ML20209H745

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Radioactive Effluent Releases & Waste Disposal,Jan-June 1986
ML20209H745
Person / Time
Site: Humboldt Bay
Issue date: 06/30/1986
From:
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20209H712 List:
References
NUDOCS 8609150338
Download: ML20209H745 (21)
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PGandE Letter No.: HBL-86-027 ENCLOSURE 1 RADIOACTIVE EFFLUENT RELEASES AND HASTE DISPOSAL FROM HUMBOLDT BAY POWER PLANT UNIT 3, COVERING THE PERIOD JANUARY 1, 1986 THROUGH JUNE 30, 1986 i

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PACIFIC GAS AND ELECTRIC COMPANY DOCKLT NO. 50-133 LICENSE N0. DPR-7 RADI0 ACTIVE EFFLUENT RELEASES AND WASTE DISPOSAL FROM HUMBOLDT BAY POWER PLANT UNIT NO. 3, C0VERING THE PERIOD JANUARY 1, 1986 THROUGH JUNE 30, 1986 -

_ _ _ . +'~

This report summarizes the quantity of each of the principal radionuclides released in liquids and gaseous effluents to unrestricted areas and summarizes radioactive waste disposal from January 1, 1986 through June 30, 1986. This report is required by Section IX.I.3.a of the Humboldt Bay Power Plant, Unit No. 3, Technical Specifications.

A. SUPPLEMENTAL INFORMATION

1. Regulatory Limits:
a. Fission and activation gases: The current license limits are 50,000 micro-Curies per second for an annual average release rate and 500,000 micro-Curies per second for an instantaneous release. .
b. Iodines: Refer to c. (Particulates).
c. Particulates: The carrent license limit "for halogens and particulate materir.1 based on the isotopes present on the sample filters after 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> decay period" is 0.18 micro-Curies per second.
d. Liquid Effluents: 10CFR20.
2. Maximum Permissible Concentrations:

The concentrations used to determine allowable release rates or concentrations are as follows:

a. Fission and activation gases: Not applicable,
b. Iodines: 3E-10 micro-Curies per cc.
c. Particulates (half-lives >8 days): 3E-10 micro-Curies per cc,
d. Liquid effluents: 10CFR20, Table II, Appendix B. Refer to Table C1 for the values used, based on the mixtures for each quarter.

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3. Average energy:

Not applicable.

4. Measurements and Approximations of Total Radioactivity:

The methods used to measure or approximate the total radioactivity in effluents and to determine radionuclide composition are as follows:-

a. Fission and activation gases: Due to the long decay time since operation (shutdown July 2, 1976) no detectable releases of fission and activation gases can be expected. Accordingly, these radionuclides are not reported,
b. Iodines: Charcoal cartridges are removed from the stack sampling system weekly and, after 48 hour-decay, are analyzed for I-131 and I-133 (Intrinsic Germanium detector). Due to the long decay time since operation (shutdown July 2, 1976) no detectable releases of radioactive iodines of plant origin can be expected,
c. Particulates: Filter papers are removed from the stack sampling system weekly and, after 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> deca for gross alpha (Internal Proportional Counter)y, are analyzed and the concentration of gamma emitting nuclides (Intrinsic Germanium detector). All statistically significant peaks are identifed.

The filters for each quarter are analyzed for radioactive Strontium (all Sr-90 due to decay time).

The error of the reported iodine and particulate release values is estimated based on uncertainty in sample flow rate, stack flow rate, detector calibration, and typical sample counting statistics,

d. Liquid effluents: Liquid waste batch samples were gamma spectrum counted and counted for gross beta radioactivity. All statistically important peaks were identified. Quarterly composites of all batches were analyzed for gross alpha, Tritium and radioactive Strontium (Sr-90).

The error of the reported release values is estimated based on uncertainty in sample volume, batch volume, detector calibration, and typical sample counting statistics.

5. Batch releases:
a. Liouid:
1) Number of batch releases: 56 (A total of 16,905 gallons of laundry waste and 166,591 gallons of treated waste tank discharge).

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2) Total time period for batch releases: 8.81E3 minutes.
3) Average time period for a batch release: 1.57E2 trinutes.
4) Maximum time period for a batch release: 4.27E2 .ninutes.
3) Minimum time period for a batch release: 1.50E1 minutes.
6) Average stream flow during periods of release of effluents into a flowin Not applicable (Discharge is into HumboldtBay)gstream:
b. Gaseous: None.
6. Abnormal releases:
a. Liquid:
1) Number of releases: None.
2) Total activity released: None,
b. Gaseous:
1) Number of releases: None.
2) Total activity released: None.

B. GASE0US EFFLUENTS The monitoring systems associated with the liquid radwaste system vent to atmosphere indicated that no detectable releases of radioactive gases occurred during the report period. Because quarterly checks of the HEPA filters on the vent were satisfactory, only gaseous radioactive waste releases made via the 250 foot stack are reported.

Table B-1 summarizes the total quantities of radioactive effluents released by quarter. Table B-2 summarizes the total quantities for each of the nuclides determined to be released.

The ambient atmosphere was found to contain Ru-103, I-131 and Te/I-132 after the Chernobyl reactor accident. Because these nuclides did not originate from Unit No. 3 operation, they are not included in Tables B-1 and B-2, and their contribution to population doses was not calculated.

The quantities of these nuclides transported through the plant ventilation system (discharged from the stack) were 5.41E-06 Curies, 1.98E-07 Curies, and 1.80E-06 Curies for 1-131, Te-132, and Ru-103, respectively.

C. LIQUID EFFLUENTS Analysis of weekly composite samples from the plant intake and the plant effluent canal and monitoring by the liquid radwaste discharge monitor confirmed that no unaccounted release of radioactive waste occurred during the report period.

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7 Table C-1 summarizes the total quantities of radioactive liquid effluents released by quarter. Table C-2 summarizes the total quantity for each of the nuclides determined to be released.

D. SOLID WASTE

~

~~ Dtiring the Teport period,-a- total of 450.2 cubic meters of solid .

radioactive waste, totaling 334.9 Curies, was shipped. Table D-1 ~'

summarizes these radioactive waste shipments.

E. RADIOLOGICAL IMPACT ON MAN Plant releases continued to be much lower than when the plant last operated. A comparison of calculated doses by various paths has shown that the off-site doses are primarily due to direct radiation and to the consumption of aquatic foods. Other pathways contribute less than 5% of the total doses to the public. Maximum doses to individuals are summarized in Table El. These doses comply with 40CFR190 since there are no other fuel cycle facilities within 8 km.

1. Doses to the average individual in the population from all receiving-water-related pathways were calculated for the releases detected, based on the guidance of Regulatory Guide 1.109. The maximum results were 0.018 mrem per Yr (Total Body) for the Adult age group, and 0.027 mrem per Yr for the liver of the Teen age group.
2. Total body doses to the average individual in the population from gaseous effluents to a distance of 50 miles from the site were calculated on a comparative basis and found to be insignificant.

The highest potential calculated dose is less than 0.005 mrem per Yr.

3. Total body doses to the average individual in unrestricted areas from direct radiation from the facility have been measured with 30 dosimeter stations (Figure 1) in the vicinity of the Plant.

Ionization chambers, read on a biweekly basis, are used for dosimetry. Stations 2 and 5 are considered to be background in that they are assumed to be completely removed from the influence of the plant. In order to test for statisticall between stations, two statistical tests (ya significant differences two-way classification, and a 95% confidence limit least significant difference test) were made for the dosimeter station readings. The following table summarizes the results of this analysis. The report period exposure results for each station were based on biweekly data extrapolated to 26 weeks and are listed in order from highest to lowest exposures.

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STATISTICAL ANALYSIS OF 00SIMETRY DATA (FIRST HALF 0F 1986)

MEAN (mR) WEEKS OF TOTAL (mR)

SI6IlgN {2,y(($,PEglgg} ,,g6I6,, {2@,yEE5,PEglgg}

_ __ 9 4.4 26 57.0

'26 20~ ~ - ~ ~3 .T ' - 9e.9 21 3.6 24 46.6 1 3.6 26 46.3 15 3.5 26 45.1 16 3.5 26 45.1 27 3.5 26 45.0 26 3.4 24 44.6 23 3.4 26 44.1 22 3.4 26 43.9 8 3.3 26 43.1 29 3.3 26 42.7 4 3.3 26 42.6 2 3.3 26 42.4 11 3.3 26 42.3 6 3.2 26 41.7 5 3.2 26 41.2 25 3.1 26 40.5 3 3.1 26 40.0 30 3.1 22 40.0 14 3.1 26 39.9 18 3.0 26 39.5 28 3.0 26 39.5 13 3.0 26 39.4 l 19 3.0 26 39.0

~

17 3.0 26 38.8 10 2.9 26 38.1 12 2.9 26 37.4 7 2.8 26 36.7 24 2.8 26 36.2 Least Significant Difference between station means = 0.6 Least Significant Difference between replication means = 2.1 Stations 2 and 5 are considered background.

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. - ._ .. = - _ -.

F. METEOROLOGICAL DATA The meteorological data logging system was removed from service in 1967.

Therefore, the information specified by Regulatory Guide 1.21, Appendix B, Section F, is not readily available for this report period.

Table F1 summarizes the cumulative joint frequency distribution of wind speed, direction, and atmospheric stability for the period April,1962 3

through June, 1967 when the meteorological data logging system was in service.

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TABLE B1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1986 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES UNIT FIRST SECOND EST. TOTAL QUARTER QUARTER ERROR, %

A. FISSION GASES

1. Total Release Ci ** ** **
2. Average Release micro-Ci Rate for Period per sec. ** **
3. Percent of Tech.

Spec. Limit  % ** **

B. 10 DINES

1. Total I-131 Ci ** ** **
2. Average Release micro-Ci Rate for Period per sec. ** **
3. Percent of Tech.

Spec. Limit  % ** **

C. PARTICULATES

1. Total with Half-lives >8 days Ci 7.81E-5 2.85E-5 3.00E1
2. Average Release micro-Ci Rate for Period per sec. 1.01E-5 3.62E-6
3. Percent of Tech.

Spec. Limit  % 5.61E-3 2.01E-3

4. Gross Alpha Radio-activity C1 1.29E-6 4.77E-7 D. TRITIUM
1. Total Release Ci LT9.80E-3 LT9.91E-3 5.00E1
2. Average Release micro-Ci Rate for Period per sec. LT1.26E-3 LT1.26E-3 Note: **No release can be expected due to decay time since shutdown (July 2, 1976). Accordingly, no release is reported.

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7 TABLE B2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1986 GASE0US EFFLUENTS - ELEVATED RELEASES - CONTINU0US MODE NUCLIDES RELEASED UNIT FIRST SECOND QUARTER QUARTER A. FISSION GASES Krypton-85 Ci ** **

Krypton-85m Ci *" **

Krypton-87 Ci ** **

Krypton-88 Ci ** **

Xenon-133 Ci ** **

Xenon-135 Ci ** **

Xenon-135m Ci ** **

Xenon-138 Ci ** **

Total for period Ci ** **

8. 10 DINES Iodine-131 Ci ** **

Iodine-133 Ci ** **

Iodine-135 Ci ** **

Unidentified Ci LT3.67E-6 LT1.91E-5 Total for period Ci ** **

C. PARTICULATES Strontium-89 Ci ** **

Strontium-90 Ci 3.44E-7 3.20E-7 Cesium-134 Ci 3.02E-7 7.53E-7 Cesium-137 Ci 3.43E-5 9.84E-6 Ci ** **

Barium / Lanthanum-140 Cobalt-60 Ci 4.23E-5 1.76E-5 Manganese-54 Ci ** **

Antimony-125 Ci 8.70E-7 LT1.25E-5 Europium-154 Ci LT1.25E-5 LT1.25E-5 Unidentified Ci LT1.25E-5 LT1.25E-5 Total for period Ci 7.81E-5 2.85E-5 Note: ** No release can be expected due to decay time since shutdown (July 2, 1976). Accordingly, no release is reported.

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7 TABLE C1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1986 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT FIRST SECOND EST. TOTAL QUARTER QUARTER ERROR, %

A. FISSION AND ACTIVATION PRODUCTS

1. Total release.(not including tritium, gases, or alpha) Ci 1.18E-2 1.71E-2 1.50E1
2. Average diluted concentration micro-Ci during period per ml 5.54E-9 1.51E-9
3. Percent of applicable limit  % 4.07E-2 1.15E-2
4. Applicable limit micro-Ci used (Mixture MPC) per ml 1.36E-5 1.31E-5 B. TRITIUM
1. Total release Ci 1.94E-2 1.89E-3 1.50El
2. Average diluted micro-Ci concentration during period per ml 9.11E-10 1.67E-10
3. Percent of applicable limit  % 3.04E-5 5.57E-6 C. DISSOLVED AND ENTRAINED GASES
1. Total release ci ** ** **

D. GROSS ALPHA RADI0 ACTIVITY

1. Total release Ci LT4.73E-5 LT1.47E-4 5.00E1 E. Volume of waste released (

dilution) prior to liters 1.69E5 5.26E5 1.00E1 F. Volume of dilution water used during period liters 2.13E10 1.13E10 1.50E1 Note: ** No release can be expected due to decay time since shutdown (July 2, 1976). Accordingly, no release is reported.

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7 TABLE C2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1986 i

LIQUID tFFLUENTS - BATCH MODE

! NUCLIDES RELEASED UNIT FIRST SECOND i i QUARTER QUARTER l Strontium-89 Ci ** **

l 1

Strontium-90 Ci 8.78E-5 1.40E-4 Cesium-134 Ci 1.86E-4 2.30E-4 i.

Cesium-137 Ci 1.01E-2 1.54E-2 Iodine-131 C1 ** **

I Cobalt-58 Ci ** ** 1 Cobalt-60 Ci 1.41E-3 1.37E-3  !

j Iron-59 Ci ** **

[

Zinc-65 Ci ** ** t i Manganese-54 Ci ** ** l Chromium-51 Ci ** **

3 I Zirconium / Niobium-95 Ci ** **

Molybdenum-99 Ci ** **

j Technetium-99m Ci ** **

i Ci ** **

j Barium / Lanthanum-140 Cerium-141 Ci ** **

i 4

Unidentified Ci Lil.86E-b LT1.08E-4 ,

. 1 l  !

l Total for period (above) Ci 1.18E-2 1.71E-2 Xenon-133 Ci ** **

2 Xenon-135 Ci ** ** i i

! Note: ** No release can be expected due to decay time since shutdown j (July 2, 1976). Accordingly, no release is reported.  ;

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TABLE D1 EFFLUENT AND WASTE DISF0 SAL SEMIANNUAL REPORT FIRST HALF 0F 1986 SOLID WASTE AND IRRADIATED FUEL SHIRMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL-(Not irradiated fuel)

1. Type of waste UNIT 6-month EST. TOTAL Period Error %
a. Spent resins, filter Cubic sludges, evaporator Meter 1.24E+02 1.0E+01 bottoms, etc. C1 3.20E+02 1.5E+01
b. Dry compressible Cubic waste, contaminated Meter 3.24E+02 1.0E+01 equipment, etc. Ci 1.43E+01 2.0E+01
c. Irradiated components Cubic control rods, etc. Meter None -----

C1 None -----

d. Other (absorbed Cubic liquids) Meter 2.12E+00 1.0E+01 C1 9.36E-01 1.5E+01__
2. Estimate of major nuclide composition (by type of waste).

Type Nuclide

a. H-3  % 3.44E-02 C-14  % 1.56E-02 Mn-54  % 2.38E-02 Fe-55  % 6.98E+01 Co-60  % 1.97E+01 Ni-59  % 1.93E-02 Ni-63  % 2.60E+00 Zn-65  % 1.48E-02 Sr-90  % 3.57E-01 Tc-99  % 8.88E-04 Sb-125  % 3.13E-02 I-129  % 1.44E-04 Cs-134  % 9.23E-02 Cs-137  % 6.13E+00 j Ce-144  % 2.60E-05 Eu-152  % 4.47E-03 Eu-154  % 3.0ZE-02 Eu-155  % 7.57E-03 Ra-ZZ8  % 1.88E-06 U-235  % 2.10E-06 U-238  % 2.35E-05 DCPP2 11 _ _ _ _ _ -

7 TABLE D1 (Continued)

a. (Continued)

Pu-238  % 1.76E-02 Pu-239  % 7.88E-03 Pu-240  % 8.16E-03 Pu-241  % 1.13E+00 Am-241  % 2.56E-02

b. H-3  % 2.11E-02 C-14  % 6.48E-U2 K-40  % 7.08t-02 Mn-54  % 3.50E-02 Fe-55  % 7.70E+01 Co-58  % 5.llE-03 Co-60  % 1.15E+01 Ni-59  % 1.40E-02 Ni-63  % 1.59E+00 Zn-65  % 2.52E-02 Sr-90  % 3.70E-01 Nb-94  % 3.64E-03 Zr-95  % 5.39E-03 Tc-99  % 6.12E-01 I-129  % 8.54E-03 Cs-134  % 8.96E-02 Cs-137  % 6.37E+00 Ce-144  % 2.87E-03 Eu-152  % 9.66E-01 Eu-154  % 6.23E-03 Eu-155  % 4.82E-01 Pu-241  % 8.19E-01 Am-241  % 1.53E-02
d. H-3  % 5.55E-01 C-14  % 9.50E-02 Fe-55  % 3.10E+01 Co-60  % 1.60E+01 Ni-b9  % 1.07E-01
Ni-63  % 3.95E+00 Sr-90  % 7.90E-01 Tc-99  % 1.17E+00 I-129  % 5.45E-02 Cs-134  % 5.13E-01 Cs-137  % 4.49E+01 Pu-241  % 9.18E-01
3. Solid Waste Disposition:

Nuniber of Shipments Mode of Transportation Destination 52 Truck Richland, Washington B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None --- ---

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7 TABLE El EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 0F 1986 MAXIMUM 0FF-SITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC Annual Dose, Millirem (8)

Third Fourth First Second Four Quarter Quarter Quarter Quarter Quarter Source 1985 1985 1986 1986 Average 0.08(6) 0.07(6) 0.04(6) 0.10(6) 0.07 Liquid Effluents (1) 0.12(7) 0.10(7) 0.05(7) 0.15(7) 0.10 Airborne Effluents (5)

Iodines & Particulates (2) -- -- -- -- --

Noble Gases (3) -- -- -- -- --

Direct Radiation (4) 0.30 0.35 0.30 0.34 0.32 Notes: 1. Maximum total body and organ doses to individuals in unrestricted areas from receiving-water-related exposure pathways has been calculated for detected liquid releases, based on the average concentrations for the report period, and the generic parameters of Regulatory Guide 1.109.

2. Total body and skin doses to individuals exposed at the point of maximum off-site ground-level concentrations of radioactive materials in gaseous effluer: was not calculated because there were no significant releases of i.:ioactive noble gases.
3. Organ doses to individuals in unrestricted areas from radioactive Iodine and radioactive Particulates for all pathways of exposure was calculated on a comparative basis and found to be insignificant.

The highest potential calculated dose to any organ of an individual is less than 0.005 mrem /Yr.

4. Total body doses (to the maximum individual in the population) are based on TLD results of stations at the site boundary, using the shore-line occupancy factors given in Regulatory Guide 1.109 for the maximum potential individual (Teen age group).
5. Based on mete.rology data as discussed in section F.
6. Total Body (Adult age group)
7. Liver (Teen age group)
8. The dose shown for each quarter is calculated on an annual basis for four identical quarters.

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,g TABLE F1 PERCENT OF TIME FOR EACH WIND SPEED AND DIRECTION FOR THE PERIOD APRIL, 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STABILITY CLASS: PASQUILL 'C' WIND WIND SPEED (MPH)

DIRECTION ------------------------------------------------------

(DEGREES) 0-3 4-7 8-12 13-18 19-24 >24 Total 0 0.02 0.06 0.05 0.03 0.02 0.01 0.20 10 0.02 0.03 0.04 0.03 0.01 0.00 0.13 20 0.03 0.03 0.01 0.01 0.00 0.00 0.08 30 0.02 0.02 0.00 0.00 0.00 0.00 0.04 40 0.00 0.01 0.00 0.01 0.00 0.00 0.02 50 0.01 0.01 0. 0 0.00 0.00 0.00 0.02 60 0.01 0.01 0.00 0.00 0.00 0.00 0.03 70 0.00 0.00 0.00 0.00 0.00 0.00 0.00 80 0.01 0.00 0.00 0.00 0.00 0.00 0.01 90 0.00 0.00 0.00 0.00 0.00 0.00 0.01 100 0.00 0.00 0.00 0.00 0.00 0.00 0.00 110 0.00 0.00 0.00 0.00 0.00 0.00 0.01 120 0.01 0.01 0.01 0.00 0.00 0.00 0.03 130 0.01 0.01 0.00 0.01 0.00 0.00 0.03 140 0.00 0.01 0.01 0.00 0.01 0.00 0.02 150 0.00 0.01 0.01 0.02 0.01 0.00 0.06 160 0.00 0.01 0.01 0.01 0.01 0.00 0.04 170 0.00 0.00 0.02 0.02 0.01 0.01 0.07 180 0.00 0.01 0.02 0.02 0.00 0.00 0.05 190 0.01 0.01 0.01 0.01 0.01 0.00 0.04 200 0.00 0.02 0.02 0.02 0.00 0.01 0.09 210 0.02 0.03 0.06 0.02 0.01 0.00 0.13 220 0.01 0.02 0.08 0.04 0.03 0.02 0.19 230 0.01 0.06 0.12 0.14 0.05 0.02 0.39 240 0.01 0.09 0.22 0.15 0.02 0.03 0.51 250 0.02 0.18 0.26 0.10 0.02 0.00 0.58 260 0.02 0.13 0.24 0.04 0.01 0.00 0.44 270 0.02 0.16 0.22 0.02 0.01 0.00 0.42 280 0.02 0.13 0.11 0.01 0.00 0.00 0.27 290 0.02 0.10 0.10 0.01 0.01 0.00 0.24 300 0.01 0.09 0.06 0.00 0.00 0.00 0.15 310 0.01 0.04 0.06 0.01 0.00 0.00 0.12 320 0.01 0.03 0.05 0.01 0.01 0.01 0.12 330 0.01 0.03 0.03 0.01 0.02 0.01 0.11 340 0.01 0.04 0.04 0.03 0.02 0.01 0.15 350 0.01 0.02 0.06 0.07 0.05 0.01 0.22 Rows may not sum to exact total due to rounding off.

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7 TABLE F1 (Cont)

PERCENT OF TIME FOR EACH WIND SPEED AND DIRECTION FOR THE PERIOD APRIL, 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STABILITY CLASS: PASQUILL 'D' WIND WINDSPEED(MPH)

DIRECTION ------------------------------------------------------

(DEGREES) 0-3 4-7 8-12 13-18 19-24 >24 Total 0 0.11 0.34 0.78 0.85 0.49 0.48 3.05 10 0.04 0.27 0.52 0.46 0.38 0.27 1.95 20 0.05 0.21 0.32 0.19 0.16 0.11 1.04 30 0.06 0.20 0.16 0.08 0.03 0.04 0.58 40 0.05 0.11 0.05 0.02 0.00 0.01 0.23 50 0.03 0.05 0.08 0.00 0.01 0.00 0.16 60 0.04 0.08 0.04 0.00 0.00 0.00 0.15 70 0.04 0.02 0.01 0.01 0.00 0.00 0.08 80 0.02 0.04 0.00 0.01 0.00 0.00 0.07 90 0.01 0.04 0.03 0.00 0.00 0.00 0.09 100 0.02 0.01 0.02 0.00 0.00 0.00 0.05 110 0.00 0.03 0.01 0.01 0.00 0.00 0.06 120 0.02 0.03 0.03 0.02 0.01 0.00 0.11 130 0.01 0.03 0.02 0.02 0.01 0.00 0.10 140 0.02 0.03 0.02 0.04 0.01 0.01 0.13 150 0.03 0.03 0.03 0.09 0.03 0.02 0.23 160 0.01 0.04 0.05 0.10 0.04 0.01 0.26 170 0.02 0.05 0.12 0.16 0.04 0.01 0.40 180 0.04 0.08 0.12 0.13 0.03 0.01 0.40 190 0.02 0.07 0.09 0.06 0.03 0.02 0.28 200 0.05 0.10 0.17 0.11 0.02 0.01 0.46 210 0.05 0.12 0.20 0.08 0.04 0.01 0.51 220 0.05 0.14 0.14 0.12 0.05 0.02 0.51 230 0.03 0.14 0.17 0.11 0.06 0.02 0.53 240 0.08 0.22 0.21 0.06 0.03 0.01 0.61 250 0.08 0.17 0.13 0.04 0.01 0.00 0.43 260 0.08 0.22 0.13 0.02 0.01 0.00 0.47 270 0.12 0.21 0.11 0.03 0.01 0.00 0.49 280 0.05 0.20 0.11 0.04 0.00 0.00 0.40 290 0.04 0.22 0.11 0.02 0.00 0.00 0.39 300 0.10 0.21 0.21 0.02 0.01 0.00 0.53 310 0.08 0.28 0.19 0.03 0.02 0.01 0.60 320 0.07 0.25 0.33 0.09 0.04 0.01 0.80 330 0.06 0.21 0.35 0.16 0.09 0.03 0.90 340 0.0/ U.24 0.50 0.47 0.17 0.08 1.53 300 0.07 0.33 0.82 0.86 0.49 0.33 2.87 Rows may not sum to exact total due to rounding off.

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)

TABLE F1 (Cont)

PERCENT OF TIME FOR EACH WIND SPEED AND DIRECTION FOR THE PERIOD APRIL, 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STABILITY CLASS: PASQUILL 'E' WIND WINDSPEED(MPH)

DIRECTION ------------------------------------------------------

(DEGREES) 0-3 4-7 8-12 13-18 19-24 >24 Total 0 1.04 1.06 2.00 1.84 0.82 0.10 6.86 10 0.17 0.80 1.55 0.90 0.36 0.10 3.78 20 0.30 0.83 1.26 0.47 0.13 0.00 2.99 30 0.37 0.73 0.64 0.19 0.01 0.00 1.94 40 0.21 0.60 0.47 0.02 0.00 0.00 1.31 50 0.18 0.56 0.28 0.02 0.00 0.00 1.05 60 0.21 0.54 0.19 0.00 0.00 0.00 0.93 70 0.19 0.44 0.07 0.00 0.00 0.00 0.81 80 0.20 0.41 0.07 0.00 0.00 0.00 0.68 90 0.27 0.47 0.17 0.01 0.00 0.00 0.82 100 0.17 0.24 0.06 0.01 0.00 0.00 0.49 110 0.20 - 0.31 0.10 0.00 0.00 0.00 0.60 120 0.18 0.31 0.19 0.01 0.02 0.00 0.70 130 0.14 0.25 0.08 0.08 0.03 0.03 0.72 140 0.09 0.22 0.21 0.23 0.22 0.25 1.21 150 0.09 0.24 0.22 0.45 0.52 0.46 2.08 160 0.05 0.22 0.25 0.62 0.44 0.21 1.79 170 0.04 0.26 0.43 0.73 0.23 0.09 1.89 180 0.26 0.32 0.45 0.43 0.20 0.02 1.77 190 0.15 0.26 0.37 0.35 0.15 0.02 1.20 200 0.22 0.48 0.47 0.26 0.18 0.06 1.77 210 0.20 0.44 0.58 0.18 0.05 0.04 0.60 220 0.20 0.40 0.55 0.15 0.14 0.03 1.37 230 0.23 0.43 0.40 0.14 0.13 0.05 1.39 240 0.24 0.39 0.23 0.15 0.13 0.01 1.24 250 0.21 0.32 0.16 0.03 0.01 0.01 0.84 260 0.24 0.31 0.17 0.03 0.00 0.00 0.85 270 0.35 0.35 0.13 0.12 0.01 0.00 0.97 280 0.19 0.30 0.15 0.01 0.01 0.01 0.67 290 0.19 0.33 0.17 0.01 0.01 0.01 0.81 300 0.21 0.37 0.16 0.01 0.00 0.01 0.88 310 0.20 0.47 0.29 0.02 0.00 0.00 0.98 320 0.20 0.59 0.65 0.12 0.01 0.05 1.72 4

330 0.22 0.87 0.98 0.35 0.02 0 02

. 2.45 340 0.20 0.88 1.55 0.74 0.01 0.00 3.48 350 0.19 1.02 2.02 1.41 0.55 0.13 5.22 Rows may not sum to exact total due to rounding off.

DCPP2 16

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TABLE F1 (Cont)

PERCENT OF TIME FOR EACH WIND SPEED AND DIRECTION FOR THE PERIOD APRIL, 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION  ;

STABILITY CLASS: PASQUILL 'F' WIND WIND SPEED (MPH)

DIRECTION ------------------------------------------------------

(DEGREES) 0-3 4-7 8-12 13-18 19-24 >24 Total 0 0.42 0.08 0.03 0.00 0.00 0.00 0.53 10 0.05 0.06 0.05 0.01 0.00 0.00 0.18 20 0.05 0.09 0.08 0.03 0.00 0.00 0.24 30 0.12 0.11 0.10 0.04 0.00 0.00 0.37 40 0.07 0.13 0.10 0.03 0.01 0.00 0.34 50 0.09 0.13 0.06 0.00 0.00 0.00 0.27 '

60 0.14 0.19 0.07 0.01 0.00 0.00 0.40 70 0.11 0.22 0.08 0.00 0.00 0.00 0.40 80 0.10 0.22 0.07 0.00 0.00 0.00 0.40 90 0.14 0.25 0.07 0.00 0.00 0.00 0.46 100 0.11 0.29 0.09 0.01 0.01 0.00 0.51 110 0.13 0.31 0.13 0.02 0.00 0.00 0.59 120 0.15 0.33 0.18 0.03 0.00 0.00 0.69 130 0.10 0.23 0.14 0.02 0.00 0.00 0.50 140 0.10 0.22 0.11 0.09 0.02 0.00 0.54 150 0.12 0.19 0.10 0.07 0.03 0.02 0.52 160 0.08 0.15 0.16 0.08 0.01 0.00 0.47 170 0.07 0.15 0.14 0.07 0.00 0.00 0.43 180 0.16 0.26 0.13 0.02 0.00 0.00 0.56 190 0.12 0.18 0.13 0.02 0.00 0.01 0.46 200 0.13 0.25 0.18 0.02 0.00 0.00 0.58 210 0.18 0.32 0.20 0.02 0.00 0.01 0.73 220 0.14 0.28 0.09 0.02 0.00 0.00 0.54 230 0.18 0.24 0.07 0.01 0.01 0.00 0.50 240 0.19 0.19 0.05 0.02 0.00 0.00 0.45 250 0.15 0.16 0.01 0.00 0.00 0.00 0.32 260 0.17 0.10 0.01 0.00 0.00 0.00 0.29 270 0.18 0.09 0.01 0.00 0.00 0.00 0.28 280 0.10 0.04 0.01 0.00 0.00 0.00 0.15 290 0.11 0.05 0.01 0.00 0.00 0.00 0.16 300 0.13 0.07 0.00 0.00 0.00 0.00 1.19 310 0.07 0.05 0.01 0.00 0.00 0.00 0.13-320 0.09 0.05 0.03 0.00 0.00 0.00 0.17 330 0.09 0.09 0.01 0.00 0.00 0.00 0.19 340 0.06 0.10 0.03 0.01 0.00 0.00 0.20 350 0.07 0.09 0.05 0.01 0.00 0.00 0.21 Rows may not sum to exact total due to rounding off.

DCPP2 17

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