Text

Semiannual Radioactive Effluent Release Rept Jul-Dec 1992
	ML20034F328
Person / Time
Site:	Grand Gulf
Issue date:	12/31/1992
From:	Poe W; ENTERGY OPERATIONS, INC.
To:	;
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ML20034F327	List: ML20034F325; ML20034F328; ML20034F329;
References
	NUDOCS 9303030035
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4 6

I i

Grand Gulf Nuclear Station i

l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT t'

July 1 - December 31, 1992 s

- i i

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l Prepared By:

r' [

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/ 2' /8' 7 3 Reviewed By:

W /tdd

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Approved By:

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SRER901.2/SRREVFLR - i 9303030035 930226

.t PDR ADOCK 05000416 R

PDR

TABLE OF CONTENTS SUBJECT PAGE J,

l 1.

INTRODUCTION............................

1 i

II. OETAILED INFORMATION...................................................

2 A.

Regulatory Limits.................................................

2 1.

10CFR20 Limits a.

Fi s si on and Acti va ti on Ga se s.............................

2 l

b.

Radiciodines and Particulates............................

2 c.

Liquid Effluents.........................................

2 i

2.

10CFR50, Appendix I Limits l

a.

Fission and Activation Gases.............................

3 i

i b.

Radiciodines and Particulates............................

3 c.

Liquid Effluents.........................................

3 j

t 3.

40CFR190 Limits.....................

4 i

B.

Maximum Permissible Concentrations................................

4 I

1.

Airborne...............................................

4 l

2.

Liquid........................................................

4 i

r

?

C.

Average Energy....................................................

4 D.

Measurements and Approximations of Total Activity..................

5 i

1.

For Fission and Activation Gases..............................

5 i

2.

For Particulates and Radioiodines.............................

6 3.

For Continuous Releases.......................................

6 l

4.

For Batch Releases:

Gases.....................................

6 i

5.

For Batch Releases: Liquid Effluents..........................

7 l

i E.

Batch Releases...................................................

7 3.

Liquid......

7 l

2.

Gaseous.......

8 1

F.

Unplanned Releases................................................

8 3.

Liquid.......................................................

8 2.

Gaseous.......................................................

8 t

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TABLE OF CONTENTS (Continued) j 1

P_AG.E A

SUBJECT t

a G.

Estimate of Total Error..........................................

8

)

1.

Liquid.......................................................

8 i

2.

Gaseous.....................................................

9 3.

Solid Radioactive Waste......................................

9 H.

Solid Radioactive Waste Shipments................................

9 I.

Meteorological Data...............................................

9 1

J.

Radioactive Effluent Monitoring Instrumentation Operability......

10 1

i K.

Annual Sewage Disposal Summary.................................

10

[

l III. 1992 RADIATION DOSE

SUMMARY

10 A.

Water-Related Exposure Pathways................................

10 B.

Airborne-Related Exposure Pathways..............................

11 l

t I

IV. OFFSITE DOSE CALCULATION MANUAL /RADI0 ACTIVE l

1 WASTE TREATMENT SYSTEM CHANGES j

1 r

A.

Offsite Dose Calculation Manual (0DCM)...........................

12 l

l B.

Radioactive Waste Treatment Systems...............................

12 l

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i LIST OF TABLES i

i TABLE EAGE j

1A Gaseous Effluents - Summation of All Releases..............

lA-1

]

1B Gaseous Effluents - Elevated Releases......................

IB-1 l

IC Gaseous Effluents - Ground-Level Releases..................

IC-1 l

ID Radioactive Gaseous Waste Sampling and Analysis Program.... 10-1 2A Liquid Ef fluents - Summation of All Releases..............

2A-1 i

2B Liquid Effluents - Continuous and Batch Modes.............

2B-1 l

i A

2C Radioactive Liquid Waste Sampling and Analysis Program....

2C-1 t

3 Solid Radioactive Waste and Irradiated Fuel Shipments.............................................

3-1 t

4A Meteorological Data - July - September, 1992.... 4A-1 to 4A-17 j

4B Meteorological Data - October - December,1992..

4B-1 to 4B-17 1

4C Meteorological Data Summary (January-December).... 4C-1 to 4C-17 l

4D Classification of Atmospheric Stability...................

4D-1 i

i LIST OF ATTACHMENTS i

Attachment I - Amended Table 3 From January - June 1992 Report l

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i 1.

INTRODUCTION i

i This Semiannual Radioactive Effluent Release Report for the period j

i of July 1 through December 31, 1992 is submitted in accordance with

('i Section 6.9.1.8 of Appendix A to Grand Gulf Nuclear Station (GGNS) License No.

j

)

NPF-29.

The monitoring of radioactive effluents is referenced in Appendix A, j

i Sections 3/4-11 and 3/4-12 and the Offsite Dose Calculation Manual (ODCM).

i l

Airborne discharges at GGNS are considered ground-level releases. All liquid

[

and airborne discharges to the environment were analyzed in accordance with f

ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM.

j i

Projected offsite doses were within the dose limits specified by the ODCM.

l l

1 The summation of all gaseous releases during the reporting period is given in

{

Table 1A, while elevated releases and ground-level releases are given in Tables l

IB and IC, respectively. Table ID describes the radioactive gaseous sampling

[

and analysis program implemented at GGNS.

l The summation of all liquid releases during the reporting period is given in r

i Table 2A, while continuous and batch mode releases are given in Table 2B.

Table l

2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS.

t Solid radioactive waste and irradiated fuel shipments during the reporting f

period are summarized in Table 3.

Meteorological data is included in Tables 4A -

i 4C.

Table 4D presents atmospheric stability classifications.

[

I includes an amended Table 3 for the period of January - June j

f 1992.

SRER901.2/SKREVFLR - 1

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f II.

DETAILED INFORMATION j

i A.

Regulatory Limits 1.

10CFR20 Limits t

I t

a.

Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary i

shall be such that:

j average total body dose rate in the current year (mrem /yr) j D

=

ib 5

X/Q E K Q

5500 mrem /yr

=

g j

a D,

average skin dose rate in the current year (mrem /yr)

=

3 i

X/Q I (L 4 1.1 M ) Q

$3000 mrem /yr

=

g g

g I

where the terms are defined in the GGNS ODCM.

I s

b.

Radiciodines and Particulates - The release rate limit for the

=empling period for all radiciodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days l

shall be such that:

average organ dose rate in current year (mrem /yr)

{

i D

=

9 IWP Q'f $1500 mrem /yr

=

g g

i where the terms are defined in the GGNS ODCM.

{

c.

Licuid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas 1 m the

{

reactors at the site shall not exceed at any time the values specified in 10CFR20, Appendix B. Table II, Column 2.

The

{

concentration of dissolved or entrained noble gases, released in i

liquid effluents to unrestricted press from all reactors at the t

i site, shall be limited to 2 x 10 " microcuries/ml total

~

activity.

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2.

10CFR50, Appendix I Limits a.

Fission and Activation Gases - The dose from noble gases in f

gaseous effluents to areas at or beyond the site boundary

(

shall be such that:

D = sir dose due to gamma emissions from noble gases g

= 3.17 x 10~

I, M X/Q' Qg $5 mrad /qtr 510 mrad /yr l

I a-D = air dose due to beta emissions from noble gas g

-8

= 3.17 x 10 I N X/Q' Q 510 mrad /qtr f y g

520 mrad /yr i

where the terms are defined in the GGNS ODCM.

l b.

Radiciodines and Particulates - The dose to an individual from l

tritium, 1-131, I-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents j

shall be such that D = dose to an individual from tritium, I-131, 1-133 and P

1 radionuclides in particulate form with half-lives i

greater than 8 days (mrem) i

-8 3.17 x 10 7 p, p. Q, 57.5 mrem /qtr Any Organ

=

i 515 mrem /yr Any Organ j

i where the terms are defined in the GGNS ODCM.

Liquid Effluents - The dose from radioactive materials in r

c.

liquid effluents shall be such that:

m r

IA I At C F] 51.5 mrem /qtr Total Body DTau " If iTau g yg g

t=1 55 mrem /qtr Any Organ i

53 mrem /yr Total Body 510 mrem /yr Any Organ where the terms are defined in the GGNS ODCM.

SRER901.2/SRREVFLR - 3

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3. '40CFR190 Limits

[

t Doses are calculated for Tission and Activation Gases; Radiciodines and Particulates; and Liquid Effluents according to j

equations contained in Sections 2.(a), (b), and (c) respectively, with j

the exception that the limits applied are:

l t

525 mrem /yr, Total Body or any Organ except Thyroid f

575 mrem /yr, Thyroid 4

- i 510 mrad T/qtr or $20 mrad I/yr, Fission and Activation Gases l

t-520 mrad 0/qtr or 540 mrad 6/yr, Fission and Activation Gases 515 mrem /qtr or $30 mrem /yr, any Organ, Iodine and farticulates j

53 mrem /qtr or 56 mrem /yr, Total Body, Liquid Effluents

$10 mrem /qtr or 520 mrem /yr, any Organ, Liquid Effluents

[

B.

Maximum Permissibic Concentrations 1.

Airborne The Maximum Permissible Concentration (MPC) of radioactive materials in gaseous effluents is limited by the dose rate restrictions of l

10CFR20.

In this case, the MPCs are actually determined by the dose l

factors in Table 2.1-1 of the GGNS ODCM.

)

2.

Liquid l

The MPC of radioactive materials in liquid effluents is limited by i

10CFR20, Appendix B, Table II, Column 2.

The MPC chosen is the most conservative value of either the soluble or insoluble MPC for each radioisotope.

l C.

Average Energy l

1 Not applicable for GGNS ODCM Appendix A.

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'D.

Measurements and Approximations of Total Activity j

The following discussion details the methods used to measure and l

approximate total activity for the following:

j 1.

Fission and Activation Gases 2.

Radiciodines

{

3.

Particulates

.l 4.

Liquid Effluents i

Tables ID and 2C give sampling frequencies and minimum detectable j

]

sensitivity requirements for the analysis of gaseous and liquid effluent streams, respectively.

a Values in the attached tables given as zero do not necessarily imply l

that the radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables ID and 2C.

For some radionuclides, lower detection limits than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is i

reported.

{

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1.

For Fission and Activation Gases t

i i

The following noble gases are considered in evaluating gaseous f

airborne discharges:

i I

Ar-41 Xc-131m I

Kr-85m Xe-133 Kr-85 Xe-133m Kr-87 Xc-135m Kr-88 Xe-135 l

Kr-89 Xe-138 l

i Periodic grab samples from Station effluent streams are analyzed by a j

l computerized pulse height analyzer system utilizing high-resolution j

germanium detectors.

(See Table ID for sampling and analytica) l requirements.)

Isotopic values thus obtained are used for dose j

release rate calculations due to effluent releases as given in l

Section 11.A.I. of this report. Only those radionuclides that are detected are used in this computation.

During the period between grab samples, the amount of radioactivity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis, using the following relationship:

l i

U G j g+m

=

where C;

isotopic calibration factor for isotope i

=

i i

1 SRER901.2/SRREVFLR - 5

.~

concentration of isotope i in the grab sample in pCf/ml.

U =

g l

net monitor reading associated with the effluent stream j

m =

(determined at the time of grab sampling).

1 These calibration f actors, along with the hourly ef fluent monitor l

values and flow rates, are entered into the laboratory computer where l

the release rates for individual radionuclides are calculated and stored. If no activity is detected in the grab sample, the calibration i

factor defaults to a historical mixture of Kr-88, Xc-133, Xe-135m, l

Xe-135, and Xe-138.

j 2.

For Particulates and Radiciodines l

The radiciodines and radioactive materials in particulate form to be j

considered are:

t

}

Zn-65 I-133 Cr-51 Cs-134 j

jl Mn-54 Cs-136 Fe-59 Cs-137 Co-58 Ba-140 j

Co-60 Ce-141 l

Sr-89 Ce-144 Sr-90 Other radionuclides l

Zr-95 with half-lives l

f Sb-124 greater than I-131 8 days.

I 3.

For Continuous Releases i

i Continuous sampling is performed on the continuous release points l

(i.e., Radwaste Vent, Containment Purge, Fuel Handling Area Vent, Turbine Building Vent). Particulate material is collected by j

I filtration. Radiciodines are collected by adsorption onto a charcoal

{

filter.

Periodically these filters are removed and analyzed on the j

pulse height analyzer to identify and quantify radioactive materials

~

collected on the filters. Particulate filters are then analyzed for gross alpha and Strontium-89 and -90 as required. Gross alpha l

determinations are made using a 2-pi gas flow proportional counter.

i Strontium-89 and -90 values are obtained by chemical separation and l

subsequent analysis using 2 pi gas flow proportional counters.

Tritium concentrations are determined'using liquid scintillation

{

techniques. During major operational occurrences, the frequency of

+

sampling is increased to satisfy the requirements of footnote "c" of f

Table 3D, " Radioactive Gaseous Waste Sampling and Analysis," (GGNS ODCM Appendix A, Table 4.11.2.1.2-1).

j 4.

For Batch Releases: Gases i

l The processing of batch type releases (from Containment Purge) is 4

]

analogous to that for continuous releases.

t I

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-l 5.

For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid l

effluents.

i H-3 Mo-99 ~

I Co-58 Tc-99m Co-60 1-131 s

Fe-55 1-132 Fe-59 I-133 Zn-65 1-135 Mn-54 Cs-134 I

Cr-51 Cs-137 j'

Sr-89 Ba-140 Sr-90 La-140 J

Nb-95 Ce-141 Zr-95 Ce-144 i

1 Representative pre-release grab samples are obtained and analyzed as required by Table 2C.

Isotopic analyses are performed using the computerized pulse heigbt analysis system previously described.

d Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C.

Strontium determinations are made by performing a chemical i

j separation and counting the separated strontium using a 2-pi gas flow proportional counter. Gross alpha determinations are made using 2-pi l'

gas flow proportional counters. Tritium and Iron-55 concentrations are determined by using liquid scintillation techniques. Dissolved t

gases are determined employing grab sampling techniques and then counting on the pulse height analyzer system.

[

l i

i E.

Batch Releases 8

1 1.

Liquid Batch Releases (1992)

{

Ist 2nd 3rd 4th 1992 f

I Otr..

Otr Otr Qir Total i

a.

Numbar of relenses 64 87 72 40 263 j

Time Period (in minutes) i b.

Total for all batches 19,722 26,856 21,998 12,218 80,794 l

c.

Max time for a batch 325 425 325 320 425

]

d.

Avg time for a batch 308 309 306 305 307

)

e.

Min time for a batch 240 50 229 263 50 i

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2.

Gaseous No batch releases were made during report period.

F.

Unplanned Releases 1.

Liquid l

No unplanned liquid release occurred during report period.

t 2.

Gaseous i

No unplanned gaseous ralease occurred during report period.

i' G.

Estimate of Total Error l.

Liquid The maximum errors are collectively estimated to be Fission &

Dissolved &

Activation Entrained Gross i

Products Tritium Gases Alpha l

Sampling 26%

26%

Measurement 68%

65%

61%

92%

Total 73%

70%

66%

95%

Sampling errors include uncertainty associated with mixing, I

representative sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples and, for germanium detectors, i

the least-readily-detectable radioisotope. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

l

?

Total error is calculated by taking the square root of the sum of the squares of the individual errors.

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2.

Gaseous s

The maximum errors (not including sample line loss) are collectively l

f estimated to be Fission &

l Activation Gross Gases lyding Particulate Alplig Tritium j

Sampling 32%

23%

22%

23%

i Measurement 61%

67%

65%

101%

62%

2 Total 69%

71%

69%

103%

66%

Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration.

Measurement errors include uncertainty associated with instrument calibration and preparation and counting of _ low-activity samples.

a Measurement and total errors are calculated by the same methods used j

for liquid effluents.

l 3.

Solid Radioactive Waste See Table 3 for error terms.

l l

H.

Solid Radioactive Waste Shipments i

See Table 3 for shipment in forma tion.

y 8

I.

Meteorological Da*a 3

1.

Meteorological Data Recovery Rate (1992)

]

\\

Parameter

% Data Recovery l

i ist Otr 2nd Otr 3rd Otr 4th Ott 1992 1

50m Wind Direction 99.27 92.54 97.78 92.16 95.43 50m Wind Speed 99.27 92.31 97.78 92.21 95.39 10m Wind Direction 99.27 92.54 97.78 92.16 95.43 10m Wind Speed 99.27 92.54 97.78 91.98 95.39 Temperature 99.27 92.54 97.15 91.67 95.15 Dew Point 99.18 92.31 97.78 89.77 94.74 Delta T 99.27 92.54 97.78 88.99 94.64 Precipitation 99.27 92.54 99.28 94.88 96.49 1

y 2.

Meteorological data for the period of the report is included in Tables 4A through 4C.

SRER901.2/SRREVFLR - 9 r

i J.

Radioactive Effluent Monitoring Instrumentation Operability i

No reportable instances of inoperability occurred during the report l

period.

l i

K.

Annual Sewage Disposal Summary No Sewage Waste was disposed of during 1992 l

l I

III. 1992 RADIATION DOSE

SUMMARY

l Indicated below is the annual summary of offsico doses attributable to GGNS i

during 1992.

Inspection of the values indicate that GGNS releases were within l

the 10CFR50, Appendix I design objectives.

Since there are no other fuel cycle facilities within 8 km of GGNS, 40CFR190 i

limits have also been met during this period.

All parameters listed were calculated in accordance with the GGNS ODCM.

j A.

Water-Related Exposure Pathways The values calculated in this section utilize the information provided in l

Tables 2A and 2B of this report and the calculational methodology of the

{

ODCM.

l I

Liauld Effluents i

I Total body dose and critical organ doses are computed for the maximum l

exposed individual. The maximum dose contribution from 11guld effluents is considered to occur in the adult age group via consumption of fish.

l i

1992 Liquid Effluent Dose (mrem)

Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Total i

Whole Body 3.55E-03 1.92E-02 8.81E-03 2.65E-02 5.81E-02 l

i Bone 1.53E-02 1.47E-02 3.89E-02 1.26E-01 1.95E-01 j

i Liver 9.27E-03 2.86E-02 1.72E-03 1.75E-03 4.13E-02 I

1 Thyroid 1.09E-02 2.95E-02 3.81E-04 2.98E-04 4.11E-02 Kidney 1.92E-03 8.87E-03 5.97E-04 3.96E-04 1.18E-02 Lung 2.36E-03 4.23E-03 6.53E-04 8.61E-04 8.10E-03 r

GI-LLI 3.42E-02 1.95E-02 8.40E-03 1.11E-02 7.32E-02

{

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l B.

Airborne-Related Exposure pathways i

?

The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculational methodology of the ODCM. Doses and dose rates are computed for locations at the site l

f boundary or at unrestricted areas within the site boundary. The use of unrestricted areas within the site boundary as controlling receptor i

locations provides assurance that offsite doses will not be substantially l

t underestimated, as well as determining the radiation dose from gaseous l

i effluents to members of the public due to their activities inside the site l

)

boundary.

i Particulate, Radiciodine and Tritium i

l 5

Organ doses from exposure to radiciodines, tritium and particulates are l

computed for an individual located in the south sector at a distance of 0.5 miles. This location corresponds to one cf the two onsite GGNS gardens.

Pathways considered in the dose calculations are inhalation, ground plane, grass / cow / milk, grass / cow / meat and vegetation. For a a

j particular radionuclide, the maximum dose factor obtainable from a I

combination of age groups and organs is used in the calculation of organ dose.

Noble Gases

[

d Gamma and beta air dose and individual total body and skin dose rates from j

exposure to a semi-infinite cloud of noble gas are computed for a location i

3 in the west-northwest sector at a distance of 0.75 miles. This controlling location corresponds to the highest annual average atmospheric dispersion for an unrestricted area inside the site boundary (Hamilton i

4 Lake).

The total body and skin doses reported below are derived from the quarterly average of the maximum instantaneous dose rates determined daily j

during the reporting period and would represent the maximum possible dose 1

received by members of the public onsite.

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4 Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermeluminescent dosimeter (TLD) badge.?. located at control locations from average doses measured by TLD badges 13cated near the site boundary.

1992 Airborne Effluent Dose (mrem) 1992 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total lodine, Tritium &

1.21E400 2.33E+00 8.45E-03 3.77E-03 3.56E+00 Particulat-es Fission and Activation 2.22E-02 4.61E-01 4.98E-02 2.09E-02 5.54E-01 Gases (Total Body dose)

(Skin dose) 4.59E-02 1.05E+00 8.59E-02 3.32E-02 1.22E+00 Gamma Air dose

2.19E-03 1.26E-02 1.01E-02 4.10E-03 2.90E-02 Beta Air dose

2.51E-03 2.71E-02 8.10E-3 4.40E-03 4.21E-02 Direct Radiation 0.9 0

1.5 0

2.4

Measurement units are mrad IV.

OFFSITE DOSE CALCULATION MANUAL /RAQJ0 ACTIVE WASTE TREATMENT SYSTEM CHANGES A.

Offsite Dose Calculation Manual (ODCM)

No changes were made to ODCM during the report period.

B.

Radioactive Waste Treatment Systems No major changes were made during the report period.

SRER901.2/SRREVFLR - 12

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TABLE 1A I

t EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1992 J-GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES j

I JULY - DECEMBER 1992 i

3 l

l Unit j

___________________________________________________-Q_uarter l Quarter lEst Total l 6

l Grand Gulf Nuclear Station UNIT 1l l

3 l

4 l Error % l

[

t i

A.

Fission & Activation Gases s

l 1.

Total release l

Ci

'l 2.95E+01l 1.77E+01l 6.90E+01l j

1 f

l

2. Average release rate for period l uCi/secl 3.75E+00l 2.23E+00l l

l 3.

% of Technical specification limit l j 2.01E-01] 8.22E-02l l

4 e

s 1

B.

Iodines r

________________________________________________________________________________ i l

1. Total iodine-131 l

Ci _

l 1.40E-05l 1.44E-06l 7.10E+01l f

3 l

2. Average release rate for period l uCi/secl 1.78E-06l 1.81E-07l 1

l 3.

% of Technical specification limit l l 7.00E-04] 7.18E-05l l

C.

Particulates a

l 1.

Particulates with half-lives >S days l Ci l 8.36E-06l 2.21E-05l 6.90E+01l

{

4 i

l

2. Average release rate for period l uCi/secl 1.06E-06l 2.77E-06l l

3.

% of Technical specification limit l l 1.50E-03l 3.12E-03l l

2 l

4. Gross alpha radioactivity l

Ci l 1.22E-08l 2.44E-08l f

i i

D. Tritium I

l 1.

Total release l

Ci l 1.95E+00l 3.38E+00l 6.60E+01l l

2. Average release rate for period l uCi/secl 2.48E-01l 4.25E-01l l

3.

% of Technical specification limit l l 2.32E-02l 4.01E-02l E. Tritium,radiciodines and particulates j

l 1.

% of Technical specification limit l l 2.47E-02l 4.33E-02l J

1, 4

i i

TBL1A 1

SRER901.2/SRREVFLR - 1

~ -.

---. ~. -..

~

.h i

l 1

i TABLE 1B GRAND GULF NUCLEAR STATION l

JULY - DECEMBER 1992 i

i l

QASEOUS EFFLUENTS - ELEVATED RELEASES i

i i

4 i

l 1

)

(Not Applicable - GCNS releases are considered ground level) j i

' f t

5 b

I i

l TBLIB SRER901.2/SRREVFLR - 1 1

TABLE 1C Grand Gulf Nuclear Station UNIT 1

i JULY - DECEMBER 1992 I

l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1992 j

\\

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE i

CONTINUOUS MODE BATCH MODE l Nuclides Released l Unit l Quarter l Quarter l Quarter l Quarter l f

l l

l 3

l 4

l 3

l 4

l l

1.

Fission gases XE-133 Ci 1.25E+01 8.28E+00 0.00E+00 0.00E+00

.j KR-88 Ci 5.31E-01 3.53E-01 0.00E+00 0.00E+00 XE-135 C1 1.19E+01 7.92E+00 0.00E+00 0.00E+00 l

XE-138 Ci 3.19E-01 2.12E-01 0.00E+00 0.00E+00 t

XE-135M C1 1.41E+00 9.34E-01 0.00E+00 0.00E+00 l

AR-41 Ci 2.88E+00 0.00E+00 0.00E+00 0.00E+00 i

t l Total for period l

Ci l 2.95E+01l 1.77E+01l 0.00E+00l 0.00E+00]

2.

Iodines I-131 Ci 1.40E-05 1.07E-06 0.00E+00 0.00E+00 I-132 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 C1 2.61E-06 4.11E-06 0.00E+00 0.00E+00 I-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j

)

l i

l Total for period l

Ci l 1.66E-05l 5.18E-06l 0.00E+00l 0.00E+00l r

j 3.

Particulates i

l H-3 Ci 1.95E+00 3.38E+00 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l

Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00

}

MN-54 Ci 5.55E-07 4.86E-07 0.00E+00 0.00E+00 CO-60 Ci 7.80E-06 1.74E-06 0.00E+00 0.00E+00 TC-99M Ci 0.00E+00 9.48E-06 0.00E+00 0.00E+00 i

I-131 Ci 0.00E+00 3.71E-07 0.00E+00 0.00E+00

'I LA-140 Ci 0.00E+00 5.59E-07 0.00E+00 0.00E+00 I-133 Ci 0.00E+00 7.13E-06 0.00E+00 0.00E+00 BA-140 Ci 0.00E+00 6.75E-07 0.00E+00 0.00E+00 l

SB-124 Ci 0.00E+00 7.48E-08 0.00E+00 0.00E+00

)

L CR-51 Ci 0.00E+00 1.54E-06 0.00E+00 0.00E+00 1

I I

l Total for period l

Ci l 1.95E+00l 3.38E+00l 0.00E+00l 0.00E+00l l

TBLIC l

SRER901.2/SRREVFLR - 1 1

=

r i

.. _ ~ - -

= -.

3 4

i f

i IA.BLE 1D l,

Grand Gulf Nuclear Station j

RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM I

Lower Limit Lower Limit of Detection Gaseous Minimum Type of of Detection (Worst Case)

Release Sampling Analysis Activity Required (LLD) Capability Type Frequency Frequency Analysis (pCI/ml)"

(pCJ/ml)"

l A.

(1) Radwaste M

M Principal 1E-04 1.5E-07 Building Grab Sample Gamma b*c Ventilation Emitters Exhaust 11 - 3 1E-06 1.8E-10 i

(2) Fuel Con t in uou s

W' 1-131 1E-12 6.0E-13 ilandling Charcoal Area Sample Ventilation 1-133 1E-10 9.0E-13 j

Exhaust Continuous W'

Principal IE-11 9.6E-13 (3) Containment.

Particulate Gamma i

Ventilation Sample Emitters" Exhaust (I-131, i

Others) d (4) Turbine Continuous M

Gross Alpha 1E-11 1.8E-14 Building Composite i

Ventilation Particulate Exhaust Sample l

Continuous Q

Sr-89, 1E-11 1.lE-14 Composite Sr-90 i

Particulate i

Sample Continuous Noble Gas Noble Gases 1E-06 4.4E-07 Monitor Gross Beta or Gamma Note:

Footnotes indicated are IJsted in GGNS ODCM APPENDIX A, Table 4.11.2.1.2-1.

i i.

I i

i TBL1D SRER901.2/SRREVFLR - 1

(

~

6 9

I TABLE ID (Continued)'

a Grand Gulf Nuclear Station RADIDACTIVE GASEOUS WASTE SAMPLING AMD ANALYSIS PROERAM i

4 i

i Lower Limit i

Lower Limit of Detection Gascous Minimum Type of of Detection (Worst Case) l Release Sampling Analysis Activity Required (LLD) Capability l

Type Frequency Frequency Analysis (pCf/ml)#

(pCi/ml)"

l B.

(1) Offgas Post M

M Principal IE-04 5.4E-05 Treatment Grab Sampic Gamma l

1

Exhaust, Emitters whenever j

there is j

j flow i

(2) Standby Gas j

Treatment A

Exhaust, whenever there is l

flow (3) Standby Gas Treatment B i

Exhaust, 4

whenever there is flow a

4 1

1 2

1 Note:

Footnotes indicated are listed in GGNS ODCM Appendix A, Table 4.11.2.1.2-1.

I a

TBLID SRER901.2/SRREVFLR - 2

,,--,-w,,

1 i

TABLE 2A l

Grand Gulf Nuclear Station

?

JULY - DECEMBER 1992 j

LIQUID EFFLUENTS-SUMMATION Of ALL RELEASES l

i' l

Unit l Quarter l Quarter IEst Totall l

l 3

1 4

l Error % l A.

Fission & activation products l 1 Total release (not including H3 l

l l

j i

gases, alpha)

I Ci l 1.94E-021 1.90E-02l 7.30E+011 1

2.

Auerage diluted concentration l

l l

l j

l during period I uCi/ral l.2.05E-08l 5.37E-0BI l

3.

Percent of applicable l i ra i t l 1.70E-011 9.87E-01l B.

Tr i t i oin i

l 1.

Total release l

Ci l 6.03E+001 4.36E+00l 7.00E+011 l

2.

Auerage diluted concentration l

l l

]

1 during period l uti/mi l 8.06E-061 1-.23E-05l l

3.

Percent of applicable limit l

l 2.95E-01l 4.11E-011 E.

Dissolved and entrained geses l

1.

Total release l

Ci i 1.12E-04l 8.40E-05l 6.60E+011 l

l 2.

Auerage diluted concentration l

l l

J during period I uCi/ml l 1.65E-10l 2.37E-10l j

l 3.

Percent of applicable l i ro i t I

i 2.47E-03l 3.56E-031 D.

Gross alpha' radioactivity i

I i 1 Total release l

Ci l 0.00E+00l 0.00E+00l 9.50E+01l l

1 lE. Volume of waste (prior to dilution){ litere 1 7.59E+06] 4.19E*06l 5.00E+001 i

lF. Volume of dilution water used l liters l 6.73E4081 3.50E+081 5.00E+001 TEL2A SRER901.2/SRREVFLR - 1 m

l l

l I

i i

TABLE 2B j

I Grand Gulf Nuclear Station 4

JULY - DECEMBER 1992 l

1 LIQUID EFFLUENTS - CD,NTINUGUS AND BATCH MODES

[

CONTINUOUS MODE BATCH MODE l

Nuclides Released l Unit l Quarter l Quarter ] Quarter l Quarter l 1

l l

l 3

l 4

l 3

l 4

l i

l strontium-89 l

Ci l 0.00E+00l 0.00E+001 1.20E-031 3.63E-03l l

strontium-90 l.

Ci l 0.00E*001 0.00E+00l 2.21E-041 6.66E-04l 3

j l

cesium-134 l

Ci l 0.00E+001 0.00E+00l 0.00E+001 0.00E+00]

l cesium-137 l

Ci 1 0.00E+00l 0.00E+00l 0.00E+00l 0.00C+00l I

iodine-131 l

Ci l 0.00E+00l 0.00E+001 0.00E+00l 0.00E+001 I

cobalt-58 l

Ci l 0.00E+00l 0.00E+00l 2.93E-05l 4.67E-061 j

i cobalt-60 l

Ci l 0.00E+001 0.00E+00l 1.73E-03l 1.49E-031 l

j i

iron-59 i

Ci j 0.00E+001 0.00E+00l 1.81E-05l 0.00E-00l

}

l zinc-65 l

Ci l 0.00E+001 0.00E+00l 0.00E+00l 0.00E+00l j

j l

manganese-54 l

Ci 1 0.00E*00l 0.00E+00] 6.02E-04l 2.5BE-04l l

chromium-51 l

Ci l 0.00E+00l 0.00E+001 1.16E-02] 5.98E-031 E

l z i r c er i um n i ob i urn-95 l

Ci l 0.00E+001 0.00E+00l 0.00E+00l 0.00E+001 I

mo l y b denurn-9 9 i

Ci j 0.00E+00l 0.00E+001 0.00E+00] 0.00E+00!

t J

t e c h net i urn-9 9ta l

Ci I 0.00E*00l 0.00E+00l 0.00E+001 7.94E-06l I

l bar i urn-l an thanum-140 l

Ci l 0.00E+00l 0.00E+001 0.00E+00l 0.00E+001 J

cerium-141 l.

Ci l 0.00E+00l 0.00E+001 0.00E+00l 0.00E+00l i

l 1

Ce-144 i

Ci l 0.00E+00l 0.00E+001 0.00E+00l 8.72E-06l i

i U-187 l

Ci l 0.00E+00l 0.00E+00l 3.42E-06] 0.00E+00l l

i Cu-64 l

Ci j 0.00E+00l 0.00E+001 1.31E-041 5.76E-061 i

l As-76 i

Ci l 0.00E+00l 0.00E+001 2.85E-051 3.54E-05l l

Fe-55 l

Ci l 0.00E+00l 0.00E+00l 3.82E-031 6.91E-03l l

i Total for period (aboue) l Cil 0.00E+00l 0.00E+001 1.94E-021 1.90E-021 f

a I

1 i

1 xenon-133 i

Ci l 0.00E+001 0.00E+001 3.28E-05l 1.64E-051 I

xenon-135 i

Ci l 0.00E+00l 0.00E+00l 7.94E-051 6.76E-051 I

Xe-133rn Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l 4

i TBL2B l

l SRER901.2/SRREVFI,R - 1 8

_~

i 1

l I

TABLE 2C Grand Gulf Nuc1 car Station RADIDACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM f

1 1

l l

Lower Limit Lower Limit of Detection Liquid Minimum Type of of. Detection (Worst Case) l Release Sampling Analysis Activity Required (LLD) Capability Type Frequency Trequency Analysis (pC1/ml)a

( Ci/ml)a A.

Batch P

P Principal SE-07 1.6E-07 Waste Each Each Gamma d

Release Batch Batch Emitters Tanks' 1 131 1E-06 2.3E-08 P

M Dissolved IE-05 7.1E-08 l

One and Batch /M Entrained Gases (gamma emitters)

P M

11 - 3 1E-05 4.4E-06 b

l Each Composite Batch Gross IE-07 3.8E-08 i

Alpha l

I l

P Q

Sr-89, SF.-08 2.6E-08 b

Each Composite Sr-90 l

Batch

}

Fe-55 1E-06 1.4E-07 l

l l

B.

SSW Basin Principal SE-07 1.6E-07 (prior to Each Each Gamma I

d blowdown)

Blowdown Batch Emitters i

1-131 IE-06 2.3E-08 t

Note: Footnotes indicated are listed in GGNS ODCM Appendix A, Table 4.11.1.1.1-1.

i l

TBL2C SRER901.2/SRREVELR - 1 l

i l

l

b.. --.

TABLE 3 Grand Gulf Nuclear Station JULY - DECEMBER 1992 SOLID RADI0 ACTIVE WASTE AND IRRADIATED FUEL SIIIPMENTS A.

Solid Waste Shinned Offsite for Burial or Discosal I

i 1.

Type of Waste 6-Month Estimate Total Unit Period Error. %

3 I

a.

Spent resins, filter s1.udges, m

1.14E+02 i

oil, evaporator bottoms, etc.

C1 2.41E+03 7.2E+01 3

b.

Dry compressible waste, m

1.34E401 contaminated equipment, etc.

Ci 5.32E-01 6.9E+01 j

r Irradiated components, control m

None N/A

{

c.

rods, etc.

C1 i

d.

Other 3

m 2.98E+01

Ci 5.39E-01 7.2E+01 1

t

Total curie quantity determined by measurement.

Total volume used is burial container volume.

2.

Estimate of major radionuclide composition (by type of waste as identified above),

a.

Fe-55 69%

Co-60 11%

Mn-54 11%

Cr-51 3%

RU-106 4%

All Others 2%

b.

Fe-55 85%

Mn-54 7%

Co-60 6%

Fe-59 2%

c.

N/A N/A d.

Fe-55 76%

Co-60 18%

Ce-144 6%

TBL3 SRER901.2/SRREVFLR - 1

i i

TABLE 3 (Continued)

Grand Gulf Nuclear Station JULY - DECEMBER 1992 l

SOLID RADIDACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS

{

i 3.

Solid Waste Disposition Resins were dewatered in steel liners or liigh Integrity Containers a.

according to the requirements of the GGNS PCP and shipped to Barnwell, l

SC for burial. Some resin was shipped to Scientific Ecology Group j

(SEG) of Oak Ridge, TN for volume reduction.

SEG shipped reduced waste to Barnwell, SC.

Reduced volume was used in providing information given in A.1.a.

b.

DAW was packaged in 20' scalands or B-25 boxes and shipped to Scientific Ecology Group (SEG) of Oak Ridge, TN for volume reduction.

l SEG shipped reduced waste to Barnwell, SC.

Reduced volume was used in j

providing information given in A.1.b.

No irradiated components were shipped.

c.

4 d.

Electrobydraulic Fluid (EllC) was shipped to Quadrex Recycle Center in Oak Ridge, TN for solidification. Quadrex shipped the solidified waste to Richland, WA.

Solidified volume disposed of was used in j

providing information given in A.1.d.

i i

Number of Sh.loments Mode of Transportation Destination

[

I 1

71 Truck Barnwell, SC 5

Truck Richland, WA

[

i B.

Irradiated Fuel Shinments (Disposition) i Number of Shloments Mode of Transportation Destination None N/A N/A

)

C.

Annual Seware Sludre Summary Total Average Co-60 Average Mn-54 l

Number of Shipments Gallons Act ivity (nC1/11 Activity (nC1/1) i f

No Sewage was disposed of during 1992 l

l 1

I i

I TEL3 SRER901.2/SRREVFLR - 2 l

i l

i

~ -~

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1 l

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j W3130HOILf f 3VT QVIV - 0011-S3d13W83H I66Z l

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it 1

rINC 5d33C )h/S( 41 LC-W 73A3~

i L3 v/D' 0-Z f-I c-9 6-LL L2-ti tS-L2 VAC 0c 1CJY7 5dI30

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?

i TABLE 4A (Continued) l t

METEOROLOGICAL DATA - JULY-SEPTEMBER 1992 i

I l

NEUT;AL STA31 ITY CLA5S )

2ERIOD 3F RE*3R): 7/ 1/92, 300-- 13/ 1/32, 030 l

t WIdD SFEED (9/5) AT 13-M LEVEL i

1E A/G i

0- 2 3-5 6-E 9-11 12-1?

If-17 AND u?

TJr4L SPIED i

N 9.3

.3 3

.3

.0

.3 9.3 1

WNE 5.4

.2

.3

.]

.0

.0 5.;

1 l

NE 5.4

.2 3

.3

.0

.C 5.5 1

l ENE 3.7

.2

.0

.3

.0

.3

.0 3.?

.0 D E 1.2

.0 0

.]

.0

.0 1.

0-I ESE 1.3

.0 5

.3

.5

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't - ]

0 i

R SE 2.3

.0

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.0

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l ei SSE L.7

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.0 0

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l V T 35W t.:

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.0 3

3

.0

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METEOROLOGICAL DATA - JULY-SEPTEMBER 1992 SLIGHTLf STa3 E STA3I.ITf CLASS I

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3L SnTLY S T13L I STA3!.ITY Ctags E

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........................--......--.......--.....----.a-..........a-.4..

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___________________..________________;_._______.___..a____________a_,

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2

f

C

C L*I L CC"C

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5c* urruS 03 4VC E %ISSINO CV1? 03 2*2 c?k33A1 3Ch EEC? HC ne S.

1 t

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SH336OI'Z/SMH3A31H - 19 i

I

TABLE 4A (Continued)

METEOROLOGICAL DATA i

{

PERIOD OF RECORD: 7/1/92. 000 -- 10/1/92. 000 r

P E R C E tii eAD D4TA R2 PORT

?E333T COVER 5 220' HOURS

.40uRS P E :. C ita r 509 D I R E C TI O N' 40 2.22 i

f E0t WIN) SPEE0 49.

2.22 109 DIRECTION 4?.

2.22 109 WIND PIED 42 2.22 TE9)ERATURE 6:.

2.25 DE4 POINT 43 2.22 DELTA T 47 2.22 P2iCIPITET10t.

15.

.71

[

t L

I e

F e

i f

a

)

i A

i i

i I

i

)

i l

i a

4 SRER901.2/SRREVFLR - 17 g

n

>-w=

3 i

4 e

j TABLE 4B METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 EXTRE.'iE_Y U9ETas.E STAa!.ITY CLA55 %

i PE2:;S 3F RE:3 R): 10/ 1/32, 300--

1/ 1/?3, 333 4:NO I2EED (w/I) AT 13-M LEVE.

13 A/S 3-2 3-E a-3 0-11 12-le 13-17 A90 US T3rAL SP!ID N

4.1 1.2

.3

.0

.3 5.5.

.1 1

N r. E

.2

.5

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sc-

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2.3

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.?

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4

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4AW

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.1 l

CAli 2.3 2.3 13'.1

.1 TOTAL di.4 12.5

.3

.0

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~. 200R5 ?F EA? J: '!55IrlG DATA 3R

.3 PERCENT FOR 24c 0013 I

i l

t I

i r

t t

I t

1 i

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{

t SRER901.2/SRREVFLR - 1 l

i

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L r

TABLE 4B (Continued) r EETEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 t

i iC'ERATILY J1STA3LE STA?ILITY CLASS 3 l

s PERIOD JF RE DR):10/ 1/72, 200--

1/ 1/?3r 030 s

s ; *: 0 Of E D ( *. / S ) AT 13-M LEVE.

13 A/S i

-I 1 -!

t:

9-11 12-le 15-17 AND US T3rAL 3PIID s

13.J

.2

.~

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.0

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.2 AE s.s c.:

.5

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.2-di 2.3

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.5

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W E S01 10.5

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D I 3.

a.L

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CALM

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TOTAL V6.3 4.3

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3.

riC U R L 0F 'A) JC MI S '!! G JATA C i-

.0 PER05NT F04 50 h3013 i

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f.

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)

b i

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i iw SRER901.2/SRREVFLR - 2 P

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-.-y a

1 a

TABLE 4B (Continued)

METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 i

i Oil,HTL( UNSTA3.E ST AG!.lTr CL Ass *

.:R:3D 3F RE 0R): 10/ 1/02, 300- - 1/ 1/?3, 033 41NO 2, 3 E 5 ")

( 4 / ', ) AT 1]-f LIVE.

la AIG v-I 3-5 t-3 0-11 12-14 15-17 AND US T 3r At.

30!33

v s.:

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.?

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s.2

) ;

3.1

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i

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. n.=

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1.5 1.,

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d C u ?. ; CF

~J ) JR ". ! S S I N G >ATA 3F

.3 PERCENT F39 64 H3013 I

4 1

l i

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1 SRER901.2/SRREVFLR - 3

TABLE 4B (Continued)

METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 "iUT-AL 5TASI ITY.CL455 )

PT-Op 3F 8.E C O R ): 10 / 1/72, 300--

1/ 1/?3, 03 0

. ;.t 2EI'; (4/t) AT 13-1 LEVE.

13 A/G 2-I 3-11 1_-14 15-17 AM) U2 TOTAL S P I'I S 1;.1

.i

.]

. ~. -

.]

10.5

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.7

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.? PERCENT FOR

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M9 2 3 t

l 6

f r

r J

l 1

SRER901.2/SRREVFLR - 4

7, l

r i'

TABLE 4B (Continued)

METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 1

CL**WTLf S T a 3. 2 3TAEI.ITY CL ASS I l

PERILD 3F Ri'3 R):10 / 1/ 9 2, 300--

1/ 1/73, 033:

JIND 3rii) ( al / 5 ) AT 13-V'LEVE.

18 A/G G-2

' -5 t-s 0-11 12-14 15-17 AND JP TOTAL SPIID d

s.4

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1.5

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}

C A L.1 f.;

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nJU.L OF CAD C.i %I5 SING )ATA DE

.3 PIRCENT FOR 716 H3013 I

l i

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i SRER901.2/SRREVFLR - 5 1

i

TABLE 4B (Continued)

METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992

0024aTiLY 57A3.2 ST ABI.ITY CLA35 F SI4I.0 3F RE;DR3: 10 / 1/ ? Ei 300--

1/ 1/73, 030 J~*.c

riED (1/L) AT 13-M LIVE.

13 A/G u-:

~

7-11 12-16 15-17 49D 00 T3TAL 3P52D 9

a.!

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.]

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.]

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.]

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.]

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0

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l SRER901.2/SRREVFLR - 6 l

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i TABLE 4B (Continued)

METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 EXTSiti_Y STa9LI

- 3 T ABI' ITY Class 5

?:0:;3 ;F diC30:1J/ 1/72, 300--

1/ 1/73, 030

< I:J O trii) ( !/ 3) ST 13-* LEVE.

12 A/G L-2 3-5

-11 12-11 15-17 AND US T;TAL SPEID 4

.c

.]

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J: 2

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I SRER901.2/SRREVFLR - 7 I

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t TABLE 4B (Continued) l i

METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 t

-xTSE"5 r UNii %E iTesI.ITY CLA;S 6 os3: LO OF :E :0 ? ): 10 / 1/ ; ?,

333--

1/ 1/73, 033 I

s ! *; ;. SeCE'a (*/0) AT 53-1 LEVI.

l 18 A/G-C-;

3-5 f-i 9-11 12-1:.

15-17 A VD ' P ' TOTAL SPIED J

N L.,

1.

.]

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.]

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METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 i

t i

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i METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 1

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METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 i

A NEUT UL STA9I.ITY CLASS )

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METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 40LERATELY sia2_E ST A3!.ITY CL ASS F PERIOD 3F RE* 0 0: 10/ 1/02, 300--

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METEOROLOGICAL DATA - OCTOBER-DECEMBER 1992 f

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PERIOD OF RECORD:

10/1/92.

000 -- 1/1/93. 000 i

PERCENT SAD DATA REPORT I

REPORT COVERS 220SHOURS HOURS PERCINT 501 DIRECTION 173.

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METEOROLOGICAL DATA

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TABLE 4C'(Continueil J

METEOROLOGICAL DATA

SUMMARY

JANUARY - DECEMBER 1992 PERIOD OF RECORD:

1/1/92. 000 -- 1/1/93. 000 l

'l f

PERC f4T SAD DATA REPORT REPCPT COVERS 3704dOURS l

HOURS PE RCE NT t

509 DIRECTION 4J1.

4.57 539 WI '!D SSEED 405.

4. 61 134 DIRECTION 401.

4.57:

l 104 W I 'J D S>EED 405.

4.d1 TEMPERAT'JRE 426.

4. 85 i

i DE4 DOINT 462.

5.25 l

DE_TA T 471.

5.35-i

> R E CIP IT A T I,f4 IOS.

3.51 l

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SRER901.2/SRREVFLR - 17 k

i re- =

r

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e TABLE 4D CLASSIFICATION OF ATMOSPHERIC STABILITY a

Statulit y PsacuHI of Temperature change Ctessificanon Categones (degrees}

wrth heeght (* C/loomi Extremely unstable A

25.0

<-1.9 Moderately unstable B

20.0

-1.91o.1.7 Slightly unstable C

15.0

-1.71o.1.5 Neutral D

10.0

.l.510 0.5 Slightly stable E

5.0 4.5 to 1.5 Moderately stable F

2.5 1.5 to 4.0 l

Extrernely stable G

1.7

>4.0 t

a Standard deviation of horizontal wind direction fluctuation over a penod of 15 minutes to I hour. The values shown are average for each stability classification.

l l

t 3

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l SRER901.2/SEREVFLR - 1 i

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ML20034F328

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