HBL-89-015, Semiannual Radioactive Effluent Release Rept Jul-Dec 1988

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Semiannual Radioactive Effluent Release Rept Jul-Dec 1988
ML20235V142
Person / Time
Site: Humboldt Bay
Issue date: 12/31/1988
From: Fujimoto W
PACIFIC GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HBL-89-015, HBL-89-15, NUDOCS 8903100053
Download: ML20235V142 (18)
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h hm PG&E Letter No. HBL-89-015 ENCLOSURE HUMBOLDT BAY POWER PLANT UNIT 3 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT July 1, 1988 through December 31, 1988 i

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PACIFIC GAS AND ELECTRIC COMPANY i DOCKET N0; 50-133-LICENSE NO. DPR-7 RADIOACTIVE EFFLUENT RELEASES AND MASTE DISPOSAL FROM

HUMBOLDT BAY POWER PLANT UNIT 3, COVERING THE PERIOD JULY 1,1988 THROUGH DECEMBER 31, 1988 This report summarizes the quantity of each of the principal radionuclides released in liquid and gaseous effluents to unrestricted areas and summarizes radioactive waste disposal from July 1, 1988 through December 31, 1988. This report is required by Section VII.H.3 of the Humboldt Bay Power Plant Unit 3 Technical Specifications.

A. SUPPLEMENTAL'INFORMATION

1. Regulatory Limits License amendment No. 23 was issued on July 19, 1988. This is the first Semiannual Radioactive Effluent Release Report under the provision of that amendment. Regulatory limits presented below reflect the new license requirements.
a. Fission and activation gases: The regulatory release rate limit is based on the appropriate Maximum Permissible Concentrations from 10 CFR 20, divided by a dispersion factor of 1.4E-6 seconds per-cubic meter,(determined to be the annual average dispersion factor for the sector with the least atmospheric dispersion).
b. Iodines: Due to the long decay time since the Unit was last operated (July-2,1976), no detectable releases of radioactive iodines are expected. The license recognizes this and no longer requires monitoring for radioactive iodines, nor does it define a corresponding release rate limit.
c. Particulate: The regulatory release rate limit is based on the appropriate Maximum Permissible Concentrations from 10 CFR 20, divided by a dispersion factor of 1.4E-6 seconds per cubic meter .

(determined to be the annual average dispersion factor for the sector j with the least atmospheric dispersion). l

d. Liquid effluents: 10 CFR 20.

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2. Maximum Permissible Concentrations The concentrations used to determine allowable release rates or allowable concentrations are as follows:
a. Gaseous effluents:

l (1) Fission and activation gases: 10 CFR 20, Appendix B.

Table II.

(2) Iodines: Not applicable.

(3) Particulate, with half-lives >8 days): 10 CFR 20, Appendix B, Table II.

b. Liquid effluents: 10 CFR 20, Appendix B Table II.

I

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 radionuclides 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 short half-life fission and activation gases can be expected.

Accordingly, these radionuclides are not reported. The "less than" value for Kr-85 is based on the estimated sensitivity of the stack Kr-85 monitor.

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 does not require 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 for the concentration of gamma-emitting nuclides (intrinsic germanium detector). All statistically significant peaks are identified. The filters for each quarter are analyzed for radioactive strontium (all Sr-90 due to decay time).

l 2548S/0067K _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _

-The error of the reported particulate release values is 1 estimated based on uncertainty in sample flow rate, stack flow j rate, detector calibration, and typical sample counting statistics. i

d. Liquid effluents: Liquid waste batch samples were counted for  !

gamma spectrum and gross beta radioactivity. All statistically l important peaks were identified. Quarterly composites of all batches were analyzed for gross alpha, tritium, and radioactive ,

strontium (Sr-90).  ;

1 The error of the reported release values is estimated based on ,

uncertainty in sample volume, batch volume, detector j calibration, and typical sample counting statistics.  ;

5. Batch releases
a. Liquid (1) Number of batch releases: 7 (2) Total time period for batch releases: 3.05E3 minutes (3) Average time period for a batch release: 4.36E2 minutes (4) Maximum time period for a batch release: 5.90E2 minutes (5) Minimum time period for a batch release: 3.65E2 minutes (6) Average stream flow during periods of release of effluents into a flowing stream: Not applicable (discharge is into Humboldt Bay)
b. Gaseous: None j
6. Abnormal releases
a. Liquid (1) Number of releases: 1 (2) Total activity released: 3.20E-7 Curies
b. Gaseous (1) Number of releases: None (2) Total activity released: None 2548S/0067K -3 1

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B. GASEOUS EFFLUENTS All ventilation exhausts and system vents are routed to the exhaust l stack. Table B1 summarizes the total quantities of gaseous radioactive I effluents released by quarter. Table B2 summarizes the total quantities for each of the nuclides determined to be released.

C. LIQUID EFFLUENTS All normal liquid releases were collected, filtered, and analyzed before discharge (on a batch basis) through the liquid radwaste process monitor. Analysis of weekly composite samples from the plant intake and the plant effluent canal did not detect any additional release of radioactive liquids during the report period.

Table C1 summarizes the total quantities of radioactive liquid effluents released by quarter. Table C2 summarizes the total quantity for each of the nuclides determined to be released.

This report includes a conservative estimate of radioactivity that was assumed to have reached the effluent canal by way of the yard drains, even though the release would have been diluted to non-detectable levels before discharge to unrestricted areas.

The unplanned release was monitored by sampling water found in the yard drains. Based on sample analysis and a conservative volume estimate, the release was less than 0.26 micro-Curies of Cs-137 and 0.06 micro-Curies of Co-60. This release is included in the calculation of potential radiological impacts described in section E, below. There is no significant impact from this release, because its contribution to calculated offsite doses is less than 0.1% of the doses calculated for the normal releases.

D. SOLID HASTE Table 01 summarizes the total quantities of solid waste shipped for disposal during the report period.

E. RADIOLOGICAL IMPACT ON MAN A comparison of calculated doses from various paths has shown that the off-site doses are primarily due to direct radiation and to the consumption of aquatic foods. 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 results were 0.003 mrem /yr (total body) for the Adult age group, and 0.002 mrem /yr for the bone of the Child age group.

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2. Total body doses to the average individual in the population from gaseous effluents to a distance of 50 miles from the site are not ,

l significant. For cca.parison, a conservative calculation (with the same dispersion and deposition parameters as were used to calculate maximum exposure) resulted in total body exposures of less than 0.005 arem/yr.

3. Total body doses (to the average individual in unrestricted areas from direct radiation from the facility) are based on TLD results of stations at the site boundary, using the shoreline occupancy factors given in Regulatory Guide 1.109 for the highest average potential individual (Teen age group). For this group, direct radiation would result in an exposure of 0.069 mrem /yr.

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 available.

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 HASTE' DISPOSAL SEMIANNUAL REPORT - 1988 GASEOUS EFFLUENTS - SUMATION OF ALL RELEASES UNIT THIRD FOURTH EST. TOTAL 00ARTER OUARTER ERROR. 1 A. FISSION GASES

1. Total Release Ci (1.63E1 <1.63E1 5.00E1
2. Average Release micro-Ci Rate for Period per sec. <2.05E0 <2.05E0
3. Percent of applicable limit 1 <9.58E-4 <9.58E-4 B. 10 DINES
1. Total Release Ci
2. Average Release micrc-Ci Rate for Period per sec.
3. Percent of ** **

applicable limit  %

C. PARTICULATE

1. Total with Half-lives >8 Days C1 3.25E-5 3.29E-5 3.00E1
2. Average Release micro-Ci Rate for Period per sec. 4.09E-6 4.14E-6
3. Percent of applicable limit 1 2.30E-6 1.73E-6
3. Applicable limit micro-Ci (Mixture MPC) per cc 2.50E-10 3.35E-10
4. Gross Alpha Radioactivity Ci 9.99E-7 9.22E-7 D. TRITIUM
1. Total Release Ci <1.00E-2 <1.00E-2 5.00E1
2. Average Release micro-Ci Rate for Period per sec. <1.26E-3 <1.26E-3 Note: **No release can be expected due to decay time since shutdown (July 2, 1976). Accordingly, no release is reported.

l 2548S/005 % _____-_- --_ _ _ _ _ -

TABLE B2 EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT - 1988 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE NUCLIDES RELEASED UNIT THIRD FOURTH OUAPTER OUARTER A. FISSION GASES Krypton-85 C1 <1.63E1 <1.63E1 Unidentified Ci Total for period Ci (1.63E1 <1.63E1 B. 10 DINES Unidentified Ci Total for period Ci C. PARTICULATE Strontium-89 C1 Strontium-90 C1 1.49E-6 1.88E-7 Cesium-134 Ci <3.68E-6 <3.68E-6 Cesium-137 C1 1.74E-5 1.29E-5 Cobalt-60 C1 1.36E-5 1.98E-5 Unidentified Ci <3.68E-6 <3.68E-6 Total for period C1 3.25E-5 3.29E-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 NASTE DISPOSAL SEMIAhNUAL REPORT - 1988 LIQUID EFFLUENTS - S!M4ATION OF Alt. RELEASES UNIT THIRD FOURTH EST. TOTAL OUARTER OUARTER ERROR. %

A. FISSION AND ACTIVATION PRODUCTS

1. Total release (not including tritium, gases, or alpha) Ci 5.73E-4 4.84E-3 1.50E1
2. Average diluted concentration micro-Ci during period per ml 3.52E-11 2.76E-10
3. Percent of applicable limit 1 8.69E-4 1.79E-3
4. Applicable limit micro-Ci (Mixture MPC) per ml 4.05E-6 1.54E-5 B. TRITIUM
1. Total Release Ci 9.82E-5 3.49E-4 1.50E1
2. Average diluted concentration micro-Ci during period per ml 6.02E-12 1.99E-11
3. Percent of applicable limit  % 2.01E-7 6.63E-7 C. DISSOLVED AND ENTRAINED GASES **
1. Total Release C1 D. GROSS ALPHA RADI0 ACTIVITY
1. Total Release Ci (2.15E-5 <5.35E-5 2.00E1 E. Volume of waste released (prior to dilution) liters 5.42E4 1.35E5 1.00E1 F. Volume of dilution water used during period liters 1.63E10 1.75E10 1.50E1 l

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 - 1988 LIQUID EFFLUENTS - BATCH N00E HUCLIDES RELEASED UNIT THIRD FOURTH OUARTER 00ARTER Strontium-89 Ci Strontium-90 C1 3.68E-5 2.41E-5 Cesium-134 C1 4.20E-6 2.96E-6 Cesium-137 Ci 4.99E-4 4.28E-3 Cobalt-60 Ci 3.53E-5 5.28E-4 Unidentified Ci <1.45E-6 <4.02E-6 Total for period Ci 5.73E-4 4.84E-3 Xenon-133 Ci Xenon-135 C1 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 NASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF OF 1988 SOLID NASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID NASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

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

bottoms, etc. Ci None --

b. Dry compressible Cubic waste, contaminated Meter 3.54E1 1.0E1 equipment, etc. Ci 9.24E-2 2.0E1
c. Irradiated components Cubic control rods, etc. Meter None --

Ci None --

d. Other (absorbed Cubic liquids) Meter 4.50E0 1.0E1 C1 6.67E-3 2.0E1
2. Estimate of major nuclide composition (by type of waste).

TYPE NUCLIDE UNIT 6-MONTH PERIOD

b. H-3  % (2.63E-1 C-14  % 7.25E-2 Fe-55 1 6.14E1 Co-60 1 6.24E0 N1-63  % 1.99E0 St-90  % 1.61E0 Tc-99  % 9.05E-1 1-129  % (7.04E-2 Cs-137  % 2.67El Pu-241  % 8.24E-1 254BS/0067K I

\ ______ -___________-___--_ - ______- _ ___.

1 TABLE D1 (Continued)

TYPE NUCLIDE UNIT 6-MONTH PERIOD

d. H-3 1 <5.10E-1 C-14  % 2.55E-1 Fe-55 1 4.64E1 Tc-99  % 7.65E-1 I-129  % <2.55E-1 Cs-137  % 5.17El
3. Solid Haste Disposition:

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 1 Truck Richland, WA B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None -- --

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J TABLE El 4 3 EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT I

i SECOND HALF 0F'1988 MAXIMUM OFF-SITE DOSES AND DOSE COMITNENTS TO MEMBERS OF THE PUBLIC ANNUAL DOSE, MILLIREM (9)'

First Second Third Fourth. Four Quarter. Quarter . Quarter Quarter Quarter Source 1988 1988 1988 1988 Averaae Liquid Effluents (1) <0.01(6) <0.01(6) <0.01(6) 0.02(6) 0.01 0.01(7) <0.01(7) <0.01(7) 0.03(5) 0.02 Airborne Effluents Iodines & I Particulate (2) <0.01(8) <0.01(8) <0.01(8) <0.01(8) <0.01 1 0.02(7) <0.01(7) 0.02(7) <0.01(7). 0.02 Noble Gases- (3) --- -- -- -- --

Direct Radiation (4) 0.23- 0.01 0.18 0.02 0.11 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, following the applicable portions of Regulatory Guide 1.109.

2. Maximum total body and organ doses to individuals in unrestricted areas from airborne-particulate-related exposure pathways have been calculated for detected airborne particulate releases based on the average concentrations for the report period, following the applicable portions of Regulatory Guide 1.109.
3. Total body and skin doses to potentially exposed individuals ,

located at the point of maximum offsite ground-level concen- I trations of radioactive gaseous effluents were not calculated because there were no detected releases of radioactive noble gases, and because the doses would be less than 0.005 mrem /yr at the level at which the releases could be detected.

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 agt group).
5. Liver (Teen age group).
6. Total body (Adult age group).
7. Bone (Child age group).
8. Total body (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 HIND SPEED AND DIRECTION FOR THE PERIOD APRIL 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STABILITY CLASS: PASQUILL 'C' HIND HIND 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.

i 2548S/0067K _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ - - .

.c '

TABLE F1 (Cont.)

PERCENT OF TIME FOR EACH NIND SPEED AND DIRECTION

! FOR THE PERIOD APRIL'1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION ,'

STABILITY CLASS: PASQUILL 'D' WIND HIND SPEED (MPH)

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

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

1 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' O.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 0.07 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.

2548S/0067K _ _ - - _ _ - _ . . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - -

.. . G .1

+.. .-

.I i

.TA8LE F1 (Cont.)~

PERCENT 0F TIME FOR EACH NIND SPEED AND. DIRECTION 3 FOR THE PERIOD APRIL 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STABILITY CLASS: PASQUILL 'E' NIND 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 'O.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 1.47 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.

2548S/0067K -

1 TA8LE F1 (Cont.)

PERCENT OF TIME FOR EACH HIND SPEED AND DIRECTION FOR THE PERIOD APRIL 1962 THROUGH JUNE 1967 RECORDED AT THE 250 FOOT ELEVATION STA81LITY CLASS: PASQUILL 'F' HIND HIND 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 3 50 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.

2548S/0067K - _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _

- ~ ~ ~- - -- -

_ . 3.- ; .9 3 >

'* i ; ';,
  • 4* Pacific Gas and Electric Company

. 77 Beale Street Warren F6j;moto i

- San francisco, CA 94106 Manager . .

' 4151972 4758 Nuclear Operations Support p

March 1, 1989 i

PG&E Letter No. HBL-89-015 U.S. Nuclear Regulatory Commission }

ATTN: Document Control Desk Hashington,.D.C. 20555 Re: Docket No. 50-133, OL-DPR-7 Humboldt Bay Power Plant, Unit 3 Semiannual Radioactive Effluent Release Report Gentlemen:

Enclosed is the Humboldt Bay Power Plant Unit 3 " Report on Radioactive Effluent Releases and Haste Disposal" covering the period from July 1, 1988, through December 31, 1988. This report is required by Section VII.H.3 of the Humboldt Bay Unit 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, M j,( f -

lN H. H. Fujimoto cc: P. Anderson.

P. B. Erickson J..B. Martin P. Szalinski D. J. Homeldorf Humboldt Distribution Humboldt Service List Enclosure 2548S/0067K/RLK/1052 o

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