ML20196K149
| ML20196K149 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 06/22/1988 |
| From: | Pasciak W, Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20196J842 | List: |
| References | |
| 70-0820-88-01, 70-820-88-1, NUDOCS 8807060525 | |
| Download: ML20196K149 (5) | |
Text
,. _,
U.S. NUCLEAR REGULATORY COMMISSION REGION-I Repo.rt No.
70-820/88 Docke't No.70-820
- License No.. SNM-777 Priority 1
Category UHD' Licensee: -United Nuclear Corporation Recovery Systems Wood River Junction, Rhode Island 02894 Facility Name:.UNC Recovery Systems-Inspection At:. Wood River Junction, Rhode Island Inspection Conducted: May 24. 1988 Inspectors:
03 /2Z h o
/J J 2. Y J. Ro~th, @(ject Engineer
" / dat/
~
h2.f N Approved by d
Ch f'/datgf W. Pasqfay. CMfef, Ef fluents Radiation Protec'tfon Section, DRSS Inspection Summary:
Inspection on May 24, 1988 (Report No. 70-820/88-01)
Areas Inspected:.Special announced inspection by a ragion-based inspector for the purpose of examining the-status of-facility decoamissioning.
Results:~ No violations were identified.
The licensee completed removal of additional contaminated soil from areas inside (Grid No. B-126) the restricted area fence. The inspector conducted a verification survey and obtained soil samples for ati. lysis.
8807060525 880627
{DR ADOCK 07000820 PDC
c ib av 9
t f
DETAILS 1.
' Person Contacted
- K._Helgeson, Site Manager
===2.
Background===
During Inspection No. 70-820/87-02 the inspector was accompanied at the site by the NRC contractor, Vak Ridge Associated Universities (0RAU) for the purpose of conducting a verification survey of decontaminated grid
~
blocks D-64,.D-70/71, D-94, D-96 and B-126. Composite-soil samples were obtained from each grid block, were transported to the ORAU laboratories in Oak Ridge, Tennessee where they _were ground, mixed and split:into
-three. fractions. One fraction was analyzed by-0RAU, the second fraction was sent to the licensee's contractor, Controls for Environmental Pollution, Inc. (CEP), for' analysis and the third fraction was retained for the NRC by ORAU for referee analysis, if required.
The analysis'results for all of the samples analyzed, includiag required referee analyses, conducted by the US DOE Idaho Radiological and Environmental Services: Laboratory, are as follows:
Table 1 l-Analyses Concentration (pC1/g)
Grid By U-234 U-235 U-238 D-70/71 ORAU 16.5 1.2 0.7 1 0,3 0.9 0.3 Idaho 18.9 1 1.0 0.6 0.2 1.2 1 0.2 CEP 6.0 0.2 0.2 0.1 1.8 1 0.2 i
D-64 ORAU 32.8 3.2 1.4 1 0,P 1.1 +. 0.6 Idaho 36.7 1.5 1.1 0.2 0.8 2 0.2 CEP 8.2 1 0.5 0.3 0.1 2.5 2 0.3 B-126 ORAU 202 15 6.6 t 3.1 2.7 1.9 Idaho 247 8
8.2 1 0.7 0.8 0.3 ORAU 165 1 4 6.1 1 1.0 1.3 0.4 Idaho 245
/
10.6 0.9 3.3 0.6 4
CEP 38.9 1 1.8 1.4 1 0.2 11.9 i 1.9 The discrepancies between the ORAU/ Idaho and the CEP results were deter-mined to be related to the analytical techniques used for the analysis.
ORAU and Idaho use a fusion technique which accounts for all the uranium present in the sample and'CEP uses a leaching technique which may account for only 20-33% of the uranium present.
Althougn the leaching techniq'Je was identified as the approved EPA analytical method, this method of analysis was known by EPA to have limited capability.
?:
+
,_t.'
3-Th' analytical results shown in the preceding table indicated that Grid e
No. B-126 remained grossly contaminated.
Subsequent to that analysis, the
' licensee recleaned that grid block.
During this ' inspection, the inspector conducted radiation surveys. of' Grid No. B-126 (see Attachment No.1) at the surface.and at 1 meter above the surface. ~ Radiation 'evelt-were found to be at background levels
'(1000-2000 counts'per minute), using a Ludlum_Model 16 analyzer with a -
sodium iodide crystal detector, except at one. location approximately midpoint on the--south edge of the grid. At that point, the radiation level was about twice background.
Soil. samples were also taken in Grid-No. B-126 for analysis. One soil
. sample was taken at the location of the elevated radiation reading. A second 1 soil sample was taken at the sample location after the elevated radiation reading was reduced to background. A third soll sample was obtained by compositing soil removed-from the four corners, the center,
~
and from the elevated area of the block.
Each soil sample was mixed and split with the licensee.
NRC samples were par.kaged and sent to ORAU for analysis. The analytical results will be reviewed by the insper. tor and reported in a subsequent inspection report.
3, 1987 NRC Well Water Sample Analysis Results The NRC sample analyses results for well water samples collected on August 27-28, 1987, during Inspection No.'70-820/87-02, are presented in Table 2.
TABLE 2 NRC 1987 WELL WATER SAMPLE ANALYSIS Gross Alpha Gross Beta Sr-90 Cs-137 Well No.
(pct /1)
(pC1/1)
(pCi/1)
(pC1/1)
T-1 0.310.11 0
T-2.
T-3 0
0 T-4 T-5 T-6 0
11 3
T-7 0.3 0.11 0
T-8 0
8 3
T-9 PW-1 NOT IN SERVICE PW-2 0.8 0.2 0
W-A NOT IN SERVICE W-8 7.3 1.0 0
W0 W-E 0.6 0.15 0
W-3 W-5
h 4
TABLE 2(continued)
NRC 1987 WELL WATER SAMPLE ANALYSIS Gross Alpha Gross Beta Sr-90 Cs-137 Well No.
{pC1/1)
(pCi/1)
(pCi/1)
(pCi/1)
W-6
'#-7 1.0 0.2 9
3
'i-8A 0.55 0.14 0
W-9 W-10 W-11 NOT IN SERVICE W-12 0.7 0.13 12 3
76-U 0.6 0.2 25 3
77-B 7.9 1.3 200 11 12 3
0 77-0 0
0 OH-1 0.6 0.14 14 3
CH-1-1 NOT IN SERVICE DH-2-1 NOT IN SERVICE DH-2-2 NOT IN SERVICE As indicated in.,le 2, none f the gross alpha results exceeded the EPA drinking water limit of 15 pCi/ liter and only one of fifteen gross beta results exceeded the EPA limit of 50 pCi/ liter.
Thc EPA limits for Sr-90 and Cs-137 are 8 and 200 pCi/ liter, respectively.
Only one Sr-90 result exceeded the EPA limit.
The analytical data shown in Table 2, when compared to the results from prior years, indicate a stabilization of the ground water contamination level. Well water samples will be split with the licensee during a subsequent NRC inspection to be conducted during the summer of 1988.
4.
Licensee Discussions The inspector held discussions by telephone with the licensee representa-tive denoted in paragraph 1 at the end of the inspection.
Findings of this inspection were presented to the licensee.
Ne written material was previoed to the licensee by the inspector during this inspection.
.q a
m..
m a
1 _ - -
o i
l
=
o.
I li '
l I
e i
4
==ra Li a34+
si n.
133 p,
dNT
..Il 11lON AREA WAKHOUSE
.J Lil
. 3.
,,3
l W.3.
4.
7 T.
BUKi-313.
.33.
llll.'l llp.3
??
w.ru
.. 3
~
l MT.T3 l
B I
=
-o r
G. r53
-- 3 g
)
4 r
m -
==
- =
- 73 m
r.
s 3.
.6.,
e
,4
.so.
.ss.
UlFs q.
g f,.-
{
co l
ANNEE
.GF.
D 3,
. 43 5
oto.
75
.3 117 I
5 2 4
m.t !,
.C14 g 75 t
i 53 ef
.3--
g grq 3 PN YtO8g
. Mas ee p.
.s.i
.voo
.:s.
LREA I AREn i
I 1h4 3.
45
- G-"
.053 77
. f T.
g sa e
3.
. 3.
l k
=
. 33 3.
=
m.
.,3, i
?
. j d
k FORMER LAGOON WALLS g RESIDUAL Co-127 Y
N (Onelde Legeen Area)
CONTAMINATION FIGURE 9:
Locations in the Lagoon Area Containing Residual Cs-137 Contamination.
-- - - - -