HBL-86-003, Rept on Radioactive Effluent Releases & Waste Disposal, Jul-Dec 1985

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Rept on Radioactive Effluent Releases & Waste Disposal, Jul-Dec 1985
ML20154L498
Person / Time
Site: Humboldt Bay
Issue date: 12/31/1985
From: Shiffer J
PACIFIC GAS & ELECTRIC CO.
To: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
HBL-86-003, HBL-86-3, NUDOCS 8603110499
Download: ML20154L498 (19)
v • d • e


Text

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- PGandE Letter N3.: HBL-86-003 4

ENCLOSURE HUMBOLDT BAY POWER PLANT UNIT NO. 3 REPORT ON RADI0 ACTIVE EFFLUENT RELEASES AND HASTE DISPOSAL JULY 1, 1985 THROUGH DECEMBER 31, 1985 e

8603110499 851231 PDR R ADOCK 05000133 pop q 0604S/0042K l

  • PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-133 LICENSE NO. DPR-7 RADI0 ACTIVE EFFLUENT RELEASES AND WASTE DISPOSAL FROM HUMBOLDT BAY POWER PLANT UNIT NO. 3, COVERING THE PERIOD JULY 1, 1985 THROUGH DECEMBER 31, 1985 This report sumarizes the quantity of each of the principal radionuclides released in liquids and gaseous effluents to unrestricted areas and summarizes radioactive waste disposal from July 1,1985 through December 31, 1985. 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: Refertoc.(Particulates).

- c. Particulates: 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 micro-Curies per second.

d. Liquid Effluents: 10CFR20.
2. Maximuin 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 detennine 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 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> decay, are analyzed for I-131 and 1-133 (Intrinsic Gennanium detector). Due to the long decay time since operation (shutdown July 2,1976) no detectable releases of radioactive iodines can be expected.

Accordingly, these radionuclides are not reported.

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, and the are analyzed concentration of gama 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 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 gama 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. Liquid:
1) Number of batch releases: 71 (A total of 14,518 gallons of laundry waste and 259,858 gallons of treated waste tank discharge).

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2) Total time period for batch releases: 1.20E4 minutes.
3) Average time period for a batch release: 1.69E2 minutes.
4) Maximum time period for a batch release: 4.75E2 minutes.
5) Minimum time period for a batch release: 1.00E1 minutes.
6) Average stream flow during periods of release of effluents into a flowin Notapplicable(Dischargeisinto 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. CASE 005 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 sumarizes 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 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.

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

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. D. SOLIO WASTE During the report period, a total of 687.6 cubic meters of solid radioactive waste, totaling 181.8 Curies, was shipped. Table 0-1 summarizes these radioactive waste shipments.

E. RADIOLOGICAL liPACT 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 sunenarized in Table E1. 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 0.023 mrem per Yr (Total Body) for the AJult age group, and 0.033 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 Y r.

3. Total body doses to the average individual in unrestricted creas 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 testsa (y significant two-way differences 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 (SECONDHALF'0F1985)

MEAN (mR) WEEKS OF TOTAL (mR)

SIeI1gN {2,yE[$,[EB}gg} ,,9313,, {26,y[E$,[EB}gg}

27 3.8 26 49.6 16 3.5 26 45.7 15 3.5 26 45.5 20 3.5 26 45.1 9 3.4 24 44.5 5 3.4 26 44.3 '

10 3.4 26 43.9 6 3.4 26 43.7 18 3.3 26 43.4 23 3.3 26 43.2 29 3.3 26 43.2 1 3.3 26 43.0

7 3.3 26 42.7 26 3.3 26 42.6 8 3.2 26 41.9 l

l 22 3.2 26 41.2 3 3.1 26 40.9 14 3.1 26 40.9 24 3.1 26 40.9 11 3.1 26 40.8 13 3.1 26 40.8

2 3.1 26 40.7 4 3.1 26 40.6 30 3.1 26 40.3 21 3.1 26 40.1 12 3.1 26 39.7 17 3.0 26 39.1 l

1 25 2.9 26 37.8 19 2.9 26 37.7 28 2.8 24 37.1 l

Least Significant Difference between station means = 0.4 Least Significant Difference between replication means = 1.6 Stations 2 and 5 are considered background.

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F. METEOROLOGICAL DATA The meteorological data logging system was removed from service in 1%7.

Therefore, the information specified by Regulatory Guide 1.21. Appendix

8. Section F, is not readily available for this report period.

Table F1 sunnarizes 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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o TABLE B1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT - 1985 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES UNIT THIRD FOURTH EST. TOTAL QUARTER QUARTER ERROR, %

A. FISSION GASES

1. Total Release C1
2. Average Release micro-Ci per sec. ** **

Rate for Period

3. Percent of Tech. ** **

Spec. Limit t B. 10 DINES

1. Total I-131 C1
2. Average Release micro-Ci per sec. ** **

Rate for Period

3. Percent of Tech. ** **

Spec. Limit  %

C. PARTICULATES

1. Total with Half-lives >8 days Ci 5.26E-6 1.72E-5 3.00E1
2. Average Release micro-Ci Rate for Period per sec. 6.62E-7 2.16E-6
3. Percent of Tech.

Spec. Limit  % 3.68E-4 1.20E-3

4. Gross Alpha Radio-activity Ci 5.53E-7 2.06E-6 D. TRITIUM
1. Total Release Ci LT9.91E-3 LT9.91E-3 5.00El
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 - 1985 GASE0US EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE NUCLIDES RELEASED UNIT THIRD FOURTH QUARTER QUARTER A. FISSION GASES Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci

    • e.

Xenon-133 Ci Xenon-135 Ci ee ..

Xenon-135m Ci Xenon-138 Ci Total for period Ci B. 10 DINES Iodine-131 Ci '

Iodine-133 Ci Iodine-135 Ci Unidentified Ci LT1.87E-6 LT2.82E-6 Total for period C1 C. PARTICULATES Strontium-89 Ci Strontium-90 Ci 1.54E-7 9.28E-8 Cesium-134 C1 LT3.08E-6 LT3.80E-6 Cesium-137 C1 2.90E-6 4.90E-6 Barium / Lanthanum-140 Ci Cobalt-60 Ci 2.21E-6 1.22E-5 Manganese-54 Ci Antimony-125 Ci LT3.08E-6 LT3.80E-6 Europium-154 Ci LT3.08E-6 LT3.80E-6 Unidentified Ci LT3.08E-6 LT3.80E-6 Total for period Ci 5.26E-6 1.72E-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 - 1985 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT THIRD FOURTH EST. TOTAL i QUARTER QUARTER ERROR,%

A. FISSION AND ACTIVATION PRODUCTS

1. Total release (not including tritium, gases, or alpha) Ci 3.38E-2 2.83E-2 1.50E1
2. Average diluted concentration nicro-Ci during period __

per ml 1.38E-9 1.11E-9

3. Percent of applicable limit  % 8.02E-3 6.34E-3
4. Applicable limit micro-C1 used (Mixture MPC),.' per ml 1.72E-5 1.75E-5 B. TRITIUM
1. Total release Ci 1.01E-3 1.04E-0 1.50TT-- l
2. Average diluted concentration micro-Ci during period per ml 4.14E-11 4.08E-8 '
3. Percent of applicable limit  % 1.38E-6 1.36E-3 ,

C. DISSOLVED AND ENTRAINED GASES

. 1. Total release Ci D. GROSS ALPHA RADIOACTIVITY

1. Total release Ci LT6.66E-5 LT2.09E-4 5.00El c

E. Volume of waste -

released dilution)(priorto liters 2.38E5 7.46E5 1.00E1 F. Volume of dilution water used during period liters 2.44E10 2.55E10 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 - 1985 LIQUID EFFLUENTS - BATCH MODE NUCLIDF.S RELEASED UNIT THIRD FOURTH QUARTER QUARTER i Strontium-89 Ci [

5trortium-90 Ci 1.21E-4 8.21E-5 Cesium-134 Ci 5.25E-4 4.59E-4 Cesium-137 C1 2.39E-2 2.21E-2 Iodine-131 C1 Cobalt-58 Ci Cobalt-60 Ci 9.29E-3 5.62E-3 Iron-59 Ci Zinc-65 Ci Manganese-54 Ci LT1.63E-5 LT3.34E-5 Ci ** **

Chromium-51 Ci ** **

Zirconium / Niobium-95 **

Molybdenum-99 C1 **

Ci ** **

Technetium-99m Barium / Lanthanum-140 Ci Ccrium-141 Ci Unidentified Ci LT1.63E-5 LT3.34E-5 Total for period (above) C1 3.38E-2 2.83E-2 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 D1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 0F 1985 SOLIO WASTE AND IRRADIATED FUEL SHIPMENTS 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 1.27E+02 1.0E+01 bottoms, etc. C1 1.65E+02 1.5E+01
b. Dry compressible Cubic waste, contaminated Meter 5.58E+02 1.0E+01 equipment, etc. 01 1.67E+01 2.0E+01
c. Irradiated components Cubic control rods, etc. Meter None -----

01 None -----

d. Other (absorbed Cubic liquids) Meter 2.55E+00 1.0E+01 Ci 7.97E-02 1.5E+01
2. Estimate of major nuclide composition (by type of waste).

Type Nuclide

a. H-3  % 6.89E-02 C-14 1 5.70E-02 Mn-54  % 1.58E-02 Fe-55 1 6.llE+01 Fe-59  % 6.13E-02 C0-60  % 2.25E+01 Ni-59  % 6.98E-02 Ni-63 1 6.86E+00 Zn-65  % 1.37E-01 5r-90 1 1.07E-01 Nb-94  % 3.79E-04 Tc-99  % 3.32E-02 5b-125  % 6.32E-02 I-129  % 3.4:E-02 Cs-134 1 1.04E-01 Cs-137  % 6.30E+00 Ce-144 1 6.98E-06 Eu-152  % 3.25E-02 Eu-154  % 2.88E-02 Eu-155  % 2.08E-02 U-234  % 1.43E-06 U-235  % 7.72E-06 U-236  % 2.36E-07 DCPP2 11

TABLE D1 (Continued)

a. (Continued)

U-238  % 5.76E-07 Pu-238  % 3.17E-02 Pu-239  % 2.40E-02 Pu-240  % 2.40E-02 Pu-241  % 2.16E+00 Pu-242 1 5.18E-07 Am-241  % 9.01E-02 Am-243  % 2.06E-06 Cm-242  % 1.89E-04 Cm-243  % 4.24E-03 Cm-244  % 6.27E-03

b. , H-3  % 2.32E-01 C-14  % 2.35E-01 K-40  % 3.77E-02 Mn-54 1 7.18E-03 Fe-55  % 7.07E+01 Co-60 1 7.04E+00 Ni-63  % 1.93E+00 Sr-90 1 9.44E-01 Nb-94  % 1.78E-01 Tc-99  % 1.92E+00
  • I-129  % 2.32E-01 C5-134  % 1.14E-01 Cs-137  % 1.00E+01 Ce-144  % 1.25E-01 Eu-152 1 3.27E+00 Eu-154  % 5.69E-02 Eu-155  % 1.81E+00 Pu-241  % 1.08E+00
d. H-3  % 2.83E-02 C-14 1 3.14E-02 Fe-55 1 7.22E+01 Co-60  % 6.69E+00 N1-63  % 8.96E-01 Sr-90 1 7.52E-01 Tc-99  % 6.40E+00 I-129  % 5.04E-01 Cs-137  % 8.14E+00 Eu-152 1 2.97E+00 Eu-155  % 8.47E-01 Pu-241  % 5.10E-01
3. Solid Waste Disposition:

Number of Shipments Mode of Transportation Destination 74 Truck Richland, Washington 1 Truck Barnwell, South Carolina B. IRRADIATEDFUELSHIPMENTS(Disposition)

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

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TABLE El EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 0F 1985 MAXIMUM OFF-SITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC Annual Dose, Millirem (8)

First Second Third Fourth Four Quarter Quarter Quarter Quarter Quarter 1985 1985 1985 1985 Average Source 0.05(6) 0.11(6) 0.0B(6) 0.07(6) 0.08 Liquid Effluents (1) 0.14(7) 0.34(7) 0.12(9) 0.10(9) 0.18 Airborne Effluents (5)

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

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

Direct Radiation (4) 0.37 0.39 0.30 0.44 0.38 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 effluents was 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 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 meteorology data as discussed in section F.

6.TotalBody(Adultagegroup)

7. Gastro-intestinal tract / Lower Large Intestine (Adult age group)
8. The dose shown for each quarter is calculated on an annual basis for four identical quarters.
9. Liver (Teen age group)

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r 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' j WIND WIND SPEED (MPH)

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

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

O 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 l 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 t 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 i

Rows may not sum to exact total due to rounding off.

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1 TABLE F1 (Cont)

PERCENT OF TIME FOR EACH WIND SPEED AND DIRECTION FOR THE PERIOD APRIL, 1962 THROUGH JUNE 1967 r RECORDED AT THE 250 FOOT ELEVATION 4

i STABILITY CLASS: PASQUILL 'D'

).

WIND WIND SPEED (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' O.58 40 0.05 0.11 0.05 0.02 0.00 0.01 0.23 j 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 i 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 0.13 140 0.02 0.03 0.02 0.04 0.01 0.01 150 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 l 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 l

200 0.05 0.10 0.17 0.11 0.02 0.01 0.46 d

210 0.05 0.12 0.20 0.06 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 l 0.22 0.13 0.02 0.01 0.00 0.47 260 0.08 270 0.12 0.21 0.11 0.03 0.01 0.00 0.49 l

1 280 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 l 0.01 0.80 320 0.07 0.25 0.33 0.09 0.04 i'

330 0.06 0.21 0.35 0.16 0.03 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 I

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 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 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 1.72 330 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

TABLE F1 (Cont)

PERCENT OF TIME FOR EACH WIND SPEED AND DIRECTION

> FOR THE PERIOD APRIL, 1962 THROUGH JUNE 1967 RECORDEC*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 l i

0 0.42 0.08 0.03 0.00 0.00 0.00 0.53 l 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 C D. 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 l

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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February 28, 1986 PGandE Letter No.: H8L-86-003 Mr. John B. Martin, Regional Administrator U.S. Nuclear Regulatory Commission, Region V -

1450 Maria Lane, Suite 210 Halnut Creek, CA 94596-5368 Re: Docket No. 50-133, OL-DPR-7 Humboldt Bay Power Plant, Unit No. 3 Semiannual Radioactive Effluent Release Report

Dear Mr. Martin:

Enclosed is the Humboldt Bay Power Plant Unit No. 3 " Report on Radioactive Effluent Releases and Haste Disposal" covering the period from July 1 through December 31, 1585. This report is required by Section IX.I.3.a of the Humboldt Bay Unit No. 3 Technical Specifications and 10 CFR 50.36a(a)(2).

Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.

Sincerely, Enclosure cc: California Department of Health Services Radiologic Health Section Document Control Desk Service List Director, Office of Inspection and Enforcement Paul Anderson, MD,  ;

Humboldt County Public Health Officer Enclosure 0604S/0042K/RHS/1052 666 G

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