ML20235R225
| ML20235R225 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Perry, 05000000 |
| Issue date: | 12/31/1986 |
| From: | OHIO, STATE OF |
| To: | |
| References | |
| NUDOCS 8707210268 | |
| Download: ML20235R225 (110) | |
Text
- - - - _
7 ,
',3//. $
l l
OHIO ANNUAL ENVIRONMENTAL MONITORING REPORT 1986 FOR SPLIT SAMPLING PROGRAMS I ) IN THE VICINITY OF DAVIS-BESSE AND PERRY NUCLEAR POWER STATIONS 1
t I
)
w r
- OF l
OHIO DEPARTMENT OF HEALTH Bureau Of Environmental Health RADIOLOGICAL HEALTH PROGRAM Columbus, Ohio 1 ok kobhk bIOb 6 l
1986 OHIO DEPARTMENT OF HEALTH ;
l Annual Environmental Monitoring Report for Split Sampling Programs in the Vicinity of i
DAVIS-BESSE NUCLEAR POUER STATION PERRY NUCLEAR POWER PLANT Ohio Department of Health Bureau of Environmental Health Radiological Health Program 1224 Kinnear Road Columbus, Ohio 43212
.l' ~...
r L
t h
I
{ TABLE OF CONTENTS l
Executive Summary . . . . . . . . . . . . . . . . . . . . i 1
Commonly Used Abbreviations . . . . . . . . . . . . . . . ii List of Figures . . . . . . . . . . . . . . . . . . . . . p. 1 List of Tables . . . . . . . . . . . . . . . . . . . . . . p. 2 Introduction . . . . . . . . . . . . . .. . . . . . . . . p. 3 Sampling Procedures . . . . . . . . . . . . . . . . . . . p. 4 I
Analytical Procedures / Quality Assurance . . . . . . . . . p. 7 l Sensitivities and Errors . . . . . . . . . . . . . . . . . p. 8 DISCUSSION OF RESULTS Ohio Department of Health and Davis-Besse NPS . . . . . . . p. 19 l DAVIS-BESSE AIR PARTICULATE AND AIR IODINE p. 20 1
DAVIS-BESSE WATER p. 22 DAVIS-BESSE FISH p. 22 DAVIS-BESSE MILK p. 23 DAVIS-BESSE FRUIT & VEGETABLES p. 23 DAVIS-BESSE BOTTOM SEDIMENT p. 23 DAVIS-BESSE TLD (Direct Radiation) p. 24 DISCUSSION OF RESULTS Ohio Department of Health and Perry NPP . . . . . . . . . . p. 44 PERRY AIR PARTICULATE:S AND AIR IODINE p. 45 PERRY WATER p. 46 PERRY FISH p. 46 PERRY MILK p. 47 PERRY FRUIT & VEGETABLES p. 47 PERRY BOTTOM SEDIMENT p. 48 PERRY TLD (Direct Radiation) p. 48 Appendix A Figure 7, Tables 26, 27, 28 . . . . . . . . . p. 68 Appendix B Detailed ODH Lab Analyses Procedures . . . . . p. 76 Appendix C Detailed ODH Lab Quality Control Progran . . . p. 93 Appendix D ODH Sampling Procedures . . . . . . . . . . . p. 99
, ~ . . 1
LXECUTIVE
SUMMARY
In January of 1984, the Ohio Department of Health entered into a cooperative agreement with the U.S. Nuclear Regulatory Commission (NRC) to perform environmental sampling in the vicinity of the Davis-Besse Nuclear Power Station near Port Clinton, Ohio.
In 1985 this NRC agreement was expanded to include environmental sampling in the vicinity of the Perry Nuclear Power Plant located in North Perry Ohio.
Environmental samples collected in the vicinity of the two power stations include air, surface water, milk, fish, lake bottom sediments and locally grown fruit and vegetables. Additionally, the NRC main-tains a direct radiation monitoring network in the vicinity of both plants. The thermoluminescent dosimeters (TLD) used in this network i are changed by ODH on a quarterly basis.
l Air samples are collected using stationary continuous air samplers.
These air samplers utilize filter papers and charcoal cartridges to collect airborne radionuclides. These filters and cartridges are changed on a weekly basis. Surface water and milk are collected on a monthly basis. Fish and locally grown fruit and vegetables are collected semi-annually. Bottom sediment samples are collected annually.
For both programs combined, approximately 450 samples were submitted to the Ohio Department of Health Laboratory for analyses.
During 1986, an accident occurred at the Chernobyl nuclear power station in tne USSR. As a consequence of this accident, large quantities of various radionuclides were released to the atmosphere. These radio-nuclides were carried by wind currents around the world. Although the quantities reaching Ohio were very small, they were within our monitoring program's detection capabilities. The air sampling data in particular, reflects the slight increases in environmental radioactivity which resulted from this event. The detection of these small quantities gives us confidence that this program can be effective in detecting atmospheric releases of this nature.
In general, there was fairly good agreement between Ohio Department of Health, Davis-Besse and Perry analytical results. Results of all 1986 analyses indicated that radionuclides concentrations in the environment surrounding these plants were at background levels or well within applicable State and Federal limits. -
i
Commonly Used Abbreviations ODH Ohio Department of Health DBNPS Davis-Besse Nuclear Power Station PNPP Perry Nuclear Power Plant United States Nuclear Regulatory Commission
~
NRC EPA Environmental Protec' tion Agency pCi picocurie m meter 1 or L liter g gram kg kilogram TLD thermoluminescent dosimeter mm millimeter um micrometer m3 cubic meter (I) indicator (C ) control mg milligram LLD lower limit of detection ND not detected N/A not applicable mR milliroentgen 11
LIST OF FIGURES l' Fi,gure $ Title Page #
i 1 Analysis Requirements for NRC Sponsored Environmental Monitoring Program . . . . . . 9 2 DBNPS Sample Collection Frequency . . . . . . 10 2A DBNPS Sample Location Identification . . . . 11 3 Map Indicating DBNPS Sampling Locations . . . 12 3A Map Indicating DBNPS Sampling Locations . . . 14 4 PNPP Sample Collection Frequency . . . . . . 15 4A PNPP Sample Location Identification . . . . . 16 5 Map Indicating PNPP Sampling Locations . . . 17 6 Map Indicating PNPP TLD Locations . . . . . . 18 k 7 USEPA Intercomparison Studies Schedule . . . 69 1
LIST OF TABLES Table # Title Page #
1 DBNPS Air Particulate Loc.#01 25 2 DBNPS Air Iodine Loc.#01 26 3 DBNPS Air Particulate Loc.#25 27 4 DBNPS Air Iodine Loc.#25 28 5 DBNPS Quarterly Air Filter Composites 29 6 DBNPS Radioiodine & Gamma Isotopic Analysis of Monthly Water Samples Loc.#03 30 7 DBNPS Radioiodine & Gamma Isotopic Analysis of Monthly Water Samples Loc. #03 31 8 DBNPS Tritium Analysis of Quarterly 32 l
Water Composites l 9 DBNPS Fish 33 l
10 DBNPS Milk 34 11 DBNPS Produce 35 12 DBNPS Bottom Sediment 36 13 DBNPS TLD 37 l 14 PNPP Air Particulate Loc.#07 49 15 PNPP Air Iodine Loc.#07 50 16 PNPP Air Particulate Loc.#06 51 17 PNPP Air Iodine Loc.#06 52 18 PNPP Quarterly Air Filter Composites 53 19 PNPP Radiciodine & Gamma Isotopic Analysis of Monthly Water Samples Loc.#34 54 20 PNPP Radioiodine & Gamma Isotopic Analysis of Monthly Water Samples Loc.#36 55 21 PNPP Tritium Analysis of Quarterly Water Composites 56 22 PNPP Fish 57 23 PNPP Milk & Vegetation 58 24 PNPP Produce 60 25 PNPP Bottom Sediment 61 26 PNPP TLD 62 27 Results of 1986 EPA Intercomparison Studies 70 28 NRC Required Detection Capabilities 74 28 ODH Laboratory Detection Capabilities 75 l
i
m e
- INTRODUCTION The Ohio. Department of Health (ODH) . conducts a split sample environ-mental' monitoring program,in the vicinity of Ohio's two nuclear power stations. This program _ is performed through a cooperative agreement with the U.S. Nuclear Regulatory Commission. An environmental mon-itoring program of this type can provide data for population dose.
calculations,' detect changes .in levels of environmental radioactivity and provide information'to the public. This report summarizes the results of the analyses' performed on environmental samples collected in hc accordance with this agreement (Modification No. 3 to Cooperative Agree-ment NRC-30-83-646) during the time period of January 1 to' December 31, 1986. .
.The Davis-Besse Nuclear Power Station (DBNPS) is located approximately 120 miles from Columbus where the Ohio Department of Health (ODH ) is located. .To accommodate NRC. required sampling frequencies, the ODH maintains a' contractual agreement with the Ottawa County Health Depa rtmen t for the actual collection and shipment of samples to the ODH Laboratory in Columbus. 'The Ottawa County Health Department is
. located approximately 10 railes from the station in Port Clinton, Ohio.
Sampling procedures and_ training have been provided to the Ottawa County Health Department personnel. These procedures are detailed in Appendix D.
.In 1985 ODH began a simlar monitoring program in the vicinity of the Perry Nuclear Power Plant (PNPP). Perry Nuclear Power Plant is located on Lake Erie in Perry, Ohio. ODH maintains a. contractual agreement with the Lake County Health Department for the collection and shipment of all samples collected for this program.
\~ - - - - _
H SAMPLING PROCEDURES All samples collected for the ODH Environmental Monitoring Program are split samples whenever possible. Splitting samples is a method which can be used to check analytical quality control. Splitting a sample involves obtaining 2 identical samples from a single collected volume.
One sample is then analyzed by the utility and the other by ODH. The analytical results can then be compared. In some instances, samples may need to be taken in duplicate instead of split. For example, it is better to collect milk samples simultaneously instead of obtaining them from a single container due to the tendency of radionuclides to plate '4 out on the surface cf the collection container.
The following samples are either split samples or are collected simul-taneously with utility personnel.
Air Samples Air particulate samples are collected on 47 mm Millipore Type AA, 0.80 um filters. Air iodine samples are collected using Scott TEDA impregnated charcoal cartridges mounted in tandem with the air par-ticulate filter in a quick disconnect assembly. The average sampling rate is 3 - 4 cubic feet per minute (CFM). The air samplers used by DBNPS and PNPP have an average sampling rate of 1 CFM.
The indicator locations for DBNPS and PNPP were chosen based on calculations which predict that these locations should receive the the highest exposure or deposition of radioactive material.
DBNPS: The indicator air sampler is co-located with a DBNPS air sampler at ODH location #01. The control sampler is located independently at Loc. #25, Portage Elementary School, Port Clinton, Ohio.
PNPP: The indicator air sampler is co-located with a PNPF air sampler at ODH location #07 on Lockwood Road. The control sampler is located at the Auburn Career Center on Auburn Road and is designated location #06. This sampler is approx-imately 0.5 miles from the PNPP location #06 control air sampler.
Surface Water i
DBNPS : Weekly 1 quart water samples are taken from Lake Erie at two locations. The four 1 quart samples collected over a period of a month are then composited into a 1 gallon cubitainer at the end of each month and then shipped to the ODH Laboratory in Columbus for analyses.
_4_
- - - - - - - - - - - - - - - _ - - - /
I I
i l Sampling procedures continued . . .
1 The indicator sample location (#3) is located in proximity to the
- DBNPS liquid effluent discharge line. The sample is taken from the shoreline at the site boundary near the mouth of the Toussaint River.
, In the winter, when the lake is f rozen over, the indicator sample is j drawn from a raw water tap on level 85 in the Davis-Besse Water Treat-A ment Plant. -
b
.I The control, or background sample (#27) is an untreated surface water
$ sample taken from a tap off the raw water line at the Port Clinton Water
]/ Works in Port Clinton, Ohio.
PNPP: At the indicator location (#34), Perry Plant Intake, surface water from Lake Erie is collected using a Horizon Interval Sampler s which collects a small volume of water at short intervals. At the i i
end of a 1 month time period a volume of 5 gallons of water has been ;
collected. A one gallon sample is taken from this volume and shipped to the ODH Laboratory for analyses.
At the control location (#36), Painesville Water Treatment Plant, an interval sampler is also uced to obtain a water sample This sampler collects a 1 minute sample of water from the raw water sample line every hour. At the end of a 1 month time period a volume of 5 gallons of water has been collected. A one gallon sample is taken from this volume and shipped to the ODH Laboratory for analyses.
Milk DBNPS: A raw milk sample is collected monthly from location #23.
PNPP: The only milk animals within close proxinity to the PNPP are goats. The collection of milk from goats has been limited by 2 major f actors; the limited supply of milk which can be produced by a goat at any given time and the seasonal production of milk by goats. During the spring and summer months, whenever possible, a 1 gallon sample of milk is collected at location #31. During the winter months, or when milk is not available from the goats, vegetation (grass or leaves) is collected as a substitute. The vegetation samples are collected at location #7.
Sediment DBNPS: Bottom sediments f rom Lake Erie are required to be collected on an annual basis in the vicinity of the plant effluent discharge. In 1986, sediment samples were collected on a semi-annual basis in the vicinity of both the plant intake and discharge. Sediment samples are
r Sampling procedures continued . . . _
collected by DBNPS personnel in the vicinity of the effluent discharge I (Loc. #30) and the plant water intake (Loc. #29) using a shovel, emory dredge or similar device. Split samples are then picked up at the plant by our contractor and shipped to the ODH Laboratory for analysis.
PNPP: Bottom sediments from Lake Erie are collected annually at Loc.#25 in the vicinity of the plant effluent discharge. Samples are collected -
l with a Petite Ponar Grab Sampler and then transferred to a plastic con-l tainer. Approximately 1 kilogram of sediment is taken from this samp]e and shipped to the ODH Laboratory for analyses.
i Pish DBNPS: Several species of commercially or recreationally important fish are collected from Lake Erie by Davis-Besse sampling personnel on a semi-annual basis. Samples are collected both from within a 5 mile radius and outside a 10 mile radius of the DBNPS using shorc seines, nets, fish traps or hook and line. Split samples are provided to the ODH contractor and then shipped to the ODH Laboratory for analyses.
PNPP: Several species of commercially or recreationally important fish are collected primarily from the same location as the sediment sample on a semi-annual basis. Samples are collected using a gill net which is set in the evening and removed the following morning.
The ODH contractor is present at the collection site and obtains approximately 1 kilogram of each of the several species caught.
Food Products DBNPS: Split samples of a variety of in-season fruit and green leafy vegetables are collected semi-annually from a private farm or garden in the immediate area of the plant. The samples are collected from Loc. #23 and/or Loc. #24.
PNPP: Split samples of a variety of in-season fruit and green leafy vegetables are collected semi-annually from a private farm or garden in the immediate area of the plant. The samples are collected at Loc.638 or Loc. #49.
Direct Radiation - Continuous monitoring of direct radiation is performed quarterly using thermoluninescent dosimeters (TLD's) provided by the U.S.
Nuclear Regulatory Commission (NRC). The dosimeters are placed at 22 locations in the vicinity of the Davis-Besse Nuclear Power Station and at 26 locations in the vicinty of the Perry Nuclear Power Plant. The TLD's are changed quarterly and returned to the NRC for processing.
Results of this monitoring are published by the NRC in NUREG-0837 and in Tables 13 and 26 of this report.
\
ANALYTICAL PROCEDURES Analytical procedures for the radiochemical analyses of the environmental samples collected under this agreement are provided in Appendix B of this report.
QUALITY CONTROL /OUALITY ASSURANCE,
, The Ohio Department of Health Laboratories maintain their own quality assurance program. The following quality control measures are used by the Radiochemistry Section in the analysis of environ-mental samples.
- 1. Use of prescribed method
- 2. Initial method validation
- 3. Instrument performance checks
- 4. Method blanks
- 5. Internal quality control standards
- 6. Internal quality control samples
- 7. Duplicate sample analysis
- 8. Spiked sample analysis
- 9. Calibration verification
- 10. External quality control samples A detailed description of these quality control measures is provided in Appendix C of this report.
The ODH Laboratory's Radiochemistry Section also participates in the U.S. Environmental Protection Agency's (EPA) Intercomparison Studies Program as part of their quality control program. A schedule of the studies in which the ODH Laboratory participates is provided in Fig. 7.
A complete listing of the U.S. EPA Intercomparison Study results is provided in Table 27.
_7_
l l
l l
l SENSITIVITIES AND ERROR The NRC's sensitivity requirements are listed in Table 25 of this report.
These sensitivity requirements are given as lower limits of detection for each radionuclides and medium in which it is detected. Table 29 outliner the ODH Radiochemistry's actual detection capabilities for each method used as well as the parameters that are involved in obtaining these limits.
The LLD for each radionuclides is calculated using the following equation:
1 LLD = 4.66 B 7 t
- kt E x V x 2.22 x exp where:
B = instrument or sample background t = ~
counting time V = sample volume or weight t = sample holding time
= decay constant of the nuclide of interest E = 1. Efficiency (cpm /dpm) is determined for each sample.
This applies to gross alpha, beta and H-3 where no yield factor applies.
- 2. Efficiency = instrument efficiency x chemical yield (E xY)
- 3. Efficiency (cpm /dpm) = instrument efficiency x abundance This applies to gamma counting on the MCA where no chemical yield factor applies.
l Figure 1 i ANALYSIS REQUIREMENTS FOR NRC SPONSORED ENVIRONMENTAL MONITORING PROGRAM SAMPLE TYPE ANALYSIS FREQUENCY TYPE OF ANALYSIS Airborne:
Particulate weekly composite gross beta quarterly composite gamma isotopic analysis Radioiodine weekly composite for I-131 Waterborne composite monthly gamma isotopic analysis composite quarterly tritium analysis Milk monthly gamma isotopic analysis and radioiodine analysis Fish semi-annually gamma isotopic analysis of edible portions Food or Vegetable semi-annually gamma isotopic and i radiciodine analysis i
. Sediment annually gamma isotopic analysis !
_ 9_
(. _ _____ _ _ _ _ - - - _ - - _ _ _ _ _ - - -- J
f i.
Fig. 2 DBNPS SAMPLE. COLLECTION FREQUENCY Location.4 Sample Media Frequency 1 TLD. .
quarterly' ~
l Air' Particulate / Iodine (I) weekly'
quarterly-
, Surf ace Wate'r Untreated - (I) *' weekly 4 TLD- ' quarterly (
5 TLD
~"
6 TLD
.7- TLD~ "-
8' TLD "
9 TLD E
10 TLD.
11 :TLD 12- TLD 13- TLD 14 TLD 15 TLD.
'18 TLD "
-21 TLD 22 TLD quarterly 23 Milk (I) monthly Produce (I) semi-annually 24 Produce (I ) semi-annually
'25 Air Particulate / Iodine (C) weekly 27 Surface Water: Untreated (C) weekly ,
28-5 Fish (I) semi-annually "
28-10 Fish (C) semi-annually 29 Bottom = Sediment-(I) annually 30 Bottom Sediment.(I) annually
.50 Surface Water Untreated (I) . weekly 0 Quart. water samples are taken f rom ' Lake Erie weekly and composited into a l' gallon cubitainer monthly which is sent to the ODH lab for' analysis.
NOTE: When the lake freezes, the water sample is drawn from a raw water tap on level 85 at the Davis Besse Water Treatment Plant or at T-50 Erie Industrial Par.k.
00 Location #19 is the upwind control TLD and is not shown on the map in Fig. 2 ., It is located at Crane Creek State Park.
(C) - control (I) - indicator l
s, .
l .
t Fig. 2A DBNPS SAMPLE LOCATION IDENTIFICATION AND SECTOR (S ), DISTANCE (D) CODING f ODH DBNPS S_ D, Davis-Besse Air Sampler Loc.#01 T-1 C 0.5 Portage Air Sampler Loc.#25 N/A F 12.7
! Davis-Besse Water Sample Loc.#3 T-3 C 1.4 Davis-Besse Water Sample Lo c . # 50 T-50 G 4.62 Port Clinton Water Treatment Plant Loc.#27 T-ll G 9.75 Moore's Produce and Vegetables Lo c . # 2 3 T-8 M 2. 6 - - - - --
Miller's Produce and Vegetables Loc.#24 T-25 K 5. 0 Davis-Besse Milk - Moore's Dairy Lo c . # 2 3 T-8 M 2. 6 Sediment - Discharge Loc.#26 T-30 E 0. 9 Sediment - Intake Loc . # 2 9 T-29 D 1. 5 Fish - within 5 miles Loc.#28-5 T-33 E 5.0 Fish - outside 10 miles Loc.#28-10 T-35 E 10.0
/
P
./.
/
/ FIG. 3 DBNPS SAMPLING LOCATIONS
%,!v '. .1 I
\
L AKE E J? 28
/-/- 1 - / .
.h.) .
w m T.,j.,0 S. ? /
i f
l 353it.f).hD I l
_ ;p:.;... 30%ao%.. , -
- r w yp:+y.:.42SRe;s+h..
m :=m* -
VI" yf'
- 4. . . . . . c. . .*
f.t.'n s. Lits.msH: %(,. 't ,u.a
g .
- f 10 -
' 29 '
_.4I 4<r I A. II ;
.1- 1 -n s h : n 5yf - W fj ) 3 j- ,7_2 mkmap. f 3 Y W
- -,r s =
+.m--Dp.y 26 l
n 3
1- , ,
pry si 7-Q a ,
y y.
.r
=
=Ls.r* .ap.- 3 m l pu-
.-g. -20
- s e. w o } e w .2 .o 2 -, -
r e .- ..y oys,_{ , - i.:.u -) ,
e_ gg .r ..g1 J l g,6 g
) *Ty f t -~ -
.:. ~ . .e - i L (3 >$)n )8 )},s,?_g E O{ 0 #CA.Nf;.
- i .nU'%g '. .
%b 6 IN A
,dr m)
/ 1 A F; "
D' 4b i 9 3 "" &.jp
""" 3J7 isMh y pi m 23 - - / ~ Wge %.I 3p I '
m,w .n o M s.h+ ,. , 10
,~
- : s ., {fk 3 f, ix 5 e m .-.m
>l c- ) . .. C t i u ,.-
r.s'm. aN et W
. _4 ;g '-~ R M 1A I J
! (g ) W " _ . _ W'-Ly s g 1 :23 rygy/ ., - -
- D ,a ec .-Q, t l El p%
T.;'#jf[ .rc.a; e re li~~Is._-j/] u ~1 Srditse h,6'f"N(
s i r-w gj. s g s woor
, n
[y = h-r u p \s rn A
-T am d 7.3. ' s A{ R R T .. -0 !L ._ Li w spAD wc.
A c w ,, a,{LC
- m. , ,_e
,: ~t y
- 'l
. e l
t jf2.==E, c
- m. g{
( - a r *.s MJ w II 2 '
..n i "'**6
, b'
( $ T21
,g 22"*"gg'23 e
'i;gg m_ .
i =
'$ l :
-- ~ u'> ,, 5
- ,ff \.r a w*tgfr.5".1t ...JJ_j f*... 7 L ; U RK '
1
[-- -9
- . 1u a .:.
g ;
s =r-3 - - ~
15 N_ /
2 wn 3 / y. .14 :-- - - 24 4; ' l.3 . _
-r
_.) '-
~
,_ _nge j 29 27, . p g g' p2g
, 30j g , % t ___
iM p 2hi .i 6,"~ . . - g; -
d I
b --~~ ~ ~'"
3E g' [ g I k g d., F'?,*J.%,..
. ..t d ?U----, TT '
I
- Fi 1",dg
.- =-
le C'"* '
s
- U '~i"i . -Qfp*1 . , }i
"'g ly N-
-w'--
' K n T
lL.: c[~ ,3li-% g , Q xl f ; x ,t p @
/ ro .s _- .
5 p f% '
- . -' c - e J-
[ ,, gY-.
t , ,
L Y. Laam, -
h ' C '-! h f E ~ h. ci'~; -I h 31 [ ,x _
t ,. 'i' e
- n. 22 ci.u 1,V,.
q, -
- y. .j n E::
E1
- o.uriw -l -
P-j i a rap >
i EE -
- s. a :
I AF**r l '
- e .q iv I'-%_% , __ -
, e. ; c3 g .
?-
,,H ,. , ~8- .D' , A*. ... a. -.cn
- .,.n,N,a<
l 4 d c'-- .
- 'h--
t' 6 w: ,5: :
1 -- ',. 3 ) se n'> ',' a..: i ,.y* ,. I r-n-
. f J -- -
. qgf ; s -, - , -- --."-a-- i ,- _t-Rp= , ",, f&37L4-r- '
T,'~" { .t SCALE OF MtLES - gb, & gYbY - -~~,, . 4'l..'. ":.T
- ' ' -KQ
Er * - $ _" r! ; g g 7---,
pQnY:, ,*
) 3 I'
~_ ; '
t c G8 -- " ,
i' ': y I 3
& V: .l,:. : 5'. . . D t,_,_ =- .n
4b FIG. 3 1
ui
,q J
"#"*.. dl ?
e.u,as,,s.uf.
mm..
g*y&.*
g,, (3 -i,. :
, i
. L A L, E ERIE caucor< ws,-:.2N5 cw,. g W .',
p.,.7 i N x\
cg d
- 1 ji; cannag g .9 =
- ~kj n'e = yi,y @ g y I g
coconge,,
9 - * .
l ~.. ,.
l i
- l A i
f e.. .
_ _ e. _ e- -
$I
- ~ - f a:.
$N.
- e O _y u.. (
/h,,b. $,Y~Q A -
j 27.v., -
is- -
%- !: sue vanay N ja , TEN!D y, -
@Mu>.
75'JL"cn w:s h d-
- E =-
co 1 couw -
tv "2 r,
e f $k" #
7;i F, -$ _ l W i A6 gg yf , -g ' #6gj
^
,. - ha -g -
3< # S -!-----AR 9 15 , .&.
.~. . . .
< ~
gj 8 . J p! *% 4 ,
,~ - % %n w
e (a ..u ,64 7..,~.m.
atoou mawr
{.Of
. .. , sr ) go,ni_ sw I
9cl ,:
{' 1 L. 'I
, ]2.- 4- I E ^1 1"-- A.,
g Eg4jv;fy,.
' ~
_ hi. .=r
- l k [
y :~ .; Q"'.,f r i _.- 1 l 3 d l ['S' ,t ) )
. .0 j; 1 4 ~~.
3 'u
,M gc12%
=
ergs: im.3 -
g i
--- 10 j .,4
" .y u g:
a.
3 feig-.9g 6 g %.Jojyj3...:o
.- .=
Erf .r. g.!Lo- - -./. ~.,, .
.f.J,,,p tys;gstt' ; ted a 129=. n . ,u. .
if v':g&,g'.sy,=-~ ,M ..
T .~. a p 12T: 15e L
' by y
}. '<
E~
E' , ,
yflg4cm ,:MM..etp ;i aj j / m tin i 132 7~.
- S 141 gf, c:=
,.- l .
1 W ,*Wq# 5 l
/ , ,.< '. ,. /
'. , (
l SANDUSTY BAY f I %,
i ! ' .
' .-l -* j
- -'G U usAY -$h: - "- - -- - - - - - - '" ' '" ,,.,,, . . -
uy &g q A -l
) A!f)nh I .
Y ( d.g. , 2 h s, w;, g i
seats or mitts 3
y/
i ,. . e
? _. K 1
2
.N- -
/
o _ . . _ . . . . . .
Ii n y o r a
i A
i t
o d n
j k ni a c
l o uo
- b g
n e ilpm iS t
E E K /
o - A #
S
- L E a)Q -
e
)/ m _
_ 5 _
l _..
- 3 j..
s n .
o ,6. .
i t -.r1 .- ..
a - i '
. c \ jm _l .
a
_ o * ,
_ . .d, l o.
h,'j, - .~
i e -
'f
_ o -
.m,
_ r 0 - .
_ a - -
A ;/ _
3 h
c 4 'e -
1 1
s L _
i bp,'", ' -
A D N _
. O _ -
' ' . .o G d n
i I
T E I
a i.
r A RH _
F i 5 T RS _
S AR ia e
r
,L,
+
\
O R
n 0 _
I .
a _
S P
_ ( .
S .
/ ..
R P
N r..
C E
, B R E
V K
_ B _
A _. I D A T E -
R N _SL
_ l
. Y _
t I
,. vC _
u
_ AU DN ( ;-
\ u TY
+
e N ri y
e w
PO - -
M S
u w -
S o o . - . _
(T o a f n ..c- U I
P c
o n
a O _
a T
s 9 w u 0
9 R
o .
l
- 0/
3
\ 7,.
I
, - k, ' '
\ -
. ~
o ':
- a o
n -
a w
n w .
r -
r u
e ay W,
i
~*' '
l!,!!
Fig. 4 PNPP SAMPLC COLLECTION FREQUENCY Location # Sample Media Frequency 1 TLD quarterly 3 TLD "
4 TLD "
5 TLD "
6 TLD 6 Air Particulate / Iodine (C) weekly 7 TLD quarterly 7 Air Particulate / Iodine (I ) weel.ly 8 TLD quarterly 9 TLD "
10 TLD "
I 11 TLD "
{ 12 TLD "
l 13 TLD "
l 14 TLD "
l 15 TLD "
18 TLD "
19 TLD "
20 TLD "
25 Fish (I ) semi-annually Sediment (I ) annually 26 TLD quarterly 27 TLD quarterly 31 Milk (I ) monthly 32 Fish (C) semi-annually Sediment (C) annually 34
- Surface Water Untreated (I ) weekly 36
- Surface Water Untreated (C) weekly 38 Produce (I ) annually 49 Produce (I ) annually
- These sampling stations employ continuous sampling devices which composite a 5 gallon sample each month.
(C) - control (I ) -
indicator
Fig.,4A PERRY SAMPLE LOCATION IDENTIFICATION AND SECTOR (S), DISTANCE (D) CODING ODH PNPP S D Lockwood Rd. Air Sampler Loc . # 07 07 C 0. 6 Auburn Rd. Air Sampler Loc.#06 06 K 11.0 Perry Water Sample Loc.#34 34 0 0.7 Painesville Water Sample Loc.636 36 M 3.9 Produce and Vegetables Loc.#38 38 E 1.1 Loc.#49 49 C 0. 8 Milk Loc.#31 31 F 1.4 Vegetation Loc.A'- 07 C 0. 6 Sediment - Discharge Lo.- -
5 25 R 0. 6 Fish - Dir, charge Loc.#25 25 R 0. 6
_ - ---,--r---- r-------, -
t O
em 3 ,
tr - .
s j y ,.. L; n g,.e .. a%, ,%qL 4 .,u v..o (
m >F....,1>r, -
tx ,, ;m~ -
/ %
" %kEjD L LA .
riinwr;m;r, 1\)) I%
\t g :'" n \ N G . .
b 3
/.
D W .
gf/- . , . m c 6 ".c . -
pe .
( t ~
a
~
_r -.. i s-
.gj x _-' .
v o
_,m w4 _ ,M,It :
%i .
p y t.) Y nY 3'
.p[-
s f) a, h
.iw r
[ r 1QC' 1, e
'\- W ,
El'f)7'-N g l
\4h((QG* u ew sax Iy '
I s
c
,k 9 rg(g_#$<%amQ =gg
(_'N '
L i- 3
-H .
n , ey Q ; $ y\O99iWf$j
= _
3 2 y ; ny rg) N .
g big he, .3 f
~
k *P c si
- .^Tj;
!pu 9me- ' dEm? 't ' !i s W *
-f2 I jil t[]
M
'mm y,
H "g
V' Mg.
.M e
/,,p v, ,2%, 3D u.~
t y. g ,,,, p b g+u\ ,a\
i ..
i
- y
- a. \ \sxx
[gT"\ d m m.
wp- O a c- \ M 1__3._
m i s% t1g,N s ..- - y .. e s u
W-mu
. y mfy:: d ta Rrn n 2 t
~
- xu t 4%ud 's
\, ;W. u; y gj s @y gu ,o.
w- /
..e m a wik . 3 e
p% '7.s NJ yW^ r77 7
=
\__*_ o %- -
l 3 a}L ~ 27 7 y~
S
- m_.3^'kkg s M,f'\k ,n )4 ns s
_4 ,_;_,_
m -+y ,
k A g T~ . \. .\( N N W ~
f y$
\ ' k pI, s AY I
. N @Y ,$'a M_%i.l f- , . n.t
\ .
?* ,
b s b N n j[ ,,, jy
__ g , , q g .s 1 ' ' ' '- /
l _
p s # 1-g g.-u.. :&: ._ , - . . 's - f
,,, ;g
.j i
.._,._. a tu. . _ '.-
Nat .}Ng^ ' .
m x-
.<l % hf
- l
1 t
I i
l ENVIRONMENTAL MONITORING RESULTS FOR DAVIS-BESSE NUCLEAR POWER STATION Davis-Besse Nuclear Power Station is located approximately 7 miles north of Oak Harbor, Ohio. Environmental media collected in the vicinity of this station include air, water, -
milk, sediment, vegetation and fish. Direct radiation is also measured using TLD's provided by the NRC.
/*
- )
DISCUSSION OF RP.SULTS - DAVIS-BESSE NPS Air Particulate (Tables 1 & 3 pp. 25 & 27)
The ODH and DBNPS indicator air samplers are co-located at Loca-tion #01 (Fig.3). There was fairly good agreement between the gross beta activity in air data reported for the ODH and DBNPS Location #01 with the exception of the last quarter of 1986. Both ODH and DBNPS gross beta results were slightly elevated, however DBNPS results were greater than ODH gross beta results by approximately a f actor of three.
Several of the air particulate results for Loc.#01 were elevated above the background level normally detected. These were for the sample weeks ending on 3-13 and 5-13 through 5-28. The 3-13 sample results were elevate 1 due to an unusually low volume of air drawn by the sampler.
l The 5-13 through 5-28 results were elevated due to fallout from the I accident at Chernobyl on April 26, 1986. Elevated concentrations of airborne radioactivity remained detectable up to the week of June 9 as shown by results from the control location (#25). ODH was unable to track this activity at Location #01 due to a work stoppage and picket line enforced by the IBCW union which prevented our contractor from entering the DBNPS property to collect samples. Additional problems with air sample collection occured from 8-25 through 10-06 when DBNPS had transformer failures which resulted in either low volumes or complete loss of power to the sampler.
The ODH and DBNPS maintain separate air sampling control locations.
Therefore, only ODH data for Loc. #25 is reported in Tables 1& 3.
As discussed above, elevated gross beta activity resulting from fallout was reported from 5-13 through 6-9. The unusually low gross beta activity reported on 1-13 was due to accidental damaging of the filter paper. Low volume and subsequent loss of data for the period 11-17 through 12-2 was due to the failure of the air sampler pump.
Except for the anomalous data mentioned above, there was no significant difference between the gross beta activity levels detected at the in-dicator and control locations.
Radiciodine In Air (Tables 2 & 4 pp. 26 & 28)
Several of the air iodine results reported for Loc.#01 by ODH were above background level normally reported. Increases in I-131 levels were detected in the 5-13 through 5-28 samples due to fallout from Chernobyl. DBNPS also detected I-131 during this same time period, however, DBNPS results differed from ODH results by a factor of 10.
For the sample weeks 6-2 through 6-9 no data was collected due to the work stoppage mentioned above. Similarly the anomalous and missing data for the time period 8-25 through 10-6 was due to power failures at the DBNPS site. The LLD for I-131 in air was not met for the 3-3 sample due to an unusually low volume of air collected over the sampling period.
In addition to I-131, 0.2 + 0.1 pCi/m3 of Ru-106 was detected in the 5-28 air sample at Loc.#017 This radionuclides is a fission product
I 1
l
-, Discussion of Results continued . . .
which was most likely part of the fallout from Chernobyl.
Air iodine levels were detected at the control location (#25) during-the same time period as those detected at the indicator location (#01).
For the sample week ending on 5-19 a number of radionuclides in addition to I-131 were detected. They are as follows:
Xe-133m: 0.1 + 0.1 pCi/m3 Xe-135 : 0. 09 + 0. 08 pCi/m3 Mo-90 : 0.3 + 0.3 Mo-99 : 0.01 + 0.01
~
Tc-99m : 0.2 + 0.2 Co-57 : 0.01 + 0.01 pCi/m3 Ru-106 : 0.4 + 0.2 pCi/m3 Ce-144 : 0.1 + 0.08 pC1/m3 Ra-226 : 0.08 + 0.04 pCi/m3 Except for Ra-226, which is naturally occuring, the unusual appearance of these fission and activation products in this sample on this date is most likely due to fallout from the Chernobyl accident.
Low volume and subsequent loss of data for the period 11-17 through 12-2 was due to the failure of the air sampler pump.
Except for the anomalies mentioned above, there was no significant I
difference between the air iodine results obtained at the indicator and control locations.
Air Filter Composites (Table 5 p.29)
No direct comparison can be made between analyses of ODH and DBNPS quarterly air filter composites. This due to the fact that the DBNPS composites all of their indicator locations for quarterly gamma isotopic analysis. The ODH composites filter papers from only one indicator location for gamma isotopic analysis.
Several radionuclides in addition to natuarally occuring Be-7 were reported by both ODH and DBNPS during the second quarter of 1986.
Small quantities of Cs-137 and Cs-134 were detected in the composites which included filter papers on which elevated gross beta activities were detected. The occurance of these radionuclides is attributed to fallout from the Chernobyl accident. DBNPS also detected the presence of Ru-103 and Ru-106 in the second quarter composite. ODH was not able to detect these radionuclides. The fact that DBNPS composites include
_7 all indicator locations may explain this greater sensitivity.
4 There was no significant difference between results for the indicator and control sample locations.
None of the radionuclides identified above, exceeded levels for re-lease to air in unrestricted areas as specified in 10CFR20 Appendix B, Table 2 , Column 1.
Discussion of results continued . . .
Water (Tables 6,7 & 8, pp. 30-32)
No direct comparison can be made between the monthly gamma isotopic analysis data for water samples collected by the ODH and DBNPS at indicator Loc.#3. This is due to the fact that the DBNPS does not perform monthly gamma isotopic analysis on split samples collected at DBNPS locations T-28 and T-3. Quarterly gamma isotopic analyses are performed however.
During the months of January through April 1986, the indicator water samples were collected at DBNPS Loc. T-50 instead of Loc. T-28. DBNPS does perform gamma isotopic analyses on monthly composites from T-50.
From May through December the samples were collected at DBNPS Loc. T-3.
The only gamma emitting radionuclides in water reported by DBNPS for either location was Cs-137. All results were reported as < 10 pCi/1.
All results reported by ODH for this radionuclides were < 4 pCi/1.
The ODH Laboratory reported results for the radionuclides K-40, I-131, Cs-137, Cs-134, and Ba-140. As can be seen in Table 7 a trace of I-131 was detected in the May water sample from Loc. # 3. Small amounts of Ru-106 and Cr-51 were also reported for the January and April samples respectively.
At control Loc.#25 the presence of Mo-99, Tc-99m and I-133 and naturally occuring U-235 were reported for various samples. These radionuclides l were not reported by DBNPS and were not detected in the indicator water samples.
It was noted that the ODH Laboratory was able to meet the LLD require-l ment of 1 pCi/1 I-131 in water for most of 1986.
There was good agreement between ODH and DBNPS on the H-3 analysis of quarterly composites of untreated surface water samples at both the indicator and control locations. No quantities of H-3 above the ODH and DBNPS lower limits of detection were reported.
None of the radionuclides identified above, exceeded levels for release to water in unrestricted areas as specified in 10CFR20 Appendix B, Table 2 , Column 2.
Fish (Table 9, p.33)
There was generally good agreement between levels of Cs-137 and K-40 in fish reported by the ODH and DBNPS for both indicator and control sampling locations. An exception to this occurs for the analysis of the white bass sample taken on 5-27 at Loc.#28-5. A small amount of Cs-137 above the DBNPS's LLD was detected by ODH.
There was no significant difference in radioactivity levels in fish caught within 5 miles and outside 10 miles of the DBNPS in 1986.
/ .
Discussion of results continued . . .
Milk (Table 10, p.34)
The results of the radiciodine and gamma isotopic analyses of milk ,
samples reported by ODH and DBNPS were in fairly good agreement. In addition to naturally occurring K-40, small quantitiles of I-131 were detected by DBNPS in the 5-14, 5-19 and 6-9 milk samples. This activity was due to fallout resulting from the Chernobyl accident. ODH reported ,j.
the presence of several additional radionuclides in the July and August ' -1 milk samples. These included Cd-113m, Ru-106, Mo-99, and Ra-226.
During 1986, the ODH Laboratory was not able to meet the required LLD for I-131 in milk. This prevented ODF from detecting the presence of ,
the I-131 detected by DBNPS in their analyses.
Produce (Table 11, p.35) l There was generally good agreement between the ODH and DBNPS results .
Other gamma emitting radionuclides detected by the ODH Laboratory in several samples were Be-7, Cs-137 and I-131. ODH reported the detec-tion of Cs-137 in the apple sample collected on 7-21 and I-131 in the lettuce sample collected on 8-18. No corresponding activities were reported by DBNPS. The presence of I-131 in the lettuce sample in particular could not be confirmed by DBNPS as it was not a split sample.
As noted in Table 11, in this one instance DBNPS collected broccoli and ODH collected lettuce due to a small supply of broccoli.
The presence of Xe-131m was reported for the 10-14 pear sample. The report of this radionuclides in such quantity on the multi-channel analyzer printout is most likely the result of the software program .-
parameters used by ODH. Xe-131m is a fission gas and would not be -
detected in this type of sample.
It was noted that the ODH Laboratory did not meet the required LLD for I-131 in produce for the 10-14 cabbage sample and the 8-18 cabbage sample.
Bottom Sediment (Table 12, p.36)
There was fairly good agreement between the K-40 and Cs-137 data re-ported by the DBNPS and the ODH. In addition to these radionuclides, the presence of naturally occurring Th-234 was reported in the 10-25 sediment sample taken in the vicinity of the DBNPS discharge. As dis-cussed above, it is possible that existence of this radionuclides in this quantity may be a result of the MCA's programmed counting par-l ameters. The gamma energies associated with Th-234 are very low '. .
energy and have very small abundances.
A 0 value for K-40 was reported for the 10-25 sample taken in the '
vicinity of the discharge. The ODH Lab could provide no explanation for this lack of normal K-40 activity. ;
l I i
Discussion of results continued . . .
No significant differences between results for the indicator and control locations were noted for the radionuclides K-40 and Cs-137.
Direct Radiation (Table 13, pp. 37-43)
Direct radiation in the environment was measured using TLD's. These-TLD's were changed on a quarterly basis. Over the time period 3-85 to 7-86 ambient radiation exposure rates measured at various locations in the vicinity of DBNPS ranged from 10.8 - 25 .4 mR/ standard quarter.
The annual average exposure measured at each location was comparable to the average exposure that would be expected from background sources of radiation. Background scurces of radiation are cosmic rays and radio-nuclides in the earth's crust.
1
g.
'.y _
A> AIR PARTICULATE- TABLE 1 Davis-Besse Nuclear Power' Station f January : December 1986 3.- ODH Location 101 / DBNPS T-1 DATE STATE RESULTS DBNPS RESULTS
-Gross Beta (pCi/m3) Gross Beta-(pci/m3) 01-06 0.01 +/- 0.002 0.024 +/- 0.004 01-13 0.01 +/- 0.001 0.015 +/- 0.003 01-20 0.01 +/- 0.002 0.025 +/- 0.004 01-27 0.01 +/- 0.002 0.026 +/- 0.004 02-03 0.01 +/- 0.002 0.021 +/- 0.004 02-10 0.01 +/- 0.001 0.017 +/- 0.003 02-19 'O.01 +/- 0.002 0.035 +/- 0.004 02-25 0.01 +/- 0.002 0.027 +/- 0.004 03-03 0.11 +/- 0.22
- 0.027 +/- 0.004 03-11 0.01 +/- 0.001 0.015 +/- 0.003 03-17 0.01 +/- 0.002 0.011 +/- 0.003 03-24 0.01 +/- 0.001 0.016 +/- 0.003 04 0.01 +/- 0.001 0.019 +/- 0.003 04-07 0.01 +/- 0.001 0.012 +/- 0.004 04-14 0.01 +/- 0.001 0.012 +/- 0.002 04-21. 0.01 +/- 0.002 0.012 +/- 0.003 04-28 0.01 +/- 0.002 0.021 +/- 0.003
- 05-05 0.01 +/- 0.001 0.019 +/- 0.003 05-13 0.07 +/- 0.004 0.085 +/- 0.006 05-19 0.066 +/- 0.004 0.136 +/- 0.007 05-28 0.063 +/- 0.003 0.159 +/- 0.007 06-02 Unable to Collect Data No Collection due to work stoppage 06-09 Unable to Collect Data 0.118 +/- 0.005 06-16 0.02 +/- 0.002 0.023 +/- 0.003 06-23 0.01 +/- 0.002 0.022 +/- 0.003' 06-30 0.01 +/- 0.001 0.018 +/- 0.003 07-07 0.01 +/- 0.001 0.020 +/- 0.003 07-14 0.01 +/- 0.001 0.019 +/- 0.003 07-21 0.01 +/- 0.001 0.018 +/- 0.003 07-28 0.01 +/- 1.002 a.024 +/- 0.004 08-04 0.01 +/- 0 ,. 0 5 < 0.018 +/- 0.003 l
08-11 0.01 +s 0.002 0.029 +/- 0.004 08-18 0.01 +/- '6> 0.032 +/- 0.004 08-25 0.01 +/- u.v23 1 0.019 +/- 0.006
- 09-02 0.01 +/- 0.008
- 0.044 +/- 0.023
- 09-08 Air Sampler Down No data due to pump malfunction 09-15 Air Sampler Down No data due to pump malfunction 09-22 Air Sampler Down 0.027 +/- 0.005
- 09-29 Air Sampler Down 0.022 +/ -0.004 10-06 Air Sampler Down 0.010 +/- 0.003 10-14 0.01 +/- 0.001 0.026 +/- 0.004 10-20 0.01 +/- 0.002 0.017 +/- 0.003 y 10-27 0.02 +/- 0.002 0.057 +/- 0.004 11-03 0.01 +/- 0.002 0.035 +/- 0.004 11-10 0.01 +/- 0.002 0.027 +/- 0.004 11-17 0.01 +/- 0.001 0.036 +/- 0.004 11-24 0.01 +/- 0.001 0.037 +/- 0.004 12-02 0.01 +/- 0.002 0.033 +/- 0.004 12-08 0.01 +/- 0.002 0.027 +/- 0.004 12-15 0.02 +/- 0.002 0.032 +/- 0.004 12-22 0.02 +/- 0.002 0.046 +/- 0.005 12-29 0.02 +/- 0.002 0.068 +/- 0.005
- Low volume _ __ - - - _ - _ - - _ _ _ -
AIR IODINE TABLE 2 Davis-Besse Nuclear Power Station January - December 1986 ODH Location #01 / DBNPS T-1 DATE STATE RESULTS DBNPS RESULTS pCi/m3 pCi/m3 01-06 < 0.04 All results < 0.07 pC1/m3 01-13 < 0.04 unless otherwise noted 01-20 < 0.04 01-27 < 0.04 02-03 < 0.04 02-10 < 0.04 02-19 < 0.04 02-25 < 0.04 03-03 < 8.5
- 03-11 < 0.04 03-17 < 0.04 03-24 < 0.04 04-01 < 0.04 04-07 < 0.04 04-14 < 0.04 04-21 < 0.04 04-28 < 0.04 05-05 < 0.04 05-13 0.07 +/- 0.02 05-19 0.08 +/- 0.02 0.70 +/- 0.11 05-28 0.03 +/- 0.01 0.31 +/- 0.04 06-02 Unable to Collect Data No collection due to work stoppage 06-09 Unable to Collect Data < 0.08 Delay in counting 06-16 < 0.04 06-23 < 0.04 06-30 < 0.04 07-07 < 0.04 07-14 < 0.04 07-21 < 0.04 07-28 < 0.04 08-04 < 0.04 08-11 < 0.04 08-18 < 0.04 08-25 0. 0 5 + /- 0. 0 3 * < 0.10 Low Volame 09-02 0.3 +/- 0.1 * < 0.19 Low Volume 09-08 Air sampler down No data due to pump malfunction 09-15 Air. sampler down No data due to pump malfunction 09-22 Air sampler down 09-29 Air sampler down 10-06 Air sampler down 10-14 < 0.04 10-20 0.04 +/- 0.02 10-27 < 0.04 11-03 < 0.04 11-10 < 0.04 11-17 < 0.04 11-24 < 0.04 12-02 < 0.04 (2-08 < 0.04 12-15 < 0.04 12-22 < 0.04 12-29 < 0.06
- Low Volume AIR PARTICULATE TABLE 3 Davis-Besse Nuclear Power Station January - December 1986 0DH Location #25 DATE. STATE RESULTS DBNPS RESULTS Gross Beta (pci/m3) 01-06 0.01 +/- 0.002 Loc.# 25 is the ODH control 01-13 0.0004 +/-0.0006
- location. DBNPS does not 01-20 0.01 +/- 0.002 have an air sampler co-located 01-27 0.01 +/- 0.002 at this location.
02-03 0.01 + /- 0. 002 02-10 0.01 +/- 0.002 02-19 0.01 +/- 0.002 02-25 0.01 +/- 0.002 03-03 0.01 +/- 0.002 03-11 0.01 +/- 0.001 03-17 0.01 +/- 0.002 03-24 0.01 +/- 0.001 04-01 0.01 +/- 0.001 04-07 0.01 +/- 0.002 04-14 0.01 +/- 0.001 04-21 0.01 +/- 0.002 04-28 0.01 +/- 0.002 05-05 0.01 +/- 0.002 05-13 0.024 +/- 0.003 05-19 0.073 +/- 0.004 05-28 0.089 +/- 0.004 06-02 0.05 +/- 0.004 06-09 0.086 +/- 0.005 06-16 0.01 +/- 0.002 06-23 0.01 +/- 0.002 06-30 0.01 +/- 0.001 07-07 0.01 +/- 0.001 07-14 0.01 +/- 0.002 07-21 0.01 +/- 0.001 07-28 0.01 +/- 0.002 08-04 0.01 +/- 0.002 08-11 0.01 +/- 0.002 08-18 0.01 +/- 0.002 08-25 0.01 +/- 0.002 09-02 0.01 +/- 0.001 09-08 0.01 +/- 0.002 09-15 0.01 +/- 0.002 09-22 No Data, Pump inadvertently not restarted after 9-15 changeout 09-29 0.01 +/- 0.002 10-06 0.01 +/- 0.001 10-14 0.01 +/- 0.001 10-20 0.01 +/- 0.002 10-27 0.02 +/- 0.003 11-03 0.01 +/- 0.002 11-10 0.01 +/- 0.002 11-17 0.01 +/- 0.01 **
11-24 No Data due to pump malfunction 12-02 No Data due to pump malfunction 12-08 0.01 +/- 0.002 12-15 0.01 +/- 0.002 12-22 0.01 +/- 0.002 12-29 0.02 +/- 0.002
- Anomalous data due to damaged filter paper _ g7 _
- Low volume
AIR IODINE TABLE 4 Davis-Besse Nuclear Power Station January - December 1986 ODH Location #25 DATE STATE RESULTS DBNPS RESULTS pCi/m3 01-06 < 0.04 Loc.#25 is an ODH control 01-13 < 0.04 location. DBNPS does not 01-20 < 0.04 have an air sampler co-located 01-27 < 0.04 at this location.
02-03 < 0.04 02-10 < 0.04 02-19 < 0.04 02-25 < 0.04 03-03 < 0.04 03-11 < 0.04 03-17 < 0.04 03-24 < 0.04 04-01 < 0.04 04-07 < 0.04 04-14 < 0.04 04-21 < 0.04 04-28 < 0.04 05-05 < 0.04 05-13 < 0.04 05-19 0.1 +/- 0.02 (See p.21 of Conclusions for additional 05-28 0.05 +/- 0.01 radionuclides detected) 06-02 < 0.04 06-09 < 0.04 06-16 < 0.04 06-23 < 0.04 06-30 < 0.04 07-07 < 0.04 07-14 < 0.04 07-21 < 0.04 07-28 < 0.04 08-04 < 0.04 08-11 < 0.04 08-18 < 0.04 08-25 < 0.04 09-02 < 0.04 09-08 < 0.04 09-15 < 0.04 09-22 No data, Pump inadvertently not restarted after 9-15 changeou?
09-29 < 0.04 10-06 < 0.04 10-14 < 0.04 10-20 < 0.04 10-27 < 0.04 11-03 < 0.04 11-10 < 0.04 11-17 < 0.04
- 11-24 No data due to pump malfunction 12-02 No data due to pump malfunction 12-08 < 0.04 12-15 < 0.04 12-22 < 0.04 12-29 < 0.07 **
- Low volume ** LLD not attained due to delay in counting
QUARTERLY GAMMA ISOTOPIC ANALYSES OF AIR FILTER PAPER COMPOSITES Davis-Besse Nuclear Power Station TABLE 5 January -
December 1986 ODH QUARTERLY COMPOSITES (pCi/m3)
Loc.# 01 Jan - March Apr - June July - Sept Oct - Dec
\
Be-7 0.030+0.010 0.060+0.050 0.020+0.010 0.40 + 0.20 K-40 ND ND ND ND Nb-95 ND ND ND ND Zr-95 ND ND ND ND Ru-103 ND ND ND ND Ru-106 ND ND ND ND Cs-134 ND 0.004+0.001
- ND ND Cs-137 ND 0.008[0.001
- ND ND Ce-141 ND ND ND ND Ce-144 ND ND ND ND Loc.# 25 Jan - March Apr - June July - Sept Oct - Dee Be-7 0.030+0.010 0.030+0.040 0.050+0.010 0.50 + 0.20
[ K-40 ND ND ND ND Nb-95 ND ND ND ND Zr-95 ND ND ND ND Ru-103 ND ND ND ND Ru-106 ND ND ND ND Cs-134 ND 0.003+0.001
- ND ND Cs-137 ND 0.005+0.001
- ND ND Ce-141 ND ND ND ND Ce-144 ND ND ND ND DBNPS DATA COMPOSITE OF ALL INDICATOR LOCATIONS T-1,2,3,4,7 and 8 Jan - March Apr - June July - Sept Oct - Dec Be-7 0.053+0.002 0.098+0.006 0.097+0.005 0.043+0.002 K-40 < 0.0055 0.014+0.003 < 0.0060 0.0044+0.0012 Nb-95 < 0.0002 < 0.0006 < 0.0005 < 0.0002 Zr-95 < 0.0004 < 0.0010 < 0.0008 < 0.0004 Ru-103 < 0.0003 0.012+0.00l*
< 0.0004 < 0.0003 Ru-106 < 0.0003 0.012+0.00l* < 0.0004 < 0.0003
) Cs-134 < 0.0002 0.008570.0005* < 0.0004 < 0.0002 Cs-137 < 0.0003 0.0157_0.001* < 0.0004 < 0.0002 Ce-141 < 0.0003 < 0.0007 < 0.0004 < 0.0004 Ce-144 < 0.0006 < 0.0013 < 0.0010 < 0.0012
- Elevated activity due to radioactive fallout from Chernobyl accident.
b i
0-
'RADI0 IODINE AND GAMMA ISOTOPIG ANALYSIS TABLE 6 E OF. MONTHLY COMPOSITE WATER-SAMPLES-Davis-Besse Nuclear Power Station? #
January - December 1986: k ODH Loc.# 3 / DBNPS T-3, ',,
- 50-/ DBNPS T-50' i
r ODHLDATA Loc.#50 & 3- (pci/l i 2 sigma error)
L F
DATE- K-40 I-131 Cs-137 Cs-134 Ba-140 Other 101-27-86'* < 22 '< 3 <2 <2 <9 Ru-106 611' 02-25-86
- 13168 < 1 <4- <-4 < 14 03-24-86 *- <.38 <1 <4 .<4 < 14
'04-28-86
- 23+40 < 1- <4 <4 < 14 Cr-51 6+1.5 l 19+63
~
05-28-86 1.35+0.75 <4 <4 < 20 ,
l 06-23-86 '39+65 < 1 <4 <4 < 14 (
28 79+33 <1 <4 <4 < 14 08-25-86: 17T65'
~
<1 <4 -< 4' < 14 09-22-86 49+35 <1 <4 <4 < 22 j 10-27-86' < 26 <2 <4 <4 < 14 E
11-24-86' 50+30. <1 <4 <4 < 14 .,
22-86 '6728- <2 <4 <4 < 14 l l-Note: Radionuclides-other than those reported were not detected. j
. . 1 e
DBNPS-DATA -Loc. T-50 & T-3 The only gamma-emmitting. emitting radionuclides reported by DBNPS was Cs-137. No radioiodine results are reported for any water samples. !
-\
Cs-137:
Jan-April T-50 All results < 10 pCi/1.
-May-Dec. T-3 ** Cs-137: All results < 10 pCi/1. e
'* From Jan'-Apr, water samples were collected at Loc.#50. From May-Dec water samples were collected at Loc.#03. ,
- DBNPS does not perform monthly radioiodine and gamma analyses on i(
samples from Loc. T-3. The analyses are performed quarterly.
a s
30 -
RADIOIODINE'AND GAMMA ISOTOPIC ANALYSIS TABLE 7 0F MONTHLY COMPOSITE WATER SAMPLES Davis-Besse Nuclear Power Station January -
December 1986 ODH Loc.#27 / DBNPS T-11 ODH DATA Loc.#27 (pC1/1 1 2 sigma error)
__ DATE K-40 1-131 Cs-137 Cs-134 Ba-140 Other 01-27-86 < 21 <3 <4 <4 < 14 02-25-86 4+26 <1 <4 <4 < 14 03-24-86 21734 < 1 <4 <4 < 14 04-28-86 78738 < 1 <4 <4 < 44 05-28-86 2762
~
<1 <4 <4 < 18 06-23-86 < 46 Not Reported <4 <4 < 14 07-28-86 <45 <1 <4 <4 < 14 08-25-86 24+66 < 7 <4 < 4 < 14 08-25-86 21{71 Not Reported <4 <4 < 18 U-235 22121 09-22-86 79'+44
< 1 <4 <4 < 14 10-27-86 < 28 <2 <4 <4 < 14 11-24-86 2+30 <2 <4 <4 < 14 12-22-86 4[21 <2 <4 <4 < 14 U-235 48122 Other radionuclides r e p o r t. e d : 12-22-86: Mo-99 8 1 3 pCi/1 Tc-99m 571 1 261 pCi/1 I-133 7 1 6 pCi/1 DBNPS Loc. T-11 The only gamma-emmitting radionuclides reported by DBNPS was Cs-137.
No radioiodine results are reported for any water samples.
Jan-Dec. T-11
- Cs-137: All results < 10 pCi/1.
- DBNPS does not perform monthly radioiodine and gamma analyses on samples from Loc. T-11. The analyses are performed quarterly.
l I
l 1
TRITIUM ANALYSIS OF QUARTERLY. COMPOSITES 0F UNTREATED SURFACE WATER SAMPLES TABLE 8 Davis-Besse. Nuclear Power Station January - December 1986 ODH Loc. #3 / DBNPS Loc. (T-3) & T-50 ODH Loc. # 27 LOCATION DATE ODH RESULTS DBNPS RESULTS (pCi/1 + 2 sigma) (pci/1)
H-3 H-3 ODH T-50 Jan-Mar * < 1500 < 330 a ODH T-50/#3 Apr-Jun ** < 1500 < 330 a ODH #3 July-Sept < 1500 < 330 ODH #3 Oct-Dec < 1500 < 330 ODH #27 Jan-Mar < 1500 < 330 Apr-Jun < 1500 < 330 July-Sept < 1500 < 330 Oct-Dec < 1500 < 330
- From January to April, water samples were taken at Erie Industrial Park (T-50).instead of Loc. #3.
- From May through December, water sample collection was resumed at Loc. #3.
a DBNPS T-50 is not compoeited quarterly. It is composited monthly from weekly samples. All monthly composites were < 330 pCi/1.
L______ ________ --_-- J
l CAMMA ISOTOPIC ANALYSIS OF RADIONUCLIDES IN FISH TABLE 9 Davis-Besse Nuclear Power Station l January - December 19S6 I I
Location #28-5 (T-33) Inside 5 mi.
- 28-10 (T-35) Outside 10 mi.
t ODH DATA (pC1/kg + 2 sigma error) l 5-27-86 5-27-86 10-25-86 10-25-86
., Loc.#28-5 Loc.#28-10 Loc.#28-5 Loc.#28-10 Walleye /Wh. Bass Walleye /Wh. Bass Walleye /Wh. Bass Walleye /Wh. Bass ;
Cs-137 13+9 15+12 < 30 < 30 < 30 < 30 < 30 < 30 Cs-134 < TO < Y0 < 20 < 20 < 20 < 20 < 123 < 20 Mn-54 <20 < 20 < 20 < 20 < 20 < 20 < 20 < 24 Fe-59 < 52 < 70 < 65 <42 < 280 < 130 < 155 < 159.
Co-58 < 20 < 23 < 20 < 20 23 < 37 < 30 < 40 Co-60 < 30 < 30 < 30 < 30 <40 < 30 < 30 < 30 Zn-65 <40 < 40 < 40 <40 < 40 < 40 < 40 < 54 K-40 1700+232 2044+280 1656+262 985+191 1666+267 2664+369 2770+370 19 61 + 3 f.
y Wh. Bass - White Bass Note: Radionuclides other than those reported were not detected.
DBNPS DATA (pCi/kg wet)
I Loc.T-33 Loc.T-35 Loc.T-33 Loc.T-35 5-27-86 05-27-86 10-25-86 10-25-86 Walleye /Wh. Bass Walleye /Wh. Bass Walleye Wh. Bass Walleye /Wh. Base Cs-137 < 16 < 10 < 22 < 29 < 37 < 24 < 25 < 27 K-40 2930+140 2610+220 2160+190 3030+210 2910+250 2940+230 3480+220 1900+30r s
DBNPS T-33: Lake Erie 1.5 mi. NE of station T-35 Lake Erie 15 mi. NE of station F.
o __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - . . _ _-._____-___ _ ____________________ __________ ___ ___ _ _ _
r-_--- ,
'r t
i RADI0 IODINE AND GAMMA ISOTOPIC ANALYSIS OF MILK TABLE 10 k Davis-Besse Nuclear Power Station i January - December 1986 ODH Loc.#23 / DBNPS T-8 (EARL MOORE FARM)
+
ODH DATA (pCi/1 + 2 sigma error) l Date I-131 K-40 Cs-134 Cs-137 Ba-La-140 01-20-86 < 2. 5 1309 + 78 <4 <4 < 14 02-19-87 < l.8 1269 I 53 <4 <4 < 14 03-17-86 < l.9 1246 I 55 <4 <4 < 14 04-07-86* < 34 1311 7 56 <4 <4 < 38 05-19-86 <4 1431 I 81 <4 <4 < 14 06-09-86 <3 1320 I 78 <4 <4 < 14 07-21-86 < 2 1280 I 62 <4 <4 < 14 08-18-86 <2 1390 I 58 <4 <4 < 14 09-15-86 <5 1516 7 66
~
<4 <4 < 14 10-20-86 <2 1303 + 58 <4 <4 < 14 11-10-86 <3 1348 + 60
~
<4 <4 < 14 12-01-86 <3 1354 + 63 <4 3+2 < 8 NOTE: Other radionuclides detected: '
On 7-21: Cd-113m 757+111 pCi/1, Ru-106 17+16 pCi/1, On 8-18: Mo-99 2+2 pCi/1, Ra-226 5+4 pCi/1.
c Milk sample for 4-07-86 was not true split. DBNPS collected the #
April sample on 4-14-86.
DBNPS DATA 01-20-86 < 0.5 1240 + 140 < 10 < 10 02-19-86 < 0.4 1320 I 60 < 10 < 10 g 03-17-86 < 0.4 1620 7 40 < 10 < 10 04-14-86 < 0.2 1320 I 70 < 10 < 10 05-14-86 a 2.0 + 0.3 1240 7 30 < 10 < 10 05-19-86 a 1.2 I 0.1 1420 I 40 < 10 < 10 06-09-86 a 0.770.3
~
1240 I 5 < 10 < 10 06-23-86 <04 1220 I 30 < 10 < 10 07-07-86 < 0.4 1100 I 80 < 10 < 10 07-21-86 < 0.4 1270 7 70 < 10 < 10 08-04-86 < 0.5 1150 7 130 < 10 < 10 08-18-86 < 0.3 1210 7 100 < 10 < 10 09-03-86 < 0.3 1310 7 100 < 10 < 10 09-15-86 < 0.2 1370 I 80 < 10 < 10 10-06-86 < 0.2 1430 7 80 < 10 < 10 10-20-86 < 0.2 1210 1 130 < 10 < 10 11-10-86 < 0.4 1640 + 180 < 10 < 10 12-01-86 < 0.3 1300 [ 140 < 10 < 10 a Elevated I-131 activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April 26, 1986.
RADI0 IODINE AND GAMMA ISOTOPIC ANALYSIS OF RADIONUCLIDES IN PRODUCE Davis-Besse Nuclear Power Station TABLE 11 January - December 1986 Loc.#24 (T-25) Miller's Farm ODH DATA (pCi/kg (wet) 1 2 sigma error)
Sample Date I-131 Cs-137 Cs-134 K-40 Other Apples 7-21-86 < 33 7. 0+4. 0 <8 14901129 Mo-99 1251118 Pears 7-21-86 < 35 5.0+5.0 < 8 1357+125 Pears 10-14-86 185+366 5.077.0
~
< 11 1431I143
~
Xe-131m 3875+329 Plums 10-14-86 <I 4.018.0 616 1715+1542
~
Broccoli 7-21-86 < 34 < 9.0 < 12 3798+235 Be-7 146+111 Potatos* 7-22-86 90+118 < 9.0 < 12 51507245 Ba-140 29+84 Lettuce 7-21-86 < 12 3.0+4.0
~
<6 29297136
~
Be-7 7 9+4 6 Ba-140 T0+17 Lettuce ** 8-18-86 211+193 < 6.0 < 10 2583+169 Be-7 271+88-Cabbage 8-18-86 < 83 < 4. 0 <6 1952I114 Cabbage 9-08-86 < 11.5 < 2.8 <4 1403172 Cabbage 10-14-86 < 326 < 6.0 <9 162911.0 Sw. Pot.Tps.9-08-86 < 31 < 7.0 < 10 55831204 Be-7 273171 Tomatoes 20-14-86 <4 <6 <1 2879+171 DBNPS DATA Fruit & Vegetable Samples (pCi/kg wet)
Sample Date Zr-95 Cs-137 Ce-141 K-40 Ce-144 Nb-95 Ru-10e Apples 7-21-86 < 34 <23 < 16 21001210 < 61 < 17 < 150 Pears 7-21-86 < 44 <23 < 20 2130+250 < 84 < 24 < 250 Pears 10-14-86 < 11 < 6 < 13 970750 <48 <7 < 52 Plums 10-14-86 <43 < 23 <44 1630I180 < 120 <27 < 200 Broccoli 7-21-86 <43 < 24 < 57 45607450 < 260 < 24 < 230 Potatoes 7-21-86 <49 <23 < 19 52007340 < 82 < 21 < 180 Cabbage 10-14-87 < 12 < 7 < 12 1860_I150 < 52 <7 < 61
.1 Tomatoes 10-14-86 < 12 <7 < 13 2220+70 < 39 < 7 < 55
\
! Green Leafy Vegetables I-131 Cs-137 Ce-141 K-40 Ce-144 Nb-95 Zr-95 Lettuce 7-21-86 < 12 < 16 < 22 4740+200
~
< 93 < 13 < 24 Broccoli 8-18-86 < 12 < 13 < 16 3700+280 < 72 < 12 < 21 1
Cabbage 8-18-86 < 31 < 22 < 27 2830+380 < 100 < 25 < 39 i Cabbage 9-08-86 < 14 < 11 < 1 2870+150 < 65 < 9 < 18 f Sw. Pot.Tps. 9-08-86 < 13 < 12 < 18 5160+340 < 85 < 13 < 21 A
GAMMA ISOTOPIC ANALYSIS OF BOTTOM SEDIMENT TABLE 12 Davis-Besse Nuclear Power Station January - December 1986 ODH Loc.# 29/DBNPS T-29 (vicinity of intake) 30/DBNPS T-30 (vicinity of discharge)
ODH DATA (pCi/kg + 2 sigma error)
Loc. #29 Loc. #30 Loc. #29 Loc. #30 (Intake) (Discharge) (Intake) (Discharge) 5-27-86 5-27-86 10-25-86 10-25-86 Cs-137 < 93 < 90 < 106 < 90 Cs-134 < 110 < 110 < 110 < 110 K-40 18010 + 1500 12760 + 1372 18640 + 2274 0.0 + 0 Ra-226 898 + 182 706 + 185 906 + 265 493 + 172 Additional radionuclides reported:
10-25-86 Intake: Hg-203 536 + 419 pCi/kg 10-25-86 Discharge: Th-234 289,100 + 1392 pC1/kg DBNPS DATA (pCi/kg dry)
T-29 T-30 T-29 T-30 (Intake) (Discharge) (Intake) (Intake) 5-27-86 5-27-86 10-25-86 10-25-86 Cs-137 < 34 < 25 <49 < 26 l
K-40 19190 + 510 _
15060 + 370 20070 + 650 9320 + 320 NOTES: DBNFS data was reported as pCi/g. This has been converted to pCi/kg for comparison with ODH data.
Intake Location - See Fig. 3A Discharge Location - See Fig. 3A
f, k
f DIRECT RADIATION MONITORING KETWORK TABLE 13 f DATA EXCERPTED FROM NUREG-0837
?
I y preface f
The U. S. Nuclear Regulatory Commission (NRC) Direct Radiation Monitoring l Network is operated by the NRC in cooperation with participating states to pro-f vide continuous measurement of the ambient radiation levels around licensed NRC f facilities, primarily power reactors. Ambient radiation levels result from
[ naturally occurring radionuclides present in the soil, cosmic radiation con-
! stantly bombarding the earth from outer space, and the contribution, if any, 8
5 from the monitored facilities and other man-made sources. The Network is in-tended to measure radiation levels during routine facility coerations and to f establish background radiation levels used to assess the radiological impact
-f of an unusual condition, such as an accident. This report presents the radia-tion levels measured around all facilities in the Network for the second quarter of 1985. A complete listing of the site facilities monitored is included. In
, some instances, two power reactor fa>-ilities are monitored by the same set of I
dosimeters (e.g., Kewaunee and Point Beach).
All radiation measurements are made using small, passive detectors called thermoluminescent dosimeters (TLDs), which provide a quantitative measurement of the radiation levels in the area in which they are placed. Each site is monitored by arranging approximately 40 to 50 TLD stations in two concentric rings extending to about five miles from the facility. All TLD stations are outside the site boundary of the facility. A complete description of the pro-gram can be found in NUREG-0837, Volume 2, Number 4 and NUREG-0837, Volume 3, Number 4. The National Bureau of Standards (NBS) has been performing an inde-pendent study of the following characteristics of the NRC dosimetry system; energy response, angular dependence, temperature and humidity sensitivity, fading, light dependence, self-irradiation, and reproducibility. NBS has also tested the response of the NRC's dosimetry system against the requirements of ANSI N545-1975 and NRC Regulatory Guide 4.13. Details of this testing can be found in NUREG/CR-2560, NUREG/CR-3120, and NUREG/CR-3775.
The radiation levels are presented as gross and net exposures. The gross ex-posure includes naturally occurring background radiation, radiation levels resulting from a facility's o;ieration, and the exposure received during trans-port and storage of the TLD. Net exposures are obtained by subtractir.g an esti-mate of the exposure received by the dosimeter during transit from the gross exposures. .All exposures are normalized to a 90-day quarter (standard quarter) and reported in units of milliroentgen (mR). Station numbers for which no data are reported included stations which have been deleted, stations for which the TLD was lost during the quarter, or stations for which the TLD was damaged.
When control dosimeter data are unavailable, no net exposures are calculated.
Three sets of data are presented for each site. The first set-includes the TLD station number, its direction and distance from the site, the integrated gross exposure for the period, and the net exposure normalized to a 90-day quarter 1 (standard quarter). All measurements are listed with their respective randem
{ and total uncertainties.
l
\
I t.
{ ~ 37 -
J - - - - . - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - -- - --
i TW uncertainties are listed in the following format:
X S;U x x
where X = value of the result S = random uncertainty expressed as one standard deviation x
U, = combined total uncertainty The second set of data summarizes the average net exposure measured in each of the 16 standard windrose sectors around the facility, normalized to a standard quarter. The third set of data summarizes the average not exposure measured at three ranges of distances from the facility, normalized to a standard quarter; When average net exposures cannot be reported because of the unavailability of the site's control dosimeters, the average gross exposures,' normalized to a standard quarter, are reported in these two sets of data, The "std.dev." :re-fers to the standard deviation of the measurements made in each sector and 5 range, respectively.
Maps indicating the measured doses around a site are presented in this report.
Due to the constraints of digitizing the entire monitoring area onto the limited , space orf the map, some TLD data are not included.
This report is one of a continuing series of technical reports covering the results and experiences of the operation .of the NRC TLD Direct Radiation Monitoring Network. Suggestions on methods to improve the presentation or analysis of the data contained in this NUREG are appreciated and should be sub-mitted to NRC Region I, 631 Park Avenue, I!ing of Prussia, Pennsylvania 19406, ATTN: ' Radiation Dosimetry Specialist: ~ '
L L___________________________________________________ _ _ _____ _ _ _ _ _ _ _ _ _ ____
1 DIRECT RADIATION TABLE 13 I
i DAVIS BESSE 1 TLD DIRECT RAIIATION ENVIRONMENTAL MONITORING FOR THE PERIOD 850313-850715 125 DAYS l FIELD TIME 102 DAYS '
HRC LOCATION GROSS HET EXPOSURE RATE STATION AZIMUTH /DIST EXPOSURE (mR) mR/St d. Qt r.
4 (deg.) (mi.) +- Rdm; Tot. +- Rdm 12.6 + ; Tot.
t 001 50 0.6 15.9 +- .5 ; 2.4 .5 ; 4.7 ,
.5 ; .5 ;
002 86 0.9 15.9 + . 2.4 12.6 +- 4.7 1 003 116 1.4 16.0 +- .5* 2.4 12.7 +- .5 ; 4.7 004 172 0.8 MISSINGORDAbAGEDDOSIMETER
, 005 200 1.5 21.5 +- .6; 3.2 17.5 +- .6 ; 5.0 1 006 226 1.0 19.8 +- .6 ; 3.0 16.1 +- .6 ; 4.9 i j 007 249 1.5 20.8 +- .6 ;- 3.1 16.9 +- .6 ; 5.0 a 008 267 1.8 22.2 +- .7 ; 3.3 18.2 +- .6
.6 ;
5.1 i 009 285 1.8 21.8 +- .7 ; 3.3 17.8 +- 5.1 010 306 1.5 19.0 +- .6 ; 2.9 15.3 +- .6 ;; 4.9
}3 011 344 0.9 17.1 +- .5 ; 2.6 13.6 +- .5 ; 4.7
{ 012 142 4.5 21.0 +- .6 ; 3.1 17.1 +- .6 ; 5.0 j 013 158 4.0 23.6 +- .7 ; 3.5 19.4 +- .7 ; 5.2 2 014 180 3.8 20.0 +- .6 ; 3.0 16.2 +- .6
.6 ;
4.9 i 015 207 4.8 19.9 +- .6 3.0 16.1 +- 4.9 016 225 4.5 19.8 +- .6 ; 3.0 16.1 +- .6 ; 4.9 l .7 ;; .7 ;;
- 017 254 2.7 24.1 +- 3.6 19.8 +- 5.2 1 018 269 3.0 27.1 +- .8 ; 4.1 22.5 +- .8 ; 5.5 i 019 295 5.3 22.4 +- .7 ; 3.4 18.3 +- .6 ; 5.1 l 020 25 0.5 15.7 +- .5 ; 2.3 12.4 +- .5 ; 4.7 1 021 -
132 9.7 19.4 +- .6 ; 2.9 15.7 +- .6
.6 ;; 4.9
(
022 210 6.5 20.6 +- .6 ; 3.1 16.8 +- 5.0 TRANSIT DOSE = 1.6 +- .3 ; 4.7 l
1 .
8 4.
I
-t I
\
\
i
-\ 1 i
_ _ _ _ - - - - - - - - - - - - - - - - - - - - - - _ - - 1
DIRECT RADIATION TABLE 13 DAVIS BESSE TLD DIRECT RAFIATION ENVIRONMENTAL MONITORING FOR THE PERIOD 850618-851009 114 DAYS FIELD TIME 93 DAYS NRC LOCATION GROSS NET EXPOSURE RATE STATION AZIMUTH /DIST EXPOSURE (mR) mR/Std 0tr.
(dea.) (mi.) +- Rdm; Tot. +- Pim 13.2 . ; Tot.
001 50- 0.6 15.2 +- .5 ; 2.3 .5 ; 4.7 002 86 0.9 16.8 +- .5 ; 2.5 14.7 +- .6 4.8 003 116 1.4 17.4 +- .5 ; 2.6 15.4 +- .6 ;; 4.9 004 172 0.8 19.6 +- .6 ; 2.9 17.5 +- .6 ; 5.1 005 200 1.5 23.6 +- .7 ; 3.5 21.4 +- .7 ; 5.4 006 226 1.0 20.1'+- .6 3.0 18.0 +- .6 l 5.1 007 249 1.5 20.4 +- .6 ; 3.1 18.2 +- .6 ; 5.1 008 267 1.8 22.0 +- .7 ;~ 3.3 19.8 +- .7 ; 5.3 009 285 1.8 22.3 +- .7 ; 3.3 20.1 +- .7 ; 5.5 010 306 1.5 19.5 +- .6 ;; 2.9 17.4 +- .6 l 5.1 011 -
344 0.9 17.7 +- .5 ; 2. 6' 15.6 +- .6 ; 4.9 012 142 4.5 MISSING OR DAMAGED DOSIMETER 013 158 4.0 22.9 +- .7 ; 3.4 20.7 +- .7 ; 5.4 014 180 3.8 20.7 +- .6 ; 3.1 18.6 +- .7 ; 5.2 015 207' 4.8 21.1 +- .6 ; 3.2 18.9 +- .7 ; 5.2 016 225. 4.5 20.7 +- .6 ; 3.1 18.6 +- .7 ; 5.2 017 254 2.7 23.7 +- .7 3.5 21.4 +- .7 5.4 018 269 3.0 21.4 +- .6 ;; 3.2 19.2 +- .7 ; 5.2 019 295 5.3 24.0 +- .7 3.6 21.7 +- .7 ;; 5.4 020 - 0. 5 16.9 +- .5 ; 2.5- 14.8 +- .6 4.9 021 132 9.7 19.8 +- .6 ;; 3.0 17.7 +- .6l; 5.1 022
~
210 6.5 27.8 +- .8 l 4.2 25.4 +- .9 l 5.8 TRANSIT DOSE = 1.5 +- .3 ; 4.3
- e l
l l
i
(
L
- DIRECT RADIATION- TABLE 13 i
DR!IS'BESSE" TLD DIRECT RAIIRTION ENVIRONMENTAL MONITORING FOR~THE PERIOL.850916-860124 131 DAYS FIELD' TIME 94 DAYS NRC LOCATIDH GROSS HET EXPOSURE RATE mR/Std.0tr.
=STRT10H RZIMUTH/DIST EXPOSURE (mR)
(dea.)- (mi.) . +- Rdm; Tot.' +- Rdm; Tot.
001' 50- 0.6 18.5 +- .6 ; 2.8 13.2;+- .6 ; '5.8
.002 86 0.9 19.3 +- .6 2.9- .14.0 + ' .7 ;- 5.9 003. 116: 1.4 19.2 +- . 6 ;;. 2.9 13.9 + - .7 ; -5.9 004 172 0.8 28.3 +- .8 ; 4.2 22.6 +- .9 ; 6. 6'
=005 200 1.5- 23.9 +- .7 ; 3.6 18.4 +- .8 6.2 226 1.0 22.5 +- .7 ; 3.4 17.0 +-- . 7 ;;- 6.1 006
,007 249 1'. 5 - 24.6 +- .7 ; 3.7 19.1 +- .8' ; 6.3 008 267 1.8 '24.2 +- .7 ; ~3.6 18.7 +-
.8 ;- 6.2 1.8- 24.8 +- .7 ; 3.7 19.3 +- .8 009- 285 23.0 +- .7 ; 3.5 17.6.+- .8 ;. 6.3 6.1 1 010 306 1.5 .7 ;;
011' 344- 0.9 20.3 +- .6 ; 3.0- 15.0 +- 5.9-1 1
012 142 4.5 25.3 +- .8 ; 3.8 19.7 +- .8 ; 6.3 l 013 158 4.0 26.4 +- .8 ; 4.0 20.8 +- .8 ;- 6. 4-014 180 3.8 23.5 +- .7' 3.5 18.1 +- .8 ; 6.2 015 207 4.8 MISSINGORDRb8GEDDOSIMETER-016- 225 4.5 23.'2 +- .7 ; 3.5 17.7.+ . .8 ; 6.2 017 254 2.7 26.5 +- .8 ; 4.0 20.9 +- .8 ; 6:.4 018 269 3. 0 - 24.0 +- .7 ; 3.6 18.5 +- .8 ; 6. 2 -
019 295 5.3 24.6 +- .7 ; 3.7 19.1 +- .8' 6.3 020 25 0.5 19.2 +- .6 ; 2.9 13.9 +- .7 ; .5.9 021 132 9.7 23.7 +- .7 ; 3.6 18.2 +- .8 ; 6.2 022 210 6.5 22.5 +- .7 ; 3.4 17.1 +- .7 ; 6.1 TRRHSIT DOSE = 4.6 +- .4 ;'5.4' W
L__----_-.____-._-_
I l l j i
DIRECT RADIATION TABI.E 13 l-DAVIS BESSE TLD DIRECT RAIIATION ENVIRONt4 ENTAL MONITORING FOR THE PERIGI 851216-860403 109 DAYS FIELD TIME 84 DAYS NRC LOCATION GRhSS HET EXPOSURE RATE STATION AZIMUTH /DIST EXPOSURE (mR) mR/Std.Qtr.
(dea.) (mi.) +- Rdm; Tot. +- Rdm 001 50- 0.6 11.6 +- .3 ; 1.7 10.8 + ; Tot.
.5 ; 4.6 l 002 86 0.9 12.8 +- .4 ; 1.9 12.0 +- .5 4.7 003 116 1.4 14.4 +- .4 ; 2.2 13.7 +- .5 :; 4.9 l- 004' 172 0.8 15.8 +- .5 ; 2.4 15.2 +- .6 ; 4.9 005 200 1.5 16.7 +- .5 2.5 16.2 +- .6 5.0 006 -226 1. 0 - 14'.8 +- .4 ; 2.2 14.2 +- .5 ;; 4.9 l-007 249 1.5 16.4 +- .5 ; 2.5 15.9 +- .6 ; 5.0 008 267 1.8 16.0-+- .5 ; 2.4 15.4 +- .6 ; 5.0 009 285 1.8 16.7 +- .5 ; 2.5 16.2 +- .6 5.0 l 010 306 1.5 15.7 +- .5 ;- 2.3 15.1 +- .6 ;; 4.9 011 344 0.9 MISSINGORDAf1AGEDDOSIMETER 612 142 4.5 16.4 +- .5 ; 2.5 15.9 +- .6 ; 5.0 013' 158 4.0 17.7 +- .5 ; 2.7 17.3 +- .6 : 5.1 ,
014 180 3.8 15.2 +- .5 ; 2.3 14.6 +- .6 i 4.9 '
015. 207 4.8 15.2 +- .5 ; 2.3 14.6 +- .6 t 4.9 016 225 4.5 15.4 +- .5 ; 2.3 14.8 +- .6 i 4.9 017- 254 2.7 18.4 +- .6 2.8 18.0 +- .7 i 5.2 018 269 3.0 16.2 +- .5 ;; 2.4 15.6 +-
.6 ; 5.0
.6 019 295 5.3 17.1 +- .5 ; 2.6 16.7 +-
020 25 0.5 12.1 +- .4 ; 1.8 11.2 +- .5 ;1 5.1 4.7 021 132 9.7 17.1 +- .5 2.6 16.7 +- .6 5.1 022 210 6.5 17.5 +- .5 ;; 2.6 17.1 +- .6 ;; 5.1 TRANSIT DOSE = 1.6 +- .3 ; 4.0 9
l i
DIRECT RADIATION TABLE 13 DAVIS BESSE TLD DIRECT RAIIATION ENVIRONMENTAL MONITORING FOR THE PERIDE 860306-860722 139 DAYS FIELD TIME 108 DAYS NRC LCCATION- GROSS HET EXPOSURE RATE STATION AZIMUTH /DIST EXPOSURE (mR) mR/Std.0tr.
(dea.) (mi.) +- Rdm: Tot. +- Rdm 001 50- 0.6 16.8 +- .5 2.5 11.7 + ; Tot. .5 ; 4.9 002 86 0.9 18.1 +- .5 ; 2.7 12.7 +- .5 5.0 003 116 1.4 17.9 +- .5 ;
- 2.7 12.6 +- .5 ;; 5.0 004 172 0.8 MISSING OR DAMAGED DOSIMETER 005 200 1.5 24.6 +- .7 ; 3.7 18.2 +- .7 5.4 006 226 1.0 21.6 +- .6 ; 3.2 15.7 +- .6 ;; 5.2 007 249 1.5 23.5 +- .7 ; 3.5 17.3 +- .7 ; 5.3 008 267 1.8 23.9 +- .7 3.6 17.6 +- .7 5.4 009 285 1.8 24.4 +- .7 ; 3.7 18.0 +- .7 ;; 5.4 010 306 1.5 21.7 +- .7 ; 3.3 15.8 +- .6 ; 5.2 011 344 0.9 19.6 +- .6 ; 2.9 14.0 +- .6 ; 5.1 012 142 4.5 23.3 +- .7 ;, 3.5 17.1 +- .7 : 5.3 013 158 4.0 26.3 +- .8 ; 3.9 19.6 +- .7 5.5 014 180 3.8 22.1 +- .7 ; 3.3 16.1 +- .6 ;; 5.3 015 207 4.8 23.4 +- .7 ;; 3.5 17.1 +- .7 5.3
'016 225 4.5 22.9 +- .7 3.4 16.7 +- .6 ; 5.3
+ 017. 254 2. 7 26.0 +- .8 ;; 3.9 19.3 +- .7 ;; 5.5 018 269 3.0 22.6 +- .7 3.4 16.5 +- .6 5.3 019 295 5.3 24.5 +- .7 ; 3.7 18.1 +- .7 ; 5.4 020 25 0.5 18.3 +- .5 ; 2.7 12.9 +- .5 5.0 021 132 9.7 23.9 +- .7 ; 3.6 17.6 +- .7 :; 5.4 022 210 6.5 H22.9 +- .7 ;; 3.4 16.7 +- .6 ; '5. 3 TRANSIT DOSE = 2.8 +- .4 ; 5.4 s
a ENVIRONMENTAL MONITORING RESULTS FOR PERRY NUCLEAR POWER PLANT 4
TM > , Perry Nuclear Power Plant is located on the shore of Lake Erie in North Perry, Ohio. Environmental media collected
', in the vicinity of this plant include air, water, milk,
'i sediment, vegetation and fish. Direct radiation is also measured using TLD's provided by the U.S. NRC.
s
,A
" g i
Y
'2 - #
1(
1 L _ _ _ _ _ _ _ _ _ - - - - __ _ _
p.
p ' DISCUSSION OF RESULTS - PERRY NUCLEAR POWER PLANT Air' Particulate (Table 14 & 16,. pp.49:& 51)
The collection of environmental samples in the vicinity of-the-PNPP was initiated in the.latter part of 1985. The air sampling stations however, were not installed-and operated.until the early part of 1986.-
Collection of air samples" began on 1-29-86 at Loc. #07 and on 4-16-86 a t i Loc. # 0 6.- Both the ODH indicator and control air sampler for Perry are.co-located'with-PNPP air samplers at Location #07'and'#06.respec-tively.
There was very good agreement between ODH and PNPP gross beta analyses.
at both locations. . Elevated gross beta activity was detected by.both ODH and L PNPP . for. the ' air samples collected from 5-14 to 6-11. This .
increase in activity was.a result of fallout from the Chernobyl accident. A very slight increase in gross beta activity also seems to have occured during the last three weeks of December. This was fpossibly due to additional fallout from.Chernobyl.
At Loc. #07 the ODH air sampler was unplugged (vandalized)'for a short period of time resulting in a low volume of air collected for the week ending on May.7. Several other instances of vandalism occurred during 1986 but these did not afffect sample collection. Since this time no further vandalism has occured.
Results of all analyses indicate that there was no significant dif-ference between the gross beta activity in air measured at the indicator location and the activity measured at the control location.
Air Iodine (Tables 15 & 17,.pp.50 & 52)
.All air iodine analyses performed by ODH and PNPP were in good agreement. Elevated levels of I-131 in air were detected at both the indicator and control air sampling locations in 1986. This activity was attributed to fallout from the Chernobyl accident. No significant difference in air. iodine concentrations was seen between the indicator location and the control location.
The required LLD for iodine in air was not met by ODH for the 12-24 samples due tu a delay in counting.
Air Filter Composites (Table 18, p. 53 )
The naturally occurring radionuclides Be-7 was detected in all of the quarterly gamma isostopic analyses performed. Be-7 is produced in the atmosphere when cosmic rays interact with isotopes of nitrogen, oxygen and carbon. In addition to the detection of Be-7, during the second quarter of 1986,-ODH analyses detected the presence of several other radionuclides. At control Loc. #06, small concentrations of the fission products Cs-137 and Cs-134 were detected.
Discussion of results continued . . .
At the indicator location-(#07) the fission. products Ru-103 and Ru-106 were detected as well. The-presence of these radionuclides Ewas attributed to fallcut from Chernobyl. Corresponding activities ware not reported by PNPP as they were below the PNPP's specified lower. limits of detection.
All other ODH analysis results were in good agreement with PNPP results. Other than the above mentioned radionuclides there was no significant difference between the analysis results obtained at
.the control location and those obtained at the indicator. location.
Water (Tables 19, 20 & 21, pp.54-56)
.ODH performs both radiciodine and gamma isotopic analyses on monthly water samples. PNPP performs only a gamma isotopic analysis on these samples, therefore, no direct comparison of.radiciodine analysis results could be made. The ODH Lab was able to meet the LLD for I-131
'in water,for 7 out of the 12 monthly water samples collected in 1986.
This is expected to improve further.in 1987.
'PNPP reported results for the radionuclides Cs-134, Cs-137 and Ba-140.
There was f airly good agreement between the ODH and PNPP results for these gamma emitters at both the indicator (#34) and control (#36) location. All results were below the ODH and PNPP lower limits of detection.
In addition to naturally occuring K-40, small amounts of Zr-95 and Mo-99 were-detected by-ODH in the January and June water samples collected at Loc.'#34 as~noted in Table 19.
'There'was very good agreement betweeen the ODH and PNPP results of tritium analyses performed on quarterly composites.of the monthly water samples. There was no significant difference between analysis results for water samples obtained at the indicator location and re-sults for samples obtained at the control location. All tritium (H-3) results were less than the ODH an- PNPP lower limits of detection.
F_ish (Table 22, p.57)
Fish samples were the first environmental samples to be collected when
.the environmental monitoring program in the vicinity of the PNPP was initiated in 1985. Table 22, therefore, includes results of analyses performed on fish collected in 1985 and 1986. In 1985, the individual species of fish collected were not kept separate. Analysis was, therefore, performed on a composite of 2 species. Subsequent fish camples were kept separate and were analyzed individually.
Discussion of results continued . . .
The only radionuclides to be detected, in addition to naturally occuring K-40, was Cs-137. As indicated in Table 22, small quantities of this radionuclides were detected in various fish species and at various locations by both ODH and PNPP. Detection did not occur in the same samples however.
Milk and Vegetation (Table 23, p. 58)
Due to the limited supply of milk available from goats, ODH was only able to obtain a split sample of milk during 2 months of the milking season. Two varieties of broadleaf vegetation were collected in lieu of milk during the other months in order to monitor the iodine path-way.
An increase in radiciodine concentrations in milk was detected by PNPP in the May and June milk samples. This activity was attributed to the fallout from the accident at Chernobyl. The ODH Lab reported traces of Cs-137 in the September and October milk samples. Corresponding activities of this radionuclides were not detected by PNPP.
It was noted that the LLD for I-131 in milk was not met by the ODH Lab in either of the milk samples collected in 1986.
Vegetation samples collected by ODH And PNPP consisted of grass and staghorn sumac leaves. The naturally occuring radionuclides K-40 and Be-7 were detected in these samples. Small quantities of the fission products Cs-137, Cs-134 and Ru-103 were also detected by ODH in several of the vegetation samples. Corresponding levels of Cs-134 and 1
Cs-137 were not detected by PNPP as the quantities were below the PNPP specified lower limits of detection for these radionuclides. The presence of these radionuclides was most likely a result of the fallout from Chernobyl. These radionuclides have half-lives which are sufficiently long enough to allow them to remain in the environment for several years. Removal of these radionuclides from vegetation is, therefore, dependent on the action of weathering processes such as wind, rain, etc.
Produce (Table 24, p.60)
No produce samples were split with PNPP in 1986. The produce samples were collected earlier than scheduled by PNPP and the ODH contractor was not notified of this change in schedule.
\ ____ _ _ _ _______ --------- . - . . . - . -
Discussion of results continued . . .
Bottom Sediment (Table 25, p. 61 )
There was fairly good agreement between the ODH and PNPP bottom sediment analysis results. Radionuclides including Cs-137, Cs-134 and Co-60 were shown to be present in detectable quantities. Several naturally occuring radionuclides including K-40, Be-7, thorium \and '
members of the uranium decay chain were also detected. In addition, ,
the presence of the radionuclides Cd-109 and Nb-95 were reported by the ODH Laboratory.
Direct Radiation (Table 26, p.
Direct radiation in the environment was measured using TLD's. These TLD's are changed on a quarterly basis. Over the time period 12-14-84 to 7-22-86, ambient radiation exposure rates at various locations in 4 the vicinity of PNPP ranged from 13.8 - 23.4 mR/ standard quarter. The mean exposure rates measured at each location were comparable to average exposure rates expected from background sources of radiation.
Sources of background radiation are cosmic rays and radionuclides in the earth's crust.
l l
p$
p- -
AIR PARTICULATE <
TABLE 14
- j; Perry [ Nuclear; Power Station January . December 1986 9 9
'0DH Location.#07 STATE RESULTS, . PNPS RESULTS Gross BetaL(pCi/m3); Gross Beta (pci/m3)
L., 02-05 0.02 '+/- 0.002 0.02' +/- 0.01 "Q .- 02-12 0.01 .+/- 0.002' O.024 +/- 0.009.
02-19 0.02 +/ =0.002, 0.034 +/- 0.007 02-26 l0.02 +/--0.002 0.020 +/- 0.007
'03-05 0.02 +/ 0.002 0.020 +/- 0.007 ni 03-12' O.01 +/- 0.002 0.018 +/- 0.007.
/* 03-19. H0.01 +/- 0.002 0.018 +/- 0.007-1 103-26 0.02 +/- 0.002 0.023 +/- 0.007 04-02 0.01 +/- 0.002 0.024 +/- 0.007' 04-09 0.01 +/- 0.002 10.016 +/--0.006 04-16 0.01 +/- 0.001 0.006 +/ 0.006 04 0101 +/- 0.002- 0.014 +/- 0.006-04-30 0.02 +/- 0.002 0.019'+/- 0.007.
05-07 0.02 +/- 0.002
- 0.018 +/- 0.006 05-14 0.14 +/- 0.005 0.174 +/- 0.013 s- 05-21 0.044'+/- 0.003 0.037 +/- 0.008 05-28 0.079 +/ -0.004 0.087 +/- 0.010 0.186 +/- 0.013
. 06-04 0.07 +/- 0.004 06-11 0.032 +/- 0.003 0.057 +/- 0.009 06-18 0.01..+/- 0.002 0.020 +/- 0.006 06-25 0.02 +/- 0.002 0.018 +/- 0.007 07-02 0.01 +/- 0.002 0.018.+/- 0.006 07-09 0.01- +/- 0.002 0.024 +/- 0.007 07-16 0.01 +/- 0.002 0.006 +/- 0.006 07-23 0.02 +/- 0.002 0.013 +/- 0.007 07-30 ~ 0.02 +/- 0.002 0.014 +/- 0.006 08-06 0.02 +/- 0.002 0.013 +/- 0.006 08-14 0.02 +/- 0.002 0.015 +/- 0.007 08-20 0.02. +/- 0.002 0.024 +/- 0.007 L 08-27 0.02 +/- 0.002 0.018 +/- 0.006 09-03 0.02 +/- 0.002 0.016 +/- 0.007 09-10 0.01 +/- 0.002 0.022 +/- 0.007 I L 09-17 .0.01 +/- 0.002 0.016 +/- 0.007 09-24 0.02 +/- 0.002 0.019 +/- 0.007 L 10-01 0.01 +/- 0.002. 0.016 +/- 0.006 10-08 0.01 +/- 0.001 0.009'+/- 0.006 10-15 0.01 +/- 0.002 0.009 +/- 0.006 10-22 0.01 +/- 0.002 0.014 +/- 0.007 10-29 0.03 +/- 0.002 0.032 +/- 0.008 11-05 0.02 +/- 0.002 0.020 +/- 0.007 11-12 0.02 +/- 0.002 0.013 +/- 0.007 11-19 0.02 +/- 0.002 0.029 +/- 0.008 11-26 0.02 +/- 0.002 0.019 +/- 0.007 12-03 0.02 +/- 0.002 0.018 +/- 0.007 12-10 0.02 +/- 0.002 0.018 +/- 0.008 12-17 0.03 +/- 0.003 0.031 +/- 0.008 17-24 0.03 +/- 0.003 0.019 +/- 0.008 12-31 0.03 +/- 0.002 0.036 +/- 0.008
- Low volume
'k AIR IODINE TABLE 15 l: . Perry Nuclear Power Station f j l January - December 1986 i j ODH Location #07 l
l l DATE STATE RESULTS PNPS RESULTS l pC1/m3 pCi/m3 02-05 < 0.04 All results < 0.04 pCi/m3 .!
02-12 < 0.04 unless otherwise noted.
02-19 < 0.04 !
i 02-26 < 0.04 L 03-05 < 0.04 l 03-12 < 0.04 i l 03-19 < 0.04 03-26 < 0.04
- 04-02 < 0.04 1
04-09 < 0.04 04-16 < 0.04 04-23 < 0.04 04-30 < 0.04 05-07 < 0.04
- 05-14 0.20 +/- 0.02 0.16 +/- 0.04 i 05-21 0.06 +/- 0.02 0.05 +/- 0.03 05-28 0.08 +/- 0.02 0. 0 9 + /- 0. 04 06-04 < 0.04 ;
06-11 < 0.04 06-18 < 0.04 06-25 < 0.04 07-02 < 0.04 i 07-09 < 0.04 !
07-16 < 0.04 j 07-23 < 0.04 i 07-30 < 0.04 08-06 < 0.04 08-14 < 0.04 08-20 < 0.04 08-27 < 0.04 09-03 < 0.04 09-10 < 0.04 09-17 < 0.04 09-24 < 0.04 10-01 < 0.04 10-08 < 0.04 10-15 < 0.04 10-22 < 0.04 10-29 < 0.04 11-05 < 0.04 11-12 < 0.04 11-19 < 0.04 11-26 < 0.04 12-03 < 0.04 12-10 < 0.04 12-17 0.03 +/- 0.02 12-24 < 0.08 12-31 < 0.05 0 Low volume
,1 ' AIR PARTICULATE . TABLE 16 Perry. Nuclear; Power Station January 1- December 1986
- 0DH Location #06
, DATEE STATE RESULTS PNPS RESULTS
' Gross' Beta (pCi/m3) Gross Beta (pci/m3) 04-23 'O.01 +/- 0.002 0.012 +/- 0.006 104-30' 0.02 +/- 0.002 0.019 +/- 0.007 05-07 0.02 +/- 0.002 0.019 +/- 0.007
, 05-14' O.14 +/- 0.005 0.197 +/- 0.014 05-21 0.044 +/- 0.003 0.056 +/- 0.009-05-28' .0.074 +/- 0.004 0.100 +/- 0.010 06-04: 0.07' +/- 0.004 '0.171 +/- 0.013 06-11 0.043 +/- 0.003 0.040 +/- 0.008 06-18 :0.01 .+/- 0.002 0.022.+/- 0.007
'06-25 0.02 +/- 0.002 0.021 +/- 0.007 07-02 0.01 .+/- 0.002- 0.017 +/-' O.006 07-09 0.02 +/- 0.002 0.025 +/- 0.007 07-16. 0.01 +/- 0.002 0.009 +/- 0.006 07-23 0.02 +/- 0.002 0.014 +/- 0.007 07-30 0.02 +/- 0.002 0.019 +/- 0.007 08 0.02 +/ 0.002 0.017 +/- 0.007 08-14 0.02L +/ '0.002 0.015 +/- 0.007 08-20 0.02 +/- 0.002 0.021 +/- 0.007 08-27 0.02 +/- 0.002 0.018 +/- 0.006 09-03 0~02- +/- 0.002
. 0.013 +/- 0.007-09-10 0.02 +/- 0.002 0.017 +/- 0.007 09-17 0.02 +/- 0.002 0.011 +/-:0.006 09-24 0.02 +/- 0.002 0.022 +/- 0.007 10-01 0.01 +/- 0.002 0.014 +/- 0.006 10 0.01 +/- 0.002 0.003.+/- 0.006 10-15 0.02 +/- 0.002 0.016 +/- 0.007 10-22 0.02 +/- 0.002 0.G23 +/- 0.007 1
10-29 0.02 +/- 0.002 0.041 +/- 0.008 11 0.02 +/- 0.002 0.024 +/- 0.007 l 11-12 0.02 +/- 0.'002 0.015 +/- 0.007 11-19 0.02 +/- 0.002 0.026 +/- 0.008 i
11-26 0.02 +
'/- 0.002 0.024 +/- 0.008 12-03 0.02 +/- 0.002 0.023 +/- 0.008 12-10 0.02 +/- 0.002 0.015 +/- 0.008 12-17 0.03 +/- 0.003' O.028 +/- 0.008 12-24 0.03 +/- 0.003 0.018 +/- 0.008 12-31 0.03 +/- 0.002 0.042 +/- 0.009 i
l
[
T 4
5 i
.) .
s
'4
AIR IODINE TABLE 17 Perry Nuclear Power Station January - December 1986 ODH Location #06 STATE RESULTS PNPS RESULTS pCi/m3 pC1/m3 04-23 < 0.04 All results < 0.04 unless 04-30 < 0.04 otherwise noted.
05-07 < 0.04 05-14 0.20 +/- 0.02 0.23 +/- 0.04 05-21 0.06 +/- 0.02 0.09 +/- 0.04 05-28 0.04 +/- 0.01 0.05 +/- 0.04 06-04 < 0.04 0.05 +/- 0.04 06-11 < 0.04 l 06-18 < 0.04 l 06-25 < 0.04
! 07-02 < 0.04
! 07-09 < 0.04 l 07-13 < 0.04 07-16 < 0.04 f
l 07-23 < 0.04
( 07-30 < 0.04 08-06 < 0.04 08-14 < 0.04 08-20 < 0.04 08-27 < 0.04 09-03 < 0.04 09-10 < 0.04 09-17 < 0.04 09-24 < 0.04 10-01 < 0.04 10-08 < 0.04 10-15 < 0.04 10-22 < 0.04 10-29 < 0.04 11-05 < 0.04 11-12 < 0.04 j 11-19 < 0.04 11-26 < 0.04 12-03 < 0.04 12-10 < 0.04 12-17 < 0.04 12-24 < 0.09 12-31 < 0.05 1
QUARTERLY GAMMA ISOTOPIC ANALYSES OF AIR FILTER PAPER COMPOSITES i
Perry Nuclear Power ~ Plant TABLE 18 January - December 1986 Location # 06 & 07 Location #06 (pCi/m3)
ODH DATA Jan - March Apr - Jor t July - Sept Oct -
Dee Be-7 No Data
- 0.10+0.005 0.06+0.01 0.05+0.01 K-40 ED 0.008I0.006 ND Nb-95 ND ND ND Zr-95 ND ND ND Ru-103 ND ND ND Ru-106 ND ND ND Cs-134 0.006+0.002 ND ND Cs-137 0.01010.002 ND ND Ce-i41 ND ND ND Ce-144 ND ND ND PNPP DATA Be-7 0.070+0.020 0.070+0.030 0.070+0.030 0.080+0.020 Cs-134 < 07040 < 07040 < 07040 < 0.040 Cs-137 < 0.030 < 0.030 < 0.030 < 0.030 Location #07 ODH DATA Jan - March ** Apr - June July - Sept Oct - Dec Be-7 0.05+0.01 0.08+0.05 0.07+0.01 0.04+0.02 K-40 5D 0.005IO.007 ED 5D Nb-95 ND ND ND ND Zr-95 ND ND ND ND Ru-103 ND 0.01+0.007 ND ND Ru-106 ND- 0.003I0.007 ND ND Cs-134 ND 0.005+0.002 ND ND Cs-137 ND 0.00810.001 ND ND Ce-141 ND ND ND ND Ce-144 ND ND ND ND Other radionuclides detected: July-Sept - Cd-109: 0.01 + 0.01 pC1/m3 PNPP DATA "e-7 0.070+0.020 0.070+0.030 0.070+0.030 0.080+0.020 Cs-134 < 07040 < 07040 < 07040 < 0.540 Cs-137 < 0.030 < 0.030 < 0.030 < 0.030 I
h ND - Not Detected Air sampling at Location #06 was begun on April 16, 1986.
- Afr' sampling at Location #07 was begun on January 29, 1986.
i.
l RADIOI0 DINE AND.GAMMALISOTOPIC ANALYSIS TABLE 19
.0F MONTHLY COMPOSITE. WATER SAMPLES Perry Nuclear. Power Plant-January - December 1986 Loc.#34-ODH' DATA Loc.#04 (pCi/l +2 sigma error):
DATE' K-40 I-131 Cs-137 Cs-134 Ba-140 Other-01-27-66 < 22 < 4- <; 4 ' (' 4 ' < 14 Zr 2+2
~ ' '
02-24-86 < 23 < 1.8 <'4 <4 <'14 03-24-86 3.2+34 <1 < 4. <~4 < 14 04-28-86 34739 < 1 <4 <- 4 <37 05-27-86 5765 '< l' <4 <4 < 17 06-23-86 19T64 <1 <'4 <4 < 14 Mo-99 6+5
~'
07-28-86' 8T70'
~
<L 1 <4 <4 < 30.
'08-25-86 <47 <1 <4 <4 < 16 09-22-86 -<48 <1 <4 <4 < 22' 10-27-86 6+25 <3 <4 <4 < 14 11-24-86 5731 <4. <4 <4 < 14 12-22-86 0.8728 < 3' <4 <4 < 14 Note: Radionuclides other'than.those reported were not detected.
PNPP' DATA Loc.#34 (pCi/1 + sigma)
DATE K-40 I-131 Cs-137 Cs-134 Ba-140 Other 01-27-86 Not Reported < 2.4- < 2.8 < 25 02-24-861 < 2.4. < 2.8 '< 25 03-24-86 < 2.4 < 2.8 <25 04-28-86 < 2.4 < 2.8 .< 25 05-27-86: < 2.4 < 2.8 < 25
'06-23-86. <'2.4 < 2.8 < 25 07-28-86 < 2.4 < 2.8 < 25 08-25-86 < 2.4 < 2.8 < 25 09-22-86 < 2.4 < 2.8 < 25 10-27-86' < 2.4 < 2.8 < 25 11-24-86 < 2.4 < 2.8 < 25 22-86 < 2.4 < 2.8 < 25 p
p RADI0 IODINE AND GAMMA ISOTOPIC ANALYSIS TABLE 20 0F MONTHLY COMPOSITE WATER SAMPLES
- Perry Nuclear Power > Plant January -LDecember 1986 Loc.#36 0DH DATA Loc.#36 (pci/1 + 2 sigma error)
+
DATE K-40 I-131 Cs-137 Cs-134 'Ba-140' Other 01-27-86" <,24 <3 <4 <'4 '< 14 02-24 (-23 < 1.7 <4 <4 <'14 03-24-86 < 27. <1 <4 <4 '<?14:
04-28-86 106+345 < 1 <4 <4 <46-05-27-86 7 74 <1 <4 <4 < 15 06-23-86 39767 . '< 1
<4 <4 < 14 l- 07-28-86 19765 <l <4 <4 < 16 08-25-86 < 50 <1 <4 <4 < 21 09-22-86 58+41 <1 <4 <4 < 22' 10-27-86 ST25 <2 <4 <4 < 14 Xe-133m 28+8 11-24-86 5+31
~
<6 <4 <4 ( ' 14 12-22 < 25 <3 <4 <4 < 14 Other. radionuclides reported: 12-27-86: Ru-106 14 + 13 pCi/1' Note: Radionuclides other than those reported were not detected.
PNPP DATA- (pCi/12+ sigma)
DATE K-40 I-131 Cs-137 Cs-134 Ba-140 Other 01-27-86. Not Reported < 2.4- < 2.8 < 25 02-24-86 < 2.4 < 2.8 < 25 03-24-86 < 2.4 < 2.8 < 25 04-28-86 < 2.4 < 2.8 < 25 05-27-86 < 2.4 < 2.8 <25 06-23-86 < 2.4 < 2.8 <25 07-28-86 < 2.4 < 2.8 < 25 08-25-86; < 2.4 < 2.8 < 25 09-22-86 < 2.4 < 2.8 < 25 10-27-86 < 2.4 < 2.8 < 66.7 a
- , 11-24-86 < 2.4 < 2.8 < 25
.12-22-86 < 2.4 < 2.8 < 25 a Did not meet PNPP Tec. Spec. or requirements on lower limit of detection.
l TRITIUM ANALYSES OF QUARTERLY COMPOSITES OF UNTREATED SURFACE WATER SAMPLES TABLE 21 Perry Nuclear Power Plant January -
December 1986 Location # 34 & 36
'DATE LOCATION' ODH RESULTS PNPS RESULTS (pCi/1 + 2 sigma) (pC1/1 + sigma)
H-3 H-3 Jan-Mar Loc. #34 < 1500 < 2000 Apr-Jun < 1500 < 2000 July-Sept < 1500 < 2000 Oct-Dec < 1500 < 2000 Jan-Mar Loc. #36 < 1500 < 2000 Apr-Jun < 1500 < 2000 July-Sept < 1500 < 2000 Oct-Dec < 1500 < 2000
7_ ;
u; d
-?
v GAMMA ~ ISOTOPIC ANALYSIS' 0F' RADIONUCLIDES-IN FISH: TABLE 22 s
Perry Nuclear Power Plant January - December.1986 i; Location #25"(Inside 5 mi.)
- 32 (Outside'10'ai.)
0DH DATA' (pCi/kg + 2. sigma error)-
^
10-08-85 10-08-85 05-06-86 10-20-86 10-16 Loc. #25 1 Loc. #32 Loc. #25 Loc. #25' Freshwater Drum Wh. Sucker and Y. Perch- and Y. Perch Walleye /Y. Perch Walleye 'Wh. Sucker Cs-137 < 30 12+12 22+11 < 30 28+28 < 35 y Cs-134 < 31 < 20 < 20 < 20 < 32 < 32 Mn-54 < 26 < 22 < 20 < 20 < 29- < 37 0 Fe-59 < 228 < 171 < 73 < 94 < 105 < 113 Co-58 < 66 < 44 < 20 < 28 < 39 < 54 Co-60 < 26- < 30 < 30 < 30 < 30 < 31
[! Zn < 66 <47 <40 < 43 < 59 _ < 64 h .K-40 2700+520 2203+336 1933+228 2436+375 3354+505 2758+564
)
Y. Perch - Yellow Perch l'
Wh. Sucker - White Sucker Note: Radionuclides other than those reported were not detected.
=
PNPP DATA (pC1/kg wet + 2 sigma) 10-08-85 10-08-85 05-06-86 10-20-86 10-16-86 Loc. #25 Loc. #32 Loc. #25 Loc. #25 Drum /Y. Perch W. Sucker /Y. Perch Walleye /Y. Perch Walleye /Wh. Sucker Cs-137 78+35 72+40 < 50 < 50 < 50' ( 50 < 50 < 50 Cs-134 < 50 < $0 < 50 < 50 < 50 < 50 < 50 < 50 Mn-54 ~< 5 0 < 50 < 50 < 50 < 50 < 50 <50 < 50 Fe-59 < 150 < 150 < 150 < 150 < 150 < 150 < 150 < 150 Co-58 < 50 < 50 < 50 < 50 < 50 < 50 < 50 < 50 I Co-60 < S0 < 50 < 50 < 50 < 50 < 50 < 50 < 50 Zn-65 < 150 < 150 < 150 < 150 < 150 < 150 < 150 < 150 K-40 3350+666 5180+1060 2160+190 3680+602 4030+585 3180+494 4180+644 3490+69:
57 -
. . 1
RADIOJ0 DINE AND GAMMA ISOTOPIC ANALYSIS OF MILK AND VEGETATION TABLE 23 Perry Nuclear Power Station January - December 1986 Loc.# 31 & 7 ODH DATA Loc.#07 Vegetation (pC1/kg i 2 sigma error)
Date Type I-131 K-40 Cs-134 Cs-137 Be-7 08-26-86 Grass < 28 4847+412 <6 <5 3671+258 08-26-86 Leaves * < 89 36917232 17+13 8+9 6497115 09-24-86 Leaves < 24 2234I202 < 13 479
~
5537105 09-24-86 Grass < 11 1398I87 <6 <5 949761 10-28-86 Grass < 19 2766I240 < 17 10+10 21367169 11-25-86 Grass < 41 161 [+ 232 < 18 1179
~
3064I208 ,
12-26-86 Grass 13+26 1642+185 ND 4 9 3347_I200 I
A 1
(pCi/1 + 2 sigma)
Loc.#31 I-131 _K-40 Cs-134 Cs-137 Ba-La-140 ;
09-22-86 Milk <3 2059+74 <4 3+2 < 14 ,
10*27-86 Milk <3 1738+62 <4 8+3 < 14 Other radionuclides reported: 08-26-86 Grass: Ru-103 31 + 22 pCi/kg 10-28-86 Grass: Ra-226 35 + 33 pCi/kg 12-26-86 Grass: Nb-95 11 +_ 11 pCi/kg
- Staghorn Sumac Leaves
?
TABLE 23 continued- l RADIOI0 DINE AND GAMMA ISOTOPIC ANALYSIS OF MILK ~AND VEGETATION PNPP DATA Loc.#07-Vegetation (pCi/kg 4' sigma)
-Date Type I-131- K-40 Cs-134 Cs-137 Be-7 08-26-86 Grass- <.40 '4200+1270 < 50' < 5 0. 2080+773
'08-26-86 Leaves * <'40 53807850' < 50 < 50- 7847273' 09-24-86 Leaves <47 41707844' < 50 < 50 12307359 09-24-87 ' Grass <63 b. 3690T917 < 50 < 50 35007608 10-28-86 Grass '< 72 b 46607982 < 50. < 53 56407811 11-25-86 Grass <52 25507865 < 50 < 50 6020T989- l 12-26-86 Grass <40 4 4 20_T6 78 < 50 < 50 5870[540 1 (pC1/1 + 2 sigma)
Loc.#31 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 04-28-86 Milk < 0.8 1764+401 <3 <2 < 25 <6 05-12-86 Milk 5.8+1.3 a 16607350 <3 <2 < 25 <6 05-27-86 Milk 31.573.8 a 15837362 < 3. <2 <25 <6 '
06-09-86' Milk 1171 a 17107357 <3 19+11 <25 <6 1.970.7 a 06-23-86 Milk 1320T319 <3 <2 '< 25 <6 07-14-86 Milk < 078 16707346~ <3 <2 < 25 <6 07-28-86 Milk < 0.8 19407393 <3 <2 < 25 <-17.7 b 08-11-86 Milk < 0.8 19907420 <3 < 2 <25 <6 09-08-86 Milk 10.62+9.9 c- 15007348 <3 < 2' <25 < 16.5 b-
.09-22-86 Milk 0.96T9.9.c 15407350 < 3 <2 <25 <6 10-13-86 Milk 0.95T9.9 e 1720T377 <3 <2 < 73.2 <6 10-27-86 Milk < 078 23207415 < 3 <2 < 66.2 <6 11-24-86 Milk < 0.8 21501431 < 3 <2 < 25 <6 a Elevated I-131 activity is due to fallout from the Chernobyl Nuclear Plant (USSR) accident on April.26, 1986.
b .Did not meet PNPP Tech. Spec. for lower limit of detection.
c PNPP Vendor laboratory has determined this is not I-131 activity.
See section 4 in Results & Discussions of PNPP Annual Report.
l t '
l I i
RADI0 IODINE AND GAMMA ISOTOPIC ANALYSIS OF RADIONUCLIDES IN PRODUCE Perry Nuclear Power Station TABLE 24 January - December 1986 Loc. #38 & 49 No produce samples were split with PNPP in 1986. The produce samples were collected earlier than scheduled by PNPP and the ODH contractor was not notified of this change in schedule.
Better coordination of sample schedules will be encouraged in the future.
1
GAMMA ISOTOPIC' ANALYSIS OF BOTTOM SEDIMENT TABLE 25 Perry Nuclear Power Plant January - December 1986 Location # 25 (vicinity of discharge)
(pCi/kg + 2 sigma)
LOC. #25 ODH PNPP
_DATE 05-05-86 05-05-86 Cs-137 299 + 122 240 + 60 Cs-134 34 7 27 < T00 Co-60 47 I 23 62 + 9 K-40 13490 [ 1127 8480 [ 994 Additional Radionuclides:
Ra-226 783 + 162 Be-7 < 100 Cd-109 2179 I 533 Th-232 661 + 31 Nb-95 56 [ 39 Pb-214 630 [ 53 l
\- i
DIRECT RADIATION ';ABLE 26 PERRY TLD DIRECT RADIATION ENVIRONMENTAL MONITORING FOR THE PERIOD 841214-850418 127 DRYS FIELD TIME p8 DAYS HRC LOCATION GROSS HET EXPOSURE RATE STRTIDH AZIMUTH /DIST EXPOSURE (mR) mR/St d. Qt r.
(dea.) ( m i . '- +- Rdm; Tot. +- Rdm; Tot.
001 72 5.0 18.3 +- .5 ; 2.7 H0 NET Df!TR 003 88 5.5 18.2 +- .5 ; 2.7 N0 NET DATR 004 112 6.0 18.0 +- .5 ; 2.7 H0 NET DATR 005 130 4.R 18.~3 +- .5 ; 2.7 H0 NET BfiTR 006 155 5.0 22.1.+- .7 ; 3.3 H0 HET FATR 607 178 5.2 19.9 +- .6 ; 3.0 H0 HET DflTA 003 205 4.6 18.9 +- .6 ; 2.8 H0 NET DATR 009 220 5.2 18.0 +- .5 i 2.7 H0 NET DATA 010 225 7.4 MISSING OR DRMAGED DOSIMETER Oil 240 5.8 19.5 +- .6 ; 2.9 N0 NET DATR 812 225 19. 24.9 +- .7 ; 3.7 N0 NET DATR 013 225 19. 17.8 +- .5 ; 2.7 N0 HET DATA 014 212 12. MISSING OR DRMAGED DOSIMETER 015 248 1.4 18.1 +- .5 ; 2.7 H0 NET DATA 016 225 0.8 17.2 +- .5 2.6 H0 NET DfiTR 017 205 0.7 16.0 +- .5 ;; 2.4 NO HET DflTR 618 180 .0.8 17.3 +- .5 ; 2.6 H0 HET DfiTR 019 152 1.8 18.2 +- .5 ; 2.7 N0 NET DATR 820 123 1.6 17.4 +- .5 2.6 H0 NET DATR 021 105 1.4 17.5 +- .5 ;; 2.6 HO HET DATR 022 85 1.2 17.7 +- .5 ; 2.7 H0 NET DflTR 023 65 1.4 18.4 +- .6 ; 2.8 H0 HET-DATA 024 40 0.6 18.2 +- .5 ; 2.7 H0 HET DftTR 025 40 0.6 19.3 +- .6 ; 2.9 N0 NET BATR 826 182 2.8 18.2 +- .5 ; 2.7 H0 NET DATR 627 175 2.8 18.1 +- .5 2.7 H0 NET DATA HO TRRHSIT DOSE CALCULATED (TLD CONTROLS; MISSING OR OTHERWISE.NOT COM
DIRECT EADIATION TABLE 26 s
PERRY TLD DIRECT RALIATION ENVIRONMENTAL MONITORING FOR THE PERIOL 850313-850715 125 DAYS FIELD TIME 83 DAYS NRC LOCATION GROSS NET EXPOSURE RATE '
STATION AZIMUTH /DIST EXPOSURE (mR) mR/St d. Qt r.
(dea.) (mi.) +- Rdm 20.0 +; Tot..6
+- Rdm 17.2 + ; Tot.
001 72 5.0 3.0 .7 6.1 003 88 5.5 20.7 +- .6 ;; 3.1 18.0 +- .8 ; 6.2 l- 004 112 6.0 21.0 +- .6 ; 3.1 18.3 +- .8 ; ,6. 2 005 130 4.0 22.1 +- .7 3.3 19.5 +- .8 ; n5. 3 006 <
155 5.0 24.3 +- .7 ; 3.6 21.9 +- .9 ; 6.5 007 178 5.2 21.1 +- .6 ;; 3.2 18.5 +- .8 ;; 6.2 008 205 4.6 HISSING OR DAMAGED DOSIMETER ___ -.
009 220 5.2 20.5 +- .6 ; 3.1 17.8 +- .8 ; 6.1 010 225 7.4 23.0 +- .7 ; 3.5 20.5 +- .8 ; 6.4 011 240 5.8 21.8 +- .7 ; 3.3 19.2 +- .8 ; 6.3 012 225 19. 21.4 +- .6 ; 3.2 18.8 +- .8 ; 6.2 013 225 19. 20.2 +- .6
.8 ;
3.0 17.5 +- .7 ; 6.1 014 212 12. 25.7 +- 3.8 23.4 +- .9 ; 6.6 015 248 1.4 20.9 +- .6 ;; 3.1 18.3 +- .8 ; 6.2 016 225 0.8 19.2 +- .6 ; 2.9 16.4 +- .7 ; 6.0 017 205 0.7 17.9 +- .5 2.7 15.0 +- .7 5.9 018 180 0.8 19.4 +- .6 ; 2.9 16.6 +- .7 ; 6.0 019 152 1.8 r 20.5 +- .6 ;*
3.1 17.8 +- .8 ;; 6.1 020 123 1.6 MISSINGORDRl1AGEDDOSIMETER 021 105 1.4 18.6 +- .6 ; 2.8 15.8 +- .7 ; 6.0 022 85 1.2 23.6 +- .7 ; 3.5 21.2 +- .8 6.4 023 65 1.4 19.7 +- .6 ; 3.0 17.0 +- .7 ;; 6.1 024 -
40 0.6 19.8 +- .6 ; 3.0 17.1 +- .7 ; 6.1 025 40 0.6 25.5 +- .8
.8 ; 3.8 23.3 +- .9 ; 6.6 -
026 182 2.8 25.7 +- 3.8 23.4 +- .9 6.6
.6 ;;
, 027 175 2.8 18.5 +- 2.8 15.7 +- .7 ;; 6.0 TRANSIT DOSE = 4.1 +- .3 ; 4.8 ,
DIRECT RADIATION TABLE 26 k'
t l
l PERRY TLD DIRECT RRDIRTION EN'/IRONMEHIRL MONITORING FOR THE PERIOD 850617-851009 115 DRYS FIELD TIME 92 DAYS HRC LOCATION GROSS NET EXPOSURE RATE STRTION RZIMUTH/DIST EXPOSURE (mR) mR/Std.0tr.
(dea.) (mi.) +- Rdm; Tot. +- Rdm 15.7 + ; Tot.
001 72 5.0 19.3 +- .6 ; 2.9 .6 5.5 003 88 5.5 18.8 +- .6 ; 2.8 15.3 +- .6 ;; 5.5 00d 112 6.0 17.9 +- .5 ; 2.7 14.4 +- .6 ; 5. 4 005 130 4.0 19.0 +- .6 ; 2.9 15.5 +- .6 ; 5.5 006 155 5.0 23.6 +- .7 ; 3.5 20.0 +- .8 ; 5.9 007 178 5.2 21.1 +- .6 ; 3.2 17.6 +- .7 ; 5.6 008 205 4.6 19. 9 -+- .6 ; 3.0 16.4 +- .7 ; 5.6 ,
009 220 5.2 19.4 +- .6 ; 2.9 15.9 +- .7 ; 5.5 010 225 7.4 MISSING OR DRf1RGED DOSIMETER 011 240 5.8 21.0 +- .6- ; 3.2 17.5 +- .7 ; 5.6 012 225 19. 19.5 +- .6 ; 2.9 16.0 +- .7 ; 5.5 013 225 19, 19.7 +- .6- 3.0 16.2 +- .7 ; ~
5.5 014 212 12. HISSINGORDRl1RGEDDOSIMETER 015 248 1.4 18.7 +- .6 ; 2.8 15.2 +- .6 ; 5.5 1 016 225 0.8 18.6 +- .6 2.8 15.1 +- .6 -; 5.5 I 017 205 0.7 16.7 +- .5 ; 2.5 13.2 +- .6 ; 5.3 i 018 180 0.8 18.3 +- .5 ; 2.7 14.8 +- .6 ; 5.4 1 019 152 1.8 19.7 +- .6 ; 3.0 16.2 +- .7 5.5 020 123 1.6 17.3 +- .5 ;; 2.6 13.8 +-- .6 ; 5.4 j 021 105 1.4 18.5 +- .6 ; 2.8 15.0 +- .6 ; 5.4 022 85 1.2 18.0 +- .5 ; 2.7 14.5 +- .6 ;; 5.4 4 023 65 1.4 20.4 +- .6 ; 3.1 16.8 +- .7 ; 5.6 l 024 40 0.6 19.1 + - .6 ; 2.9 15.6 +- .6 ; 5.5 025 40 0.6 19.9 +- .6 ; 3.0 16.3 +- .7 ; 5.5 1 026 182 2.8 19.1 +- .6 ; 2.9 15.6 +- .6 ; 5.5 027 175 2.8 19.1 +- .6 ; 2.9 15.5 +- .6 ; 5.5 TRANSIT DOSE = 3.2 +- .3 ; 4.8 f
- DIRECT RADIATION .
PERRi! . .
TLD DIRECT RADIATION ENVIRONMENTAL M0HITORDIG FOR THE PERIGI! 850916-860124 131 DAYS FIELD TIME -101 DAYS HRC .
' LOCATION GROSS .
HET EXPOSURE RATE ~
~ STATION RZIMUTH/DIST- EXPOSURE (mR)' mR/Std.Qtr.
(deo.) '(mi.) +- Rdm; Tot. + Rdm 17.2 + ; Tot..7 '; 5.6-
~001 72 5.0 22.7 +- .7 3. 4-003 88' 5.5 22.6 +- .7 ; - 3.4 17.1.+- .7 . 5. 6 '
112 6.0- 23.2-+ . .7 ;; 3.5; 17.7 +- . 7 ;;- 5.6 004 .
005 130' 4.0- 24.2'+ - .7-; -3.6 18.6 +- .7 ; 5.7-006 155 5.0 25.8 +- .8 ; 3.9 20.0 +- '
.8 ; 5.8 007 178 5.2: 23.5 +- .7 3.5 18.0 +- . 7- ; 5.6 008- 205 4.6- 27.4 +- .8';;-- 4.1 21.5 +- .8 ; 5.9 009' 220 5.2- 21.8 +- .7 ;' 3.3 16.5 +- .7 : 5.5 010; 225 7.4 '25.3 +- .8 ; 3.8 19.5 +- .7 ; 5.8 011 240 5.8 25.0'+- .7 ; 3.7 19.3 +- .7 ;. 57 012 225- 19. 23.7 +- .7 ; 3.5 18.1 +- .7 ; 5.6 013 225 19. '22.9 +- .7 ; 3.4 17.4 +- .7 ; 5.6 014 212 12, 28.9 +- .9 ; 4.3 22.8 +- .8 ; 6.1 015 248 1.4 21.8 +- .7 ' 3.3 16.4 +-- .7 ; 5.5 016. 225 0.8 HISSINGORDAf1AGEDDOSIMETER
.017 205 20.2 +- 3.0 15.0 +- .6 ; 5.4 018 180
- 0. 7-0.8 23.7 +- .6
.7 j' 3.5 18.1 +- .7 ; 5.6 019 152 1.8 23.0 +- . 7 ;; 3.5 17.5 +- .7 ; 5.6 020 123 1.6 21.6 +- . 6' ; . 3.2 16.2 +- .7 ; 5.5 20.5 +- .6 3.1 15.3 +- .6 ; 5.4-021 022.
105 85 1.4
- 1. 2 ' 25,1.+- .8; 3.8 19,4 +- .7 ; 5.8 023 65 1.4 21.1 +- .6 ;. 3.2 15.8 +- .6 ; 5.5 024 40 0.6 21.8 +- . 7 ' ;; -
3 .3 16.5 +- .7 ; 5.5 025 40 0.6 26.8 +- .8 ; 4.0 20.9 +- .8 ; 5.9 026 182' 2.8 26.5 +- .8 4.0 20-7 . +- .8 ; 5.9 027- 175 2.8 21.2 +- .6 ;; 3.2 15.9 +- .6 ; 5.5 TRANSIT DOSE = 3.3 +- .3 ; 5.2 t
1 1
l DIRECT RADIATION TABLE 26 l
PERRY
' TLD DIRECT RRIIATION ENVIRONMENTAL MONITORING l FOR THE PERIDE 851216-860403 109 D9YS e 4
E FIELD TIME 79 DAYS URC LOCATION GROSS NET EXPOSURE RATE STRTION RZIMLTH/DIST EXPOSURE (mR) mR/Std.0tr.
(dea.) (mi.) +- Rdm; Tot. +- Rdm 001 72 5.0 15.9 +- .5 ; 2.4 14.9 + ;iot.
.6 ; 5.5 003 88 5.5 15.5 +- .5 ; 2.3 14.5 +- .6 ; 5.4 004 112 6.0 MISSING OR DRMAGED DOSIMETER 005
- 130 4.0 16.3 +- .5 ; 2.4 15.4 +- .6 ; 5.5 ;
006 155 5.0 '19.7 +- .6 ; 3.0 19.2 +- .7 ; 5.8 )
007 178 5.2 16.9 +- .5 ; 2.5 16.0 +- .7 ; 5.6 1 008 205 4.6 16.5 .+- .5 ; 2.5 15.5 +- .6 ; 5.5 {
009 220 5.2 15.6 +- .5 ; 2.3 14.6 +- .6 l 5.5 l 010 225 7.4 18.1 +- .5 ; 2.7 17.4 +- .7 ; 5.7 1 011 240 5.8 17.4 +- .5 2.6 16.6 +- .7 ; 5.6 012 225 19. 15.1 +- .5 ; 2.3 14.0 +- .6 5.4 j 013 225 19. 15.4 +- .5 ;; 2.3 14.3 +- .6 ;; 5.4 !
014 212 12. MISSING OR DAMAGED LOSIMETER 015 248 1.4 15.8 +- .5 2.4 14.8 +- .6 ; 5.5 016 225 0.8 15.4 +- .5 ;; 2.3 14.3 +- .6 ; 5.4 017 205 0.7 14.4 +- .4 ; 2.2 13.1 +- .6 ; 5.4 018 180 0.8 16.5 +- .5 ; 2.5 15.6 +- .6 ; 5.5 019 152 1.8 16.4 +- .5 ; 2.5 15.4 +- .6 ; 5.5 020 123 1.6 15.9 +- .5 ; 2.4 14.9 +- .6 5.5 021 105 1.4 16.1 +- .5 ; 2.4 15.1 +- .6 ;; 5.5 022 85 1.2 13.9 +- .4 ; 2.1 12.6 +- .6 ; 5.3 023 65 1.4 17.3 +- .5' 2.6 16.4 +- .7 ; 5.6 024 40' O.6 MISSINGORDRb8GEDDOSINETER 025 40 0.6 15.9 +- .5 2.4 14.9-+- .6 ; 5.5 026 182 2.8 16.0 +- .5 ;; 2.4 15.0 +- .6 ; 5.5 027 175 2.8 16.1 +- .5 ; 2.4 15.1 +- .6 ; 5.5 TRANSIT D0SE = 2.8 +- .3 ; 4.2 4
i
DIRECT RADIA'130N TABLE 26 y
(' PERRY TLD DIRECT RAIIATION ENVIRONMENTAL M0HITORING G 'FOR.THE PERIDI 860306-860722 139 DAYS FIELD TIME 106 DAVS i Y l F HRC LOCATION GROSS HET EXPOSURE RATE g STATION AZIMUTH /DIST EXPOSURE (mR) mR/Std. Qt r.
(dea.) (mi.) +- Rdm; Tot. +- Rdm; Tot. ,
001 72 5.0 21.5 +- .6 ; 3.2 16.1 +- .6 ; 5.2 i 003 88 5.5 MISSING OR DAMAGED DOSIMETER 004- 112 6.0 22. 7 + -.7; 3.4 17.1 +- .6 ; 5.3 005 :130 4.0 22.4 +- .7 ; 3.4 16.8 +- .6 ; 5.2 006 155 5.0 25.5 +- .8 ; 3.8 19.5 +- .7 ; 5.5 007 178 5.2 23.5 +- .7 ; 3.5 17.8 +- .7 ; 5.3 L 008 205 4.6 26.1 +- .8' 3.9 20.0 +- .7 ; 5.5 009 220 5.2 MISSING'ORDAl1AGEDDOSIMETER 010- 225 7.4 25.2 +- .8 ; 3.8 19.2 +- .7 ; 5.4 l 011 240 5.8 25.0 +- .7 ; 3.7 19.1 +- .7 ; 5.4
< 012 -225 19. 23.4 +- .7 ; 3.5 17.7 +- .7 ; 5.3 013 225 19. 21.1 +- .6 ; 3.2 15.8 +- .6 ; 5.2 014 212 12. 27.6 +- .8 ; 4.1 21.3 +- .8 ; 5.6 015 248 1.4 21.6 +- .6 ; d.2 16.2 +- .6 ; 5.2 L 016 225 0.8 24.0 +- .7 ; 3.6 18.3 +- .7 ; 5.4
} 017- 205 0.7 18.7 +- .6 ; 2.8 13.8 +- .6 ; ~5. 0 018 180 0.8 20.5 +- .6 ; 3.1 15.3 +- .6 ; 5.1 l
019 152 1.8 22.1 +- .7 ; 3.3 16.6 +- .6 ; 5.2 020 123 1.6 19.6 +- .6 ; 2.9 14.5'+- .6 ; 5.1 021 105 1.4 19.8 +- .6 ; 3.0 14.6 +- .6 ; 5.1 022 85 1.2 25.0 +- .8 ; 3.8 19.1 +- .7 ; 5.4 023 65 1.4 20.2 +- .6 ; 3.0 15.0 +- .6 ; 5.1 024 40 0.6 MISSING OR DAMAGED DOSIMETER 025 40 0.6 26.4 +- .8 ; 4.0 20.3 +- .7 ; 5.5 026 182 2.8 26.5 +- .8 ; 4.0 20.3 +- .7 ; 5.5 027 175 2.8 20.4 +- .6 ; 3.1 15.2 +- .6 ; 5.1 TRANSIT DOSE = 2.5 +- .3 ; 5.2
i-5 y1 i
t.
l l
1 i
)
I f
This page left blank intentionally ,
I i
i a
)
APPENDIX A
This page left blank intentionally I
I i
Figure 7 U.S. ENVIRONMENTAL PROTECTION AGENCY EMSL LABORATORY INTERCOMPARISON STUDIES SCHEDULE 1
Contact Person: Elizabeth Clark
Title:
Laboratory Supervisor I ,
Laboratory: State of Ohio, Department of Health l Industrial Chemistry Lab I Address: 1571 Perry Street, Columbus, Ohio 43216 !
P.O. Box 2568 NRC License: Type (S ) 34-02305-03 l
Frequency of Participation
> e !
% D d i b b d N d 6 > I F b 5 s d fe!@B s < as a WATER:
hhh h DIET: hh h Gross alpha, Beta l lUl IZl I Sr, gamma l )( l l l l
Gamma U 11 l l H-3i i[_Jl iN C URINE:
Pu -2 3 9 Ul l H-3 l ll 1U Ra-226, Ra-128 Ul lMM AIR FILTER:
U-238 @l l Gross a, B Cs-137, Sr-90 { U Sr-89, Sr-90 C 71l l MILK:
Mixed a, B, gamma (B1ind Performance) 7l Q Er, gamma [Xll l I-131 W [._j I-131 Low Level Z Low Level I-131 @
i
'2 l 1
it '
TABLE 27 .
, -( RESULTS OF EPA.INTERCOMPARISON STUDIES FOR 1986
, 'h' Ohio Department of Health Laboratory is Code K EPA GDH DATE TYPE OF STUDY RADIONUCLIDES KNOWN AVG. DEVIATION (pCi/1 1 I sigma) 04/86 Air Filter Alpha 15 1 5 14.33 1 58 .23
+
1 Eeta 47 + 5 53.67 + 3.05 2.31
.Sr-90 18 I 1.5 15.33 7 1.52 -3.08 Cs-137 10 [ 5 21.66 [ .58 4.04 09/86 Air Filter Alpha 22 1 5 19.33 + 1.15 .92 Beta 66 + 5 75.00 + 1.73 3.12 Sr-90 22 I 5 23.33 7 1.5 1.54
. .) ,
Cs-137 22 [ 5 28.00 [ 4.36 2,07 04/86 Low Level Iodine I-131 9+6 6.0.1 0.0 .87 In Water 08/86 Iodine in Water I-131 4516 42.66 + 1.15 .67 01/86 Strontium in Water Sr-89 31 + 5 32.66 + .58 .58 Sr-90 15 [ 1.5 15.00 [ 1.00 .00 05/86 Strontium in Water Sr-89 515 3.33 1 1.52 .'58 Sr-90 5 + 1.5 5.00 1 1.00 .00 03/86 Racium in Water Ra-226 4.1 + .62 3.76 + .23 .93 Ra-226 12.4 [ 1.85 12.23 [-2.73. .15 09/86 Radium in Water Ra-226 6.10 + .92 5.00 + .17 -2.07 Ra-228 9.10 + 1.37 8.10 1 72 -1.26 02/86 Tritium in Water M-3 5227 + 523 5143 + 393 .27 06/86 Tritium in Water H-3 3125 [ 360 3050 [ 212.83 .36 01/86 Gross Alpha, Beta Alpha 315 4 +0 .34 In Water Beta 7+5 9.67 + .56 .92 07/86 Gross Alpha, Beta Alpha 6+5 5.33 1 58 - .23 In Water Beta 18 + 5 17.33 + 4.16 .23 02/86 Uranium in Water U-238 9 + 6 9+0 0.0 08/86 Uranium in Water U-238 4[6 3.66 [ .58 .10 70 -
1 C. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 27 continued (EPA Intercomparison Studies) 02/86 Gamma Emitters Cr-51 38 + 5 30 + 3.46
~
-2.77 In Water Ru-106 .00 7 5 < 24
i Cs-134 30 I 5 32.66 + 1.52 .92 Co-60 18 I 5 18.33 7 .58 .11 Zn-65 40 I 5 43.33 7 3.2 1.15 Cs-137 22 [ 5 24 ~ l .69 ..
10/86 Gamma Emitters Cr-51 59 + 5 54.67 + 3.05 -1.5 In Water Ru-106 74 7 5 78.00 7 11.27 1.38 Cs-134 28 I 5 32.33 7 1.15 1.5 ,
Co-60 31 7 5 32.66 7 1.52 .58 Zn-65 85 I 5 83.00 I 3.00 .69 I Cs-137 44 _T 5 45.66 [ 4.93 .58 04/86 Blind Performance Alpha 11.6 + 2.08 -1.84
! (Mixed a, B, gamma Ra-226 2.9 1 44 2.53 1 06 -1.44 in water) Ra-228 2.0 + .3 1.96 + .2 .19 Nat. U 576 4.33 7 .58 -
.19 Sr-89 7I5 12.00 7 2.00 1.73 Sr-90 7 I 1.5 6.33 I .58 .77 Co-60 10 [ 5 11.00 T 1.73 .34 .. ___
Cs-134 5+5 7.67 + 1.52 .92 Cs-137 575 6.33 7 .58 .46 Beta 35 [ 5 62.33 [ 2.51 9.47 10/86 Blind Performance Alpha 52 + 13 47.66 1 8.39 .58 -
Ra-226 6.3 + .95 5.27 + .20 -1.88 Ra-228 10.10 I 1.52 9.87 I .68 .26 Nat. U 876 8.67 I .58 .19 Sr-89 27 I 5 21.66 I .58 -1.84 6.67 I .58
~
Sr-90 -2.69 Co-60 18 + 5 17.33 7 1.52 .23 Cs-134 18 I 5 17.66 7 2.08 11 Cs-137 18 I 5 18.66 7 1.15 .23 Beta 75 7 5 81.33 7 3.21 2.19 02/86 Low Level Iodine I-131 916 9.33 1 1.52 .10 In Milk 06/86 Radionuclides in Sr-89 0+5 7.67 + 2.08 2.65 Milk Sr-90 16 I 1.5 10.33 7 1.15 -6.54 I-131 4176 44 I 2.64 .87 Cs-137 31 I 5 36 I 1.00 1.73 K 1600 [ 80 1633.33 1 106.92 .72 11/86 Radionuclides in Sr-89 9+5 No Data Provided Milk Sr-90 0 + 1.5 No Data Provided 1-131 4976 59.33 + 6.11 2.98 Cs-137 39 I 5 44.33 7 2.08 1.84 K 1565 [ 78 1524.33 [ 65.29 .90
4 TABLE 27 continued ( L' P A Intercomparison Study) 01/86 Radionuclides in Sr-89 25 + 5 No Data Food (pCi/kg) Sr-90 10 [ 1.5 No Data I-131 20 + 6 18.33 + 2.31 .48 Cs-137 15 7 5 16 7 0 .34 K (mg/kg) 950 7 143 866.67 7 11.54 -1.00 07/86 Radionuclides in Sr-89 30 + 5 No Data Food (pC1/kg) Sr-90 19 [ 1.5 No Data I-131 30 + 6 29.66 + 2.51 .10 Cs-137 20 7 5 22.33 I 2.88 .81 K (mg/kg) 1150 [ 58 1153.33 [ 15.27 .10 l
l l
l 1
l l F
SC p
(
s t) ct ue dw o
rg Pk 0 0 0
/ 6 6 8 d1 oC op F(
S I
S .
Y L )
A 2 N k/
A li 1 5 8 5 iC 1 1 1 E Mp L c, ( .
P d M b e A ) s S D L
u L L ) e A ( t -
b T e N N w, y E O h a M I sg 0 0 0 0 0 0 m D N T i k 3 6 3 6 3 5 E O C F/ 1 2 1 2 1 1 1 R R E i /
8 ,
,I I T C f 2 U V E p C Q N D ( p E E E F
L R 0 B R O 0 A ,
O 0 T C F T 3 R I e N SE M t f I a o I L l)
T u3 e I R cm u L E i/ l I W ti a B O rC v A L ap 1 7 5 6 P P( 0 0 0 0 a A
C es 0 0 0 0 ,
na s N rG t O o s I br i T ro x C i e
E A T y E a D w h
t a
p
) r 1
- d e r/ 4 0 5 0 5 0 5 I 5 8 5 t ei 0 1 3 1 3 1 1 1 1 a tC 0 w ap 2 W( g n
i k
a n i
t 0 r s e 0 5 4 d i b 6, 9 1 s - 4 7 - o y s 4 9 8 5~ b 1 3o 3 a n l s 5 5 5 6 N 3 1 1 L a o 3 - - - - - 1 - - - f n r - n e o n r - s s a I A g 1 1 M F C Z Z I C C B *
~
p 7 ,
i47 p ,j
] t :
) 3 3 3 2
( L h 3
/
m n
/
1 L I
C
/
/m /m 1
1 C
1 C
o L C L L L L L Lt L L / L P C F P i / P / / / / /1 / /1 / 1 / P s t 1 i 1 1 1 1 1 C 1 1 2 2 ct C 0 C C C C C C C C F C 0 4 0 0 ei P 0 P P F P P P P P P 0 0 0 0 t m 5 4 bi 4 1 3 '5 3 3 5 3 4 4 1 5 0 0 0 'O I'L
)
s 4-1
(
, . e i
r ,
m uT A A A A A a / / / / /
r my N N 4 4 4 4 4 4 4 4 4 4 N 2 N N S y i a xc E
I h
t mDe T h I t L l I a B b I A
P l A ac )
C i .
g n N o gi O oi l
i(
nm 9 I t 0 0 0 0 0 0 0 0 0 0 2 T d ner 0 0 0 0 0 0 0 0 0 0 0 0 E
C aR E OT mi 0 3
0 1
4 1
4 1
4 1
4 1
4 1
4 1
4 1
4 1
4 1
h 1
0 2
0 6 6 0
6 0
L T -
B E A
T D oin Y t c
R e 3 l O t t L L m m0 T e ee 3 3 0 A D l u pq 0 2 L L L L L L L L L L m m0 0 0 R f ri 0
1 0
0 5 5 5 5 5 5 5 5 5 5 0
0 0 0, 0, O o al SA
. 0 0 0 0 B t 0 0 3 3 3 3 3 3 3 3 3 3 1 1 1 1
. A i L mi l L iD r O a w Wy t
o c) nm eo 2 B 7 3 4 7 0 4 0 5 id 2 1 2 1 1 3 2 2 0 1 0 5 5 c/ 1 1 0 0 0 0 0 0 0 0 0 0 3 2 1 1 i m 3 3 0 0 0 0 0 0 0 0 0 0 4 0 0 0 f p f c 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E(
l n
x) nmp q6 9 2 2 2 1 2 3 2 3 3 2 9 8 2 2 k( 0 C 'O '2 'O 0 O 0 0 0 0 0 O O 0 0 0 0 B '
B' x
i r r er r r r r r r r r r r e e e e e e e a e e a t
h t
a t
a t
a t
a t
a t
a t
a t
a t
a t
a t
a t
a !
r I j fr- i r r W W W W W W W W W W W W A A A A 0 '
4 4 5 1 a - 1 4 7 - a 1 r
e t
e a
s 8
5 6 0 &5 t
9 3
1 3
1 3
1 n
u t
b 3
1 P n t
e*
- s i n m5 a
9 y
- i t
- t t nu at r -
mo nna n
iut 5
6 i
s e
n 4
3 7
j a s t g r larh 1 t t l t c n i 1 r o i n tn s s rn n b r c ml i d 1
t a r r n oi l o e s P c Rte I C CZl I I c eua Ct t i Z o t r
C C 8 yb ,
ll'
t i
i 4
m i
5 9 L 1 :
~
n g o
rx g
r r x 1 g g g t , g K tt x i g g rJ L K /
r K K K F / i / L e c/1 /
1
/
1 A
I
/
1
/
1
/
1 L
/1 L
/
L
/
/
1 C
/1 C
/
i C
1 C r t
1 C 1
/
b .
e C C C C C 1 i P P P P F TU t
c tN F F K F F F C F M C P 0 c e 0 0 0 0 4 0 0 0 1 1
0-91 O D02 0 0 4 2 3 4 4 4 1 4 2 2 3 2 3
. )
iy i a *
. D .
.( I
. me um ~
~
0 0 0 2 2 mi 2 2 2 2 2 2 2 3 3 3 1 1 1 1 1 3 iT xay 1 1 1 1 1 1 1 3 e
Ma c ~
e D
)
- gn '
ni 0 0 0 0 0 0 0 0 O 0 0 0 0 0 0 0 0 0 0 o im t( 0 1 0 0 0
0 0 0 0 0 0 4 h 4 1
h 1
0 4 4 0
4 0 0 2 2 a 1 1 1 1 1 1 1 1 n
ue om C.Ti -
rx rx
~
L L L L rx rx g
et x Fx ir rx Y x x T g
K 5 5 5 5 r 2 2 L
~
lpuo F F 2 2 2 2 2 2 3 3 3 3 I 1 I 0 0 1 mq ai Sl A
9 2
y)
E cm )
3
)
3
)
3
)
3
)
37 L nt ( ( ( ( (4 B ed 4 6 I
A i/ 5 0 4 7 0 4 8 7 0 4 5
T cm ip0 2
2 7
1 3
2 8
1 0
1 0
2 0
2 0
3 0
2 0
2 0
0 0
3 0
2 0
2 0
5 6 0 0 3 0 1 0 0 0 0 0 0 0 0 0 0 0 0 f c 0 0 0 0 0.
f( 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E
d m
t) 6 7 om rp 2 2 2 1 3 2 2 4 2 3 3 3 2 2 0 0 1 0 0 0 O 0 O 0 0 0 gc 0 0 0 0 0 k(
c B
a' 1
t t e e ec n n imL e e c r u u fu a x hs h sh h h k k k k f t o
ce re Ws t Ce h h s s s l l l l o r m d .
i s s i i i i i i i i i r c r i i F F F M M M M P t t F F F F 1
a . -
1
- 0 _
r k 4 I e e 5 1 s 7 - 1 4 7 : 7 v t -
4 3
7 3 3 '3 3 s 3 3 3 13 3i ee 8 0 1 1 u 1 1 1 1 1 t m sw 5 6 1 1 1
> c a
9 5 t t
6 5 w r
s r
u r e r >
t w em ss h im t
w s
t e
t n i5 =9 s
i 11 i
r r
a m n-l a
l a
e i t
t s
i i l s t' i t sr i i i s s i_ s11 a b bt n ise e eil I v__ e eC r aCTh1 u o eC , _ l&
r r o c_
Ph t 1 C O Z C C I ci I C
' y:
z 7- , i llll t
m-----
f l
l l
l i
l l
l This page leit blank intentionally 1
l,
- l l
l i i
j
'l 1
l 1
4 i.
4
1 n
i p
s 1
APPENDIX B l
e i*
C Q ,
ic M
n r
i 1
4 This page left blank intentionally
.r . _ - - - - - - - - - - - - - - - -
.ag .
aV ll R!
i Determination of Gross Beta Activity in Airborne Particulate Air Filters for Gross Beta
- 1. PRINCIPAL 1.1 All airborne particulate samples contain both natural and man-made
. radioactivity. A screening technique is used to determine the quan-tities of beta-emitting nuclides. Based on results obtained from this screening technique, the need f or radiochemical analysis is
', determined.
- 2. APPLICATION .,
2.1 This method is applicable for determination of gross beta concentra-tion of airborne particulate collected on a filter, or any other material collected on a filter where self absorption can be ignored (for example, wipes).
- 3. RANGE 3.1 In reality there is no upper range. A practical upper range is approxi-mately15 x 10 5 beta counts per minute. Above this level, there is a r significant decrease in counting efficiency.
- 4. INTERFERENCES 4.1 Since this is a gross analysis, there are no. interferences from other nuclides. Samples collected over a long period of time, or samples collected in an area with a high concentration of airborne particu- .
late matter, may result in filter overloading. Part of the collected particulate matter may then flake off the filter, yielding a non-representative sanple.
- 5. LOWER LIMIT OF DETECTION 5.1 The lower limit of detection (LLD) is defined as the. smallest concen-tration of radioactive material sampled that has a 95% probability of being validly detected.
Ltg . 4.66 sb 4.44 X L X b Where 4.66 = 2/2 k, where k is the value for the upper percentile of the standardized normal variate corresponding to the preselected risk for concluding falsely that activity is present = .05.
Sb=
Standard deviation of the background 2.22 = dpm/pci E = Fractional Counting Efficiency S = Sample Size
- 6. PRECISION AND ACCURACY 6.1 Inaccuracies are primarily attributable to samples containing beta emitters of different energies than the calibration standards or a large amount of particulate matter being accumulated on the filter creating some self absorption, and some of the collected particulate matter may flake off.
y l w
~
L .
6.2 Analyzing " filters containing known amounts of Sr-90 and Cs-137 pro- .
duces results'within 10% of the known-value at the 95% confidence level. For standard samples close to background, the 95% confidence
- interval is approximately 5 pC1 per filter.
.. 7. SHIPMENT AND STORACE OF SAMPLES AND SAMPLE STABILITY 7.1.. Sampics are shipped by purolator carrier, 1 day service and counts must be made after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 8. REACENTS-8.1 No. reagents are used.
- 9. ' APPARATUS 9.1 Tennelee planchet system and wide beta counter.
~
9.2 Filter - AA Iype - Millipore.
- 10. PROCEDURE 10.1 Air filter samples with their field data sheets enclosed are received in.the mail and their receipt date documented.
. 10.2 Filter is placed in a planchet to be counted. The filter is held in-place with baseline placed on the edges of planchet.
10.3 Iilters.with sto filter and a background are counted for 20 minutes each .cn1 both the alpha and beta plateau.
- 11. CALIBRATION 11.1 A series of millipore filters, a variety 47 mm with matrix composed of tale, calcium carbonate and 245 mesh free silica and corresponding to density thickness from 1-10 and Sr-90/Y-90 activity taken to dryness and beta counted. An efficiency factor can be determined for the counting system which is specific for a particular instrument.
L 12. ' QUALITY COI; TROL '
12.1 Each morning a background and beta check source is beta counted. The results are recorded and appropriate quality control charts are maintained.
j 12.1 Samples are counted with a blank filter and standard in each set.
l 1$. CALCULATIONS 13.1 Gross Beta (pC1/m3 ) = nepm 2.22 E V l
Where nepm =
gross counts - background counts / counting time l _ 2.22, = dpm/pCi j L E =
Counting Efficiency V = Sample Volume (m3 ).
This is reported with a 2 sigma counting error.
4 Error pC1/m3 = / gross epm + bkg epm ( x 1.96 = cpm s
Time dpm x V x ef f l
)
s 1
b Fish Samplesi Fish samples.are delivered to the lab ~ frozen. -
Two sources are represented, with several fish from
~
.each source. 'The two-sources are kept separated during sample preparation. Analysis is on the edible. portion of the fish.
1 To prepare the sample for analysis, the frozen' fish is allowed to thaw overnight. The fish is weighed to find a total weight. Scales are scraped off, and fins, head, and tail are removed.. The bones' are removed and the remaining fish is weighed, cut into smaller pieces, and placed in a blender container, Distilled water is added to the fish pieces in the blender container, to obtain a homogeneous purec.
After blending the sample is poured into a'Marinelli beaker for counting:
_ . . ___._m____ _ . . _
Ff01T & PRODUCE SAMPLES
- 1. Weigh total fruit sanple in tared beaker or weighing vessel. -1
- 2. Out sanple in pieces to accommodate the blender. i I
3 . Blend in_ waring blender starting with low speed and progmssing to !
nedium speed. Approximately 200 mis of H2 O to 500 mis of sanple is i
- 4. Another weight is taken of the blended sanple.added at $ntervals to
- 5. 'Ibe sample is then ready to be pnrna counted.
i i
0
1 if n.
- - SEDINENI' & SOIIS Dry samples overnite at 100*C. If necessary gr$14 and sieve the sa@le prior to analysis. Wet and dry weights will be reported with the analytical results. If the sa @ le requires sieving, the weights of both the plus and minus 35-mesh (0 500 mn) fractions will also be reported. The analyses will be perforned only on the minus 35-mesh fractions when they cornprise 50% or nore of the dry weight. If the plus 35-mesh fraction comprises nore than 50% of the dry sa@le weight, pebbles ard small rocks (greater than about 0.25 inches in diameter) will be removed and the plus 35-mesh fraction reweighed. If the plus 35-mesh fraction still exceeds
- .F 50% of the dry sanple weight, the material will be ground and blended with the minus 35-mesh fraction and the analysis performed on the entire sagle minus peb-bles and small rocks.
4 1
1
Isotopic Analysis By Gamma Ray Spectroscopy Using ,
Thallium-Activated, Sodium Iodide Crystals 1
\
- 1. PRINCIPLE.
1.1 Environmental samples 'contain varying amounts of naturally occur-ring and man made radionuclides. Analysis of a sample's gamma ray spectrum method requires minimal sample preparation for identifying and quantifying the gamma-emitting radionuclides which are present.
- 2. APPLICATION 2.1 This method is applicable for analyzing all types of samples which can be homogeneously placed in a standard counting geometry and %, !
contain radionuclides emitting gamma rays with energies ranging from approximately 60 thousand electron volts (60 kev) to 2 mil-lion electron volts (2 MeV).
l
- 3. RANCE 3.1 There is no upper range for NaI(Tl) gamma spectroscopy. The elec-tronics have an upper limit of approximately 1 X 106 detector counts per minute (cpm). If a sample contains radionuclides concentrations, resulting in a count rate of greater than 1 X 106 cpm, then either the distance between the sample and detector is increased or an aliquot of the sample is analyzed.
- 4. INTERFERENCES 4.1 ,1f the spectra for 2 or more radionuclides have an overlapping photo-peaks, then the spectrum of a sample containing these nuclides can be resolved with an increase in the error terms associated with the nuclides. If the nuclides have identical or very similar spectra, the spectrum of a sample containing these nuclides cannot be directly resolved by this method.
- 5. MINIMUM DETECTABLE CONCENTRATIONS 5.1 The minimum detectable concentrations (MDC's) of individual radio-nuclides are dependent upon the following factors:
- a. branching ratio of radionuclides in question
- b. energy of gamma rays being emitted
- c. sample size
- d. the geometry in which the sa=ple is contained
- e. length of count
- f. number of gamma-emitting radionuclides present in the sample For example, if Cesium-137 is the only radionuclides present in a 3.5 liter liquid sample contained in a 4.-0 liter Marinelli beaker and
- counted for 100 minutes, then the Cesium-137 MDC is approximately 5 picoeuries per liter (pCi/1).
i
- 6. PRECISION 6.1 The 2 sigma 95% confidence interval for a result obtained by Camma Spectroscopy is approximately the MDC for samples with gamma activities close to background or 10% for samples with higher activities, i.e., the 95% confidence interval is the MDC or 10%, whichever is greater.
i l
_ _ _ - _ - _ _ _ - - _ _ J
k This is based on non-overlapping gamma photopeaks. In the case of photopeak multiplets, the precision decreases with the degree of overlap.
l
- 7. SHIPMENT AND STORAGE OF SAMPLES 7.1 Samples containing or suspected of containing short lived radionu-clides require expeditious handling. Care should be exercised with all samples to be sure that they are, and remain, representative and homogeneous. This may require the addition of acid to water samples to prevent dissolved nuclides from plating out on the sample container's walls, the addition of formaldehyde to aid in the pre-servation of milk samples, etc.
- 8. REAGENTS 8.1 Radon-Free water is used for dilutions of aqueous samples to a con-stant volume.
- 9. APPARATUS 9.1 Beaker, Marinelli, Plastic, 4 liter 9.2 Can, Aluminum, 200 ml 9.3 Container, Polyethylene, 400 ml
. 9.4 Crystal, 4 by 4 NaI(T1) 9.5 Planchets, Stainless Steel 2 inch 9.6 Spectrometer, Gamma l
- 10. PROCEDURE 10.1 Prepare homogeneous sample in a standard geometry. The standard geometries are
, a. Sample contained in 2 in planchets.
l b. Aqueous samples (3.5 liters) contained in 4 liter polyethylene Marinelli beaker.
- c. Soil sample equivalent in volume to 100 ml of water contained in 200 m1 scaled aluminum can.
- 11. VARIANCES 11.1 Planchet, stainless steel 2 inch instead of 5 cm of 11 cm diameters.
11.2 Polyethylene Marinelli 4 liter beaker instead of 4 liter Aluminum Marinelli Beaker.
11.3 Cs-137 and Co-60 used f or calibration of instrument instead of Bi-207.
- 12. CALIBRATION 12.1 Cesium-137 emits gamma ray with energy of 0.66 MEV and Cobalt-60 emits gamma ray energies of 1.17 MEV and 1.33 MEV. Adjust the amp-11fier gain and threshold controls until the .66 MEV forms a photo-peak whose centroid is in channel 132 and the 1.17 MIV gamma forms a photopeak centroid is in channel 234. The 1.33 MEV forms a photo-peak whose centroid is in channel 266. The 1024 channel gamma spectrometer is now calibrated from 0-2 MEV at 0.04 MEV per channel.
12.2 The capability to quantitate a particular radionuclides from a gamma ray spectrum is achieved by counting a known standard of that radio-nuclide in each geometry used.
- 13. QUALI1Y CONTROL 13.1 The NaI(Tl) gamma spectrometer is energy calibrated daily. Logs and quality control charts are maintained.
13.2 Known standar-s for quantification are counted as needed.
13.3 Approximately 10% of all samples submitted for gamma spectrum analysis are resubmitted as blind samples. The results of these duplicate analyses are submected to standard statistical tests. A summary of the results from the statistical tests, along with the individual analytical results, are logged in hard back books. Results outside control limits are examined for possible remedial actions.
13.4 Standard samples are received from the EHSL-LV, Quality Assurance Branch, Las Vegas. These samples are analyzed and the results are analyzed by the originating office. If the results are unsatisfac-tory, the reason for the anomaly is found and all results generated during the questionable time period are evaluated for possible cor-rective action.
- 14. CALCULATIONS 14.1 Nuclides are identified by the presence or absence of photopeaks and their ratios to each other.
14.2 Identified radionuclides are manually quantitated by:
- a. Integrating one of its photopeaks. *
- b. Subtracting the area of the photopeak beneath the continum.
- c. Comparing the epm found in this net area to the cpm found in the corresponding area of a known standard of that radionuclides counted in the same geometry on the same gamma spectrometer.
- d. Many types of environmental samples, which must be analyzed rou-tinely, have a f airly constant radionuclides content which is limited to a specific minimal number of nuclides. Examples are milk contaminated with 10 day or older f allout, 30 days or older atmospheric fallout particulate, or effluents from normal reactor operations if short lived nuclides are decayed out.
A convenient method for the quantitative analysis of this type of sample is the simultaneous equation method. This method entails a mathematical approach for eliminating compton interferences from photopeaks. The only requirements for application of this method are:
- 1. That all nuclides present in the sample are identified.
- 2. That a different photopeak be present for each nuclide in the sample. This does not exclude the possibility of many overlapping peaks.
- a. Interference Factors are calculated.
- b. Simultaneous Equation Nx = xx + f yx yy Where f = Interference factor which expresses the fractional I contribution of the photopeak channel of nuclide i Y to the photopeak channel of nuclide X. l A similar development can be done for the net count rate in the photopeak channel of nuclide Y(N ), resulting in the equation: Ny = Y y + F xy Xx l
Nuclide X pCi/L = Xx (Ef f . ) (Vol. ) (2.22),
s (Eff.) (V .) (2.22)
I
- 15. REFERENCES John, F.B., Hahn, P.B., Thome, D.J. and Bretthauer, E.W., Radiochemical 3 J l Analytical Procedures for Analysis of Environmental Samples.
g U,S. Department of Health, Education, and Welfare - Public Health Service.
f Radionuclides Analyses By Gamma Spectroscopy Training Publication No. 327N. ;
f f
1 i
)
L i
Preparation of samples and standards for Ganna Spectral Analysis taken from the Training Publication No. 305N,Section V. Page 1.
Fish Food Products Sediment Water Airborne Particulate or Gas Milk l
i l
1 i
Milk:
Pour 3.5 liters of milk into Marinelli beaker and Gamma count.
Water:
Tap, surface, well and cistern water are normally counted in Marinelli beaker.
Precipitation samples are usually counted in cottage cheese or smaller containers due to their higher specific activity or limited volume of available sample.
Food Samples:
Arehomogenized(i.e.lettuceandpotatoes)inablender, garbage disposal unit or other types of grinders. After
' blending, the samples may be poured directly into a Mart-nelli beaker for counting, or the blended sample may be ashed and the resulting ash placed in a cottage cheese dish or other suitable container for counting.
Vegetation Samples:
Are blended, if possible, and processed as food samples.
Soil Samples:
Are prepared for gamma counting by drying and then grinding the dry material into a fine powder or by ashing as above.
- E6 -
- . - - . - - - . - . - - - ~ - - - -- --
t ISOTOPIC ANALYSIS BY GAMMA' RAY SPECTRA USING INTRINSIC GERMANIUM DETECTOR
'1.- PRINCIPLEi 1.1. Environmental levels of gamma-emitting radionuclides in a multitude
, of natura1' matrices are identified and quantified by gamma scintil '
lation spectroscopy. - However, in numerous cases : the success in resolving complex spectra is limited by reason of resolution in-Teases where: peak multiplets are within.the resolution'11mits of the-scintillation detector, computer. deconvolution becomes impossible.
These cases require the employment of a solid' state "high resolution" detector generally constructed of lithium drifted germanium, Ge(L1) or intrinsic germanium. The-average / resolution advantage of a high volume L(Ge(Li) detector over a NaI(TI) scintillation detector .is about.40. For this reason, Ge(Li) detectors are used fori hetanalysis of gamma-emitting' radionuclides in the environment.
2.- APPLICATION 2.1 This method is applicable for. analysis of gamma-emitting radionuclides with gamma energies ranging from nearly 60,000 ' electron volts (60 kev) to approximately'2,000,000 electron volts (2 MeV).
- 3. RANGE 3.1 There is no upper range for Ge(Li) gamma spectroscopy. The electro-nics have an upper limit of approximately 3 x 106 cpm, then either the distance between the sample' and detector is increased or an aliquot of the sample is analyzed.
. 4. INTERFERENCES 4.1 The use-of Ge)Li) detectors has greatly reduced the problem of interferences between gamma photons of nearly' identical energies.
Spectral peaks containing multiple energy contributions may be deconvoluted when actual photon energies are within 1 kev.
1
- 5. MINIMUM DETECTABLE CONCENTRATIONS 5.1- The minimum detectable concentrations (MDC's) of radionuclides vary according to the particular branching ratio of a radionuclides upon disintegration, the counting geometry, the photon energy, sample size, and the actual counting time of detection. One thousand minute counts are reasonable for low level environmental samples. The MDC of cesium-137 for such a count time is approximately 5 picoeuries per total sample. This is based on a 200 m1 sample placed dir-ctly upon the detector.
- 6. PRECISION 6.1 The 95% confidence interval for a result obtained by gamma spectro-scopy is approximately the MDC for samples with gamma activities close to background and 10%, whichever is greater. This is based on nonoverlapping gamma photo peaks. In the case of photopeak mul-tiplets, the precision decreases nonlinearity with the degree of peak overlap.
L
- 7. SHIPMENT & STORAGE OF SAMPLES 7.1- Samples containing or suspected of containing short-lived isotopes require expeditious handling. Care should be exercised with all samples to assure that they are, and remain, representative and
. homogeneous. This may require the addition of acid to water samples to prevent dissolved radionuclides from plating out on the sample container walls, or the addition of formaldehyde to aid.in the pre-servation of milk samples, etc.
- 8. REAGENTS 8.1 Radon-free water is used for dilution of aqueous samples to a con-stant volume.
- 9. APPARATUS 9.1 A ND Series 66 computer-based gamma spectrometer system with a shielded 15% 2.0 kev resolution intrinsic Ge detector (1983).
- 10. PROCEDURE 10.1 Prepare homogeneous sample in a standard geometry for counting.
This geometry must be equivalent to one for.which the detector has been calibrated to generate an appropriate efficiency vs energy curve.
10.2 Place semple in counting configuration.
10.3 Refer to manufacturer's operating manual for data acquisition and I computer operation.
10.4 Print spectrum and/or store on appropriate computer-compatible device.
- 11. CALIBRATION 11.1 To energy-calibrate, Ba-133 with a gamma emission of 81 kev and Y-88 with a gamma emission at 1836 kev are used. By adjusting the ampli-fer's gain and the analog-to-digital converter's "zero' offset," the centroids of these peaks are placed in the appropriate locations for a linear " energy-versus-channel-number" calibration. Due to the high resolution and stability of current detectors, there should be negli-gible differential nonlinearity.
11.2 Efficiency calibration is achieved by counting a standard in a given geometry where the concentrations of the isotopes are known. The results of this calibration is an efficiency-versus-energy curve in units of counts per gamma. A mixed radionuclides source is generally used which produces peaks well spaced and distributed throughout the normal analysis range.
I
- 12. -QUALITY CONTROL 12.1 The Ge system is energy calibrated daily and efficiency calibrated as needed. Logs of pertinent calibration data are maintained.
12.2 Approximately every 10th samples is run as duplicate. One sample i of each matrix is run as a spiked sample. Results outside control limits are examined for possible remedial action.
12.3 Standard samples are received from the EMSL-LV, Quality Assurance Branch. Thses samples are analyzed and the results are analyzed by the originating office. If results are unsatisfactory, the reason for the anomaly is found and remedial action are taken.
- 13. CALCULATIONS 13.1 1sotopic identifications from Ge gamma spectral data are made by the computer as follows.
- a. Identify all peak energies.
- b. Calculate all peak areas by integrating the peak region and subtracting the area beneath the continum.
- c. Identify isotopes by the presence or absence of appropriate photopeaks and their ratios to each other.
13 . 2 The concentration calculations for each isotope is:
A isotopic concentration (.Picocuries ). 2.22 x B x E x S 7 T unit of size A = Peak area above continum (counts)
B = Branching ratio for the gamma ray of the particular isotope in question (gammas / disintegration)
E = Fractional detector efficiency at photo peak energy (counts /
gamma)
S = Sample size T = Count length (minutes) 13.3 The 2 sigma counting error is calculated by:
Error (%) = 2/ A + 2 C x 100 A
C = Photopeak area below continum (counts) 13.4 To extrapolate to the time of collection, the following f ormula is applied:
Co = CelAT Co = Concentration at midpoint of collection Ce = Concentration at time of count 1 = En 2/tb AT = Time of count minus time at mid-point of collection (days) 13.5 The 2 sigma counting erroe expressed as a percent does not change under the extrapolation of 13.4, therefore, the 2 sigma counting error expressed in units of concentration is:
Error (Concentration) = Error (%) x Co 100
- 1. PRINCIPLE: A sample of water or vastewater is treated by alkaline permanga-
~
nate and distilled to remove quenching materials and nonvolatile radioactivity.
Complete transfer of tritiated water is assured by distilling to dryness.
A sub-sample of distillate is mixed with scintillation solution and the beta ;
activity is counted on a coincidence type liquid scintillation spectrometer.
- 2. _ PRECISION & ACCURACY: 1000 pC1/L 10% at 95% confidence limit. '
- 3.
REFERENCE:
Standard Methods; 15th Edition, p. 603,
- 4. VARIANCE: 2 ml of sample to 20 ml of cocktail Scintillation Sol.-Beckman's Ready-Solv. G.P.
- 5. MATRIX: Water (potable, ambient) 6.
PROCEDURE: Add two pellets of NaOH and 50 mg of KMnO4 to 50 ml of sample,
- a. Distill sample to dryness. Discarding first 10 m1, 2 ml of distillate is added to 20 ml of Beckman's Ready Solv. G.P. Cocktail. The samples are adaption.
mixed by shaking and then placed in the counter for 3 hrs dark in triplicate.
Sample setup consist of bkg-sample, with sample being done Standards consist of known cross check samples. Each sample is counted for 100 minutes.
b.
Instrument is thc LS-233 Beckman's Ambient Temp. Liquid Scintillation Spectrometer.
It offers outstanding analytical performance at room temperature with a 200 sample capacity and full two or three channel capability.
It has full electronic computation and teletype writer print out of counts or epm and 2 sigma statistical counting error in each sample data channel.
- 7. ROUTINE PERFORMANCE TESTS A 20 minute run each day of a sealed background and standard. The response is logged in the instrumental log book.
- 8. CALIBRATION STANDARDS Scaled set of quenched H-3 standards with efficiency of 0.106 to 0.564.
- 9. IN HOUSE QUALITY CONTROL A cross check sample with its own background is setup with each unknown sample. Results calculated and logged in instrumental log book.
- 10. INSTRUMENT LOG BOOK Found in Room 305
- 11. INSTRUMENT REPAIR BOOK Found in Room 305
- 12. INTERFERENCE REMOVED Non Volatile Radioactivity and Quenching Materials
l I
- 13. INTERFERENCES Volatile materials e.g. iodine, radium TRITIUM CALCULATIONS I. QUENCH CURVE CALCULATIONS A. Obtain value for tritium activity from label on quench standards. This value will be in units of disintegrations per minute abbreviated DPM.
B Correct tritium activity in quench standards for decay as indicated j below:
i Where: DPMcor = Corrected tritium activity in quench standards as per date of analysis
. COR FAC = Correction Factor
Reference:
Radioactive decay correction f actors; Public Health Service Publi-cation No. 999-RH-12, p. 68 DPM = Tritium activity indicated on quench standard label.
C. Calculate efficiencies for each of the six quench standards as indicated below: ;
EFF = NCPM DPMcor
\.
! Where EFF = Efficiency i
k NCPM a Net counts per minute determined by subtracting the
! counts per minute of the sealed background from the counts per minute of each of the quench standards.
DPMcor = Corrected tritium activity as per date of analysis.
i D. Plot each of the six efficiencies calculated above against their corre-
- sponding external standard ratios which are found on the liquid scintil-
{ 1ation print out when the quench standards are run.
t E. Use linear regression to determine the best line through the points that were just plotted. By entering into the Linear Regression Program the external standard ratios that appear when samples are run, the corre-ponding ef ficiencies can be determined.
II. SAMPLE CALCULATIONS A. Obtain the external standard ratio for the sample from the liquid scin-tillation print out. Find the corresponding efficiency as mentioned in part I-E. Do the same for the background.
B. Calculate the picoeuries per liter of tritium in the sample as indicated below:
BKG CPM eff, x 0.002 x 2.22 effb x 0.002 x 2.22 Where; pCi/L of H-3 = picoeuries per liter of tritium CPM = counts per minute in sample found on liquid scintillation print out BKG CPM = counts per minute in background found on liquid scintillation print out EFF s =
sample efficiency determined as mentioned in Part II-A EFF3= background efficiency determined as mentioned in Part II-A
APPENDIX C
l 1~
l s,
i l
n This page left blank intentionally
.~i-----_--L--_-_-_
Section No. 4.6 Revision 10.
Date October 1, 1984 Page 1 of 5
- 4.6 Quality Control Program for the Padiation Unit. .
he following quality control reasures are used by the Radiation Ihit in the analysis of sa@les:
. _ _ _ _ _ . . . . _ _ .. ~~ ~
-~ ~ ~ ~ ~'~~
- 1. Use of prescribed rethods of analysis.
- 2. Initial rethod validation.
3 Instrumnt performance checks.
- 4. N thod blanks.
5 Intemal quality control standards.
- 6. Internal quality contIol sa@les.
- 7. Duplicate samle analysis.
- 8. Spiked sa@le analysis.
9 calibration verification.
- 10. Extemal quality control sarples.
Se analyses performd by this urdt inclut gross alpha and gross beta particulate activity in water and air; gama isotopes aslysis in water, air, sedicent, food, fish, and milk; radium in water, strontium in water, food, and tilk; uranium in water; and tritium in water.
N thod of Analysis
'Ib obtain censistent, reliable sarple data, only rethods that are acceptable to the data user and that have been validated in this laboratory are used to analy::e carples. Rese nethods are documented in the Padiation Iaboratory Procedures Manual.
An analysis will not be conducted for any parareters for which a procedure has not been validated or for which trained perscnnel are not available. 'lhe Environ-rental Cheristry Subdivision W12.1 develop special rethods as requested if adequate resources are avni1nhle.
Initial Method Validation he purpose of an initial rethod validation is to demonstrate that the unit responsible for sarple analysis can satisfactorily perform the analysis on the rntrix of interest. In brief, the initial rethod validation is a study of recoveries of analysis that have been spiked into the retrix of interest. 'Ibe validation procedure is corpleted for new analytical procedures before their use
~
with sarples.
'Ibe nuclide or group of nuclides is spiked into four aliquots of sarples.
he spike level is usually five to ten tires greater than the estimated method detection licit. Rese four spikes along with an undosed aliquot 'of sa@le and a rethod blank are analy::ed by the pIVposed rethod. ' he nethod blank analysis is included to demonstrate that contardnation and artifacts are not introduced during the procedure, 4
1 Section No. 4.6 Fevision No.
Date. October 1,1984 Page 2 of 5
{
The percent recoveries of the,ibur spiked sa::ples are calculated along with I a rean and standard deviations. Control 11mitJ are established as a rean plus or l udnus 318 standard deviaticn which cormt;x>nd to a 95% confidence interval.
When these limits are used to monitor subsequent spike recoveries, about five - - -
percent o* sanple data is expected to be mleased with qualification. As more spike recovery data becomes available, the control limits are updated. Se results r>f the nethod validation stucty a.m mtained in the file of the QAO.
To ensum that the analytical capability is reintained and to detect any significant changes that usy have occurred in the accuracy end precision of the rethods used, a nethod validation Smeedure is empleted ouarterly. Por the quarterly procedure, two internal quality contml senples and a nethod blank are analyzed. Rese msults am evaluated using the previously established control l'mits.
If a rajor change is unde in the analytical system, for exarple, the introduct-ion of a new chemirt or new instrumentation, or if a quarterly validation schedule (
has not been naintained, the nethod validation procedure will be repeated with four j spiked replicates and a blank before sanple analysis is mstmed.
i Instru: rent Perfbrnance 01ecks Be performance of each instrtrent in the Radiation Lbit is monitored on a daily basis, his check consists of two parts: a) the reasurenent of instrunert background; b) neasuremnt of a "high" activity standani - the perfomance standa-d.
he response of the perfoIT:ance standard is checked against the control limits established for the instrumnt befom sample analysis begins. %e background count is urnitored to ensure that counting '.;dres are of sufficient length to provide the necessary precision. Fesults of these checks are recorded on control charts and documnted in the instru::ent logbook.
Fhthod Blanks A method blank is analyzed with-each batch of sanplen to check for ecntamination in sanple tmatrent, reagents, and glassware. Be nethod blank is an aliquot of deionized water or rounting reagent analyzed with the identical procedure used for . ;
samples. %is blank must be free of interferences befbre cample ana. lysis ccntinues.- i Sa:ple results am not corrected with rethod blank values. If the net count rate for a nethod blank is greater than the instrurent background, the sanple analysis is !
invalidated, j J
l f
l l
f l
l
Section No. 4.6 Revision No.
Date. October 1,1964 Page 3 of J Intemal Quality Control Standards -
Intemal quality control standards are reference standards prepared by the QA0 from concentrated solutions c5rpined from the USEPA Environmental Monitoring and Support laboratory in Las Vegas or . purchased from the National Bureau of Standards.
Bese standards serve as a check-oi the preparation of calibration standards, whether prepamd in-house or purchased, and on the instrument calibration. h e frequency with which these quality control standards are analyzed varies with each type of instrumnt and with each nuclide. Control limits have been established for the reference standards based on the previous instrument performance. h e data is plotted on quality control charts and in the quality control logbooks and checked for out-of-control data, trends, and biases.
Internal Quality Control Sa m les To maintain a quarterly validation schedule, internal quality control sa@les are prepared by the QAO. Bese samples are prepared for each analysis by spiking a entrix containing little or none of the nuclide or radiation of interest with a knwn amount of nuclides. The intemal quality control sa@les are analyzed as un-knowns, ie. with no knowledge of the concentration or co@osition of the nuclides added. he results of these sanples are used to ronitor the perfomance of the entire analytical procedure.
Duolicate Samole_ Analysis Duplicate sarple analysis is to analysis of two separate aliquots of the sare field sa@le. bis analysis serves as a check on the laboratory subsa@ ling technique and on the reproducibility within an analytical run.
For each matrix-type of sample being prepared, one duplicate is taken through the entire sample preparation and analytical pmcedums. Par those rethods requiring total sample analysis (eg, ganna isotopic analysis of water), the duplicate analysis will be a recount of the sane sa@le.
Results of duplicate sa::ple analysis are recorded in the quality control log book. he duplicate agreement is evaluated usirs limits established from previous analyses.
Spiked Sarole Analysis he recovery data obtained fmm the analysis of actuai sarples that have been spiked with nuclides is used to determine the accuracy and' precision of the analytical procedure in the presence of matrix interfemnees. For each matrix analyzed, ten
' percent of the sarples, with a minimu:n of one per batch, are analy::ed again after apiking. 'Ihis technique is not used in the analysis of air filters or iodine-131 charcoal canisters. The results of these spike analyses am cocpared to the control limits established for internal quality control samples to ronitor the perfonmnce of a, procedure with envizunrental samples.
9
Section NO. 4.6 Bevision No.
Date. October 1, lo84 Page 4 of 5
'~
Calibration Verification -
%e calibmtion of an instrument for a nuclide or radiation is checked
~-. Inradiately before sample analysis is begun. %e performance check standard is analyzed to deterudne if a calibration is valid by co@arison to the control- - -' --
limits established for the instrument. Wn tore than ten masumments are unde in one day, the performnce standard is reanalyzed with a frequency of ten percent.
If the control limits are exceeded, the instrumnt is recalibrates, an intemal quality control standard is analyzed to validate the new calibration, and the sa::ples are reanalyzed. In this manner, instmmnt calibration is checked fmquently to verify that the instrumnt calibration has not changed significantly, and yet minimize the number of sa@les that require reanalysis, if necessary. Results of the calibration verification am recorded in the instrumnt logbook and on the control chart.
Extemal Quality Control Samles External quality control sa@les are obtained frtra the USEPA Environmental Monitoring and Support Laboratory as part of the Interecraparison Studies Program.
Rese sa::ples are analyzed by the chemists without knowledge of the concentration.
Be extemal quality control sanples serve as an independent check m the total analytical procedure, from sa:ple prepamtion through quantification and reporting.
Evaluation is provided by the USEPA and is available for review during on-site evaluations by the USEPA and the USNRC.
A3sicnmnt of_ Responsibility A sunmary of quality contral pmcedures for the Radiation Unit is provided in Table 4.6-1. he analytical chedst perfoming sample analysis is responsible for using prescribed and validated procedures, only. he chemist ensures that the instrumnt perforcnnce checks are acceptable and documnted in the irstrunent log-book and that the method blank is interference-free and also documented before sarple analysis is continued. Each chemist is responsible for analyzing duplicate ca ples, spiked samples, and quality control standards as these apply to the analysis being done. Se che=ist also documented the results of the quality control checks in his daily logbook or analytical bench sheet ard in the quality control logbooks.
he chemist also doctrnents the results of the quality control checks in his daily losbook ard reports the values to the unit. supervisor who, after reviewing the data,
- reports the quality control data to the QA0 for documentation and evaluation. A cunmary of quality control limits for each mthod'is provided in Table 4.6-2. Because
- the agencies using the services of the Radiation Unit provide the precision require-
, - ments as detection limits, Table 4.6-3 and Table 4.6-4 outlines the typical detection limits expected of each mthod along with the parameters used to obtain these limits (cg. counting tim, efficiency, etc.)., -
f n
_.. .w-=--* * * '
- Section No. 4.6 Bevision No.
Date. gtober 1, 19811 Page 5 of 5 r
'Ibe QA0 provides the quality control material necessary (QC sanples and standards) upon the muest of the chemir,t or the unit supervisor. In the absence of the QAO, the, supervisor will provide QC material.
~ ' ~
'lhe quarterly k,thod validation schedule is maintained.by'..the QAD. Besults of the quarterly sanp,les are surnarized and reported by the QA0 to the unit supervisor and subdivision chief.
f p
L -
i h -
p t
't e
l.
I.
b-
.e
(;-
- m 9
a 4
- 9 ,
rC f
98 -
____ m__._ -____._____ -_- ____.m___________.________ ____m______ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - - __ % .
5 I
1 L
d 1
]
4 1 ;
This paye left blank intentionally I
.I 1
71
i i
i APPENDIX D l
[.
)
.. 6%
t
This page left blank intentionally i 1 l
I J
I 1
_ - - - - - _ - - - - - - - - .J
____,.____,.,__._y __ _ - _ _ _ . - _ _ -_ _ - _ _ - . _ _ _ . _ _ ,. _ _ _ _ _ , , _ . _ _ , - - __
n.
ODH ROUTINE ENVIRONMENTAL SAMPLING PROCEDURES l
I
- 100 -
This page left blank intentionally a
Ohio Department of . Health Air Sampling Prodedures The quick disconnect' filter assembly'should be loaded and unloaded in the office. .This will minimize possible loss j t
of~ filter. papers, damage to. filters by rain, etc.
LOADING THE QUICK DISCONNECT ASSEM3LY 1.. Unscrew the very top portion of the assembly.
[ 2. Place Millipore Filter Type AA, pore size 0.8 um in place.
- 3. Screw top back on.
- 4. Unscrew middle section of assembly.
- 5. . Check the seal.which sits under the cartridge to insure it is still intact and not damaged. Notify ODH. Radiological Health if a new one is needed.
, '6 . Place charcoa1' cartridge (605018-03 TEDA Impregnated Carbon) in place making sure~that the end of the cartridge with THE
[
t 7. Screw sections back together VERY SECURELY so that there is I no rattling noise when assembly is shaken.
AIR SAMPLER OPERATION
- 1. Turn.off the sampler.
L2. Record the running time meter reading (in hours).
- 3. Zero the running time meter.
- 4. Record the flow rate meter reading for end of the sampling period..(Note: This.is also the start reading for the next sample). i k 5. Remove quick disconnect assembly'and replace it with the new l' loaded.one.
- 6. Turn sampler back on.
- 7. Complete data sheet and unload quick disconnect assembly back in the office.
P UNLOADING THE ASSEMBLY
- 1. - When removing the filter paper, USE TWEEZERS. The air filter i
, should be handled with care when dust loading is observed because particulate matter is easily removed from the filter, thus invalidating the analysis, i- 2. Spray paper lightly with a clear acrylic coating.
- 3. Place paper in small plastic case provided by ODH.
- 4. Remove cartridge and place in baggie provided.
(SEE Shipping Instructions)
- 101 -
Ohic Department of Health Milk Sampling Procedures This sample must be a " split" sample with the utility.
When splitting samples for interlaboratory comparison, it is vital that both samples are representative of the media in question.
The Coleman cooler and ice packs provided by ODH should be taken with you to the sampling site so that the milk sample can be placed on ice as soon as it is obtained.
- 1. Turn on the bulk tank agitator if not already running.
If already running, continue agitation for 5 minutes. If the producer has two tanks, turn on the one containing the last milking, and sample only that tank.
- 2. Thoroughly wash hands.
- 3. Thoroughly sanitize a dipper or ladle and funnel with a disinfecting solution.
- 4. Rinse dipper several times with hot water.
- 5. Open tank lid. ,
- 6. Fill dipper with milk. The laboratory requires a 1 gallon sample for analysis. Fill 1 gallon cubitainer provided by ODH with milk. Pour each dip into the funnel and cubitainer away from the tank, so spillage will not contaminate the milk in the tank. Fill cubitainer full to the neck of the cubitainer and cap it tightly.
- 7. Label cubitainer with sample I.D.
- 8. Complete sample data sheet.
- 9. Turn off agitator if not on an automatic shut-off timer.
- 10. Close tank lid.
- 11. Thoroughly clean the dipping container and rinse any areas where milk may have been spilled.
- 12. Ship sample in cooler to ODH Laboratory as soon as possible.
(SEE Shipping Instructions)
NOTE: If milk can not be thoroughly mixed in the bulk tank before sampling, one large sample should be taken and THEN SPLIT into two separate containers OR Individual samples taken should be mixed and then split into two separate containers.
It may be necessary to reimburse the milk producer for the cost of the milk sample. (Current practice is for the milk producer to bill the sampler.)
- 102 -
Ohio Department of Health Surface Water Sampling Procedures F
- Surface water grab samples should be collected from at least two sites. One site should be located upstream from the facility disharge outfall and the second.from downstream of the facility discharge outfall. For those facilities located on a lake, the upstream or control sample should be taken far enough from the point of discharge so that the facility effluent has little or no influence on the sample content. The downstream or. indicator sample should be taken near the outfall but beyond the turbulent area caused by the discharge.
Radioactive material in water samples may deposit on sample container walls and therefore it is desirable to obtain duplicate samples simultaneously in similar containers rather than split one large sample.
A 1 quart sample must be taken weekly. As soon as the weekly sample is taken, it should be poured into the 1 gallon composite and refrigerated until composite is complete and ready to be shipped. The composit'e should contain 4 weekly water samples.
INDICATOR SAMPLE
- 1. Proceed to the sampling site preselected by ODH. Wade out into the water as far as practical. (Wear boots provided.)
Do not wear a tritium luminous dial watch as the tritium may contaminate the sample.
' 2. Before sampling, rinse the sampling device and sample container several times with the water to be sampled.
- 3. Do not disturb the sediment in the sampling area or contaminate the sample with shoreline sediment or other debris. If sediment is disturbed, do not sample until the water is clear again.
Do not include any. snow or ice during cold weather sampling.
- 4. Take sample by skimming sampling device or container as close to the surface as possible.
- 5. Cap the sample container and label with the sample I.D.
- 6. ' Label container wi th . sample I. D.
- 7. Shortly after collection, pour quart sample into a 1 gallon cubitainer for the monthly composite.
8l . At end of the month when 4 quart samples have been composited into a 1 gallon sample, label container with sample I.D.
< 9. Complete sample data sheet, i
- 10. Place sample in cooler with ice packs and ship to ODH l Laboratory. Refrigeration inhibits biological growth which
[ can absorb radionuclides, i - 103 -
Surface Water Sampling Procedures Continued CONTROL SAMPLE
- 1. The control sample for the Davis Besse Nuclear Power Station will be a composited, untreated, raw water sample taken at the Port Clinton Water Treatment Plant.
- 2. Rinse the sample container several times before collecting the sample.
- 3. Take a 1 quart sample.
- 4. Label container with sample I.D. and date.
- 6. Shortly after collection, pour the 1 quart sample into the 1 gallon cubitainer for monthly composite.
- 7. At end of the month, when 4 - 1 quart samples have been composited into a monthly 1 gallon composite, label container with sample I.D.
- 8. Complete a sample data sheet for this composite sample.
- 9. Label container with sample I.D.
l
- 9. Place water in cooler with ice packs and ship to ODH Laboratory. (SEE Shipping Instructions) ;
i 1
I i
i r
I 1
l 1
- 104 - !
i
Ohio ~ Department of Health Shoreline Sediment Sample h
l Sediment samples are.taken to indicate the buildup' rate-of radioactivity.due to sedimentation. If.the facility is. located on a : lake or ocean, a sediment sample'should be taken near the outfall but beyond the turbulent area created by the outfall.
-Favorable sampling times'for bottom sediment are prior to~and just after the spring runnoff.
y l ~. This sample lmust be split with the utility..
,j 2. Proceed - to predetermined sampling ' location.
- 3. Put on boots and wade out as.far as practical.- Note the approximate distance from the. shore.
- 4. The sample should contain at least 1 kilogram of sediment.
With sampling device, sample only .the top layer or most recent sediment.
Sediment samples should be taken in duplicate.- The total sample should be thoroughly mixed, then split and bagged for. shipment. The samples should be as uniform as possible, h taking care to avoid having larger particles concentrated in one sample.
.5.- Place sediment sample in container provided.
- 6. Label sample with sample I.D.
- 7. . Complete sample data sheet. Make notation regarding approximate-sampling distance from shore.
- 8. Ship sample to ODH Laboratory.
(SEE Shipping Instructions)
- 105 -
c.
Ohio Department of Health Fruit'and Vegetable Samples Inseason. fruit and vegetable-samples should be collected near the point of maximum. predicted annual ground concentration from stack releases and from areas.which.may.be contaminated by water into which-liquid wastes from the power plant'have been discharged.
IfLfruit and vegetables are purchased from a local roadside stand in the area of interest, it is important.to insure that the produce was actually harvested from that area.
. Exposed surfaces-of vegetation or fruit samples can provide indications of deposition and should not be washed. However caution should'be used to avoid c' contaminating the sample with any soil.. '
- l. This must be a " split"-sample with the utility.
- 2. Proceed to predetermined' sample area.-
- 3. Obtain at'least 3.5 kilograms of the edible portion of the fruit or vegetable.
Note: Each item collected must'actually be split until.enough " halves" are obtained to fulfill .
~the above requirement.
- 4. Place sampleLhalves in bag (s) or container (s) provided and
. seal.-
5.= Label bag with sample I.D.
- 6. Complete sample data sheet.
- 7. Ship sample (s) to ODH Laboratory.
(SEE Shipping' Instructions) l e 106 -
i Department of Health Fish Samples
> ,a Fish samples should include each of the principal edible types in the environment surrounding the facility. The sample may be purchased from fishermen if the origin can be determined.
- 1. This sample must be a split sample.
- 2. Whenever possible, accompany utility personnel to sampling location and observe sampling procedures. If this is not possible, arrange to obtain the fish from the same catch that the utility obtained theirs.
- 3. Approximately 0.5 to 1.0 kg per species should be taken.
If the fish weighs more than 1 pound, a piece of the fish's midsection can be used. Double bag the catch or place in plastic container provided.
l 4. Label bag or container with sample I.D.
- 5. Pl ace in cooler with ice paks.
- 6. Complete sample data sheet.
- 7. Ship sample as soon as possible to ODH Laboratory. If shipping is delayed, freeze the fish until shipment is possible. (SEE Shipping Instructions) l l
1 l
i l
l
- 107 -
I acuano r.catem cavm L. 4acum. asm. m.o.
o o ereewe An Equal Opportunity Employer / Provider a
._. . . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _