IR 05000054/1981003
| ML20043C441 | |
| Person / Time | |
|---|---|
| Site: | 05000054, 07000687 |
| Issue date: | 02/01/1982 |
| From: | Joyner J, Zibulsky H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20043C415 | List: |
| References | |
| FOIA-90-97 50-054-81-03-01, 50-54-81-3-1, 70-0687-81-05, 70-687-81-5, NUDOCS 9006050189 | |
| Download: ML20043C441 (4) | |
Text
..
I
-
,
i i
DETAILS
,
1.
Persons Contacted
- J. McGovern, Business Manager, Radiochemicals
- F. Morse, Manager, Radiochemical Process Engineer
- D, Grogan, Managtr, Radiochemical Production W. Leinheiser, Supervisor, Quality Control
The inspector also interviewed other licensee employees associated with measurements and plant operations,
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings Previous items of noncompliance were not reviewed by the inspector.
3.
Exit Interview
,
The inspector met with the licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on October 16, 1981.
The inspector summarized the scope and findings of the inspection.
4.
MC 927138 - Independent Inspection Effort No items of noncompliance were noted.
During a previous material contrcl and accounting inspection (70-687/
81-04), the inspectors determined that an internal measurement control audit dated January 31, 1981, identified areas in the measurement
-
control program that were in need of improvement. During the current inspection, the inspectors reviewed the status of licensee followup of the internal audit, An internal licensee memo dated September 16,
'
1981, from M. E. Bordoni to J. J. McGovern, discussed the status of these improvements.
The inspectors will perform a detailed followup of the licensee's action during a future inspection.
5.
MC 85206B - Measurement and Statistical Controls a.
License SNM-639 No items of noncompliance were noted,
,
l The licensee analyzed the uranium content of standards that were prepared with normal uranium and certified by the New Brunswick Laboratory.
One analyst, using the Gravimetric Davies and Gray L
titration procedure, performed the analyses.
During inspection l~
70-687/81-04, the standards analyzed by the licensee were not within the normal range of the material routinely analyzed.
The
!
- 8P #8ir '
umunuesummmuner l
HALL 90-97 PDR
-
,
..
,
'
e
'
1 concentrations of the new standards were within the licensee's normal operational range.
l The three uranyl nitrate standard solutions were as follows:
,
.
- M = 0.004983 gu/mi
- N = 0.007111 gu/mi
,
- P = 0.008989 gu/mi The three uranyl nitrate standard solutions had mean relative biases of -0.07%, -0.20%, and -0.92%.
Only the bias of the last standard was ' statistically significant at the 2-sigma confidence level.
The results of these standards identified areas in the licensee's procedure where some errors may be reduced.
The licensee will
change the type of platinum and calomel electrodes used to provide
a more immediate response.
Also, the licensee will weigh their samples and perform a specific gravity determination on the
'
solution in lieu of aliquoting the solutions.
The licensee's procedure, subject to some minor changes, is now
'
" state of the art", and will be used to analyze total uranium of irradiated fuel in a hot cell.
l l
b.
License R-81 On December 18, 1979, the licensee submitted a procedure relating I
to the Vranium Waste Recovery Process to the NRC Advanced Fuel
[
and Spent Fuel Licensing Branch.
The plan was approved on June 27, 1980
!
after an April 2, 1980 revision.
The plan involved the collection of the raw fission waste from 10-14 targets after the molybdenum had been separated.
An excess of barium acetate solution was added to the raw fission waste solution, and barium sulfate precipitated out and was allowed to settle.
The s u rnatant liquid was separated by vacuum decantation l
from the barium sulfate precipitate.
This precipitate was solidified with cement and sent to Barnwell, South Carolina for burial. The
!
l filtrate was distilled (the distillate was added to the barium l
sulfate for solidification) and the condensate was calcined and sent to the Department of Energy's plant, Aiken, Savannah River, South Carolina for recovery of the uranium.
l There is a problem determining the amount of plutonium per gram of uranium contained in the barium sulfate precipitate. The inspector reviewed with the licensee a sampling and analysis plan to assure that Barnwell is receiving material for burial that is
'
within their burial limits for transuranic elements.
Because of the high radiation levels and sampling problems, the barium l
L
_
_ _ -
___ _
_
P
.
-
.
-
.
'
p
,
-
l sulfate cannot be removed from the hot cell.
It was, therefore,
,
decided to sample at two other points in the process and determine the plutonium in the sulfate precipitate by difference. Exhibit 1
,
shows where normal sampling points are in the process.
Duplicate samples will be taken before the barium precipitation is made and after the supernatant liquid is decanted from the precipitate.
Samples fer NRC will be sent to Exxon Nuclear Idaho Company, Inc.
for analysis.
Licensee samples will go to Oak Ridge National Laboratory for analysis, j
,
The analyses requested will be-
~
(1) Total Uranium (2) Total Plutonium i
(3)
Isotopic distribution of both Uranium and Plutonium (4) Strontiun-90 (5) Cesium-137 (6) Gamma scan i
I
$
e
$
.
t r
v
,vw-m v--
^^
Ex hib"it L
_,
am2-
^
,
.
'm
.
.
.
.
.
I
f g.(
<
Uw terr 4
&
/N)X i
W
)
M
- -
umwn r
PM ur"
\\
t
]
&/k.
'
(mix W
,
75
U a Ga,agaarm p dd4 44AGAL!
bNDJ Q A Y
f
f)Wr6L n
Y
.
M/A L
>
Rssn?
Vesuwin
.
bBY v
i h3$/}V Ce43eA)3A 7~c
// M L//M
!l 0.44C/AW s.
Stoes L
>
'
v 73 S,1viw u+H 2ver
-
=wa%x.1v n,
_ _ _
_
-
.. _ _ _.
. _ _ _ _ _,... _. _ _ _ _. _ _. _. _
_
.
..
.
..
.
_
-
..
-_
'
S INTORMATION
'
- M o e-
[ p$,
.
~
u
.
NUCLE AR REG'.lLATORY COMMIS$10N
.
.
RtoloN 1
!
.
E-ut PAAM AVENVE t
mo onnuma ecuum.vania no.
9 JUL 1982
.....
,
Docket Nos.70-687 50-54 Union Carbide Corporation ATTN: Mr. James J. McGovern Business Manager, Radiochemicals P. O. Box 324 Tuxedo, New York 10987 Gentlemen:
Subject:
Inspection Nos. 70-687/82-04; 50-54/82-02 This refers to the routine safeguards inspection conducted by Mr. H. Zibulsky of this office on May 10-14, 1982 of activities authorized by NRC License Nos.
SNM-639 and R-81 and to the discussions of our findings held by Mr. Zibulsky at the conclusion of the inspection.
Areas examined during this inspection are described in the NRC Region I Inspection i
Report which is enclosed with this letter.
Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
P Our inspector also verified the steps you have taken to correct the violation brought to your attention in the enclosure to our letter dated November 10, 1981. We have no further questions regarding your action at this time.
'
Within the scope of this inspection, no violations were observed.
In accordance with Section 2.790(d) of the NRC's "r.ules of Practice," Part 2 Title 10, Code of Federal Regulations, documentation of findings of your control and accounting procedures for safeguard',ng special nuclear materials are deemed to be commercial or financial infonnation within the meaning of 10 CFR 9.5(a)(4) and shall be subject to disclosure only in accordance with the provisions of 10 CFR 9.12; therefore, except for the report cover sheet, the enclosed inspection report will not be placed in the Public Document Room and
'
will receive limited distribution.
No reply to this letter is required.
Your cooperation with us in this matter is appreciated.
Sincerely, l$
W n.2 a T omas T. Martin, trector ivision of Engineering and Technical Programs Enclosure:
Combined NRC Region I Inspection Report Number 70-687/82-04 and 50-54/82-02 (Contains 2.790 Information)
&7 Q
.w
.
...
-.
.. -
. - _ -.
.-
-. - -
- - -. -
.
- -. _ - -
1sWWEI95NMt99mme
\\
.
'
.
,,
.
Union Carbide Corporation
9 JUL 1982 ec w/ cy of report cover sheet only:
o Mr. H. Voth, Manager Nuclear Operations W. G. Ruzicka, Reactor Project Engineer C. J Konnerth, Health Physicist Dr. R. E. Bollinger, Vice President, Medical Products Division Public Document Room (PDR)
Local Public Document Room (LPDR)
i t
NuclearSafetyInformationCenter(NSIC)
i
$ tate of New York
l
.
<
.
>
J
,
b t
.
.
.
.
U. S. NUCLEAR REGULATORY COMMISSION Region I 70-687/82-04 Report Nos. 50-54/82-02 70-687 SNM-639 Docket Nos. 50-54 License Nos. R-81 Safeguards Group 1_
Licensee:
Union Carbide Corporation P. O. Box 324 Tuxedo, New York 10987
__
Facility Name:
Sterling Forest Research Center
'
Inspection At:
Tuxedo. New York Inspection Conducted:
May 10-14, 1982 Date of Last Material Control and Accounting Inspection:
January 8 and 11, 1982 Type of Inspection:
Unannounced Material Control and Accounting H.Zibulsky(,uemist[uds[b/
d 3/f).
Diueuf Inspectors:
I date si'gned
[.
d
L E. Wolt
,A itor date signed (p/dN(/62 Approved By:
.a
.
Mdy, ThTe f,
eguards Section, date sijned Technical Pr ams Branch Inspection Summary:
Inspection on May 10-14, 1982 (Combined Report Nos.
70-687/82-04 and 50-53/82-02)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of nuclear material control and accounting including:
Facility Organization and Operation; Storage and Internal Control; Records and Reports; and Management of Material Control System.
The inspection involved 64 inspector-hours onsite by two NRC regional based inspectors.
Results:
The licensee was in compliance with NRC requirements for the areas examined during the inspection.
THE INFORMATION ON THIS PAGE IS DEEMED TO BE APPROPRIATE S-F1-82-66 FOR PUBLIC DISCLOSURE PURSUANT TO 10 CFR 2.790 Copydof.f2 Copies THE REPORT DETAILS CONTAIN h
~N
~