ML20137Z476
| ML20137Z476 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/31/1996 |
| From: | Nutech T, Quennoz S PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PGE-1006-96, VPN-027-97, VPN-27-97, NUDOCS 9704240194 | |
| Download: ML20137Z476 (39) | |
Text
__- . - - _ _ _ - _ _ _ _ _ _ - - _ _ _ __ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ ____-____
~
'~
um ammes
~
m Portland General Electric Corrpinyy Stephen M. Quennoz Trojan Site Executive April 17,1997 VPN-027-97 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Dear Sirs:
PGE-1006-96. Trojan Nuclear Plant Annual Radiological Environmental Monitoring Report for 1996 This letter transmits Portland General Electric Company's Trojan Nuclear Plant Annual Radiological Environmental Monitoring Report for the calendar year 1996. This report is submitted in accordance with Trojan Permanently Defueled Technical Specification (PDTS) 5.8.1.2 and Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to Title 10 CFR 50.
Sincerely, Stephen M. Quennoz Trojan Site Executive
- n 0(%.,
)
Enclosure I g
/
e: R. A. Scarano, NRC Region IV M. T. Masnik, NRC, NRR D. Stewart-Smith, ODOE 9704240194 961231 "h'
. . lff'
. hf. c
,6 '
! ant, age!
gg i\ PortlandGeneralElectricCompany HRP-032-97 To:
Distribution From:
H. R. Pate Date:
April 17,1997
Subject:
Transmittal of PGE-1006-96, Trojan Nuclear Plant Annual Radiological Environm ental MonitorinLReport for 1996
@nclosed is your copy of PGE-1006-96, Trojan Nucle
%onitoring Report for 1996.
l ar Plant Annual Radiological Environmental flease acknowledge receipt of your copy by co sturning it to the location given below.
1RP/CKC g:losure ACKNOWI FDGMEEI PGE-1006-96 Trojan Nuclear Plant Annual Radiological Environm ental Monitoring Report for 1996 geby acknowledge receipt of Controlled C tges have been made in accordance with the iopy Number (s)_
_ of the subject document. All nstructions, and superseded pages have been destro Signature of Copy Holder Date sto: ,
Pat Schaffran, TCB-3/ Licensing Trojan Nuclear Plant 71760 Columbia River Highway Rainier, Oregon 97048 121 S W Satrnon Street Portand Oregon 97204
D m m HRP-032-97 g - PortlandGeneralElectricCenpisy
- I g To: Distribution From: H. R. Pate Date: April 17,1997
Subject:
Transmittal of PGE-1006-%,
Trojan Nuclear Plant Annual Radiological Environmental Monitoring Reoort for 1996 Enclosed is your copy of PGE-1006-%, Trojan Nuclear Plant Annual Radiological Environmental Monitoring Report for 1996.
Please acknowledge receipt of your copy by completing the lower portion of this transmittal and returning it to the location given below.
HRP/CKC Enclosure 4/17/97 ACKNOWLEDGMENT PGE-1006-%
Trojan Nuclear Plant Annual Radiological Environmental Monitoring Report for 1996 I hereby acknowledge receipt of Controlled Copy Number (s) of the subject document. All changes have been made in accordance with the instructions, and superseded pages have been destroyed.
Signature of Copy Holder Date ,
Returri to: Pat Schaffran, TCB-3/ Licensing Trojan Nuclear Plant 71760 Columbia River Highway '
Rainier, Oregon 97048 121 SW Satrron Street Portand. Oregon 971TA
Trojan Nuclear Plant Radiological Environmental Monitoring Report for Calendar Year 1996 PORTLAND GENERAL ELECTRIC COMPANY I
l PGE-1006-96 i
PGE-1006-%
TROJAN NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT January through December 1996 April 1997 l
l Prepared by PORTLAND GENERAL ELECTRIC COMPANY With Analyses By Thermo NUtech ALBUQUERQUE, NEW MEXICO
TROJAN NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL 9 MONITORING REPORT TABLE OF CONTENTS Section Title Page TABLE OF CONTENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -i-LIST OF TABLES ................................... -iii-LIST O F FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -iv-AB STRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -v-1.0 INTROD UCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 2.0 SAMPLING AND PROGRAM PROCEDURES . . . . . . . . . . . . . . . . 2-1 2.1 SAMPLING LOCATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2 SAMPLING PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2.1 Air Particulate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2.2 Ambient Radiation Measurements Using TLDs . . . . . . . . . . . . 2-1 2.2.3 Well Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2 2.2.4 Drinking Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2 2.2.5 Shoreline Soil . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2 3.0 ANALYTICAL PROCEDURES AND COUNTING METHODS . . . . . 3-1 3.1 ANALYTICAL DETECTION LIMITS AND UNC ERTAINTY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 AIR PARTICULATES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.3 DRINKING AND WELL WATER . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.4 SHORELINE SOIL . . . . . . . . . . . . . . .................... 3-2 3.5 AMBIENT RADIATION MEASUREMENTS ................. 3-2 3.6 Q UA LITY CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-2
3.7 REFERENCES
FOR ANALYTICAL PROCEDURES . . . . . . . . . . . . 3-2
-i-i
________-___._________________.__m- _ _ _ . . - - . - - _ . _ - . - . . - - _ _ . . _ - - _ . -
TROJAN NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORINO REPORT TABLE OF CONTENTS Section Title Page 4.0 RESULTS AND DISCUSSION . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT . . . . . . . . 4-1 4.1.1 Air Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1.2 Well Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1.3 Arnbient Radiation Levels . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2 SAMPLES FROM THE AQUATIC ENVIRONMENT . . . . . . . . . . . . 4-2 4.2.1 Drinking Water Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2
- 4. 2.2 Shoreline Soil . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2 4.3
SUMMARY
OF RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-3 5.0 COMMENTS ON AND TERMS USED IN DATA TABLES . . . . . . . . 5-1 l
l l
I i
-ii-
TROJAN NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT LIST OF TABIES Number Title 2-1 Sampling Locations and Frequency by Type 3-1 Program Analyses and Reported Detection Levels 3-2 1996 EPA and DOE Interlaboratory Comparison Program Results 3-3 1996 Quality Control Analyses Summary /
4-1 Average Gross Beta Concentrations for Air Particulates "
4-2 Average Ambient Gamma Radiation Levels 4-3 Average Gross Beta Concentrations for Drinking Water from Columbia River 4-4 Radiological Environmental Monitoring Program Summary 5-1 Gross Beta in Air Particulate Filters 5-2 Summary - Gross Beta in Air Samples 5-3 Ganuna Emitters: Concentrations in Air Particulate Filters 5-4 Radioactivity in Well Water 5-5 Ambient Gamma Radiation Levels 5-6 Radioactivity in Drinking Water l 5-7 Radioactivity in Shoreline Soil l
k
-lii-
TROJAN NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT I IST OF FIGURFR umkr Title 2-1 Sampling Locations l
l l
j
-iV-l l
l ABSTRACT This report presents the data obtained through the analyses of environmental samples collected through the Portland General Electric Trojan Nuclear Plant Radiological Environmental Monitoring Program for the period January 1,1996, through December 31,1996.
Most of the radionuclide analyses on the environmental samples resulted in non-detectable values for radionuclides that could be released from the Trojan Nuclear Plant. In no case did radioactivity that could be attributed to the Trojan Nuclear Plant exceed the Reporting levels of the Offsite Dose Calculation Manual for Trojan.
l l
l
-y.
l
1.0 INTRODUCTION
The Trojan Nuclear Plant, a 1130 megawatt-electric pressurized water reactor, first achieved criticality on December 15, 1975. On January 27,1993, Portland General Electric decided to permanently shut down the Trojan Nuclear Plant. This report presents the analytical data from the Radiological Environmental Monitoring Program with appropriate interpretation for 19%.
l The analytical contractor during this period has been Thermo NUtech, Albuquerque, New Mexico. In comparing data obtained during this period with those from previous periods, care should be taken to ensure that differences in procedures among the contractors are considered.
Information concerning the Radiological Environmental Monitoring Program prior to this period may be found in earlier reports.
l l
1 1
1-1
f 2.0 SAMPLING AND PROGRAM PROCEDURES 2.1 SAMPLING LOCATIONS Fifteen (15) sampling locations were used in the Radiological Environmental Monitoring Program from January 1,1996, through December 31,1996. These sampling locations are shown in Figure 2-1. Table 2-1 includes a listing of the sites, their distance from Trojan, and the type and frequency of sample collection.
During 1994 a review of the environmental sample results from 1977 through 1993 was conducted. In general, the review confirmed that radioactivity attributable to Trojan Nuclear Plant during power operations was not detected in the environmental samples. Therefore, since the production of radioactivity had ceased when the reactor was permanently shut down, and from that point forward, the radioactivity in both liquid and gaseous effluents continued to decrease, it was evident that the environmental sampling requirements could be reduced.
Therefore, revisions to the Radiological Environmental Monitoring Program were submitted to the Oregon Department of Energy (ODOE) on September 22,1994, for approval. The revisions to the program were approved on December 12,1994.
2.2 SAMPIING PROCEDURES 2.2.1 AIR PARTICULATE Air particulate sampling was performed weekly. The samples were gathered with a low-volume air sampling device which is designed to draw a constant flow rate regardless of the pressure drop across dic filter. The sampling devices were set to maintain one cfm. The sample pump, metering devices, and timer were in a weatherproof housing. The filter was located in a sample housing that is connected to an air inlet about one meter above the ground.
Glass fiber filters were used to collect particulate matter.
The glass fiber filter was removed from the air sampler and placed in a two-inch plastic petri dish. Air flow readings and other data required to compute the levels of radioactivity were recorded and submitted to the analysis laboratory along with the samples.
2.2.2 AMBIENT RADIATION MEASUREMENTS USING TLDs Thermoluminescent dosimeters (TLDs) were placed for field exposure and collected on a quarterly frequency. The TLDs were placed about 1 meter above ground level in plastic containers. The time of collection, the exposure period, and any abnormal conditions such as moisture in the holders, damage done by animals, etc., were recorded when the TLDs were retrieved. Care was taken to minimize exposure to the TLDs between collection and delivery to the laboratory. Trip TLDs were carried with the field TLDs during transport to and from the field.
2-1
l' i-l 2.2.3 WFI.I. WATER l
Well water was collected quarterly from the tap that leads off the pur2p. The line was purged ,
I for about five minutes prior to collection. Sixty milliliters were drawn from the one-gallon j
. sample for tritium analysis. The remainder of the sample was put in a one-gallon polyethylene i bottle and acidified with concentrated hcl. The bottles were securely sealed and labeled, and ;
collection data forms were prepared specifying site, date collected, volume, and sample type.
f 2.2.4 DRINKING WATER Four-week composite samples of municipal drinking water were collected for Rainier (Sample
- Location 8) and St. Helens (Sample location 9) at their respective intake structures on the !
- Columbia River. Rainier is downstream of the Trojan Nuclear Plant while St. Helens is ;
, upstream. At each location, a compositing sampler took a sample every two hours and aliquots !
of this four-week composite were sent for analysis. From these aliquots,60 milliliters are sent 1 for tritium analysis and two one-gallon polyethylene bottles are acidified with concentrated l hcl and sent for the other analyses. The bottles were securely sealed and labeled, and i collection data forms were prepared specifying site, date collected, volume, and sample type.
2.2.5 SHORFIINE SOIL Shoreline soil samples of about one quart in volume were taken twice a year. The samples were taken from a one square foot area at a depth of between one and four inches. Vegetation and large rocks were removed from the sample before it was placed in a plastic container. The containers were securely sealed and labeled. The sample site identification number, date collected, and volume obtained were recorded on the collection data forms.
2-2 h .. , r+-i , ,
Tant F 2-1 Sheet 1 of 2 SAMPLING LOCATIONS AND FREQUENCY BY TYPE-Radial Sample -
Sample Imation Distance Air Well Surface Shore (meters) Direction TLD Particulate . Water . Water Soil 1 - Trojan North Building 300 WNW Q 2 - NW Fenceline- 210 NW Q 3 - N Fenceline 191 N Q 4 - Switchyard 191 WSW Q 5 - Training Building 354 SW Q 6 - Park Entrance -354 SSW Q 7 - South End Cooling Tower 327 SE Q 8 - Rainier - 6,115 NW Q MC 9 - St. Helens (Municipal 16,898 SSE Q MC Water Supply) 10- Columbia River 116,510* E S/A 11- Prescott Water Supply 1,287 NNW Q 12- Meteorology Tower 805 S W 13- N Site Boundary at 161 NNW Q W Columbia River 14- S Site Boundary 1,332 S Q
TABIR 2-1 Sheet 2 of 2
' SAMPLING LOCATIONS AND FREQUENCY BY TYPE Radial Sample Sample Location Distance Air Well Surface Shore -
(meters) Direction TLD Particulate - Water . Water Soil
'15- E Fenceline 93 E Q i
LEGEND:
W - Weekly. .
' MC - Monthly Composite.
Q - Quarterly.
S/A- Semi-Annually.
- - Columbia River Distance refers to meters measured from mouth.
9 6
b 1
ps#
10,
' '\ s!(,s N *N '
/\ ' ' ~ .
\
j 13
\
7 s
e%
- . ay, .'
- " N s.
f f f f f f f Q[
. , ,-='* :
att
~
&eo 5 '
a l
'= _
= , ILc2 r. .
ss o N
= y 5,
.k, r&
k.
u -
- I l
- ' ' - E l I f I IIqq q ,
r y N s., ,
N y,s w ._-l C'
rA l ; =
ors L / "'.
[
u ,
D,,,,>> w ir:
t (0 :
o w :~ -
1 , , , , ,r 1 1 1 g
t
. q; ; - 1 F
l
~ ~
- : I N'3 -
-; ;- 5 i f Q ::
I.,s
.b ;
l
/w ,f..c 2
, . 1 M
,,,,,'>>c
- : l ;!
] &- .....l1llLiisi1
.h .
y.-._____% 53 :
y
.? .
/ \q O, : -w(~/ -
l ,,b..-
~
i ,,
s-
.n, f .
~
j -
_,/D%+' l.s&l~.L.~..e,
.y. .
w ,-
~ k % . -_m: s/.. -
7)
TROJAN NUm
- ._ N- FIGURE 2-1 SAMPLINqt
N
')\ [ ')
'-JK j$.; x.
/
cowMBIA RIVE i i ANSTEC '
APERTF"5
_s / I N - l i CARE
\. 1
\
k y , ,, - + b,
-N Also Avalfabis on '
A. Aperture Ca-d f -
- s. .
~ 1 y
- % m C'] Y d'
.. Q (' m = - J,>)
\ \
'N ,Q Lq, - ' \ \Yt h, s 0, o 1 e
//
\
s
\
I en N ,-
~
a To -\
E@
}\
/ -
T L_)(
\" - >
\. /-
/ ~
( ' , ; ', $-
i
%. 's'y
\
/
N, (y '
,S' E
\
/ (f ,s' ,. ,'
- i a s ,-
g- '
/
/
,:i f' x' s'j p'
/
, :: l
,s,' '
,' ,- - l \
,,- /
h -
\
~ ,-
I
~f_ 's\ i.ls' [.~ _ HN';- ,
/
i
.OCATIONS cr iogz4o# O\ ' '
3.0 ANALYTICAL PROCEDURES AND COUNTING METHODS Samples are analyzed for the various radioactive components by standard radiochemical methods. These methods are equal to, and in most cases, identical with, those of the U. S.
Department of Energy [ Health and Safety Laboratory (HASL) Procedures Manual, HASL-300, see references, Section 3.7], or those of the U. S. Environmental Protection Agency (EPA).
Analyses of individual sample types, general methods, and routine analytical sensitivities are discussed below. The analytical program and sensitivity requirements are given in Table 3-1.
3.1 ANALYTICAL DETECTION LIMITS AND UNCERTAINTY In environmental radiological analyses the dominant known uncertainty is usually the sample count rate. This uncertainty is calculated by standard methods (HASL-300), and is reported at the 95 percent confidence level (20). The lower limit of detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will yield a net indication, above system background, that will be detected with 95 percent probability with only 5 percent probability of falsely concluding that a blank observation represents a real signal. Analytical l data for samples for which concentrations are less than or equal to the LLD are preceded by the symbol " < " unless otherwise specified.
3.2 AIR PARTICULATES Gross beta concentrations are measured with low background, window-type (0.85 mg/cnf in thickness), proportional counting systems. The LLD for gross beta measurements is less than or equal to 0.01 pCi/m 3assuming a collected air volume of 285 n9/ week.
Gamma isotopic analyses are performed with germanium detectors. The LLD requirements for gamma scans are given in Table 3-1.
3.3 DRINKING AND WELL WATER Gross beta analysis of water samples is performed by evaporation of a measured aliquot of the sample, digestion, planchetting of the processed sample and radiometric assay by the low-background beta counters mentioned in Section 3.2, with an LLD of 1 pCi/ liter. Tritium analysis is perfonned on water samples to the required LLD of 1000 pCi/ liter by liquid scintillation counting. Gamma isotopic analysis is performed using germanium detectors. The LLD requirements for gamma scans are given in Table 3-1.
3-1
I 3.4 SHORFIINE SOIL l I
l Samples'are oven-dried and results reported based on dry weight. - Gamma emitters are measured with germanium detectors. The LLD requirements for gamma scan are given in Table 3-1.
{>
i 3.5 ' AMBIENT RADIATION MEASUREMENTS
_ Quarterly ambient gamma radiation measurements were made using TLDs supplied by a i
- vendor. Each environmental dosimeter is composed of two CaF2
- Dy (TLD-200) elements and j two LiF:Mg,Ti (TLD-100) elements, all of which are 0.035 inches thick. The Cah:Dy !
j clements are shielded by 80 mg/cm2 ABS plastic,0.010 inches of tantalum and 0.002 inches of l
1:ad. The LiF:Mg,Ti elements are shielded by 80 mg/cm2 ABS plastic only.
1 Environmental dosimeters retrieved from the field are sent to the vendor for processing on a quarterly basis.
3.6 OUAllTY CONTROL A large number of the analyses performed by the analysis laboratory are for quality control purposes. The analysts laboratory participates in Environmental Protection Agency (EPA) and )
Department of Energy (DOE) interlaboratory comparison programs for environmental l measurements. _ Reports of quality control analyses are presented monthly to PGE.
Results of EPA and DOE interlaboratory comparisons for 1996 are given in Table 3-2. In those cases where the laboratory failed the performance evaluation study, the laboratory performs an investigation to determine the cause and corrective action as required. Table 3-3 summarizes the spiked sample results for the year 1996.
l
3.7 REFERENCES
FOR ANALYTICAL PROCEDURES 4
- 1. American Public Health Association, American Water Works Association and Water Pollution Control Federation (1971): Standard Methods for the Examination of Water ,
and Wastewater. Thirteenth edition, pp 583-632; 12th edition, p9 32,5-352. APHA, 1740 Broadway, New York, NY 10019. L 2.' Department of Health, Education and Welfare, Public Health Service: Radionecav Procadures for Environmental Samnies. National Center for Radiological Health (1%7),
'Sec.1, pp 36-115.
J
- 3. Atomic Energy Commission: Regulatory Guide 4.3 (September 1973).
3-2
.- -. _ --- . - _ =_. . . - . -
- 4. Health and Safety Laboratory, Atomic Energy Commission: HASL Procedures Manual (now known as EML of the Department of Energy). HASL,376 Hudson Street, New York, NY 10014.
- 5. National Environmental Research Center, Environmental Protection Agency; Handbook of Radiochemient Analytical Methods. Program Element 1HA 325. Office of Research and Development, Las Vegas, NV 89114.
a 1
l J
f 3-3
TABIE 3-1 PROGRAM ANALYSES AND REPORTED DETECTION LEVELS i
l Pronram Analysis Reported Detection I.imits (I i DY81 Air Particulate-gross beta 0.01 pCi/m3 3
Air Particulate-gamma scan 0.05 pCi/m3 Cs-134 i 0.06 pCi/m3 Cs-137 Water-gross beta 1 pCi/ liter
. Water-tritium 1000 pCi/ liter Water-gamma scan 15 pCi/ liter Mn-54 15 pCi/ liter Co-58 15 pCi/ liter Co-60 30 pCi/ liter Zn-65 30 pCi/ liter Zr-95 15 pCi/ liter Nb-95 ;
15 pCi/ liter Cs-134 '
18 pCi/ liter Cs-137 Shoreline Soil-gamma scan (dry) 0.15 pCi/g Cs-134 0.18 pCi/g Cs-137 i i
Direct Radiation 0.04 mR/ day or less I
falReported detection level or LLD is defined in Section 3.1 l
l
l TABIR 3-2 Sheet 1 of 2 l 1996 EPA AND DOE INTERLABORATORY COMPARISON PROGRAM RESULTS Sample Study EPA TNU/A Deviation Tyne Amlysis Date Value oCi/l Value oCi/l (known)
Water Beta January % 7.0 i 5.0 9.3 0.1 0.79 Pass Water H-3 March % 22002 2200 19797 146 -1.74 Pass Water Beta April % 167 25 160 1 -0.51 Pass l Water Co-60 April % 31.0 5.0 32.0 0.0 0.35 Pass Water Cs-134 April % 46.0 5.0 48.0 1.0 0.69 Pass
^
Water Cs-137 April % 50.0 5.0 51.3 0.3 0.46 Pass Water Co-60 June % 99.0 i 5.0 89.3 i 3.1 -3.35 Faill Water Zn-65 June % 300 30 292 7.0 -0.46 Pass Water Cs-134 June % 79.0 5.0 77.7 2.1 -0.46 Pass Water Cs-137 June % 197 10 195 t 2.0 -0.35 Pass Water Ba-133 June % 745 75 635 i 1 -2.54 Pass Water Beta July % 44.8 5.0 36.0 2.1 -3.06 Fail 2 Water H-3 August % 10879 t 1088 9573 199 -2.08 Pass Water Beta October % 34.6 5.0 29.4 i 2.1 -1.81 Pass Water Beta October % 111.8 i 16.8 107.5 i 0.4 -0.44 Pass ,
Water Co-60 October % 15.0 i 5.0 14.0 1.0 -0.35 Pass Water Cs-134 October % 20.0 5.0 20.3 t 0.6 0.12 Pass Water Cs-137 October % 30.0 5.0 30.0 0.0 0.00 Pass Water Co-60 November % A0 5.0 41.7 3.2 -0.81 Pass Water Zn-65 November % 35.0 5.0 38.0 1.7 1.04 Pass Water Cs-134 November % 11.0 5.0 12.7 0.6 0.58 Pass Water - Cs-137 November % 19.0 i 5.0 19.7 1.5 0.23 Pass Water Ba-133 November % 64.0 i 6.0 65.0 1.0 0.29 Pass a
1' Assignable cause of problem: possible counting system bias. Corrective action: recount sample on all detectors. Results: passed performance evaluation. Subsequent performance evaluations ;
for Co-60 in water samples were acceptable.
]
2 Assignable cause of problem: poor precision of method. Corrective action: recount sample. !
Results: passed performance evaluation. Subsequent performance evaluation for gross beta in water samples were acceptable.
l
TABLE 3-2 Sheet 2 of 2 1996 EPA AND DOE INTERLABORATORY COMPARISON PROGRAM RESULTS Sample Study DOE TNU/A Tyne Analysis Date Value pCi/ Filter Value pCi/ filter Halto Filter Ce-144 April % 900.0 89.2 694.6 24.3 0.77 Pass Filter Co-57 April 96 240.5 24.3 198.4 6.4 0.82 Pass Filter Co-60 April 96 797.3 78.6 718.9 22.4 0.90 Pass Filter Cs-134 April % 397.3 i 39.5 373.0 i 11.8 0.94 Pass Filter Cs-137 April % 179.5 18.9 162.7 9.7 0.91 Pass Filter Mn-54 April % 93.0 10.3 75.4 5.1 0.81 Pass Filter Ru-1% April % 313.5 38.9 308.1 30.5 0.98 Pass Filter Sb-125 April % 264.3 27.8 261.1 12.8 0.99 Pass Filter Beta April % 47.8 4.1 41.6 3.2 0.87 Pass Filter Co-57 October 96 400.0 i 22.0 459.5 13.9 1.15 Pass Filter Co-60 October 96 233.5 11.6 264.1 i 9.6 1.13 Pass Filter Cs-134 October 96 291.9 10.6 337.8 10.9 1.16 Pass Filter Cs-137 October 96 230.3 9.9 257.0 9.1 1.12 Pass Filter Mn-54 October 96 171.6 7.3 205.1 8.0 1.20 Pass Filter Ru-106 October 96 291.9 30.8 335.1 35.9 1.15 Pass Filter Sb-125 October 96 291.9 14.6 135.1 10.0 0.46 Fail 3 Filter Beta October 96 13.5 1.4 16.0 2.4 1.19 Pass Sample Study DOE TNU/A Tyoe Analysis Date Value pCi/g Value pCjlg Ratio Soil Cs-137 April 96 9.7 i 0.3 11.2 0.4 1.15 Pass Soil K-40 April 96 12.6 0.8 11.9 1.3 0.94 Pass Soil Cs-137 October 96 41.9 0.6 39.2 1.2 0.94 Pass Soil K-40 October 96 8.1 0.7 8.2 0.8 1.01 Pass l
3 Assignable cause of problem: loss of Sb-125 by volatilization during dissolution. Corrective action: add 0.lg of potassium chloride to sample prior to addition ofifNO 3 and hcl. Monitor sample heat.
r TABLE 3-3 -
1996 QUALITY CONTROL ANALYSES
SUMMARY
The table below summarizes results of samples run for process quality control purposes during the subject year. These listings are in addition to such measurements as detector backgrounds, check source values, radiometric-gravimetric comparisons, system calibrations, etc. Detailed listings of each measurement are maintained at the analysis laboratory and are available for inspection if required.
Spiked Samples Nuclide Number of Within 2 Sigma Between 2-3 Annivzed Determs. of Known Sigma of Known Alpha 62 57 5 Beta 81 76 5 H-3 37 36 1 .
Cs-137 81 81 0 Po-210 1 1 0 Ra-226 31 28 3 Ra-228 12 11 1 Th-228 49 41 8 Th-230 49 44 5 Th-232 49 45 4 U-234 33 33 0 U-235 33 29 4 U-238 33 29 4 Pu-238 7 6 1 Pu-239 20 17 3 -
Am-241 3 3 0 Uranium 69 69 0 3-3 i .
4.0 RESULTS AND DISCUSSION 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT 4.1.1 AIR PARTICULATES The gross beta air particulate data obtained during 1996 were comparable to the data obtained during the years of 1982,1983,1984,1985,1986 (except May 1986), 1987, 1988, 1989, 1990,1991,1992,1993,1994,1995, and the preoperational period. Gross beta concentrations for air particulates for sampling periods in 1996 remained generally at low ,
levels. l Average concentrations with their average standard deviations for the years 1996 and before are presented in Table 4-1 for both onsite and offsite locations. Due to revisions of the Radiological Environmental Monitoring Program, air samples were only collected at onsite -
locations during 1996.-
In October 1980, the People's Republic of China tested a nuclear device in the atmosphere.
For this reason, the increased average concentrations in 1981 were due to increased fallout levels from the October 1980 Chinese test and not from operation of the Trojan Nuclear Plant. The larger average standard deviation for the 1986 data was due to the increased gross beta activity for May 19S6 resulting from the Chernobyl reactor acpident near Kiev, Ukraine.
For 1996, the measurement of ganuna emitting radionuclides in quarterly composites of air particulate filters resulted in no detectable activity.
Data for these air monitoring samples are listed in Chapter 5, Tables 5-1, 5-2, and 5-3.
4.1.2 WELL WATER Well water samples were collected on a quarterly basis. Tritium levels were below the sensitivity requirements of the program. Gamma emitting radionuclides were not detected in well water samples. The data are presented in Chapter 5, Table 5-4.
I 4.1.3 AMBIENT RADIATION LEVELS l
Gamma radiation levels (mR/ day) for dosimeter measurements at locations in the environs l
around the Trojan Nuclear Plant are shown in Chapter 5, Table 5-5.
The elevated radiation levels from Location 15 were due to radioactivity contained in the refueling water storage tank (RWST) and radioactive materials stored in outside areas of the l 4-1
Restricted Area during 1996. The dosimeter at this location is on the Industrial Area fence, which is immediately adjacent to Trojan's Restricted Area boundary. The elevated radiation levels were limited to a section of the East Industrial Area fence. This area is on a bluff that overlooks the Restricted Area and is also in direct line of sight with the RWST.
All of the other dosimeter measurements obtained within the Controlled Area showed no increase in ambient radiation levels. Therefore, the measurements from Location 15 were not included in the determination of the onsite mean ambient radiation level used for comparison with the mean ambient radiation level for the control locations. However, the increase in the radiation levels was evaluated by performing a dose assessment for a member of the public present in the area adjacent to the East Industrial Area fence. This dose assessment has been included in Trojan's Annual Radiological Effluent Release Report for 1996.
The mean and standard deviation for the Trojan onsite measurements was l 0.09i0.02 mR/ day. This is less than, but not significantly different from, the mean and standard deviation of 0.11 0.02 mR/ day for the control locations.
l 4.2 SAMPLRS FROM THE AOUATIC ENVIRONMENT 4.2.1 DRINKING WATER SAMPLES Composited drinking water samples were collected from municipal water supply locations on the Columbia River that are downstream (Sample Location 8) and upstream (Sample Location 9) of the Trojan site. The samples were analyzed monthly for gross beta activity, tritium, and gamma emitters. The data are presented in Chapter 5, Table 5-6.
No radioactivity attributable to operation of the Trojan Nuclear Plant was detected in any of the water samples.
Table 4-3 presents the annual average of the gross beta activity for the two water sample sites from 1980 through 1996. These samples were not collected prior to 1980. The annual average values do not differ significantly over the years.
4.2.2 SHORELINE SOIL l
Shoreline soil samples were collected from a location on the bank of the Columbia River near the Trojan site. Analyses were performed for gamma emitters. The data are presented in
- Chapter 5, Table 5-7. None of the shoreline soil samples showed detectable levels of gamma emitters.
4-2 l
l l
1 4.3
SUMMARY
OF RESULTS Table 4-4 presents a summary of the radioactivity analysis results for each medium or pathway sampled during 1996 for the Radiological Environmental Monitoring Program. The format of Table 4-4 is that which is required by ODCM Control 5.1.1.
A review of Table 4-4 shows that none of the radioactivity measurements, averaged over a quarter year period, were larger than the Reporting Levels defined by ODCM Control 3.3.1.
Air particulate samples were collected from two onsite locations during 1996. Location 13 is at the North site boundary and Location 12 is South of the plant at the meteorology tower.
The gross beta annual mean concentrations of 0.021i0.008 pCi/m' for Location 13 and 0.019i0.008 pCi/m for 3 Location 12 were both less than, but not significantly different from, the five year (1990-1994) mean concentration of 0.025 0.014 pCi/nf for the control location.
l For the ambient radiation measurements, the mean value for the control locations was not I significantly different than the mean values for the Trojan onsite locations.
For the radioactivity measurements in drinking water, the annual mean for the gross beta determination was higher (though not significantly) for the upstream or control location (St.
Helens) than it was for the downstream location (Rainier).
As is shown by Table 4-4, there is no indication that the operations of the Trojan Nuclear Plant had a radiological impact on the environs around the Plant.
i 4
4-3 1
TABLE 4-1 AVERAGE GROSS BETA CONCENTRATIONS FOR AIR PARTICULATES (10-2 pCi/m3 )
Trojan Year _ Site. Oregon Washington Preop 22 2 2 32 1976 2i6 3i8 2i4 1977 3i4 4i4 Si2 1978 2i2 2 1 2i1 1979 1 1 1 1 1 1 1980 34 34 2i4 1981 11 2 11 4 11 1 1982 25 2t7 2i6 1983 2i2 2 2 2i2 1984 2i2 2i2 2i2 1985 2 2 2 1 2 1 l 1986 37 3 6 3 7 1987 11 lil 11 1988 11 lil 11 1989 2 2 2 2 2i2 ,
1990 2i1 2i1 2t1 A 1991 2i1 2 1 2 1 1992 2 1 2 1 2i1 "'
1993 3 2 3 2 32 1994 3 2 3 1 3il l *
- 1995 2 1 1996 2 1
- Due to revisions of the Radiological Environmental Monitoring Program, air samples are l
l no longer collected at offsite locations.
l l
l l
I
(
TABLE 4-2 AVERAGE AMBIENT GAMMA RADIATION LEVELS mR/ Day
. Year Trojan Oregon Washinrrton Site 1976 0.13 0.14 0.13 1977 0.13 0.15 0.14 1978 0.11 0.13 0.13 1979 0.11 i 0.02 0.14 i 0.02 0.13 i 0.03 i 1980 0.11 i 0.02 0.14 0.02 0.12 0.01 1981 0.11 0.03 0.14 0.02 0.12 0.02 1982 0.14 i 0.03 0.16 0.02 0.15 0.02 1983 0.12 0.02 0.14 0.02 0.13 0.01 -
1984 0.12 i 0.03 0.13 i 0.02 0.12 0.02 1985 0.12 i 0.03 0.14 0.02 0.12 i 0.02 1986 0.12 i 0.03 0.14 i 0.03 0.12 0.02 1987 0.13 i 0.03 0.15 0.03 0.12 0.02 1988 0.12 i 0.02 0.14 i 0.02 0.12 0.02 1989 0.11 i 0.02 0.14 0.02 0.12 i 0.02 1990 0.11 i 0.02 0.13 i 0.03 0.11 i 0.02 1991 0.11 i 0.02 0.13 0.02 0.13 0.02 1992 0.10 i 0.03 0.13 i 0.03 0.12 0.02 1993 0.10 i 0.03 0.12 0.03 0.10 0.03 1994 0.19 i 0.03 0.22 i 0.03 0.20 0.03 1995 0.08 i 0.02 0.11 i 0.01 1996 0.09 i 0.02 0.11 0.02
- o Due to revisions of the Radiological Environmental Monitoring Program, ambient gamma radiation levels are no longer measured in the state of Washington.
~
l l
l 1
TABLE 4-3 AVERAGE GROSS BETA CONCENTRATIONS i FOR DRINKING WATER FROM COLUMBIA RIVER (Units: pCill)
No. 8 -Rainier No. 9 - St. Helens Year (Downstream) (Upstream) 1980 2 2 2i1 1981 2 1 3 1 1982 3 2 4 2 1983 3 2 4 2 1984 32 4 2 1985 32 4 1 1986 3i2 3 2 .
1987 3 2 4 1 1988 4i2 63 1989 3 2 4 2 1990 2 3 5 3 1991 3 3 1 2 1992 2 1 3 1 1993 2 1 3il l 1994 2 1 3 1 1995 2 0.4 3 1 1996 2 i0.4 3 1 l
l
IABLE 4-4 Sheet 2 of 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Trojan Nuclear Plant, Columbia County, Oregon, Docket 50-344, Reporting Period: January 1-December 31,1996 Location with Highest Type and All Indicator Annual Mean Control Locations Medium or Pathway Total Number Lower Limit Locations Name, Number of Sampled (Unit of of Analyses of Detection Mean(f)l'1 Distance, Mean(f)tal Mean(f)I'l Reportable Measurement) Performed (LLD) Range and Direction Range Range Events Ambient Radiation y-exposure-43 0.04 0.09(35/35) 6 - Park 0.10(4/4) 0.11(8/8) N/AIbl (mR/ day) 0.05-0.16 Entrance - 0.09-0.12 0.09-0.15 354 Meters SSW '
l Drinking Water Gross B-26 1 1.5(7/13) 8 - Rainier 1.5(7/13) 3.4(13/13) N/A[bl (pCi/ liter) 1.0-2.0 3.8 mi - 1.0-2.0 2.8-4.7 NW Tritium-26 1000 < LLD -
< LLD < LLD 0 y-scan-26 Table 3-1 < LLD -
< LLD < LLD 0 Shoreline Soil y-scan-2 Table 3-1 < LLD -
< LLD N/A[bl N/A[b]
(pCi/g - dry)
I'l Mean and range based upon detectable measurements only. The fraction of detectable measurements at specified locations is indicated in parentheses (f).
[blN/A - Not applicable.
IcIBased on measurements taken at a control location in Portland, Oregon, from 1990 through 1994.
1
TABLE 4-4 Sheet 1 of 2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
Trojan Nuclear Plant, Columbia County, Oregon, Docket 50-344, Reporting Period: January 1-December 31,1996 Location with Highest Type and All Indicator Annual Mean Control Locations Medium or Pathway Total Number Lower Limit Locations Name, Number of Sampled (Unit of of Analyses of Detection Mean(O tal Distance, Mean(O l'1 i Mean(O 81 Reportable
__ Measurement) Performed (T I E Range and Direction Range Range Events Air Pgiculates Gross B-102 0.01 0.020(102/102) 13 - Trojan N/Albl 0.02)(50/50) 0.025(256/256)lcl (pCi/m ) 0.007-0.058 North Site 0.007-0.058 0.007-0.107 Boundary -
161 Meters NNW y-scan-24 Table 3-1 < LLD -
< LLD < LLD Icl 0 Well Water Tritium-4 1000 < LLD < LLD N/Alb) o (pCi/ liter) y-scan-4 Table 3-1 < LLD -
< LLD N/Atbl 0 i
Inl Mean and range based upon detectable measurements only. The fraction of detectable measurements at specified locations is indicated in parentheses (O.
[blN/A - Not applicable.
[clBased on measurements taken at a control location in Portland, Oregon, from 1990 through 1994.
5.0 COMMENTS ON AND TERMS USED IN DATA TABLES Dry Weight A reporting unit used for shoreline soil in which the amount of sample is taken to be the weight of the sample after removal of moisture by drying in an oven at about 110 C for about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
pCi/m3 A reporting unit used with air particulate data which refers to the radioactivity content expressed in picocuries per unit volume of air expressed in cubic meters passed through the glass fiber filter. Note that the volumes are not corrected to standard conditions. '
Gamma Emitters Samples were analyzed by high resolution germanium gamma or spectrometry. The resulting spectrum is analyzed by a computer '
Gamma Isotopic program which scans about 50 to 2000 kev and lists the energy peaks of any nuclides present in concentrations exceeding the sensitivity limits set for that particular experiment.
Error Terms Figures following " " are error terms based on counting uncertainties at the 20 (95 percent confidence) level unless otherwise specified. Values preceded by the " < " symbol were below the stated concentration as l defined by the notation associated with Table 4.3-1 of Trojan's Offsite Dose Calculation Manual.
f.
d l
l l
5-1
TABLE 5-1 Sheet 1 of 2 GROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)
Location 12 Location 12 Collection Volume Gross B Collection Volume Gross B 3
Date 3 (m ) (pCi/m )3 Date (m ) (pCi/m3) 1/2/96 295 0.040 i 0.003 7/2/96 280 0.015 0.002 i 1/09/96 285 0.014 0.002 7/9/96 285 0.013 i 0.002 l 1/16/96 280 0.017 i 0.002 7/16/96 230 0.018 i 0.002 1/23/96 290 0.014 i 0.002 7/23/96 285 0.012 0.002 1/30/96 275 0.017 0.002 7/30/96 285 0.019 i 0.002 2/6/96 290 0.049 i 0.003 8/6/96 285 0.011 0.002 2/13/96 *
- 8/13/96 290 0.021 i 0.002 2/20/96 205 0.038 0.003 8/20/96 285 0.013 0.002 8/27/96 0.021 0.002
- l 2/27/96 285 0.015 i 0.002 275 3/5/96 290 0.025 i 0.002 9/3/96 290 0.025 0.002 3/12/96 285 0.018 i 0.002 9/9/96 240 0.020 0.002 '
3/19/96 285 0.015 i 0.002 9/17/96 330 0.017 0.002 3/26/96 290 0.022 0.002 9/24/96 285 0.018 i 0.002 4/2/96 280 0.022 i 0.002 10/1/96 285 0.022 i 0.002 4/9/96 280 0.024 i 0.002 10/8/96 285 0.027 i 0.002 4/16/96 280 0.013 0.002 10/15/96 295 0.020 0.002 4/23/96 290 0.008 i 0.002 10/22/96 275 0.015 0.002 4/30/96 290 0.017 i 0.002 10/29/96 285 0.015 0.002 5/7/96 280 0.014 i 0.002 11/5/96 290 0.030 0.002 5/14/96 265 0.023 i 0.002 11/12/96 280 0.026 0.002 5/21/96 285 0.013 0.002 11/19/96 285 0.016 i 0.002 5/28/96 290 0.015 i 0.002 11/26/96 280 0.021 0.002 6/4/96 280 0.018 i 0.002 12/3/96 285 0.009 0.002 6/11/96 285 0.017 i 0.002 12/10/96 285 0.009 i 0.002 6/18/96 295 0.014 i 0.002 12/17/96 280 0.018 i 0.002 6/25/96 285 0.015 i 0.002 12/24/96 280 0.014 0.002 12/31/96 280 0.019 i 0.002 o No sample available; air sampling equipment was submerged due to flooding of the Columbia River.
TA.BLE 5-1 Sheet 2 of 2 GROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)
Location 13 Location 13 Collection Volume Gross B Collection Volume Gross B Date 3
_QD )_ (pCi/m ) 3 Date (m )3 (pCi/m3) 1/2/% 295 0.036 0.003 7/2/96 280 0.016 0.002 1/9/96 285 0.018 0.002 7/9/96 285 0.015 0.002 1/16/96 280 0.021 0.002 7/16/96 280 0.017 i 0.002 1/23/96 290 0.017 i 0.002 7/23/% 285 0.014 i 0.002 1/30/96 280 0.015 0.002 7/30/96 285 0.021 0.002 2/6/96 290 0.058 i 0.003 8/6/96 285 0.015 0.002 2/13/96 285 0.024 i 0.002 8/13/96 290 0.017 0.002 2/20/ 6 285 0.041 i 0.003 8/20/96 285 0.019 0.002 l 2/27/96 280 0.016 i 0.002 8/27/96 275 0.019 i 0.002 3/5/96 290 0.030 0.002 9/3/96 290 0.025 i 0.002 '
3/12/96 285 0.019 i 0.002 9/9/96 240 0.020 0.002 3/19/96 285 0.018 i 0.002 9/17/96 330 0.018 0.002 l 3/26/96 290 0.025 i 0.002 9/24/96 285 0.025 0.002 4/2/96 280 0.025 i 0.002 10/1/96 275 0.025 0.002 4/9/96 280 0.022 i 0.002 10/8/96 275 0.027 0.002 4/16/96 285 0.010 0.002 10/15/96 175 0.030 0.003 4/23/96 290 0.007 0.002 10/22/96 280 0.015 0.002 4/30/96 290 0.015 i 0.002 10/29/96 285 0.015 i 0.002 5/7/96 280 0.016 i 0.002 11/5/96 290 0.029 i 0.002 5/14/96 285 0.028 i 0.002 11/12/96 280 0.025 i 0.002 5/21/96 280 0.018 i 0.002 11/19/96 285 0.013 i 0.002 5/28/96 290 0.012 0.002 11/26/96 255 0.022 0.002 6/4/96 280 12/3/96 ** **
1 0.015 i 0.002 6/11/96 12/10/96 ** **
285 0.016io.002 6/18/96
- 12/17/96 280 0.021 i 0.002 l 6/25/96 250 0.018 i 0.002 12/24/96 280 0.017 i 0.002 l 12/31/96 280 0.020 i 0.002 No sample available; lost power to automatic sampling equipment.
- No sample available; maintenance performed on power supply.
I 4
TABLE 5-2
SUMMARY
- GROSS BETA IN AIR SAMPLES oCi/m3 Mean + 1p_ hLagjmum Minimum Trojan Onsite Stations Location 12 0.019 0.008 0.049 0.008 Location 13 0.021 i 0.008 0.058 0.007
/
i
TABLE 5-3 GAMMA EMITTERS: CONCENTRATIONS IN AIR PARTICULATE FILTERS (Monthly Composites)
Collection (pCi/nh Dates Location 12 Location 13 12/26/95-1/30/96 < LLD < LLD 1/30/96-2/27/96 < LLD <LLD 2/27/96-3/26/96 < LLD < LLD 3/26/96-4/30/96 < LLD <LLD 4/30/96-5/28/96 < LLD <LLD 5/28/96-6/25/96 < LLD < LLD 6/25/96-7/30/96 < LLD < LLD 7/30/96-8/27/96 < LLD < LLD 8/27/96-9/24/96 < LLD < LLD i 9/24/96-10/29/96 < LLD < LLD 10/29/96-11/26/96 < LLD < LLD 11/26/96-12/31/96 < LLD < LLD LLD: 0.05 pCi/m 3Cs-134 '
0.06 pCi/m3 Cs-137 l
l l
i TABLE 5-4 RADIOACTIVITY IN WELL WATER Collection pCi/1 Date Location 11 Gamma Tritium Emitters 3/12/96 < 1000 < LLD 6/18/96 < 1000 < LLD 9/9/96 < 1000 < LLD 12/12/96 < 1000 < LLD LLD: 15 pCi/l Mn-54, Co-58, Co-60, Nb-95, Cs-134 18 pCi/l Cs-137 30 pCi/l Zn-65, Zr-95 1000 pCi/l H-3 l
TABLE 5-5 AMBIENT GAMMA RADIATION LEVELS mR/ Day First Quarter Second Quarter Third Quarter Fourth Quarter Location 12/27/95-3/28/96 3/28/96-6/27/96 6/27/96-9/26/96 9/26/96-12/26/96 1 0.10 0.12 0.08 0.09 2 0.09 0.05 0.07 0.07 3 0.16 0.08 0.07 0.07 4 0.10 0.08 0.07 0.09 5 0.12 0.09 0.09 0.10 6 0.12 0.09 0.10 0.10 l
7 0.07 0.07 0.09 0.07 l
8 0.12 0.09 0.09 0.10 9 0.15 0.12 0.09 0.10
- 0.11 13 0.10 0.07 14 0.10 0.08 0.08 0.09 15 0.20 0.16 0.21 0.19 o Dosimeter lost in field
TABIF 5-6 RADIOACTIVITY IN DRINKING WATER (Samples Split with State of Oregon)
Location 8 - Rainier Municipal Water Supply Location 9 - St. Helens Municipal Water Supply pCi/l pCi/l Gamma Gamma Collection Dates Gross Beta Tritium Emitters Collection Dates Gross Beta Tntiuru Emitters 12/19/95-1/16/ % 1.110.7 < 1000 < LLD 12/19/95-1/16/ % 3.510.9 < 1000 < LLD 1/16/96-2/13/ % < 1.0 < 1000 < LLD 1/16/96-2/13/96 3.3 i0.9 < 1000 < LLD 2/13/96-3/12/ % 1.2i0.8 < 1000 < LLD 2/13/96 3/12/ % 3.210.9 < 1000 < LLD 3/12/96-4/9/ % < 1.0 < 1000 < LLD 3/12/96 4/9/ % 3.2 0.7 < 1000 < LLD l 4/9/96-Sn/96 < 1.2 < 1000 < LLD 4/9/96-Sn/% 3.4i0.9 < 1000 < LLD l 5D/96-6/4/96 < 1.0 < 1000 < LLD SD/96-6/4/% 3.6il.0 < 1000 < LLD 6/4/96-7/2/96 1.5i0.8 < 1000 < LLD 6/4/96-7/2/% 3.7 1.0 < 1000 <LLD 7/2/96-7/30/96 2.0i0.8 < 1000 < LLD 7/2/96-7/30/96 3.0i0.9 < 1000 < LLD 7/30/ % -8/27/96 < 1.2 < 1000 < LLD 7/30/96-8/27/96 4.7 1.1 < 1000 <LLD 8/27/96-9/24/96 1.8i0.8 < 1000 < LLD 8/27/96-9/24/96 2.9 1.0 < 1000 < LLD 9/24/96-10/22/ % < 1.2 < 1000 < LLD 9/24/96-10/22/ % 3.410.9 < 1000 < LLD 10/22/96-11/19/ % 1.7i0.8 < 1000 < LLD 10/22/ % -11/19/96 2.8i0.9 < 1000 < LLD 11/19/96-12/17/96 1.0i0.7 < 1000 < LLD 11/19/96-12/17/ % 2.9i0.9 < 1000 < LLD LLD: 15 pCill Mn-54, Co-58, Co-60, Nb-95, Cs-134 18 pCi/l Cs-137 30 pCi/l Zn-65, Zr-95 1000 pCi/l H-3
- o
I TABIP 5-7 RADIOACTIVITY IN SHORELINE SOIL i (Semiannuti Col'.ections) pCi/g (dry) 4 Location 10 Collection Gamma Date Emitters 3/12/% < LLD 9/9/%I 'l < LLD I*3 Split sample with the State of Oregon.
LLD: 0.15 pCi/g Cs-134 0.18 pCi/g Cs-137 l
I i
1 1
_ _ _ _ _ _ - _ _ _ _ _ - - _ _ - _ - _ _ - - _ _