Text

Rept 69,Environ Radiation Study in Vicinity of Humboldt Bay Power Plant,Quarter Ending 780630
	ML19261B750
Person / Time
Site:	Humboldt Bay
Issue date:	12/06/1978
From:	Andrew C, Cayot R, Lorenz A; PACIFIC GAS & ELECTRIC CO.
To:	;
Shared Package
ML19261B751	List: ML19261B750; ML19308A284; ML19308A285;
References
	420-78.120, NUDOCS 7903050367
	Download: ML19261B750 (40)
	v • d • e

-

t, -

Report Issued: DEC6 Gy Report 420-78.120 PACIFIC GAS AND ELECTRIC COMPANY DEPARTNENT OF ENGINEERING RESEARCH REPORT N0. 69 ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA QUARTER ENDING JUNE 30, 1978 (SPRING)

~

k. F.

DT, Chief Report Prepared By:

C. H. Andrew R. W. Lorenz s*

7903050367 9

S.g,-

u ll m a_fl

+

'h w.w.mo.

J.

Page 2 4.

Measurements and Approximations of Total Radioactivity The methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition are as follows:

n.

Fission and activation gases:

During operation, samples (of air ejector off-gas) are taken at least monthly for Sodium Iodide gamma spectrum analysis and, based on six measureable nuclides (Xel38, Kr87, Kr88, Kr85m, Xe135, and Xel33), the remaining nuclides in the mixture are estimated. This analysis is used to calibrate the gross counting results of routine samples which are then used to calibrate the stack continuous monitors.

Daily average release rates determined from the stack monitors are used to derive total quantity of the mixtures released, and individual nuclides are proportioned according to the mixture found from the monthly analysis, b.

Iodines:

Charcoal cartridges are removed from the stack sampling system weekly and af ter 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months decay are gamma spectrum counted for I-131 and I-133 (with a Sodium Iodide detector).

c.

Particulates:

Filter papers are removed from the stack sampling system weekly and gross beta counted after 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months decay. After 7 days they are recounted to determine Bata140 (Sodium Iodide detector).

Filters for each quarter are decay counted to determine other particulates (long-lived), alpha emitters, and then analyzed for Sr89 and Sr90.

d.

Liquid Effluents:

Waste receiver tank and waste hold tank batch samples are gamma spectrum analyzed (Sodium Iodide detector) and gross Beta and gross Gamma counted.

If the nuclides identified do not account for the gross gamma count, the mixture is proportionately adjusted.

If the gross beta count indicates more activity than the adjusted mixture, the excess activity is recorded as " Additional But Otherwise Unspecified".

Laundry waste tanks are individually analyzed only by gross beta and gross gamma. A monthly composite is analyzed as above.

A quarterly composite of all batches is analyzed for Tritium, Sr89 and Sr90. The strontium results are subtracted from " Additional But Otherwise Unspecified" activity, and if necessary, increased to account for the excess.

Page 3 5.

Batch Releases a.

Liquid:

1)

Number of batch releases:

26 (A total of 4.904 gallons of laundry waste and 28,140 gallons of treated wastetankdischaree.)

2)

Total time period for batch releases: 25.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 3)

Maximum time period for a batch release: 5.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 4)

Average time period for batch releases:

59 minutes 5)

Minimum time period for a batch release: 9 minutes 6)

Average stream flow during periods of release of effluent into a flowing stream: Discharge is into Humboldt Bay, 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.

GASEOUS EFFLUENTS The monitoring systems associated with the emergency condenser and liquid radwaste system vents to atmosphere indicate that no detectable releases of radioactive gases occurred during the report period.

Therefore, only gaseous radioactive waste releases made via the 250 foot stack are reported.

Table B1 summarizes the total quantities of radioactive effluents released by quarter. Table B2 summarizes the total quantities for each of the nuclides determined to be released.

o Page 4 C.

LIQUID EFFLUENTS The activity in each batch of liquid radioactive waste vas either in solution at the time of discharge or the batch was filtered prior to discharge. Analysis of weekly composite samples from the plant effluent canal and monitoring by the liquid waste discharge monitor confirmed that no' unaccounted release of radioactive wasce occurred during the report period.

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

D.

SOLID WASTE During the report period a total of 36 cubic meters of solid radwaste totaling 0.38 Ci was shipped. Table D1 summarizes the radioactive waste material shipments.

e

E.

ENVIRONMENTAL MONITORING Although plant was not operating, the environmental monitoring program was continued unchanged in this period. Quarterly reports, " Environmental Radiation Study in the Vicinity of Humboldt Bay Power Plant (HBPP),

Eureka, California," contain the basic data from the Humboldt Bay Power Plant environmental monitoring program.

The most recent report issued, No. 68, 69, and 70 are attached and includes data from the first three quarters of 1978. Data from the last quarter of 1978 have yet to be issued in report form, but the dosimeter data for this period were included in the analysis for this report to determine ranges of direct exposure for the monitored area. The quarterly reports describe the sampling locations, total number of samples of each media sampled, as well as the associated measured levels of radioactivity.

The types of media sampled are marine flora, marine fish, invertebrates, bottom sediment, milk, air particulates, and external radiation measurements with ion chambers.

Since plant releases continued to be much lower than when the plant was last operated and calculated potential public exposures from them was so low at that time, potential public exposures due to the plant were calculated only from the dosimetry data.

The ion chamber measurements for the station recording the highest reading when extrapolated to yearly rates was 99.4 millirem per year for the last half of 1978.

This extrapolated dose was 22.0 millirem per year above the average of Stations 2 and 5.

As seen in Figure IE, there are currently 30 dosimetry stations in the vicinity of the plant.

Ionization chambers, which are typically read on a biweekly basis, are presently being utilized for dosimetry.

Stations 2 ar.d 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 statistically significant difference between stations, two stat istical tests (a two-way classification, aad a 95 percent confidence limit least significant difference test) <ere made during biweekly dosimeter readings for each station.

It was determined that two stations were statistically above background for the second half of 1978.

Both of these stations, Station 27 (99.4 mR) and Station 16 (96.2 mR), included one abnormally high period possibly indicating a faulty dosimeter.

The exposure extrapolated to one year for the background Stations 2 and 5 was 77.4 milliroentgens (mR). The extrapolated exposure measured at the other stations ranged from a high of 99.4 mR at Station 27 to a low of 68.8 mR at Station 13.

F.

METEOROLOGICAL DATA Wind rpeed and direction and temperature differential are presently recorded on strip charts, but 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 1977.

Table F1 summarizes the cumulative joint frequency distribution of wind speed, wir.d direction, and atmospheric stability for the period April, 1962 through June, 1967 when the meteorological data logging system was in service.

TABLE B1 EFFLUENT AND WASTE DISPOSAL SDtIANNUAL REPORT 1978 GASEOUS EFFLUENTS - SUEdATION OF ALL RELEASES i

Est.

Unit Fourth Total Third qqarter Quarter Error X

A.

Fission 6 activation gases I

LT 1.1E-5 LT 1.1E-5 2.00El 1.

Total release Ci 2.

Average release rate for period pCi/sec LT 1.38E-6 LT 1.38E-6 3.

Percent of Technical LT 2.76E-9 LT 2.76E-9 Specification limit B.

Iodines LT 3.00E-6 LT 3.00E-6 1.50El 1.

1otal iodine-131 Ci 2.

Average release rate for period (I-131) pCi/see LT 3.77E-7 LT 3.77E-7 i

3.

leretnt of Technical LT 2.09E-4 LT 2.09E-4 Specification limit C.

Particulates 1.

Particulates with half-1.14E-4 1.23E-4 1.50El lives >8 days Ci 2.

Average release rate 1.43E-5 1.55F-5 for period pCi/sec 3.

Percent of Technical 7.94E-3 i8.61E-3 Specification limit 4.

Gross alpha radioactivity Ci 1.40E-7 2.79E-7 l

D.

Tritium i

LT 1.00E-2 LT 1.onF-2 5.00El 1.

Total release Ci 2.

Average release rate LT 1.26E-3 lLT 1.26E-3 for period pCi/sec

TABLE B2 1978 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode Nuclides Released Unit Third Fourth I

i Quarter Ouarter i

1.

Fission gases krypton-83M Ci Tr1 nnv_A**

LT 1.00E-6**

,_k_ryp t on-89 Ci LT 1.00E-6**

LT 1.00E-6**

krypton-85M Ci LT 1.00E-6**

LT 1.00E-6**

I krypton-87 Ci LT 1.00E-6**

LT 1.00E-6**

i I krypton-88 Ci LT 1.00E-6**

LT 1.00E-6**

i xenon-133 Ci LT 1.00E-6**

LT 1.00E-6**

xenon-135 Ci LT 1.00E-6**

LT 1.00E-6**

xenon-135m Ci LT 1.00E-6**

LT 1.00E-6**

xenon-138 Ci LT 1.00E-6**

LT l.00E-6**

xenon-137 Ci LT 1.00E-6**

LT 1.00E-6**

xenon-133m Ci LT 1.00E-6**

LT 1.00E-6** _

Total for period ci LT 1.10E-5 LT 1.10E-5 1

2.

Iodines iodine-131 Ci LT 1.00E-6**

LT 1.00E-6**

iodine-133 Ci LT 1.00E-6**

LT 1.00E-6**

iodine-135 Ci LT 1.00E-6**

LT 1.00E-6**

Total for period Ci LT 3.00E-6 LT 3.00E-6 i

3.

Particulates strontium-89

'Ci LT 1.02F-5 LT 1.92F-6 strontium-90 Ci LT 1.08F-6 LT 1.10F-6 cesium-134 Ci LT 1. 0 5F -5

LT 8.68E-6*

cesium-137 Ci 1.04E-5 1.76E-5 barium-lanthanum-140 Ci LT 1.00E-6**

LT 1.00E-6** i cobalt-60 Ci 5.49F-5 6.64E-5 manganese-54 Ci 2.49E-5 2.35F-5 cerium-144 Ci LT 1.00E-6**

LT 1.00E-6** \\

The minimum sensitivity of the plant's Sodium Iodide spectrometer system in for a particular'nuclide depends upon the mixture of nuclides present each batch, therefore, some nuclides not detected could be present at leve:s comparable to those detected. Those nuclides expected to be present, but not detected, are reported "Less Than" (LT) typical quarter Curie maximum quantities.

- No release was detected due to the decay time since the unit was shutdown on July 2, 1976. Quantities reported are an arbitrary 1 micro-curie.

TABLE Cl EFFLUENT AND WASTE DISPOSAL SDf1 ANNUAL REPORT 1978 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES lEst.

Third

,vourth tTotal i

Unit Qt$arter Quarter Error l

A.

Fission and activation products I 1.

Total release (not including

4. 7.E

,,a 4'.56E-2 1.50E1 tritium, gases, alpha)

C1 2.

Average diluted concentra-tion during period pCi/ml 1.84E-10

1. 75 r-9 3.

Percent of applicable limit 1.42E-3 9.67E 'l 4

B.

Tritium-

"* * -3 7.94E-3 4.00E0 1.

Total release Ci 2.

Average diluted concentra-1.74E-10 3.05E-10 tion during period pCi/ml 3.

Percent of applicable limit 5.80E-6 1.02E-5 C.

Dissolved and entrained gases LT 2.00E-6 ',5.00E1 1.

Total release ci LT 2.00E-6 D.

Gross alpha radioactivity LT1.30E-5!7.50El 1.

Total release Ci 3.56E-5 E.

Volume of vaste released I

4.58E4

8. W 4

5.00E0 (prior to dilution) liter F.

Volume of dilution water 2.58E10 2.60E10 5.00E0 used during period liter

The minimum sensitivity of the plant's Sodium Iodide spectrometer system for a particular nuclide depends upon the mixture of nuclides present in each batch, therefore, some nuclides not detected could be present at levels comparable to those detected. Those nuclides expected to be present, but not detected, are reported "Less Than" (LT) typical quarter Curie maximum quantities.

TABLE C2 1978 EFFLUENT ~AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS Batch mode Nuclides Released Unit Third Fourth Quarter

. Quarter strontium-89 Ci LT 2.58E-5 LT 1.85E-5 strontium-90 C1 3.54E-5 7.51E-5 cesium-134 4.92E-4 5.47F-3 cesium-137 2.44E-3 2.78E-2 l iodine-131 LT 1.00E-6**

! LT 1.00E-6**

cobalt-58 Ci Li 1.ouh-4a LT 3.onv-4*

cobalt-60 C1 3.17E-4

3. 2 Rv.-3 zine-65 Ci LT 3.00E-4*

LT 3.00E-3*

manganese-54 Ci LT 5.00E-4*

LT 5.00E-3*

chromium-51 Ci LT 1.00E-6**

LT 1.00E-6**

zirconium-niobium-95 Ci LT 1.00E-6**

LT 1.00E-6**

molybdenum-99 Ci LT 1.00E-6**

.LT 1.00F-6**

technetium-99m Ci LT 1.00E-6**

LT 1.00E-6**

barium-lanthanum-140 Ci LT 1.00E-6**

LT 1.00E-6**

C

"*~

l 8.18E-4 8.33E-4 Ci l

neptunium-239 Ci LT 1.00E-6**

LT 1.00E-6**

Total for period (above)

C1 1

4.74E-3 4.56E-2 l

xenon-133

! ci

! LT 1.00E-6**

LT 1.00E-6**

xenon-135 i Ci I LT 1.00E-6**

LT 1.00E-6**

The minimum sensitivity of the plant's Sodium Iodide spectrometer system for a particular nuclide depends upon the mixture of nuclides present in each batch, therefore, some nuclides not detected could be present at levels cocparable to those detected. Those nuclides expected to be present, but not detected, are reported cess Than" (LT) typical quarter Curie maximum quantities.

- No release was detected due to the decav time since the unit was shutdown on July 2, 1976.

Ouantit!es reported are an arbf trarv 1 micro-curie.

TABLE D1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF OF 1978 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.

Solid Waste Shipped Offsite for Burial or Disposal (not irradiaced fuel)

I Udit Est.

Total Error Quantity 1.

Type of Waste 3

a. Solidified evaporator bottoms m

None Ci 3

b. Dry compressible waste, m

3.57El contaminated equip, etc.

C1 3.77E-1 2.50 El 2.

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

Cesium-134 Cesium-137 Unidentified Mixed Fission Products Cobalt-60 Manganese-54 b.

Cesium-134 1.00 El Cesium-137 2.00 El Unidentified Mixed Fission Products 1.50 El Cobalt-60 3.50 El Manganese-54 2.00 El 3.

Solid Waste Dispostion Number of Shipments Mode of Transportation Destination 1

Truck (Sole Use)

Richland, Washington B.

Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transporation None

8 9

i.

'Y h'

M '", -

.c p

3%

h

?byk

,,,.s.

Y" M 4 "

M l,

=

',;if k 7

MQa-f l) f jy u s %m $m Qv..,a % +

,.y9

~-

'A_.16.-2k$hf}t}f?W i

=

l' l i. $ l E F gh t:5se L

/

As e~,.

~

gh'.

h' c,\\{}t_ j,y, 4 5j^

1 "~

' i'

.[

l-yiN s

/

g,

-', l

-f '

~

o

. 3<

Q].

/.R t.<

e :~ ;

,,.y, r.

T, 7, '.,

t

};.:

kI[

Q

'.. Y $_ph<._. M p i

'~~

~

J-

/.Y"5 N

/[h f,',i y,je 1

b.

., 7 ?.

n.

6..,; - }743 3,.2 h4 t.

p y r,,,

c. y m. s '/

q,

./.i A-

'. y; q7.1,s $]. g;.

>A, A.h.,,.

w

)

jj a.'}3'.47w<f.

s n

[' ". Q,. Y f, c;; f,& ^~ &

l..l l E., lk 1

t

. v

~

n.

g l

~

..- g gqqqg

3) ppy i ogg; h$ i c'N ' d j $$$g p_y::

. pg JM$

qr=ee+f 4L(eqlQ--.;;;;;_.;.;,_ i 5 W

N3,ysg(h.dpf)[

bb h9 L

a

= = =. m _.

...y s s.

ww-m >mm a t1 p

,<p p.,.._:. _ _,,.. ~

4 y/

vo

_g

(.

l c

o

<r

M<

dk i

TABLE F1 PERCENT OF PERIOD AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: April, 1962 through June 1967 STABILITY CLASS:

C ELEVATION:

250 feet Wind Speed (eph) at 76m liv'el Wind pirection( )

0-3 4-7 8-12 13-18 19-24

>24 Totall 0.

0.02 0.06 0.05 0.03 0.02 0.01 0.20 10.00 0.02 0.03 0.04 0.03 0.01 0.00 0.13 20.00 0.03 0.03 0.01 0.01 0.00 0.00 0.08 30.00 0.02 0.02 0.00 0.00 0.00 0.00 0.04 40.00 0.00 0.01 0.00 0.01 0.00 0.00 0.02 50.00 0.01 0.01 0.00 0.00 0.00 0.00 0.02 60.00 0.01 0.01 0.00 0.00 0.00 0.00 0.03 70.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 80.00 0.01 0.00 0.00 0.00 0.00 0.00 0.01 90.00 0.00 0.00 0.00 0.00 0.00.

0.00 0.01 100.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 110.00 0.00 0.00 0.00 0.00 0.09 0.00 0.01 120.00 0.01 0.01 0.01 0.00 0.00 0.00 0.03 130.00 0.01 0.01 0.00 0.01 0.00' O.00 0.03 140.00 0.00 0.01 0.01 0.00 0 01 0.00 0.02 150.00 0.00 0.01 0.01 0.02 0.01 0.00 0.06 160.00 0.00 0.01 0.01 0.01 0.01 0.00 0.04 170.00 0.00 0.00 0.02 0.02 0.01 0.01 0.07 180.00 0.00 0.01 0.02 0.02 0.00 0.00 0.05 190.00 0.01 0.01 0.01 0.01 0.01 0.00 0.04 200.00 0.00 0.02 0.02 0.02 0.00 0.01 0.09 210.00 0.02 0.03 0.06 0.02 0.01 0.00 0.13 220.00 0.01 0.02 0.08 0.04 0.03 0.02 0.19 230.00 0.01 0.06 0.12 0.14 0.05 0.02 0.39 240.00 0.01 0.09 0.22 0.15 0.02 0.03 0.51 250.00 0.02 0.18 0.26 0.10 0.02 0.00 0.58 260.00 0.02 0.13 0.24 0.04 0.01 0.00 0.44 270.00 0.02 0.16 0.22 0.02 0.01 0.00 0.42 280.00 0.02 0.13 0.11 0.01 0.00 0.00 0.27 290.00 0.02 0.10 0.10 0.01 0.01 0.00 0.24 300.00 0.01 0.09 0.06 0.00 0.00 0.00 0.15 110.00 0.01 0.04 0.06 0.01 0.00 0.00 0.12 320.00 0.01 0.03 0.05 0.01 0.01 0.01 0.12 330.00 0.01 0.03 0.03 0.01 0.02 0.01 0.11 340.00 0.01 0.04 0.04 0.03 0.02 0.01 0.15 350.00 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 of f.

TABLE v1 (cont)

PERCENT OF PERIOD AT EACII WIND SPEED AND DIRECTION PERIOD OF RECORD: April 1962 through June 1967 STABil.ITY CLASS: D El.EVATION:

250 feet

~~

Wind Speed (sph) at 76m Level Wind Direction 0-3 4-7 8-12 13-18 19-24

24 Total 0.00 0.11 0.34 0.78 0.85 0.49 0.48 3.05 10.00 0.04 0.27 0.52 0.46 0.38 0.27 1.95 20.00 0.05 0.01 0.32 0. 19 0.16 0.11 1.04 30.00 0.06 G.20 0.16 0.08 0.03 0.04 0.58 40.00 0.05 0.11 0.05 0.02 0.00 0.01 0.23 50.00 0.03 0.05 0.08 0.00 0.01 0.00 0.16 60.00 0.04 0.08 0.04 0.00 0.00 0.00 0.15 70.00 0.04 0.02 0.01 0.01 0.00 0.00 0.08 80.00 0.02 0.04 0.00 0.01 0.00 0.00 0.07 90.00 0.01 n0.04 0.03 0.00 0.00 0.00 0.09 100.00 0.02 0.01 0.02 0.00 0.00 0.00 0.05 L10.00 0.00 0.03 0.01 0.01 0.01 0.00 0.06 120.00 0.02 0.03 0.03 0.02 0.01 0.00 0.11 130.00 0.01 0.03 0.02 0.02 0.01 0.00 0.10 140.00 0.02 0.03 0.02 0.04 0.01 0.01 0.13 150.00 0.03 0.03 0.03 0.09 0.03 0.02 0.23 160.00 0.01 0.04 0.05 0.10 0.04 0.01 0.26 170.00 0.02 0.05 0.12 0.16 0.04 0.01 0.40 180.00 0.04 0.08 0.12 0.13 0.03 0.01 0.40 190.00 0.02 0.07 0.09 0.06 0.03 0.02 0.28 200.00 0.05 0.10 0.17 0.11 0.02 0.01 0.46 210.00 0.05 0.12 0.20 0.08 0.04 0.01 0.51 220.00 0.05 0.14 0.14 0.12 0.05 0.02 0.51 230.00 0.03 0.14 0.17 0.11 0.06 0.02 0.53 240.00 0.08 0.22 0.21 0.06 0.03 0.01 0.61 250.00 0.08 0.17 0.13 0.04 0.01 0.00 0.43 260.00 0.08 0.22 0.13 0.02 0.01 0.00 0.47 270.00 0.12 0.21 0.11 0.03 0.01 0.00 0.49 280.00 0.05 0.20 0.11 0.04 0.00 0.00 0.40 290.00 0.04 0.22 0.11 0.02 0.00 0.00 0.39 300.00 0.10 0.21 0.20 0.02 0.01 0.00 0.53 310.00 0.08 0.28 0.19 0.03 0.02 0.01 0.60 320.00 0.07 0.25 0.33 0.09 0.04 0.01 0.80 330.00 0.06 0.21 0.35 0.16 0.09 0.03 0.90 340.00 0.07 0.24 0.50 0.47 0.17 0.08 1.53 350.00 0.07 0.30 0.82 0.86 0.49 0.33 2.87

TARI.E F1 (cont)

PERCENT OF PERIOD AT EACll WIND SPEED AND DIRECTION PERIOD OF RECORD: April 1962 through June 1967 STABILITY CLASS:

E ELEVATION:

250 feet Wind Speed (mph) at 76m Level Wind Direction 0-3 4-7 8-12 13-18 19-24

14 Total 0.00 1.04 1.06 2.00 1.84 0.82 0.10 6.86 10.00 0.17 0.80 1.55 0.90 0.36

.0.10 3.78 20.00 0.30 0.83 1.26 0.47 0.13 0.00 2.99 30.00 0.37 0.73 0.64 0.19 0.01 0.00 1.94 40.00 0.21 0.60 0.47 0.02 0.00 0.00 1.31 50.00 0.18 0.56 0.28 0.02 0.00 0.00 1.05 60.00 0.21 0.54 0.19 0.00 0.00 0.00 0.93 70.00 0.19 0.44 0.07 0.00 0.00 0.00 0.81 80.00 0.20

.0.41 0.07 0.00 0.00 0.00 0.68 90.00 0.27 0.47 0.17 0.01 0.00 0.00 0.82 100.00 0.17 0.24 0.06 0.01 0.00 0.00 0.49 0.00 0.00 0.60 110.00 0.20 0.31 0.10 0.00 120.00 0.18 0.31 0.19 0.01 0.02 0.00 0.70 130.00 0.14 0.25 0.09 0.08 0.03 0.03 0.72 140.00 0.09 0.22 0.21 0.23 0.22 0.25 l'.21 150.00 0.09 0.24 0.22 0.45 0.52 0.46 2.08 160.00 0.05 0.22 0.25 0.62 0.44 0.21 1.79 170.00 0.04 0.26 0.43 0.73 0.23 0.09 1.89 180.00 0.26 0.32 0.45 0.43 0.20 0.02 1.77 190.00 0.15 0.26 0.37 0.35 0.15 0.02 1.20 200.00 0.22 0.48 0.47 0.26 0.18 0.06 1.77 210.00 0.20 0.44 0.58 0.18 0.05 0.04 1.60 220.00 0.20 0.40 0.55 0.15 0.14 0.03 1.37 230.00 0.23 0.43 0.40 0.14 0.13 0.05 1.39 240.00 0.24 0.39 0.23 0.15 0.13 0.01 1.24 250.00 0.21 0.32 0.16 0.03 0.01 0.01 0.84 260.00 0.24 0.31 0.17 0.03 0.00 0.00 0.85 270.00 0.35 0.35 0.13 0.12 0.01 0.00 0.97 280.00 0.19 0.30 0.15 0.01 0.01 0.01 0.67 290.00 0.19 0.33 0.17 0.01 0.01 0.01 0.81 300.00 0.21 0.37 0.16 0.01 0.00 0.01 0.88 310.00 0.20 0.47 0.29 0.02 0.00 0.00 0.98 320.00 0.20 0.59

0. 65-0.12 0.01 0.05 1.72 330.00 0.22 0.87 0.98 0.35 0.02 0.02 2.45 340.00 0.20 0.88 1.55 0.74 0.01 0.00 3.48 350.00 0.19 1.02 2.02 1.41 0.55 0.13 5.22

TABLE F1 PERCENT OF PERIOD AT EACil WIND SPEED AND DIRECTION PERIOD OF RECORD: April 1962 through June 1967 STABILITY CLASS:

F ELEVATION:

250 feet Wind Speed (mph) at 76m Level Wind Di_rection 0-3 4-7 8-12 13-18 19-24

>24 Total 0.00 0.42 0.08 0.03 0.00 0.00 0.00 0.53 10.00 0.05 0.06 0.05 0.01 0.00 0.00 0.18 20.00 0.05 0.09 0.08 0.03 0.00 0.00 0.24 30.00 0.12 0.11 0.10 0.04 0.00 0.00 0.37 40.00 0.07 0.13 0.10 0.03 0.01 0.00 0.34 50.00 0.09 0.13 0.06 0.00 0.00 0.00 0.27 60.00 0.14 0.19 0.07 0.01 0.00 0.00 0.40 70.00 0.11 10.22 0.08 0.00 0.00 0.00 0.40 80.00 0.10 0.22 0.07 0.00 0.00 0.00 0.39 90.00 0.14 0.25 0.07 0.00 0.00 0.00 0.46 100.00 0.11 0.29 0.09 0.01 0.01 0.00 0.51 110.00 0.13 0.31 0.13 0.02

.0.00 0.00 0.59 120.00 0.15 0.33 0.18 0.03 0.00 0.00 0.69 130.00 0.10 0.23.

0.14 0.02 0.00 0.00 0.50 140.00 0.10 0.22 0.11 0.09 0.02 0.00 0.54 150.00 0.12 0.19 0.10 0.07 0.03 0.02 0.52 160.00 0.08 0.15 0.16 0.08 0.01 0.00 0.47 170.00 0.07 0.15 0.14 0.07 0.00 0.00 0.43 180.00 0.16 0.26 0.13 0.02 0.00 0.00 0.56 190.00 0.12 0.18 0.13 0.02 0.00 0.01 0.46 200.00 0.13 0.25 0.18 0.02 0.00 0.00 0.58 210.00 0.18 0.32 0.20 0.02 0.00 0.01 0.73 220.00 0.14 0.28 0.09 0.02 0.00 0.00 0.54 230.00 0.18 0.24 0.07 0.01 0.01 0.00 0.50 240.00 0.19 0.19 0.05 0.02 0.00 0.00 0.45 250.00 0.15 0.16 0.01 0.00 0.00 0.00 0.32 260.00 0.17 0.10 0.01 0.00 0.00 0.00 0.29 270.00 0.18 0.09 0.01 0.00 0.00 0.00 0.28 280.00 0.10 0.04 0.01 0.00 0.00 0.00 0.15 290.00 0.11 0.05 0.01 0.00 0.00 0.00 0.16 300.00 0.13 0.07 0.00 0.00 0.00 0.00 0.19 310.00 0.07 0.05 0.01 0.00 0.00 0.00 0.13 320.00 0.09 0.05 0.03 0.00 0.00 0.00 0.17 330.00 0.09 0.09 0.01 0.00 0.00 0.00 0.19 340.00 0.06 0.10 0.03 0.01 0.00 0.00 0.20 350.00 0.07 0.09 0.05 0.01 0.00 0.00 0.21 e

(

Report Issued: SEP 101978 Report 420-78.103 PACIFIC GAS AND ELEC'4IC COMPANY DEPARTMENT OF ENGINEERING RESEARCH REPORT NO. 68 ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLOT BAY POWER PLANT EUREKA, CALIFORNIA QUARTER ENDING MARCH 31, 1978 (WINTER) d4 R. F. CAY 0T,' Chief Report Prepared By:

C. H. Andrew R. W. Lorenz

(

Report 420-78.103 TABLE OF CONTENTS Page L I ST OF TA B L E S..........................

ii LIST OF FIGURES..........................

ii

SUMMARY

1 INTRODUCTION..

1 SAMPLE COLLECTIONS AND ANALYSES..................

1 DISCUSSION OF ANALYTICAL RESULTS.................

2 RELEASES OF GASE0US RADI0 ACTIVE WASTE...............

3

$_ REFERENCES............................

4 APPENDIX.............................

5 i

(

Report 420-78.103 LIST OF TABLES Table Page 8

1.

Samples Collected......................

2.

Radioanalysis of Marine Samples...............

9 3.

Radioanalysis of Terrestrial Samples.............

10 4.

Dosimeter Measurements....................

11 5.

F ilm P ack Measureme nts....................

12 6.

Air Particulate, Station No. 3, Gross Beta Activity.....

13 7.

Air Particulate, Station No. 45, Gross Beta Activity.....

14 LIST OF FIGURES Figure Page 1.

Station Locations of Environmental Samples..........

15 2.

Station Locations of Dosimeters and Film Packs........

16 3.

Chronological Display of Selected Environmental 1'easurements.

17 ii

(

Report 420-78.103

SUMMARY

Measurements of radioactivity in marine and terrestrial samples and in air particulates frou the environment near the Humboldt Bay Power Plant during this quarter generally remained within the range of preoperational background measurements. The maximum integrated dose measured was well below the permissible contribut' ion of 500 mrem / year in unrestricted areas.

INTRODUCTION This is the 68th quarterly report on radiation in the environment

' " near Humboldt Bay Power Plant (HBPP) covering the period January through March 1978. This report contains information on the samples collected, methods and results of radiochemical analyses, a discussion of the results,. and also information about the " Releases of Gaseous Radioactive Waste" supplied by the Department of Steam Generation.

Information on the release of liquid radioactive waste from H8PP is reported elsewhere.I*

SAMPLE COLLECTIONS AND ANALYSES Air particulate filters, dosimeters, film packs, and 12 marine and terrestrial samples were collected for this report in accordance with the requirements of the North Coast Regional Water Quality Control Board,3 2

and the Department of Health.4 A table of the samples collected and maps showing the sampling locations (Figures 1 and 2) are presented in the Appendix.

See reference page.

(

2 Report 420-78.103 Thirty-eight gross beta analyses, two iodine <131 analyses, and 13 gamma scans were performed for this report. The results are tabulated in the Appendix. All samples except the dosimeters and film packs were analyzed at the Department of Engineering Research (0 9 ).

Dosimeters were read by HBPP personnel. Film packs were read and confirmatory analyses of five samples were performed by outside contractors.

DISCUSSION OF ANALYTICAL RESULTS Most environmental samples analyzed for this report contained low levels of radioisotopes identified by ganma spectrometry. These

~ radioisotopes were fission products from Chinese bomb tests and past plant releases, and long-lived corrosion products from the plant which are quantified at lower detection limits because of improved gamma spectrometry techniques which were initiated in 1977. Garmia spectrometry was used to quantify the radioisotopes present on monthly composited air particulate filters. These analyses of particulate filters confirmed that the higher than normal airborne activity was due to fallout of fission products from weapons tests and not due to the plant stack discharge. As shown below, the confirmatory analyses by an outside contract,or are in good agreement with the DER results.

Gross Beta Activity (pCi/q dry)

Sample No.

LFE Envi snmental DER 78087 6.1 +0.6 5.4 +0.5 78090 16.0 71.2 13.7 71.0 78093 7.7 70.8 6.8 70.5 78095 8.7 70.8 6.9 T0.5 78037 9.911.0 8.810.5

f

(

3 Report 420-78.103 During the preceding 52-week period, the maximum integrated radiation exposure was measured at Station 16. The total annual exposure at Station 16 was approximately 8.0 mR above background measured at Stations 2 and 5.

Figure 3 is a chronological display of dosimeter and film pack radiation exposures per month at Station 14 and the air particulate activity at Station 3 from January 1975 through this quarter. Reports 37 and 55 contsin graphs from previous years.

RELEASES OF GASE0US RADI0 ACTIVE WASTE The routine releases of gaseous radioactive wastes have been monitored by the air ejector off-gas and stack-gas monitoring systems.

The calibration of these monitors for noble and activated gases has been checked by periodic analyses of " grab" samples on a multichannel gama scintillation spectrometer. The refueling, maintenance, and station modification outage which started in July 1976, continued through this quarter; therefore, airborne releases were insignificant.

(

4 Report 420-78.103 REFERENCES 1.

Quarterly report to Regional Water Quality Control Board on Liquid Waste Discharge from Humboldt Bay Power Plant.

2.

Letter from North Coastal Regional Water Quality Control Board to PGandE, Attn:

F. F. Mautz, concerning modifications to waste dise;arge and environmental radiation monitoring requirements, dated May 7,1965.

3.

Letter from North Coastal Regional Water Quality Control Board to PGandE, Attn: Mr. P. Matthew, concerning modifications to waste discharge requirements, dated April 8,1966.

4.

Department of Public Health letter to PGandE, Attn: Mr. P. Matthew, concerning modifications to environmental radiation monitoring requirements, dated June 17, 1966.

[ _ 5.

Environmental Radiation in the Vicinity of Humboldt Bay Power Plant, Reports 1-8.

6.

Code of Federal Regulations, Title 10, Para. 20.105.

(

5 Report 420-78.103 APPENDIX Page Methods of Sample Collection and Analysis 6

Table 1 Samples Collected 8

Table 2 Radioanalysis of Marine Samples 9

Table 3 Radioanalysis of Terrestrial Samples 10 Table 4 Dosimeter Measurements 11 Table 5 Film Pack Measurement',

12 Table 6 Air Particulate, Station No. 3, Gross Beta Activity 13

[~[_~~ Table 7 Air Particulate, Station No. 45, Gross Beta Activity 14 Figure 1 Station Locations of Environmental Samples 15 Figure 2 Station Locations of Dosimeters and Film Packs 16 Figure 3 Chronological Display of Selected Environmental

, Measurements 17 e

W

(

6 Report 420-78.103 METHODS OF SAMPLE COLLECTION AND ANALYSIS Marine samples are collected by Humboldt State College Foundation personnel under the direction of Dr. J. A. Gast. PGandE Humboldt Division nersonnel collect the remainder of the samples.

Marine and terrestrial samples are processed quarterly at DER.

Samples are freeze-dried prior to determining gross beta activity. The gross beta analysis is performed on low background, thin window, gas flow proportional counters; the limit of detectability is about 0.5 pCi/gm of a standard containing K-40.

Activities are reported both per gram of the

_ dry and per gram of the original sample.

The freeze-dried samples are gama scanned, using a Ge(Li) detector and multichannel pulse height analyzer. The limit of detectability attained in the gamna scan is typically 5 pC1/1 of water solution containing a single radionuclide.

Radioiodine analyses are performed on milk samples within eight days of collection by using the procedure abstracted in Nuclear Regulatory Comission (NRC) Regulatory Guide 4.3.

The detection limit attained by this method is typically 0.2 pCi/ liter for I-131.

The potassium content of most of the freeze-dried sampl&s is measured by flame photometry in order to estimate the K-40 contribution to the gross activities. The range of concentrations used is one to ten ppm; the standard deviation in the concentration units (Gaussian) is about 12 percent at the 5 ppm level. Using the factor of 830 pCi/g K, the activity of K-40 in a sample is calculated.

C

(

7 Report 420-78.103 The tritium (H-3) activity in domestic water is determined by analyzing a distilled aliquot of the sample with a liquid scintillation spectrometer. The limit of detection for this analysis is typically 0.2 pCi/ml of water.

The airborne particulate samplers are located at Stations 3 and 45 (Figure 1). The constant flow samplers have flow rate in the range of 30 to 40 1pm; an HV-70 filter is used. The filters are collected on a weekly basis and mailed to DER. The filters are counted to determine gross beta activity at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after collection to allow for naturally

~~_ occurring short-lived radionuclides to decay.

Ganma dosimetry is performed with two ion chambers (Victoreen, Model 239) and a film pack located at each of the 30 stations shown in Figure 2.

The ion chambers are read in the field by HBPP personnel on a biweekly basis. The lower of the two readings is normally reported since the dosimeters normally read high on failure. The Radiation Detection Company (RDC), Sunnyvale, California, supplies and reads the film packs. RDC reports film pack doses relative to " background" at the RDC laboratory, which consistently is 8 mR/ month.

The + term in the following tables is the two-sigma erro'r; i.e., the 95 percent confidence level.

TABLE 1 Report 420-78.103 SAMPLES COLLECTED Marine Verte-Clams & Other Bottom Terres-Air Dosi, Film Station Flora brates Oysters Invert. Sedim.

trial Partic. meters' _ Packs 1 K. Salmon Picnic Area 2

7 3

2 1742 Wood, Fortuna 7

3 3 Humbo'ldt Hill (HH) Rd 13 7

3 4 Wood & K, Eureka 7

3 5 Redwood Ave, Arcata 1

7 3

6 Table Bluff & Clough 7

3 m

7 Col. of the Redwds 7

3 8 Hmblt H1 Rd Hr Donna 7

3 9 lIH Rd Nr Harbor View 7

3 10 B St., Field Lndg 7

3 7

3 11 klhittier Ct & Irving 12 Bell Hill Rd, HH 7

3 13 Crab St, Buhne Pt 7

3 m

7 3

14 South Bay School 7

3 15 Eich Dr,llH 16 Bennett Dairy 1

7 3

17 Bassford Rd, Ridgewd 18 6418 Elk River Rd 7

3' 7

3 19 Noe St, Pine Hill 20 Jacobs Jr. H.S.

7 3

7

.3 21 PG&E Well 2, liH Rd 22 Sta B - 14th St 7

3 23 liarris St. Substa.

7 3

G 24 PG&E Office, Eureka 7

3 7

3 g

25 Irving Dr, Hit 7

3 B

26 Worthington Ln, liH 27 Berta Road 7

3 3

28 Berta Road 7

3 3

29 Vista Road, Illi 7

3 g

7 3

4 30 Burns Dr,liH m

45 Ilumboldt Substation 13 48 llolgerson Dairy 1

5 w

55 PG&E Outfall I

56 1000 ft. H Outfall 2

1 57 1000 ft. S Outfall 2

59 Hookton Channel 65 Coast Oyster Co.

1

I TABLE 2

' Report 420-78.103 RADI0 ANALYSIS OF MARINE SAMPLES K40 Activity Gross Beta Potassium Gross Activity m

asswm Content Activity Collec-Beta tion Counting (mg K/g (pCi/gDr{f pCi/g Orig.

(pCi/q Dry Sample)

Sta Sample Description Date Date Beta Garanal/

Dry Sample)

Sample)-

Sample) 3 55 78087 Sediment /

2/18/78 4/ 2/78 5.4210.47 Cs-137 0.02710.010 4.89 4.06 4.9010.43 56 78083 Sediment 2/21/78 4/ 2/78 7.8610.60 Cs-137 0.03210.011 7.29 6.05 6.3310.48 56 78089 Red Algae 2/21/78 4/ 2/78 12.610.90 Nb-95 0.15010.030 14.6 12.1 3.2210.2; (Giqartina agardhii) 3 56 78090 Red Algae /

2/21/78 3/30/78 13.710.97 Cs-137 0.026+0.008 15.3 12.7 2.95+0.21 (Iridaea sp.)

Ce-144 0.19110.083 57 78091 Red Algae 3/ 5/78 4/ 2/78 13.0+0.93 Nb-95 0.121+0.032 13.8 11.4 4.04+0.29 (Giqartina aqardhii)

Ce-1440.50510.097

~-

78092 Red Al 3/ 5/78 4/ 2/78 13.710.97 Ce-144 0.56910.107 15.1 12.6 3.1710.22 57 (Iridaea sp.) gae o

65 78093 Pacific Oyster /

3/ 7/78 4/ 2/78 6.82+0.53 7.27 6.03 1.3810.11 3

(Crassostrea gigas) 1/ Activity at time of sampling. Naturally occurring radioisotopes are not reported.

1/ Fork 40activityof830pCi/gmnaturalpctassium.

3/ Samples analyzed at DER then sent to State Department of Health.

O n

?'

M 8

TABLE 3 Report 420-78.101 RADI0 ANALYSIS OF TERRESTRIAL SAMPLES K40 Activity Potassium Gross Beta Gross Activity in Potassium Content Activity Collec-Beta (pCi/g Dry Sample) tion Counting

(,g gjg (pd/g Dr pCi/g Orig.

Sta Sample Description Date Date Beta Gammal/

Dry Sample)

Sample) /

Sample) 1 78106 DomesticWaterEl 3/ 7/78 5/ 5/78 9.22+1.45 0.8610.14E/

m 1 78094 Soil 3/ 5/78 4/ 3/78 7.03_+0.52 5.60 4.65 6.5210.4 5 78095 Soil 3/ 8/78 4/ 2/78 6.87+0.54 Cs-134 0.040+0.014 5.20 4.32 5.72+0.45 Cs-137 0.139 0.017 16 78037 Milki/

2/ 6/78 3/31/78 8.77+0.54 10.4 8.61 1237+76.11/

S/

2/10/78 70.20 48 78038 Milki/

2/ 6/78 3/31/78 7.37+0.46 Cs-137 0.054+0.012 9.18 7.62 ll20169.9E/

d/

2/15/78 70.20 E

1/ Activity at time of sampling. Natur'lly occurring radioisotopes are not reported.

2/For K40 activity of 830 pCi/gm nat'

, potassium.

3/ ample is evaporated for beta ana

and distilled for H-3 analysis.

H-3 activity less than 0.20 pCi/ml.

^

S S/ Iodine-131 activity, pCi/1., at ti.a of sampling.

E/pCi/1.

[

S/ ampled jointly with the State Department of Health.

y S

4 C

h z

(

l Report 420-78.103 TABLE 4 DOSIMETER MEASUREMENTS 1

Period Start:

12/27/77 1/10/78 1/24/78 2/ 7/78 2/21/78 3/ 7/78 3/21/78 3/22/77 Period End:

1/10/78 1/24/78 2/ 7/78 2/21/78 3/ 7/78 3/21/78 4/ 4/78 4/ 4/78 Elapsed Time, Days:

14 14 14 14 14 14 14 378 2/

Station Total mR Total mR Total mR Total mR Total mR Total mR Total mR Total mR 1

1 1/

6.1 4.0 3.1 3.4 2.8 2.5 74.4 2

372 3.1 3.3 3.2 3.0 3.4 2.9 82.8

-4B/

3 3.3 3.0 2.8 3.0 2.7 3.2 3.0 82.2 4

2.6 2.5 3.0 1/

3.6 3.2 3.0 77.0 5

2.8 3.1 3.0 T/

2.9 2.9 3.4 86.5 6

4.0 3.3 3.0 375 5.6 2.8 3.2 87.2 7

3.4 2.7 2.8 2.9 3.1 2.9 2.5 82.2 8

3.2 1/

3.0 3.0 2.8 2.7 2.7 78.5 50/

9 3.2 2.6 3.4 3.0 3.3 2.7 2.7 b2.0 10 3.4 2.7 2.6 2.7 3.0 2.7 3.2 85.5 11 2.6 3.1 3.3 3.1 3.2 2.9 3.0 82.7 12 3.0 2.7 3.4 2.8 3.1 2.5 2.8 76.0

-50/

13 2.4 3.8 3.0 3.0 2.9 3.2 2.5 85.2 5

14 3.5 2.6 3.2 6.6 2.5 3.1 2.5 82.9 15 3.0 3.1 3.2 3.0 5.5 2.9 3.2 85.4 16 3.8 3.8 3.9 3.2 3.6 3.0 3.0 92.7 17 3.0 3.3 3.7 4.7 3.0 3.3 3.0 85.1 18 3.3 2.7 3.5 3.1 3.1 3.3 3.2 81.5 19 3.2 2.6 3.3 3.2 5.4 2.9 3.0 84.3 20 3.0 2.6 5.2 2.9 3.0 4.5 3.0 77.6 21 3.5 2.6 3.2 2.9 3.2 1/

2.7 78.1 m

22 3.5 4.0 2.5 3.4 3.0 278 3.2 85.5 23 3.4 3.0 3.0 3.0 2.9 3.9 3.8 83.0

-50/

m 24 4.8 2.8 3.2 2.8 3.0 2.9 2.8 83.1 0

25 3.0 2.7 5.8 3.1 2.7 3.0 2.9 82.6 26 3.5 3.2 3.7 8.2 2.8 2.5 3.1 91.3 27 3.3 3.3 3.6 3.4 3.0 2.5 3.2 89.5 0

28 3.2 2.7 3.2 3.2 3.0 2.8 3.0 78.8

?

29 3.4 2.7 2.8 3.1 3.3 3.4 3.0 83.4 s

30 3.3 2.3 3.5 3.0 3.0 2.5 3.0 82.3 1/Both dosimeters read 0 and/or full scale.

2_/ Weeks of data, if less than 52.

Report 420-78.103 TABLE 5 FILM PACK MEASUREMENTS Period Start:

12/27/77 2/ 8/78 3/ 7/78 '

Period End:

2/ 8/78 3/ 7/78 4/ 4/78 Elapsed Tine, Days:

43 27 28 Stat on Total mR /

Total mR /

1 1

0 0

0 2

0 0

0 3

0 0

0 4

0 0

0 5

0 0

0 6

0 0

0 7

0 0

0 8

0 0

0 9

0 0

0 10 0

0 0

11 0

0 0

g 12 0

0 0

13 0

0 0

14 0

0 0

15 0

0 0

16 0

0 0

17 0

0 0

18 0

0 0

19 0

0 0

20 0

0 0

m 21 0

0 0

/

22 0

0 0

m 23 0

0 0

g 24 0

0 0

g 25 0

0 0

26 0

0 0

R 27 0

0 0

?

28 0

0 0

y 29 0

0 0

30 0

0 0

8

. 1/Above background of 8 mR/mo.

t l 8 Report 420-78.103 TABLE 6 AIR PARTICULATE STATION NO. 3 GROSS BETA ACTIVITY Sample Volume Collection Countinc Number (m**3)

__ Date Date pCi/m**3 78008 284.7 1/10/78 1/20/78 0.100+0.006 78018 291.7 1/17/78 1/26/78 0.069T0.004 78025 286.9 1/24/78 1/31/78 0.05810.003 78031 274.0 1/31/78 2/ 6/78 0.147+0.009 78049 297.8 2/ 7/78 2/28/78 0.121][0.005 78054 273.7 2/14/78 2/28/78 0.105+0.007 u>

78057 287.5 2/21/78 2/28/78 0.085TO.001 78074 285.7 2/28/78 3/ 7/78 0.070+0.004 78084 293.1 3/ 7/78 3/13/78 0.134+0.009 78101 281.4 3/14/78 3/21/78 0.099+0.004 78123 281.2 3/21/78 3/30/78 0.185+0.006 78132 277.8 3/28/78 4/11/78 0.132T0.004 78142 284.5 4/ 4/78 4/12/78 0.139:[0.009

-s M

i!

a e?a E3

Report 420-78.103 TABLE 7 AIR PARTICULATE STATION NO. 45 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3)

Date Date pCi/m**3 78009 431.9 1/10/78 1/20/78 0.08610.005 78019 431.4 1/17/78 1/27/78 0.06510.003 78026 426.3 1/24/78 1/31/78 0.05710.002 78032 417.2 1/31/78 2/ 6/78 0.143+0.06.

78050 440.6 2/ 7/78 2/28/78 0.129}0.008 78055 404.9 2/14/78 2/28/78 0.109+0.007 78053 433.4 2/21/78 2/28/78 0.05470.005 78075 420.2 2/28/78 3/ 7/78 0.075T0.003 a

78085 433.5 3/ 7/78 3/13/78 0.11830.006 78102 433.0 3/14/78 3/21/78 0.278+0.013 78124 432.4 3/21/78 3/30/78 0.17110.006 78133 427.3 3/28/78 4/11/78 0.139+0.004 78143 431.1 4/ 4/78 4/13/78 0.15710.011 m

c"o is a

m S

/

15

(

pe,cc: ~ 20 - 7 ^,.10 2 I

\\

{

4

\\/

+

N y

T6N O

o ARCATA

,A STATI0il flu'1BER y

., ' ')

}'

...*b ob ;)

O

-t s

%}

y*}0. 3 '

Q

,/o

//,s s

T S P.

O l-

_f

///4mli F l

/ EUREKA

~*

6 5 --

b YI -

16 W

I 56 HUMBOLDT BAY t

55 -

, POWER LANT M dEIEi'.DS p

lT 4 N LANDING 1

\\

- - '+

N

' South M'I'+

ni<e,

sy m

s, 3

4

[)

sorm en 3

43 b

I x

0 fr A

RiveY' ORTUNA

sn niv,e 3

l

[Y Raw RlW RIE

\\

<r

)I FERNDALE T2n I l E!171. 0TE.lTAL S.V'PLES 9

ENVIRONMENTAL RADtATION STUDY IN THE VICINI'Y OF HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC COMPANY o

1 2

3 4

5 G W Lt$

Figure 1

(

V.

(

Renort 42%7'i.103

\\

l

%s l

~

(.

r

~5TATIO 4 fluttBEP, H

T v

5~

4/

Tsw 24 O

ARCAT/

22 4

c!;.

g

~..goi i

e;,

c['

x h.<

Af Tsw 37 1

\\E l

q:-

s

~

e N,

HUMBOLDT BAY s

18 POWER ANT i

21 -

M t c"'"

~

12 lT 4 N 10 N INC n rs 7,,,

'4 Rive,

30

/[ -

~

s..

\\

g/p 7,

~

//

2

/

26 y

Ri w(ORTUNA z__

sn pi<e y op

__ V' RIw RIE

[

R2w FERNDALE)g

+'

jj DCSI"ETEF.S & CIL" PTCKS ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC COMPANY o

i a

a a

s s was Figure 2

\\

s - '"'~

\\

o m

is

.u t o. 6

,w r

7....

.5

.s

.... s _

+

4 Chronelocicof Olsplay.c.f S.e.lecta.d Env..snmental

.....4._-..~._..,..

. - -..Me e a wre monts..e, 6...-

.(

.-e..

j,

......-46.....

e

-................ d s,..*

6.,,.

a FL g

..._....p........

, 5-,.

g 4.

4

......- - _.]

a

-o

.3....... -.... 1..

)

...-g

....r..

..s._...---._

g

.ap

,I..__

....... =.. -... - _. _

-o

..3 g..

.....!.....l._....._.

I

=.

a. y.-..

a n

...,..._.._...1

..........l...........-

a-..

J

+............

6 o...

I

.y.

.......l

-4 g.....

e.

.o..,,,,... -.

~~.]

-9

.4.._._.._..

3....

I.

3g.............._...,....

l.......

g t1

,3.

.., 3...

o

-.9._.......

g 4

.."h r_...

w

. L.J.

p g

w.

~

I

. _ 1'.

3 2

0_..,+.-. _ - - _...

e 1

_---.V_..,.

..L..-.-.

4 4

. 4 4,

r.-..-

20

+.

= - - -. _

w...

}

s g

-_.m-4 i

i 15

-r _.

~

J 1

i.

.. - =

I~'-

- + - -

'I.--

--*

w 10

....u-_',_..

_ u..

I i

r...

g-

.p.

I g

,. +. _.

., ~... _

g

..g,.- --

w 5'-

M t

i E

---'t

=$-

-+

g

.=

6 g

4.. _

o S g

O._

.s..

__.......a..__

4.

g

-.....l e

... -.~.

=.

,..-.....,....b.......E.m g

_~_.&.~.._

= _

-.,,. _.s.

v

- - - - - - ' - - - ' ' - - + - - - - -

1 3

20'.--'----*..'_--

_ _.- _ r: _. _._-

O l

a e-..- n

_~... +... _ -,.

._.......s....

s E

e I

g g

~_-

t

......__._._..4...__...

........_..y....

..........g.

v

-.._..44 c

...g..

s

. ~. _..............._...A......

. l.. _... _ 4

- - - - - - - - -.......f...._..,_=~...j_._.

O

.4

.. 4 o

s..............

.ns o....

._.I_.-...__...

8 10 - - - - - - - --~. _..

o

...J-...-.l.*...--.".'_-....*-

e,

+

o

.]..__._

.. =.,,... _

o a

l.

... - ~......

... - - * - - - - ' ~ ~~--m~----~-

-.. 4.

E 6 S

' - - * - ~

'-~~t--

5

,.J...

..q.--.......__..

g

... _.. I a

l......

i k.

es 4

....... ~ -.

1..

,...-I_

i 4...

.3C 0 I."

-F

-t---

942423,400Z0,62427,40020,6242734mOzo34242774mOZO76242774mozo l

1975 l

1976 l

1977 l

1978 l

1979 F1;nire 3

Report 420-78.120 TABLE OF CONTENTS Page LIST OF TABLES..........................

ii LIST OF FIGURES..........................

ii

SUMMARY

1 INTRODUCTION...........................

1 SAMPLE COLLECTICNS AND ANALYSES..................

1 DISCUSSION OF ANALYTICAL RESULTS.................

2 RELEASES OF GASEOUS RADI0 ACTIVE WASTE...............

3 REFERENCES............................

4 APPENDIX.............................

5 W

W w

w W

i s

W

~w.bdMah e '-

' - '" e c *

W Report 420-78.120 LIST OF TABLES Table Page 1.

Samples Collected......................

8 2.

Radicanalysis of Marine Samples...............

9 3.

Radioanalysis of Terrestrial Samples.............

10 4.

Dosimeter Measurements....................

11 5.

Film Pack Measurements....................

12 6.

Air Particulate, Station No. 3, Gross Beta Activity.....

13 7.

Air Particulate, Station No. 45, Gross Beta Activity.....

14 LIST OF FIGURES Figure Page 1.

Station Locations of Environmental Samples..........

15 2.

Station Locations of Dosimeters and Film Packs........

16 3.

Chronological Display of Selected Environmental Measurements.

17 w*

4.

ii

.+

- -. m. m w. '

l_

_ 1_ Ned/m. nee.w - -

I-*

em

Report 420-78.120

SUMMARY

~

Measurements of radioactivity in marine and terrestrial samples and in air particulates from the environment near the Humboldt Bay Power Plant during this quarter generally remained within the range of preoperational background measurements. The maximum integrated dose measured was well below the permissible contribution of 500 mrem / year in unrestricted areas.

INTRODUCTION This is the 69th quarterly report on radiation in the environment near Humboldt Bay Power Plant (HBPP) covering the period April through June 1978. This report contains information on tha samples collected, methods and results of radiochemical analyses, a discussion of the results, and also information about the " Releases of Gaseous Radioactive Waste" supplied by the Department of Steam Generation.

Information on the release of liquid radioactive waste from HBPP is reported elsewhere.1*

SAMPLE COLLECTIONS AND ANALYSES Air particulate filters, dosimeters, film packs, and 15 marine and terrestrial samples were collected for this report in accordance with the requirements of the North Coast Regional Water Quality Control Board,3 2

and the Department of Health.4 A table of the samples collected and maps. howing the sampling locations (Figures 1 and 2) are presented in the Appendix.

See reference page.

W

.e

. esse e.emm a-

-e s.. a o mughme w

2 Report 420-78.120 Thirty-nine gross beta analyses, two iodine-131 analyses, and 16 garna scans were performed for this report. The results are tabulated in the Appendix. All samples except the dosimeters and film packs were

~

analyzed at the Department of Engineering Research (DER). Dosimeters were read by HBPP persor.nel. Film packs were read and confirmatory analyses of five samples were performed by outside contractors.

DISCUSSION OF ANALYTICAL RESULTS Most environmental samples analyzed for this report contained low levels of radioisotopes identified by gamma spectrometry. These radioisotopes were fission products from Chinese bomb tests and past plant releases, and long-lived corrosion products from the plant which are quantified at lower detection limits because of improved gamma spectrometry techniques which were initiated in 1977. Gamma spectromatry was used to quantify the radioisotopes present on monthly composited air particulate filters. These analyses of particulate filters confirmed that the h,r.er than normal airborne activity was due to fallout of fission products from weapons tests and not due to the plant stack discharge. As shown below, the confirmatory analyses by an outside contractor are in good agreement with the DER results.

Gross Beta Activity (pCi/g dry)

Sample No.

LFE Environmental DER 78182 6.6+0.8 5.6 +0.7 78187 16.171.2 13.1 T1.0 78191 7.6T0.8 7.1 70.4 78190 9.671.0 9.1 TO.3 78205 8.010.8 6.610.5

.. _ -. ~..

~

3 Report 420-78.120 e

During the preceding 52-week period, the maximum integrated radiation exposure was measured at Station 16. The total annual exposure at Station 16 was approximately 6.0 mR above background

measured at Stations 2 and 5.

Figure 3 is a chronological display of dosimeter and film pack radiation exposures per month at Station 14 and the air particulate activity at Station 3 from January 1975 through this quarter. Reports 37 and 55 contain graphs from previous years.

RELEASES OF GASEGUS RADI0 ACTIVE WASTE The routine releases of gaseous radioactive wastes have bcan monitored by the air ejector off-gas and stack-gas monitoring systams.

The calibration of these monitors for noble and activated gases has been checked by periodic analyses of " grab" samples on a multichannel gamma scintillation spectrometer. The refueling, maintenance, and station o

modification outage which started in July 1976, continued through this quarter; therefore, airborne releases were insignificant.

Extrapolated to one year from actual measurements.

w 4

1 w

....w.

h A.aan. *

~-

enE6b u.

.s

4 Report 420-78.120 REFERENCES 1.

Quarterly report to Regional Water Quality Control Board on Liquid Waste Discharge from Humboldt Bay Power Plant.

2.

Letter from North Coastal Regional Water Quality Control Board to PGandE, Attn:

F. F. Mautz, concerning modifications to waste discharge and environmental radiation monitoring requirements, dated

=

May 7, 1965.

3.

Letter from North Coastal Regional Water Quality Control Board to PGandE, Attn:

Mr. P. Matthew, concerning modifications to waste discharge requirements, dated April 8, 1966.

4.

Department of Public Health letter to PGandE, Attn:

Mr. P. Matthew, concerning modifications to environmental radiation monitoring requirements, dated June 17, 1966.

5.

Environmental Radiation in the Vicinity of Humboldt Bay Power Plant, Reports 1-8.

o 6.

Code of Federal Regulations, Title 10, Para. 20.105.

v w

W w

W 4

1

=

.,6-d---w.

ar-um

5 Report 420-78.120 APPENDIX Page Methods of Sample Collection and Analysis 6

Table 1 Samples Collected 8

Table 2 Radioanalysis of Marine Samples 9

Table 3 Radioanalysis of Terrest ial Samples 10 Table 4 Dosimeter Measurements 11 Table 5 Film Pack Measurements 12 Table 6 Air Particulate, Station No. 3, Gross Beta Activity 13 Table 7 Air Particulate. Station No. ~

Gross Beta Activity 14 Figure 1 Station Locations of Environmental Samples 15 Figure 2 Station Locations of Dosimeters and Film Packs 16 Figure 3 Chronological Display of Selected Environmental Measurements 17

%v w

%9 1

..-ec.

.. e.= h w.e s.. une 44 * * % -. ' 4 J ++e*-

6 Report 420-78.120 METHODS OF SAMPLE COLLECTION AND ANALYSIS Marine samples are collected by Humboldt State College Foundation personnel under the direction of Dr. J. A. Gast. PGandE Humboldt Division personnel collect the remainder of the samples.

Marine and terrestrial samples are processed quarterly at DER.

Samples are freeze-dried prior to determining gross beta activity. The gross beta analysis is performed on low background, thin window, gas flow proportional counters; the limit of detectability is about 0.5 pCi/gm of a standard containing K-40.

Activities are reported both per gram of the dry and per gram of the original sample.

The freeze-dried samples are gamma scanned, using a Ge(Li) detector and multichannel pulse height analyzer. The limit of detectability attained in the gamma scan is typically 5 pCi/l of water solution containing a single radionuclide.

Radioiodine analyses are performed on milk samples within eight days of collection by using the procedure abstracted in Nuclear Regulatory Commission (NRC) Regulatory Guide 4.3.

The detection limit attained by this method is typically 0.2 pCi/ liter for I-131.

The potassium content of most of the freeze-dried samples is measured by flame photometry in order to estimate the K-40 contribution to the gross activities. The range of concentrations used is one to ten ppm; the standard deviation in the concentration units (Gaussian) is about 12 percent at the 5 ppm level. Using the factor of 830 pCi/g K, the activity of K-40 in a sample is calculated.

d

. e -.w ama./. A. *h 4..waneeem w=

ee...

7 Report 420-78.120 The tritium (H-3) activity in domestic water is determined by analyzing a distilled aliquot of the sample with a liquid scintillation spectrometer. The limit of detection for this analysis is typically 0.2 pCi/ml of water.

The airborne particulate samplers are located at Stations 3 and 45 (Figure 1). The constant flow samplers have flow rate in the range of 30 to 40 1pm; an HV-70 filter is used. The filters are collected on a weekly basis and mailed to DER. The filters are counted to determine gross beta activity at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after collection to allow for naturally occurring short-lived radionuclides to decay.

Gamma dosimetry is performed with two ion chambers (Victoreen, Model 239) and a film pack located at each of the 30 stations shown in Figure ?.

The ion chambers are read in the field by HBPP personnel on a biweekly basis. The lower of the two readings is normally reported since the dosimeters normally read high on failure. The Radiation Detection Company (ROC), Sunnyvale, California, supplies and reads the film packs. RDC

~

reports film pack doses relative to " background" at the RDC laboratory, which consister is 8 mR/ month.

The I term in the following tables is the two-sigma error; i.e., the 95 percent confidence level.

W

g. ee ee ne. g w.e 4 * * -- o we s e -

o

(

f f

TABLE 1 Report 420-78.120 SAMPLES COLLECTED Marine Verte-Clams & Other Bottom Terres-Air Dosi-Film Station Flora brates Oysters Invert. Sedim.

trial Partic. meters Packs 1 K. Salmon Picnic Area 2

6 3

2 1742 Wood, Fortuna 6

3 3 Hunboldt Hill (HH) Rd 12 6

3 4 Wood & K, Eureka 6

3 5 Redwood Ave, Arcata 1

6 3

6 Table Bluff & Clough 6

3 7 Col. of the Redwds 6

3 8 Hmblt H1 Rd Nr Donna 6

3 9 HH Rd Nr Harbor View 6

3 10 B St., Field Lndg 6

3 11 Whittier Ct & Irving 6

3 12 Bell Hill Rd, HH 6

3 13 Crab St Buhne Pt 6

3 14 South Bay School 6

3 15 Eich Dr, HH 6

3 16 Bennett Dairy 1

6 3

17 Bassford Rd, Ridgewd 6

3 18 6418 Elk River Rd 6

3 19 Noe St, Pine Hill 6

3 20 Jacobs Jr. H.S.

6 3

21 PG&E Well 2, HH Rd 6

3 22 Sta B - 14th St 6

3 23 Harris St. Substa.

6 3

24 PG&E Office, Eureka 6

3 25 Irving Dr, HH 6

3 s,

F 26 Worthington Ln, HH 6

3 27 Berta Road 6

3 g

28 Berta Road 6

3 29 Vista Road, HH 6

3 r

9 30 Burns Dr, HH 6

3

[

45 Humboldt Substation 12 i

48 Holgerson Dairy 1

[

55 PG&E Outfall 1

1 1

56 1000 ft. N Outfall 2

1 l-57 1000 ft. S Outfall 2

i.

59 Hookton Channel 1

65 Coast Oyster Co.

1

(

t

(

f

(

TABLE 2 Report 420-78.120 RADI0 ANALYSIS OF MARINE SAMPLES Potassium K40 Activity Gross Beta Collec-Beta Gross Activity in Potassium Content Activity (pci/g Dry Sample) tion Counting (mg K/g (pCi/g Dry pCi/g Orig.

Sta Sample Description Date Date Beta Ga:mial/

Dry Sample)

Sample)El Sample) 55 78182 Sediment 1/

4/22/78 6/27/78 5.6410.67 137-Cs 0.01710.003 3.90 3.23 4.8910.58 55 78183 Red Algae 4/23/78 6/27/78 9.3610.82 10.6 8.76 1.4010.12 (Iridaea sp.)

55 78184 R

4/23/78 8/14/78 12.110.37 137-Cs 0.10310.038 13.5 11.2 2.4810.01 Surfperch_gtailed (Amphistichus rhodoterus) 56 78185 Sediment 4/23/78 6/27/78 8.3910.89 137-Cs 0.02910.010 6.65 5.52 6.6710.71 f

56 78186 Red Algae 4/23/78 6/27/78 13.9+0.99 95-Nb 0.073+0.015 13.9 11.5 3.51+0.25 (Gigartina agardhii) 103-Ru 0.090TO.026 106-Rh 0.164+0.095 137-Cs 0.018T0.007 144-Ce 0.36270.097 56 78187 Red Algaell 4/23/78 6/27/78 13.1+0.95 144-Ce 0.196+0.077 14.7 12.2 1.89+0.14 (Iridaea sp.)

57 78188 Red Algae 4/22/78 6/27/78 13.110.95 7-Be 0.33610.127 14.2 11.8 3.0810.22 3

(Gigartina agardhii) 95-Nb 0.075+0.014 103-Ru 0.1263 022 106-Rh 0.342+0.075 137-Cs 0.023T0.004 144-Ce 0.6859 053 57 78189 Red Algae 4/22/78 6/27/78 14.6+1.03 (Iridaea sp.)

95-Nb 0.062+0.023 17.1 14.2 1.86+0.13 65 78191 PacificOyster$I 4/26/78 8/18/78 7.06+0.37 7.57 6.28 1.4510.08 f

(Crassostrea gigas) 3 l

59 78190 Gaper Clam /

4/ 8/78 8/17/78 9.0810.33 144-Ce 0.23410.152 9.40 7.80 1.8610.07 (Tresus capex) 1/ Activity at time of sampling. Naturally occurring radioisotopes are not reported.

(

7/For K40 activity of 830 pCi/gm natural potassium.

l/SamplesanalyzedatDERthensenttoStateDepartmentofHealth.

e

(

TABLE 3 Report 420-78.120 RADI0 ANALYSIS OF TERRESTRIAL SAMPLES Potassium K40 Activity Gross Beta Collec-Beta Gross Activity in Potassium Content tion Counting

(,g gfg (pCi/g Dry Activity (pCi/q Dry Sample) pCi/g Orig.

Sta Sample Description Date Date Beta Garmial/

Dry Sample)

Sample)S/

Sample) 1 78215 Domestic Water $/

5/25/78 10/16/78 6.5911.06 0.96+0.151/

1 78192 Soil 4/23/78 6/27/78 8.65+0.73 134-Cs 0.013+0.009 7.67 6.37 7.65+0.65

~

137-Cs 0.04570.007 5 78193 Soil 4/25/78 6/27/78 6.4410.62 134-Cs 0.04310.011 4.05 3.36 5.4610.53 137-Cs 0.41810.016 16 78206 Mil' 5/22/78 6/24/78 9.2210.68 137-Cs 0.05510.02 9.33 7.74 1309196.65/

5/30/78

<0.26 g

48 78205 Mil 5/22/78 6/24/78 6.57+0.51 137-Cs 0.045+0.017 7.95 6.60 953+74.0 /

5

{

5/26/78

<0.20 1/ ctivity at time of sampling. Naturally occurring radioisotopes are not reported.

A

[

$/ or K40 activity of 830 pCi/gm natural potassium.

F l

3_/ ample is evaporated for beta analysis and distilled for H-3 analysis. H-3 activity less than 0.20 pCi/ml.

S S/ o' dine-131 activity, pCi/1., at time of sampling.

i I

E/pCi/1.

5/ ampled jointly with the State Department of Health.

S t

l

(

f

(

TABLE 4 Report 420-78.120

^

DOSIMETER MEASUREMENTS Period Start:

4/ 4/78 4/18/78 5/ 3/78 5/16/78 5/30/78 6/13/78 5/28/77 Period End:

4/18/78 5/ 3/78 5/16/78 5/30/78 6/13/78 6/26/78 6/26/78 Elapsed Time, Days:

14 15 13 14 14 13 363 2/

Station Total mR Total mR Total mR Total mR Total mR Total mR Total mR 1

1 3.5 3.5 2.9 2.4 3.2 2.7 76.4 4_8/

8 2

3.0 3.0 2.8 3.0 3.0 3.4 81.2 3

2.7 3.4 2.4 3.1 3.0 3.0 78.5 4

2.9 3.2 2.4 3.2 3.1 3.2 74.5 50/

5 3.4 1.8 2.4 2.8 2.5 5.2 80.6 50/

6 3.0 3.4 2.5 3.0 3.3 2.7 83.9 7

3.2 3.1 2.7 3.3 3.0 3.0 79.1 8

3.4 3.1 2.5 3.0 3.0 3.4 74.8 50/

9 3.0 3.3 2.8 2.7 3.3 2.5 78.4 10 3.0 3.2 1/

2.8 2.9 2.5 72.4 50/

11 3.0 3.5 2.7 3.1 2.6 3.0 78.9 12 3.4 2.7 2.7 2.9 2.9 2.5 75.7 13 2.5 3.2 2.5 3.1 3.0 2.7 82.4 14 3.0 3.6 2.4 3.2 3.2 2.6 80.8 15 2.6 3.3 1/

3.0 3.0 3.2 79.4

-50/

16 3.5 3.4 30 3.6 3.5 3.3 88.9 17 3.1 3.4 2.7 3.0 2.9 2.6 81.1 18 3.1 3.0 2.6 3.1 3.4 3.2 79.0 19 2.6 3.2 2.7 3.0 3.5 2.7 81.1 20 3.0 2.8 2.5 2.7 3.1 2.9 79.6 21 3.1 2.8 2.4 1/

2.6 3.0 70.8 22 3.1 3.1 2.8 374 2.8 2.6 80.5

--48/

23 3.5 3.5 2.6 3.0 3.3 3.2 83.7

--50/

24 5.6 3.5 2.1 2.8 3.0 3.0 81.0 25 3.2 3.2 2.3 2.9 3.0 2.7 79.2 26 3.0 3.1 2.9 2.6 3.0 3.2 87.3 27 3.6 3.3 2.6 3.0 3.5 3.4 85.9 28 3.2 3.2 2.7 2.9 2.7 2.9 75.7 29 3.2 3.5 3.0 3.2 3.1 3.0 81.9 30 3.0 3.3 2.7 2.5 2.6 3.1 78.8

.l/Both dosimeters read 0 and/or full scale.

2_/ weeks of data, if less than 52.

(

f t

t

(

Report 420-78.120 TABLE 5 FILM PACK MEASUREMENTS Period Start:

4/ 4/78 5/ 3/78 5/30/78 Period End:

5/ 3/78 5/30/78 6/26/78 Elapsed Time, Days:

29 27 27 Station Total mR /

Total mR /

1 1

0 0

0 2

0 0

0 3

0 0

0 4

0 0

0 5

0 0

0 6

0 0

0 7

0 0

0 8

0 0

0 9

0 0

0 10 0

0 0

11 0

0 0

N 12 0

0 0

13 0

0 0

14 0

0 0

15 0

0 0

16 0

0 0

17 0

0 0

18 0

0 0

19 0

0 0

20 0

0 0

21 0

0 0

22 0

0 0

23 0

0 0

24 0

0 0

t 25 0

0 0

26 0

0 0

27 0

0 0

28 0

0 0

1 29 0

0 0

30 0

0 0

1 1/Above background of 8 mR/mo.

(

Report 420-78.120 TABLE 6 AIR PART!CULATE STATION NO. 3 GR055 uETA ACTIVITY Sample Volume Collection Counting Number (m**3)

Date Date pCi/m**3 78148 292 4/11/78 4/18/78 0.32510.012 78158 276 4/18/78 4/24/78 0.161+0.010 78166 297 4/25/78 5/ 3/78 0.08820.008 78175 314 5/ 3/78 5/ 9/78 0.07810.003 78195 254 5/ 9/78 5/27/78 0.09810.006 78202 284 5/16/78 5/30/78 0.119+0.006 78213 275 5/23/78 5/30/78 0.093}0.006 Z:

78218 296 5/30/78 6/ 2/78 0.053+0.002 78233 279 6/ 6/78 4/14/78 0.104+0.003 78250 282 6/13/78 6,?0/78 0.062TD.003 78263 285 6/20/78 6/26/78 0.059T6.004 i

78270 289 6/27/78 7f 6/78 0.0671b.003 i

I g

,MD

)

b 5

(

Report 420-78.120 TABLE 7 AIR PARTICULATE STATION NO. 45 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3)

Date Date pCi/m**3 78149 431 4/11/78 4/18/78 0.340+0.011 78159 420 4/18/78 4/28/78 0.16370.005 78167 441 4/25/78 5/ 4/78 0.09270.006 78176 480 5/ 3/78 5/10/78 0.07510.003 78196 377 5/ 9/78 5/27/78 0.099+0.006 78203 417 5/16/78 5/30/78 0.12110.005 78214 423 5/23/78 5/31/78 0.147+0.005 78219 435 5/30/78 6/ 2/78 0.053+0.003 78234 429 6/ 6/78 6/13/78 0.11310.004 78251 423 6/13/78 6/21/78 0.063+0.005 78264 438 6/20/78 6/26/78 0.068TO.003 78271 420 6/27/78 7/ 7/78 0.07210.003 t

i i

k

15 Renort 420-78.120

+

N y

T6N O

O

=e

~5f 5

ARCATA

[ I).A)

STATI0il flUMBER w

/

Ji.,

o Q..

. l,

..g o' 1

2.gcf.s:

to q

s b'

Tsu Q

n

-- 4,

/ EUREKA 65 4TJTF7fu j

[

5 16 3

56 HUMBOLDT BAY s

I.U, #

55

, POWER ANT 1

I co'"-

dele-f_DS g

1 LANDING T4N h

b South

- * '4 f*re

ay R/ve, h

3

~ ~., -

/

)

y, l

Salm o n 43 t'

T 3N gs\\

j River

RTUNA s,,f gjr,,

R2W RiW '

RIE w

4 FERNDALE l

T2N j

ErlVIR0!1.'1 ENTAL SAMPLES w

ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC COMPANY C

1 2

3 4

5 4 MILES w

.: Figure 1

.,.. _,..,,. g.._ 01 a.521.9 Ni m. Z.9 d'!. ?'A,_~a. S t

16 Report 420-78.120 a

f

.a-e."

STATIO:1 flu:1BER 4""-

M T

v l

41 row 5-l 24

~

1

(

o 22

~

i

u...,

s 4

O

-.y....> j..

r,...

..:h

1.::po'i 20 jf'*za..,. io' 19 s

b TSN fe

~

37 4

1 13 f.

T a

i l 3

14 HUMBOLDT BAY s

18 21 -

N POWER LANT i

12

// o ;g#Fi L M

lT 4 N 10 DINCr a

si,,,

30

/

7

~ ~ - -

\\

/

~

g/

>~\\

=

T3N pg f /

ts

{

~

?

River

67

- v i

ORTUNA 2

S' M V

RlW 24 RIE R2W FERNDALE l

T2N q

DOSI!!ETERS & FIL'l PACKS ENVIRONMENTAL RADIATION STUDY IN THE VICINIT 1' O." HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC ' COMPANY c

I 2

3 4

S 6 MILT $

Figure 2

.... -...n e K -

~ ;h ::,,a. _,. _.

17 Reoort 420 78.120

.5 1

+

4

.w 0

?

L__.__, ;y_f--. "..C..R. ;..l. Chronologico! Olsplay of. Selected Environmental _.

j F_.

.).....

j Measurements.

--~-'--

+

4'

~ ~

~, ~

W.

6 n

i r

E' L-

- - -... - _.. -q-3.e.

t, i

N t

6,

4 I

.b S.s t

_O

\\.

.-t.

i I

.o 5

1 o

y 4

i e

a 2__..__.

3 n g e

+

o q

f, y

.g s.,

j.

4

}

G a

o c

4

.l. _.

n _.

s: >..

t

.{

. ],,,_

..j l

l 1

l g.,

i

. _.. l.,

8 6

i......

-4

.g g o.

l i

..l

.._ __..i

)

.4

.t..-..__.

..g._

.._._.J... _. _....

..!. _.,-..._.)._....,......

.f.....

, _... -.~ - - - - - - - - - - '

... m

...---g_-_----'*--',._.*o._...__.

+------t.

2 0

._.____.......--l.

._ n,

4 n,.

.t s.

..,_.............___'_'...F.. _.^ - - - - - - - ". *.

~ -"

-~

- ~ - ~ ~ ---- --_._~..m...._.,.._.._

s

., s

- - - - ' ~

IS '..

..'._'~.._"_....

l

..5......... _ _... _, _. _ -

....-._...i........

i

.__..__._.__f

.l 1...

..4..

%d l 0__ _.

L,,.

.l i

m

. +.

j E

..l....

..,f.-..._..__g,_.._..._..._ _... _.

.{...

.-q.__

[

,., j.-..___ -...._~..~... --4 T-

......._.1...

e,,

E

...........___,....-_.__._4 g g

,y

_ _ + _ _

...._...I__......"_._.._-_1,---

.i,.....-.......__.-..'_-

... _ ~ ~ - -

~~

i c

a R

~._

l i;;

O -

.."f..._

.......[..._.... _......._.._._.g_.___....___;

7

. -........ ~..,...

j J.

1._._...........

g

..___l...-

.,..._{...._...

.....v_....

._._.4.._._.._....._......._._-_...

-...... _... _ _.... ~...._...

..l..,

- ~ -- ---

- - - - - - ~ ~ -,... -..

.r.-......

e

,._.__.'_...._........'...'-'-._._-".L_.-- ~~ - ~'...'.__~.. '

..1'. _~...'. ~'---.._

.... _. +.

,w 20 8

i

._L._..__.

.._,_..L....._...._.,

i

.._._....}.....,...,._..9............._.._....._

o j

g

._..n..__..

4

. -. _ _ _........._...I....._...r_._._,__.

s 9

4._.

-... _. __..,.... __.T._.._ _

e l5.

~ ~ ~ ~ ~

~

~ ~---'.-.**.._...*. _....' ~. ~ ". _ _... - - ~ - '

.o i _.. _ _... ' -

l

.... -,...... {... _.

. _.. _.t

.t.._.__.,

g Q

3 l

..... _... _ -~_.

.1---__..-._._..q c

a o.

_-..~._........_....._- _

.t..

..i -. _ _.,

_. 4 t

u

......___. I..

..m ai a..

s a

10 _.._

....~. s.

u i,

o g

i

{...._..

r..

l t

...l.._.

. _._ l..

g

.b E 5

~ '.

- ~ '.

_ _ ~ -. _ _.... _.

r-a 1

.J -

g

..l n.

.i

..,....-------I i

i

- 0 I".._.

I.

I I

b 2 42 9,4 m oz o,6 2 4 2 3,4 m o z o,6 2 4 2 7,4m o z o,6 2 4 2 9,4 m o z o,6 24 2,,4 m o z o g

J 4

1975 1976

?

1977 i

1978 I.

1979 i

hk2 T.' 3

- 4 o "-

.m...

Report Issued:

February 27, 1979 Report 420-78.156 PACIFIC GAS AND ELECTRIC COMPANY DEPARTMENT OF ENGINEERING RESEARCH REPORT NO. 70 ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT EUREKA, CALIFORNIA QUARTER ENDING SEPTEMBER 30, 1978 (SUINER) 2rw R. F. CA

, Chief Report Prepared By.

C. H. Andrew R. W. Lorenz

e Report 420-78.156 TABLE OF CONTENTS Page LIST OF TABLES..........................

11 LIST OF FIGURES..........................

ii

SUMMARY

1 INTR 0 DUCTION...........................

1 SAMPLE COLLECTIONS AND ANALYSES..................

1 DISCUSSION OF ANALYTICAL RESULTS.................

2 RELEASES OF GASE0US RADI0 ACTIVE WASTE...............

3 REFERENCES............................

4 APPENDIX.............................

5 i

Report 420-78.156 LIST OF TABLES Table Page 8

1.

Samples Collected......................

2.

Radicanalysis of Marine Samples...............

9 10 3.

Radioanalysis of Terrestrial Samples.............

4.

Dosimeter Measurements....................

11 5.

Film Pack Measurements....................

12 6.

Air Particulate, Station No. 3, Gross Beta Activity.....

13 7.

Air Particulate, Station No. 45, Gross Beta Activity.....

14 LIST OF FIGURES Figure Page 1.

Station Locations of Environmental Samples..........

15 2.

Station Locations of Dosimeters and Film Packs........

16 3.

Chronological Display of Selected Environmental Measurements.

17 ii

Report 420-78.156

SUMMARY

Measurements of radioactivity in marine and terrestrial samples and in air particulates from the environment near the Humboldt Bay Power Plant during this quarter generally remained within the range of preoperational background measurements. The maxiii.um integrated dose measured was well below the permissible contribution of 500 mrem / year in unrestricted areas.

INTRODUCTION Th1;s is the 70th quarterly report on radiation in the environment near Humboldt Bay Power I'lant (HBPP) covering the period July through September 1978. This report contains information on the samples collected, methods and results of radiochemical analyses, a discussion of the results, and also information about the " Releases of Gaseous Radioactive Waste" supplied by the Department of Steam Generation.

Information on the release of liquid radioactive waste from HBPP is reported elsewhere.I*

SAMPLE COLLECTIONS AND ANALYSES Air particulate filters, dosimeters, film packs, and 17 marine and terrestrial samples were collected for this report in accordance with the 2

requirements of the North Coast Regional Water Quality Control Board,3 and the Department of Health.4 A table of the samples collected and maps showing the sampling locations (Figures 1 and 2) are presented in the Appendix.

See reference page.

2 Report 420-78.156 Forty-five gross beta analyses, two iodine-131 analyses, and 19 gamma scans were performed for this report. The results are tabulated in the Appendix. All samples except the dosimeters and film packs were analyzed at the Department of Engineering Research (DER). Dosimeters were read by HBPP personnel. Film packs were read and confirmatory analyses of five samples were performed by outside contractors.

DISCUSSION U ANALYTICAL RESULTS Most environmental samples analyzed for this report contained low levels of radioisotopes identified by gama spectrometry. The radioisotopes identified were fission products from Chinese bomb tests and past plant releases, and long-lived corrosion products from the plant which are quantified at lower detection limits because of improved gamma spectrometry techniques which were initiated in 1977. Gama spectrometry was used to quantify the racioisotopes present on monthly composited air particulate filters even though the beta activity continues to decrease from spring high. As shown below, the confirmatory analyses by an outside contractor are in good agreement with the DER results.

Gross Beta Activity (pCi/q dry)

Sample No.

LFE Environmental DER 78339 5.6+0.6 6.4 +0.6 78340 10.3T1.0 9.5 T0.8 78349 8.371.0 8.5 T0.7 78350 9.471.0 9.6 70.7 78351 10.021.0 9.810.8

3 Report 420-78.156 During the preceding 52-week period, the traximum integrated radiation exposure was measured at Station 16. The total annual exposure at Station 16 was approximately 9.1 mR above background

measured at Stations 2 and 5.

Figure 3 is a chronological display of dosimeter and film pack radiation exposures per month at Station 14 and the air particulate activity at Station 3 from January 1975 through this quarter. Reports 37 and 55 contain graphs from previous years.

RELEASES OF GASEOUS RADIOACTIVE WASTE The routine releases of gasenus radioactive wastes have been monitored by the air ejector off-gas and stack-gas monitoring systems.

The calibration of these monitors for noble and activated gases has been checked by periodic analyses of " grab" samples on a multichannel gamma scintillation spectrometer. The refueling, maintenance, ano station modification outage which started in July 1976, continued through this quarter; therefore, airborne releases were insignificant.

Extrapolated to one year from actual measurements.

4 Report 420-78.156 REFERENCES 1.

Quarterly report to Regional Water Quality Control Board on Liquid Waste Discharge from Humboldt Bay Power Plant.

2.

Letter from North Coastal Regional Water Quality Control Board to PGandE, Attn:

F. F. Mautz, concerning modifications to waste discharge and environmental radiation monitoring requirements, dated May 7, 1965.

3.

Letter from North Coastal Regional Water Quality Control Board to PGandE, Attn:

Mr. P. Mattnew, concerning modifications to waste discharge requirements, dated April 8, 1966.

4 Department of Public Health letter to PGandE, Attn:

Mr. P. Matthew, concerning modifications to environmental radiation monitoring requirements, dated June 17, 1966.

5.

Environmental Radiation in the Vicinity of Humboldt Bay Power Plant, Reports 1-8.

6.

Code of Federal Regulations, Title 10, Para. 20.105.

5 Report 420-78.156 APPENDIX Page Methods of Sample Collection and Analysis 6

Table 1 Samples Collected 8

Table 2 Radioanalysis of Marine Samples 9

Table 3 Radioanalysis of Terrestrial Samples 10 Table 4 Dosimeter Measurements 11 Table 5 Film Pack Measurements 12 Table 6 Air Particulate, Station No. 3, Gross Beta Activity 13 Table 7 Air Particulate, Station No. 45, Gross Beta Activity 14 Figure 1 Station Locations of Envircnu ntal Samples 15 Figure 2 Station Locations of Dosir.

s and Film Packs 16 Figure 3 Chronological Display of Oclected Environmental Measurements 17

6 Report 420-78.156 METHODS OF SAMPLE COLLECTION AND ANALYSIS Marine samples are collected by Humboldt State College Foundation personnel under the direction of Dr. J. A. Gast. PGandE Humboldt Division personnel collect the remainder of the samples.

Marine and terrestrial samples are processed quarterly at DER.

Samples are freeze-dried prior to determining gross beta activity. The gross beta analysis is performed on low background, thin window, gas flow proportional counters; the limit of detectability is about 0.5 pCi/gm of a standard containing K-40.

Activities are reported both per gram of the dry and per gram of the original sample.

The freeze-dried samples and domestic water are gama scanned, using a Ge(Li) detector and multichannel pulse height analyzer. The limit of detectability attained in the gama scan is typically 5 pCi/l of water solution containing a single radionuclide.

Radiciodine analyses are performed on milk samples within eight days of collection. Following addition of stable iodine to the raw milk to determine chemical recovery, iodine is separated from the milk by using anion ion exchange resin.

Iodine is stripped from the resin and after purification is precipitated as cuprous iodide for measurement by beta-gama coincidence counting. The detection limit attained by this method is typically 0.2 pCi/ liter for I-131.

The potassium content of most of the freeze-dried samples is measured by flame photometry in order tn estimate the V.-40 contribution to the gross activities. The range of ccncentrations used is one to ten ppm; the

7 Report 420-78.156 standard deviation in the concentration units (Gaussian) is about 12 percent at the 5 ppm level. Using the factor of 830 pCi/g K, the activity of K-40 in a sample is calculated.

The tritium (H-3) activity in domestic water is determined by analyzing a distilled aliquot of the sample with a liquid scintillation spectrometer. The limit of detection for this analysis is typically 0.2 pCi/ml of water.

The airborne particulate samplers are located at Stations 3 and 45 (Figure 1). The constant flow samplers have flow rate in the range of 30 to 40 1pm; an HV-70 filter is used. The filters are collected on a weekly basis and mailed to DER. The filters are counted to determine gross beta activity at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after collection to al's for naturally occurring short-lived radionuclides to decay.

Ganina dosimetry is performed with two ion chambers (Victoreen, Model 239) and a film pack located at each of the 30 stations shown in Figure 2.

The ion chambers are read in the field by HBPP personnel on a biweekly basis. The lower of the two readings is normally reported since the dosimeters normally read high on failure. The Radiation Detection Company (RDC), Sunnyvale, California, supplies and reads the film packs. RDC reports film pack doses relative to " background" at the RDC laboratory, which consistently is 8 mR/ month.

The +

erm in the following tables is the two-sigma error; i.e., the 95 percent confidence level.

TABLE 1 Report 420-78.156 SAMPLES COLLECTED Marine Verte-Clams & Other Bottom Terres-Air Dosi-Film Station Flora brates Oysters Invert. Sedim.

trial Partic. meters Packs 1 K. Salmon Picnic Area 2

7 3

2 1742 Wood, Fortuna 7

3 3 Humt 21dt Hill (HH) Rd 14 7

3 4 Wood & K, Eureka 7

3 5 Redwood Ave, Arcata 1

7 3

J Table Bluff & Clough 7

3 7 Col. of the Redwds 7

3 8 Hmbit H1 Rd Nr Donna 7

3 9 HH Rd Nr Harbor View 7

3 10 B St., Field Lndg 7

3 11 Whittier Ct & Irving 7

3 12 Bell Hill Rd, HH 7

3 13 Crab St, Buhne Pt 7

3 14 South Bay School 7

3 15 Eich Dr, HH 7

3 16 Bennett Dairy 1

7 3

co 17 Bassford Rd, Ridgewd 7

3 18 6418 Elk River Rd 7

3 19 Noe St, Pine Hill 7

3 20 Jacobs Jr. H.S.

7 3

21 PGLE Well 2, Hi Rd 7

3 22 Sta B - 14th St 7

3 23 Harris St. Substa.

7 3

24 PG&E Office, Eureka 7

3 25 Irving Dr, HH 7

3 26 Worthington Ln, HH 7

3 27 Berta Road 7

3 28 Berta Road 7

3 29 Vista Road, HH 7

3 30 Burns Dr, HH 7

3 45 Humboldt Substation 14 48 Holgerson Dairy 1

55 PG&E Outfall 2

1 1

56 1000 ft. N Outfall 2

1 57 1000 ft. S Outfall 2

1 59 Hookton Channel 1

65 Coast Oyster Co.

1

TABLE 2 Report 420-78.156 RADI0 ANALYSIS OF MARINE SAMPLES Potassium K40 Activity Gross Beta Collec-Beta Gross Activity in Potassium tion Counting (pCi/g Dry Sample)

Content Activity (mg K/g (pCi/gDr{f (pCi/g Orig.

Sta Sample Description Date Date Beta Gama 5, Dry Sample)

Sample)-

Sample) 3 55 78339 Sediment /

8/ 2/78 9/27/78 6.36+0.56 137-Cs 3.021+0.004 4.72 3.92 5.54+0.49 55 78343 Red Algae 8/ 2/78 10/11/78 9.5110.76 9.05 7.51 2.55_+0.21 (Gigartina agardhii) 55 78341 Red Algae 3/

8/ 2/78 10/11/78 9.0610.59 137-Cs 0.02010.012 10.1 8.41 1.9710.03 (Iridaea sp.)

55 78342 Fish 8/11/78 10/13/78 13.011.15 12.2 10.1 3.1410.28 56 78343 Sediment 8/ 2/78 9/26/78 7.18+0.59 134-Cs 0.014+0.007 4.53 3.76 5.80+0.47 137-Cs 0.012 0.005 56 78344 Red Algae 8/ 2/78 10/13/78 11.010.89 11.3 9.34 2.35+0.19 (Gigartina agardhii) 56 78345 Red Algae 8/ 2/78 10/23/78 10.110.87 8.38 6.96 2.7310.23 (Iridaea sp.)

57 78346 Sediment 8/ 2/78 9/26/78 5.9210.51 137-Cs 0.01310.004 3.98 3.30 5.5610.48 57 78347 Red Algae 8/ 2/78 10/23/78 10.410.87 10.8 8.94 2.8310.24 (Giqartina agardhii) 57 78348 Red Algae 8/ 2/78 10/24/78 9.2610.85 9.45 7.84 1.7710.16 (I_ridaea sp.)

3 65 78349 Pacific Oyster /

8/ 2/78 9/26/78 8.5110.67 8.52 7.07 1.8910.15 (Crassostrea gigas) 3 59 78350 Gaper Clam /

8/ 1/78 9/27/78 9.64C.74 60-Co 0.009+0.004 9.27 7.69 2.441-0.19 (Tresus capex) 137-Cs 0.015 0.004 1

.1/ Activity at time of sampling. Naturally occurring radioisotopes are not reported.

2/For K40 activity of 830 pCi/gm natural potassium.

3/ Samples analyzed at DER then sent to State Department of Health.

9 TABLE 3

'leport 420-78.156 RADI0 ANALYSIS OF TERRESTRIAL SAMPLES K40 Activity Potassium Gross Beta Gr ss Activity in Potassium Activity Collec-Beta Content (DCi/g Dry Sample)

(pCi/gDr{f (pCi/g Orig.

tion Counting

(,g gjg Sta Sample Description Date Date Beta

Gamal, Dry Sample)

Sample)-

Sample) 1 78386 Domestic Water /

9/12/78 10/26/78 7.47+0.78 1.31+0.125/

1/

11/ 6/78 0.36+0.19 1 78351 Soil 8/ 2/78 9/27/78 9.80+0.75 134-Cs 0.017+0.009 5.54 4.59 9.6610.74 137-Cs0.02910.006 5 78352 Soil 8/ 2/78 9/27/78 8.04+0.65 137-Cs 0.376+0.007 3.86 3.20 7.5910.62 144-Ce 0.146+0.049 16 78324 Milk 6/

8/ 7/78 9/26/78 7.29+0.59 7.19 5.37 1124+91.4E/

Il 8/14/78

<0.20 48 78325 Milk 6/

8/ 7/78 9/26/78 6.39+0.54 137-Cs 0.011+0.01 7.41 6.15 986+83.01/"_

1/

8/15/78

<0.20 1/ Activity at time of sampling. Naturally occurring radioisotopes are not reported.

2/For K40 activity of 830 pCi/gm natural potassium.

3/ Sample is evaporated for beta analysis and distilled for H-3 analysis.

4/ Iodine '31 activity, pCi/1., at time of sampling.

E/pCi/1.

5/ ampled jointly with the State Department of Health.

S 1/ Tritium activity, pCi/ml., at time of sampling.

TABLE 4 Report 420-78.156 00SIMETER MEASUREMENTS Period Start:

6/26/78 7/11/ 78 7/25/78 8/ 8/78 8/22/78 9/ 5/78 9/19/J8 10/ 4/77 Period End:

7/11/78 7/25/78 8/ 8/78 8/22/78 9/ 5/78 9/19/78 10/ 3/78 10/ 3/78 Elapsed Time, Days:

15 14 14 14 14 14 14 364 Station Total mR Total mR Total mR Total mR Total mR Total mR Total mR Total mR

-2/

1 3.1 3.3 2.5 2.6 2.6 2.7 2.8 74.0 (48) 2 2.7 3.2 2.5 2.7 3.0 2.5 3.3 78.2 3

3.0 3.1 2.6 2.4 3.0 2.8

,0 75.8 4

3.0 2.6 2.7 2.6 2.9 2.6 3

73.1 (50) 5 3.1 3.0 2.5 2.5 3.2 2.1 76.9 (50) 6 3.0 2.6 2.3 3.2 3.1 2.4 3.2 82.0 7

2.8 2.6 2.3 3.0 2.6 2.4 2.7 75.6 8

3.0 3.4 3.0 2.6 2.9 2.3 2.9 73.3 (50) 9 3.4 3.3 2.4 2.4 2.6 2.5 2.8 76.2 10 2.6 2.9 2.5 2.6 3.0 2.1 2.9 70.5 (50) 11 3.5 3.7 2.2 3.0 2.4 2.3 2.7 77.4 12 3.0 2.8 2.3 2.8 3.2 2.2 4.0 75.3 13 2.7 2.5 2.1 2.5 2.5 2.2 2.8 78.8 14 3.2 2.8 2.8 5.2 2.8 2.4 2.7 81.8 15 3.2 2.7 2.6 2.9 2.8 2.8 3.0 78.1 (50) 16 3.1 3.1 3.1 3.1 3.6 2.8 4.8 88.2 17 3.4 3.2 2.8 2.2 2.8 3.2 2.5 79.9 18 2.7 3.0 2.5 2.8 2.9 2.8 1.3 77.8 19 3.5 2.6 2.6 3.1 2.8 2.5 3.2 80.0 20 2.8 2.8 2.0 2.8 8.1 2.0 2.9 82.0 21 5.5 2.9 2.1 2.8 3.0 2.6 3.0 71.0 (48) 22 3.1 3.0 2.6 2.8 2.8 3.6 2.8 78.6 23 3.4 2.8 2.8 3.4 3.4 2.9 3.2 82.4 (50) 24 (1) 3.0 2.7 2.4 2.6 2.2 2.7 75.2 (50) 25 3.0 2.9 2.4 2.4 2.8 2.4 2.4 76.1 26 3.0 3.6 2.3 2.6 3.1 2.5 2.9 85.3 27 4.0 3.0 2.8 2.7 3.5 3.0 3.2 84.0 28 3.2 2.8 2.4 2.4 2.5 2.6 2.9 73.9 29 2.6 3.3 3.6 2.8 3.0 2.5 2.8 79.8 30 2.6 (3) 2.4 2.5 2.2 2.4 3.0 72.7 (50)

.1/Both dosimeters read 0 and/or full scale.

2_/ Weeks of data, if less than 52.

3_/No reading.

Report 420-78.156 TABLE 5 FILM PACK MEASUREMENTS Period Start:

6/26/78 7/25/78 8/22/78 Period End:

7/25/78 8/22/78 10/ 3/78 Elapsed Time, Days:

29 28 42 Station Total m Total mR Total m 1

0 0

0 2

0 0

0 3

0 0

0 4

0 0

0 5

0 0

0 6

0 0

0 7

0 0

0 8

0 0

0 9

0 0

0 10 0

0 0

11 0

0 0

12 0

0 0

13 0

0 0

14 0

0 0

15 0

0 0

16 0

0 0

17 0

0 0

18 0

0 0

19 0

0 0

20 0

0 0

21 0

0 0

22 0

0 0

23 0

0 0

24 0

0 0

25 0

0 0

26 0

0 0

27 0

0 0

28 0

0 0

29 0

0 0

30 0

0 0

1/Above background of 8 mR/mo.

4 Report 420-78.156 TABLE 6 AIR PARTICULATE STATION NO. 3 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3)

Date Date pCi/m**3 78277 322 7/ 5/78 7/11/78 0.074+0.005 78281 200 7/11/78 7/20/78 0.066T0.005 78301 292 7/18/78 7/25/78 0.029T0.002 78312 290 7/25/78 8/28/78 0.03170.002 78318 287 8/ 1/78 9/ 5/78 0.02710.003 0

78331 280 8/ 8/78 9/11/78 0.023+0.002 78337 285 8/15/78 9/12/78 0.02210.002 78367 286 8/22/78 9/19/78 0.020+0.002 78373 286 8/29/78 9/20/78 0.02210.002 78380 296 9/ 5/78 9/25/78 0.029+0.003 78387 274 9/12/78 10/ 2/78 0.033T0.003 78400 294 9/19/78 10/ 4/78 0.03970.003 78412 275 9/26/78 10/ 5/78 0.02810.002 78432 288 10/ 3/78 10/ 9/78 0.031+0.003

4 Report 420-78.156 TABLE 7 AIR PARTICULATE STATION NO. 45 GROSS BETA ACTIVITY Sample Volume Collection Counting Number (m**3)

Date Date pCi/m**3 78278 495 7/ 5/78 7/12/78 0.07410.002 78282 359 7/11/78 7/20/78 0.07410.005 78302 435 7/18/78 7/25/78 0.03210.002 78313 429 7/25/78 8/28/78 0.041+0.003 78319 421 8/ 1/78 8/29/78 0.02610.002 78332 429 8/ 8/78 9/11/78 0.025+0.002 78338 418 8/15/78 9/13/78 0.022+0.001 78368 432 8/22/78 9/19/78 0.019T0.001 78374 423 8/29/78 9/20/78 0.02410.001 78381 437 9/ 5/78 9/28/78 0.044+0.004 78388 414 9/12/78 10/ 2/78 0.03110.003 78401 433 9/19/78 10/ 4/78 0.03810.002 78413 422 9/26/78 10/ 5/78 0.026+0.001 78433 435 10/ 3/78 10/ 9/78 0.030+0.002

15 Renort a20-78.156

)

{

m

6-l pj y

e T6N O

l O

e 5

ARCATA STATI0il ilU:iBER i,).

)

l E[::f-6'j G. 5' !

Q

Q Q

TSN 4 5 -

T UREKA~p l

~

65 IlfE df ffl t

3s

.)

3 56 a

HUMBOLDT BAY s

"I,

, POWER LANT l

55 t co',

..t ElEf.DS p

LANDING lT4N 1

c

\\

South

"*' th Fork M'+

nive,

/

ay 3

f h

)

v4 o,,

saim a n 43 h[

l Ri RTUNA R2W Rlw RIE FERNDALE T2N i

EllVIP.0T!EllTAL SAMPLES ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC COMPANY o

i 2

3 4

5 s WLES Figure 1

16 Report 420-78.156

)

\\

(

4:,\\

i STATIO:1 ilU:'BER g

4,,

h T

i v

~O 2

O 23 \\

ARCATA 22 N

o 4

dpq f*

N ~

~

~ '.c 1

4 15 13

-i

[1 o

P I ',

,2 14 HUMBOLDT BAY 4

i.

18

'g

{ '#g POWER LANT 21 -

12

~ '"FI L M

// o w

10 v

DING, lN N

M i 3

ff

\\

)

\\

9/

/ '.

T 8

/

7 f

n 96!!-

id D ('

h

$7 River

"^

2 sair nivre R2W RlW 2'

RIE FERNDALE l

DCSI:1ETERS & FIL?! PACKS ENVIRONMENTAL RADIATION STUDY IN THE VICINITY OF HUMBOLDT BAY POWER PLANT PACIFIC GAS AND ELECTRIC COMPANY 0

1 2

1 4

5 C hirtt$

Figure 2

e 1]

. Report 420.-78.156

.5 Chronological Display of Selected Environmental Measurements

.4 4._..._.._.._..__..

_. ~... - _..

v.C d+e n

G p

._o

".3 e.

G 5

e e.

.2 n

a.

s s

c c

o j

_[

. _. _.. _ _ _. ~. _ _... _ _

j -',1 g

,y.

m

~.

?

.I. f.. - -. _....

r._

r-

..3__

4,

+

a____

g.-

._.,..y._.

o s

c 20

.~.~.-. :-

O i

.._....g..

-M 0-

.g t

15

)

i

.._ _ ~.._. _.....

.4 10

-).-

M

, g

,- wL

.., - a

~

er E

5 a

e

- o c Q

__.4.

._L.

o I --

e- -

- ' ' - ~

' - ~ ~ " - - ~ ~ '.

-o

..l.

1-O q

.e

_f

.~..-.-....s____....

x

.m-

.p.

_..s.

e

....s..-

s

.E 20..._.__.__..._

8

. l_..._..

c

........6__..._.-.._-..---,3 W

g

~ - -

', + _. - ' ~ _ - _.. _ _ ' _ ' *. _ -.. -

E 15....

,,g 4

.g..

TV.

j

.l-._.e i

O c

9 3

g Ub

9..

_.g

.g e

,8 lo.. _..._

h.

o l.

C'

- ~ ~ -

E 5 b.

Y.

q g

....I_.___...-.

'.r.r..,

--4 e

-- --~

+

2O I"

,k2423,4mozo,6242,,4mozo,6242,,4mozo,6242,,4mozo,6242,74mozo 1975 1976 1977 1978 l

1979

. _ ~.

Figure 3

ML19261B750

Contents

Text

SUMMARY

SUMMARY

.=

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML19261B750

Text

SUMMARY

SUMMARY

.=

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search