMENT 5-4c Plant Hatch Meteorological Tower 10m Wind Rose Third Quarter - 7/1/85 - 9/30/85 8

• e gM

, =, =,,

l t

l l

WINO SPEED LESS THAN3.S NPH 4

+ WINO SPEED LESS THAH7.5 HPH xWIND SPEED LESS THAN12.5 HPH 8 8 PERCENT CALMS

, WIND SPEED GREATER THAN 12.5 NPH (dALMS DEFINED AS SPEED LESS THANO.5) l 0 _

O ATTACHMENT 5-4d Plant 14tch Meteorological Tower 10m Wind Rose Fourth Quarter - 10/1/85 - 12/31/85

/

x 6

2

• i i

{

i I

Wits ROSE i

(WINDg FR0ft) t 1;

l WIND SPEED LESS THAN3.5 t1PH 4

+ WIND SPEED LESS THAN7.5 h/N xWIND SPEED LESS THr.N12.5 ftPH 8 8 PERCENT CAlt1S

~

, WIND SPEED GREATER THAN 12.5 NPH (dAlt1S DEFINED AS SPEED LESS THAMB.5) l 0.

O ATTACHMENT 5-5 Plant Hatch Meteorological Tower 60m Wind Rose Annual - 1/1/85 - 12/31/85 2

• i R.

f (WIND FROM) t t

4 Wits SPEED LESS THAN3.5 t1PM

+ Wits SPEED LESS THAN7.5 NPN xWItB SPEED LESS THAN12.5 MPH 8 8 PERCEffT CALMS

. WIND SPEED GREATER THAN 12.5 MPH (dAlt1S DEFINED AS SPEED LESS THANO.5)

O.- - - -,.. -. -.,

O l

ATTACHMENT 5-Sa PlantHatchMeteorologicalIc'wer60mWindRose First Quarter - 1/1/85 - 3/31/85 O

n:

WIND ROSE

~

i (WINDgFR0ff) t 49 WIND SPEED LESS THAN3.5 NPH 4

+ WIND SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 MPH 8 8 PERCENT CALHS

, WIND SPEED GREATCR THAN 12.5 NPH (dALMS DEFINED AS SPEED LESS THANO.5)

O..

OV ATTACHMENT 5-5b Plant Hatch Meteorological 60m Wind Rose Second Quarter - 4/1/85 - 6/30/85 U

s

l l

x:

I WIND ROSE (WINDS FR0ft)

N t

aWIND SPEED LESS THAN3.5 MPH

+ WIND SPEED LESS THAN7.5 HPH xWIND SPEED LESS THAN12.5 f1PH 0.8 PERCENT CALMS

, WIND SPEED GREATER'THAN 12.5 MPH (CALMS DEFINED AS SPEED LESS THANO.5)

O -

O ATTACHMENT 5-5c

'~

Plant Hatch Meteorological Tower 60m Wind Rose Third Quarter - 7/1/85 - 9/30/85 6 2 2 3 i

=

(WIND FR0ft) t l

t i

aWIND SPEED LESS THAN3.5 NPH

+UIND SPEED LESS THAN7.5 NPN xWIND SPEED LESS THAN12.5 NPH 8 8 PERCENT CALitS WIND SPEED GREATER THAN 12.5 t1PH (dALMS DEFINED AS SPEED LESS THANS.5) 4

O

O ATTACHMENT 5-5d Plant Hatch Meteorological Tower 60m Wind Rose Fourth Quarter - 10/1/85 - 12/31/85 6

• p t

i l

d I

WIND ROSE l

(WIND FROM) t l

l l

4 WIND SPEED LESS THAN3.5 NPH

, Wilt 9 SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 NPH 8 8 PERCENT CALMS

, WIND SPEED GREATER THAN 12.5 t1PH (dALMS DEFIHED AS SPEED LESS THANO.5) l 0.

1

O ATTACHMENT 5-6 PlantHatchMeteorologicalfower100mWindRose Annual - 1/1/35 - 12/31/85 2 3 2

5 2

l I

WIND ROSE

]

(WINDS FR0li)

N t

l WIPS SPEED LESS THAN3.5 tFH 4

+ WIND SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 HPH 9.8 PERCEHT CALNS

, WIND SPEED GREATER THAN 12.5 HPH (CALHS DEFINED AS SPEED LESS THANO.5) i

' O. _.

O ATTACHMENT 5-6a Plant Hatch Meteorological To0er 100m Wind Rose First Quarter - 1/1/85 - 3/31/85 12 s 0

l f

WIND ROSE

<WINDgFROM) t o

aWIND SPEED LESS THAN3.5 ffPH

+1EriD SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 HPH g,0 PERCENT CAlt1S

,WIPO SPEED CREATER THAN 12.5 MPH (CALMS DEFIffED AS SPEED LESS THANO.5) l 0 _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _

s O

ATTACHMENT 5-6b Plant Hatch Meteorological Tower 100m Wind Rose Second Quarter - 4/1/85 - 6/30/85 2

• o I

'f 3

g l

l I

WIND ROSE (WINDgFROM) t I

1>

WIND SPEED LESS THAH3.5 MPH 4

+ WIND SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAlf12.5 NPH 8 8 PERCENT CALHS

,UIND SPEED GREATER THAN 12.5 MPH (dALMS DEFINED AS SPEED LESS THANO.5)

O -__

O ATTACHMENT 5-6c Plant Hatch Meteorological Tower 100m Wind Rose Third Quarter - 7/1/85 - 9/30/85 5

• 8 2 O

i O

)

x l

WIND N

t WIND SPEED LESS THAN3.5 NPH 4

+ WIND SPEED LES3 THAN7.5 MPH xL'ItiD SPEED LESS THAN12.5 NPH 8.8 PERCENT CALttS

, WIND SPEED GREATER THAN 12.5 NPH (CALMS DEFINED AS SPEED LESS THANO.5)

O - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

ATTACHMENT 5-6d Plant Hatch Meteorological Tower 100m Wind Rose Fourth Quarter - 10/1/85 - 12/31/85 8

• o O

~

l I

WIND ROSE (WIND FROM) l l

l WIND SPEED LESS THAN3.5 MPH 4

+ WIND SPEED LESS THAH7.5 NPH xWIND SPEED LESS THAN12.5 NPH 0 0 PER0ENT CALMS l

1

,UIND S?EED GREATER THAN 12.5 NPH (dALMS DEFINED AS SPEED LESS THANO.5)

O.

ATTACHMENT 5-7

(

)

,v Plant Hatch Monthly Average and Average of the Daily Extremes of Dew Point Temperature 10m 1/1/85 - 12/31/85

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j ATTACHMENT 5-8 Plant Hatch 1985 Monthly and Annual Precipitation Precipitation Month (inches)

January 1.41 February 1.10 l

March 1.65 April 0.93 May 0.05 June 2.33 July 4.77 l

August 3.60 l

September 0.51 October 4.12 November 4.84 December 1.54 TOTAL 26.85 inches l

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i ATTACHMENT 5-9 i

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Plant Hatch Daily Precipitation Data January 1985 February 1985 Precipitation Precipitation Date (inches)

Date (inches) l 1/3 0.84 2/2 0.22 l

1/4 0.09 2/3 0.05 l

1/17 0.09 2/4 0.07 1/20 0.01 2/5 0.02 l

1/29 0.05 2/6 0.53 1/30 0.33 2/10 0.15 TOTAL 1.41 inches 2/14 0.06 TOTAL 1.10 inches i

March 1985 April 1985 Precipitation Precipitation Date (inches)

Date (inches) 3/1 0.65 4/6 0.60 3/16 0.04 4/13 0.33 3/16 0.62 TOTAL 0.93 inches 3/17 0.2E' 3/21 0.12 TOTAL 1.65 inches l

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ATTACHMENT 5-9a (dD May 1985 June 1985 Precipitation Precipitation Date (inches)

Date (inches) 5/30 0.05 6/7 1.22 TOTAL 0.05 inches 6/8 0.38 6/11 0.33 6/28 0.08 6/29 0.30 6/30 0.02 TOTAL 2.33 inches July 1985 August 1985 Precipitation Precipitation Date (inches)

Date (inches) 7/1 0.32 8/2 0.12 O

7/2 0.0e e<5 0.03 7/4 0.93 8/6 0.21 7/5 0.70 8/7 0.46 7/6 0.30 8/8 0.25 7/11 0.59 8/9 0.13 7/15 0.50 8/17 0.16 7/16 0.25 8/21 0.01 7/17 0.18 8/24 0.16 1

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7/24 0.10 8/28 0.55 7/25 0.01 8/29 0.92 7/28 0.01 8/30 0.29 7/29 0.47 8/31 0.03 7/30 0.11 TOTAL 3.60 inches 7/31 0.03 TOTAL 4.77 inches O,

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ATTACHMENT 5-9b O

V September 1985' October 1985 Precipitation Precipitation Date (inches)

Date (inches) 9/1 0.11 10/2 1.25 9/2 0.14 10/10 0.10 9/20 0.03 10/19 0.18 9/25 0.23 10/27 0.59 TOTAL 0.51 inches 10/28 1.13 10/30 0.59 10/31 0.28 TOTAL 4.12 inches t

November 1985 December 1985 Precipitation Precipitation Date (inches)

Date (inches) 11/1 0.18 12/1 0.27 11/16 0.02 12/12 0.24 l

11/19 0.02 12/13 0.67 11/20 0.80 12/28 0.13 11 /21 0.70 12/31 0.23 11/72 2.35 TOTAL 1.54 inches 11/25 0.03 11/29 0.09 11/30 0.65 TOTAL 4.64 inches l

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