ML20238B499

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Radioactive Effluent Releases & Waste Disposal from Humboldt Bay Power Plant Unit 3 for Jan-June 1987
ML20238B499
Person / Time
Site: Humboldt Bay
Issue date: 06/30/1987
From:
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20238B491 List:
References
NUDOCS 8709010248
Download: ML20238B499 (18)
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Text

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l HUMBOLDT BAY POWER PLANT UNIT 3 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i

JANUARY 1 - JUNlE 30,1987 l

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l PACIFIC GAS AND ELECTRIC COMPANY OOCKET NO. 50-133 LICENSE N0. OPR-7 RADI0 ACTIVE EFFLUENT RELEASES AND WASTE DISPOSAL FROM HUMBOLDT BAY POWER PLANT UNIT 3, COVERING THE PERIOD JANUARY 1, 1987, THROUGH JUNE 30, 1987 I

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This report summarizes the quantity of each of the principal radionuclides i released in liquid and gaseous effluents to unrestricted areas and summarizes '

radioactive waste disposal from January 1,1987, through June 30, 1987. This ,

report is required by Section IX.I.3.a of the Humboldt Bay Power Plant Unit 3 {

Technical Specifications. '

A. SUPPLEMENTAL INFORMATION

1. Regulatory Limits
a. Fission and activation gases: The current license limits are 50,000 microcuries per second for an annual average release rate and 500,000 microcuries per second for an instantaneous l release,
b. Iodines: Refer to c. below (Particulate).
c. Particulate: The current license limit "for halogens and ,

particulate material 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 microcuries per second.

d. Liquid effluents: 10 CFR 20.
2. Maximum Permissible Concentrations I

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

a. Gaseous effluents: I
1) Fission and activation gases: Not applicable.
2) Iodines: 3E-10 microcuries per cc.
3) Particulate (half-lives >8 days): 3E-10 microcuries per cc
b. Liquid effluents: 10 CFR 20, 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, i
4. Measurements and Approximations of Total Radioactivity The methods used to measure or approximate the total radioactivity in effluents and to determine radionuclides composition are as follows:
a. Fission and activation gases: Due to the long decay time since I operation (shutdown July 2,1976), no detectable releases of i fission and activation gases can be expected. Accordingly, I these radionuclides are not reported. f l
b. Iodines: Due to the long decay time since operation (shutdown July 2, 1976), no detectable releases of radioactive iodines of plant origin can be expected. Since the license no longer requires that these radionuclides be monitored, these radionuclides are not reported,
c. Particulate: 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 /> decay, are analyzed for gross alpha (internal proportional counter) 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 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 counted for gamma spectrum and 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. I

5. Batch releases
a. Liquid
1) Number of batch releases: 16 (1,830 gallons of laundry waste and 90,419 gallons of treated waste tank discharge) l 1

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2) Total time period for batch releases: 4.73E3 minutes
3) Average time period for a batch release: 2.96E2 minutes
4) Maximum time period for a batch release: 4.15E2 minutes
5) Minimum time period for a batch release: 1.20E1 minutes
6) Average stream flow during periods of release of effluents into a flowing stream: Not applicable (discharge is into HumboldtBay)
b. Gaseous: None
6. Abnormal releases
a. Liquid
1) Number of releases: None l 2) Total activity released: None
b. Gaseous l
1) Number of releases: None
2) Total activity released: None i

B. CASE 0US 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 J 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.

C. LIQUID EFFLUENTS Analysis of weekly composite samples frorr, 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.

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.

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D. SOLID WASTE No radioactive waste was shipped during the report period.

E. RADIOLOGICAL IMPACT ON MAN Plant releases continued to be nuch lower than when the plant last ope ra ted. A comparison of calculated doses by various paths has shown that the offsite 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 40 CFR 190 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 0.006 mrem /yr (total body) for the Adult age group, and 0.009 mrem /yr for the bone of the Child 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 /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 statistical 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 DOSIMETRY DATA (FIRST HALF 0F 1987)

MEAN (mR) WEEKS OF TOTAL (mR)

SI6I!9tj 12;yEE[_((B199} __g616,_ {26;gEEB,[EB]gg}

16 5.0 24 65.6 27 4.8 24 62.9 9 4.7 26 61.0 29 4.6 26 60.2 8 4.6 26 59.8 21 4.5 26 58.4 23 4.5 26 58.1 20 4.4 26 57.4 18 4.4 26 56.9 6 4.4 26 56.7 11 4.4 26 56.6 2 4.3 26 56.4 13 4.3 26 55.8 12 4.3 26 55.5 15 4.3 26 55.4 17 4.2 26 55.1 10 4.2 26 54.7 19 4.2 26 54.7 28 4.2 26 54.7 22 4.2 26 54.1 1 4.1 26 53.6 25 4.1 26 53.3 4 4.1 26 53.0 26 4.1 26 52.8 14 4.1 26 52.7 24 4.0 26 52.4 7 4.0 26 52.1 30 3.9 26 50.9 5 3.9 26 50.7 3 3.6 26 47.1 Least significant difference between station means = 0.5 Least significant difference between replication means = 2.3 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 through June 1967, when the meteorological data logging system was in service.

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TABLE B1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1987 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT FIRST SEC0hD 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. PARTICULATE

1. Total with Half-lives >8 Days Ci 1.12E-5 1.95E-5 3.00E1
2. Average Release micro-Ci Rate for Period per sec. 1.44E-6 2.48E-6
3. Percent of Tech Spec Limit  % 8.00E-4 1.38E-3
4. Gross Alpha Radio-activity Ci 4.03E-7 7.07E-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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TABLE B2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1987 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTIllV0US MODE NUCLIDES RELEASED UNIT FIRST SECOND OUARTER 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 ** **

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

Iodine-133 Ci ** **

Iodine-135 Ci ** **

Unidentified Ci ** **

Total for period Ci ** **

C. PARTICULATE Strontium-89 Ci ** **

Strontium-90 Ci 1.28E-7 5.66E-7 Cesium-134 Ci LT4.09E-6 LT3.91E-6 Cesium-137 Ci 3.11E-6 7.33E-6 Barium / Lanthanum-140 Ci ** **

Cobalt-60 Ci 7.94E-6 1.16E-5 Manoanese-54 Ci ** **

Unidentified Ci LT4.09E-6 LT3.91E-6 Total for period Ci 1.12E-5 1.95E-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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TABLE C1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1987 LIQUID EFFLUENTS - SUMMATION 0F ALL RELEASES UNIT FIRST SECOND EST. TOTAL QUARTER QUARTER ERROR, % l l

A. FISSION AND ACTIVATION PRODUCTS )

1. Total release (not )

including tritium, .

gases, or alpha) Ci 5.62E-3 2.30E-3 1.50E1 j

2. Average diluted l concentration micro-Ci )

during period per ml 3.73E-10 1.44E-10 1

3. Percent of l applicable limit  % 4.98E-3 3.53E-3 -
4. Applicable limit micro-Ci I used (Mixture MPC) per ml 7.49E-6 4.08E-6 B. TRITIUM
1. Total release Ci 1.72E-4 2.29E-4 1.50E1
2. Average diluted concentration micro-Ci during period per ml 1.14E-11 1.43E-11
3. Percent of applicable limit  % 3.80E-7 4.77E-7 C. DISSOLVED AND ENTRAINED GASES
1. Total release Ci ** ** **

D. GROSS ALPHA RADI0 ACTIVITY l

1. Total release Ci 1.59E-5 LT3.00E-5 5.00E1 E. Volume of waste released (priorto dilution) liters 2.65E5 8.04E4 1.00E1 l

F. Volume of dilution water used during period liters 1.51E10 1.60E10 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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TABLE C2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1987

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I LIQUID EFFLUENTS - BATCH MODE NUCLIDES RELEASED UNIT FIRST SECOND QUARTER QUARTER Strontium-89 Ci ** **

Strontium-90 Ci 1.43E-4 1.39E-4 Cesium-134 Ci 7.33E-5 1.51E-5 Cesium-137 Ci 5.14E-3 1.59E-3 Iodine-131 Ci ** **

Cobalt-58 Ci ** **

Cobalt-60 Ci 2.69E-4 5.52E-4 Iron-59 Ci ** **

Zinc-65 Ci ** **

Manganese-54 Ci ** **

Chromium-51 Ci ** **

Zirconium / Niobium-95 Ci ** **

Molybdenum-99 Ci ** **

Technetium-99m Ci ** **

Barium / Lanthanum-140 Ci ** **

Cerium-141 Ci ** **

Unidentified Ci LT1.59E-5 LT2.41E-6 Total for period (above) Ci 5.62E-3 2.30E-3 Xenon-133 Ci ** **

Xenon-135 Ci ** **

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

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TABLE 01 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 0F 1986 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL l (Not irradiated fuel) '

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1. TYPE OF WASTE UNIT 6-MONTH EST. TOTAL PERIOD ERROR %
a. Spent resins, filter Cubic j sludges, evaporator Meter None -----

bottoms, etc. Ci None -----

b. Dry compressible Cubic waste, contaminated Meter None -----

equipment, etc. Ci None -----

c. Irradiated components Cubic control rods, etc. Meter None -----

Ci None ----- .

d. Other (absorbed Cubic  !

liquids) Meter Mone -----

Ci None -----

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

None

3. Solid Waste Disposition:

Number of Shipments Mode of Transportation Destination .

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B. IRRADIATED FUEL SHIPMENTS (Disposition) l 1

Number of Shipments Mode of Transportation Destination l

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None --- ---

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TABLE El EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 0F 1987 MAXIMUM 0FFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC ANNUAL DOSE, MILLIREM (9)

Third Fourth First Second Four Quarter Quarter Quarter Quarter Quarter' SOURCE 1986 1986 1987 1987 Average 0.03(6) 0.05(6) 0.03(6)' 0.01(6) 0.03 Liquid Effluents (1) 0.05(8) 0.07(8) 0.04(8) . O.02(8) '0.05 Airborne Effluents (5)

Iodines & Particulate (2) -- -- -- -- --

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

Direct Radiation (4) 0.13 0.21 0.05 0.08 0.12 Notes: 1. Maximum total body and organ doses to individuals in unrestricted areas from receiving-water-related exposure pathways have 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 offsite ground-level concentrations of radioactive materials in gaseous effluents were not calculated because there were no significant releases of radioactive noble gases.
3. Organ doses to individuals in unrestricted areas from radioactive iodine and radioactive particulate for all pathways of exposure were 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 shoreline occupancy factors given in Regulatory Guide 1.109 for the maximum potential individual (Teen age group).
5. Based on meteorology data as discussed in Section F.
6. Total body (Adult age group)
7. Liver (Teen age group)
8. Bone (Child age group)
9. The dose shown for each quarter is calculated on an annual basis for four identical quarters.

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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 0.00 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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l TABLE F1 (Cont.) i PERCENT OF TIME FOR EACH WIND SPEE0 AND DIRECTION FOR THE PERIOD APRIL 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION 4, i

STABILITY CLASS: PASQUILL 'D'  !

I WIND WIND SPEED (MPH) l DIRECTION ------------------------------------------------------ J (DEGREES) 0-3 4-7 8-12 13-18 19-24 >24 Total I

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 'O.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 i 100 0.02 0.01 0.02 0.00 0.00 0.00 0.05 l 110 0.00 0.03 0.01 0.01 0.00 0.00 0.06 l 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 1 140 0.02 0.03 0.02 0.04 0.01 0.01 0.13 J 150 0.03 0.03 0.03 0.09 0.03 0.02 0.23 1 i

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 1 230 0.03 0.14 0.17 0.11 0.06 0.02 0.53 i 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 0.07 0.24 0.50 0.47 0.17 0.08 1.53 350 0.07 0.30 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 OIRECTION FOR THE PERIOD APRIL 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STABILITY CLASS: PASQUILL 'E' WIND WIND SPEED (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 i 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 i 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 l 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 i

l 150 160 0.09 0.05 0.24 0.22 0.22 0.25 0.45 0.62 0.52 0.44 0.46 0.21 2.08 1.79

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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 l 230 0.23 0.43 0.40 0.14 0.13 0.05 1.39 l 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 1 270 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 l 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 1.72 330 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.

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TABLE F1 (Cont.)

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

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

l (DEGREES) 0-3 4-7 8-12 13-18 19-24 >24_ Total I

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' O.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 i 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 i 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 l 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.

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R2W Y Rlw N RlE ERNDALE T2N DOSIMETERS & FIUt PACKS ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC COMPANY o i e s 4 4 g uts Figure !.

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