ML19332C427
| ML19332C427 | |
| Person / Time | |
|---|---|
| Site: | 05000112 |
| Issue date: | 11/14/1989 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19332C421 | List: |
| References | |
| 50-112-89-02, 50-112-89-2, NUDOCS 8911280111 | |
| Download: ML19332C427 (9) | |
See also: IR 05000112/1989002
Text
.,
,
b
..
'
.
.. ,
APPENDIX
,
U.S. NUCLEAR REGULATORY COMMISSION
i
[
REGION IV
i
I'
NRC Inspection Report:
50-112/89-02
License:
R-53
l-
Docket: 50-112
i
Licensee:
University of Oklahoma
[.
865 Asp Ave., Room 212
?
Norman, Oklahoma 73019
Facility Name: AGN-211P, Research Reactor (200KW)
,
i
Inspection At: University of Oklahoma, Norman, Oklahoma
i
Inspection Conducted:
October 11, 1989
!
Inspector:
ll
N
Monald E. Baer, Health Physicist, Facilities
Date
"
Radiological Protection Section
'
(,I.
Accompanied
By:
Blaine Murray, Chief, Facilities Radiological
Protection Section
b
Aoproved:
.
laine urray, Chief
Facilities Radiological
Difte
!
'
,
Protection Section
.
Inspection Summary
Inspection Conducted October 11,1989 (Report 50-112/89-02)
,
Areas Inspected:
Special, announced, closeout inspection involving the review
activities associated with the decommissioning of the University of Oklahoma
AGN-211P Research Reactor facility.
The inspector also performed confirmatory
radiological sarveys regarding the reactor equipment and f acilities. The
!
guidance provided in NRC Inspection Procedure 83890 was utilized,
bbk kdhb 12
pm -
,o
"
e
- - . - .
'24;
',$l
'
- r
,
.g.
1Results: The licensee's action concerning personnel radiation protection, fuel
-
dispositione and external radiation exposure and loose contamination' levels for-
equipment and fe.cilities metLestablished regulatory criteria. Confirmatory
radiological surveys conducted by the inspector verified that the facility met-
.the recommended guidance in NRC. Regulatory Guide 1.86 for release of the
jf' -
i facility for unrestricted ase.
Vc
' No violations or deviations were identified in the areas inspected.
?
l,
.. .
jq
g
- . i. ,
>
l'
f.
- - -r
l-
y-.
,
k
e
o
x
s
.
l:
l
d-
e
i
s;
g,
..
.
'
-3-
!
l.
I
DETAILS
1.
persons Contacted
i
i
University of Oklahoma
- Dr. D. M. Egle. Director, School of Aerospace and Mechanical Engineering
'
- Dr. P. Skierkowski, Radiation Safety Officer
h
- Denotes those present during the exit interview on October 11, 1989.
,
2.
Followup on Previously Identified Insoection Findings
,
(Closed) Violation (112/8701-03):
Failure to provide Emergency Response
l
Training - This violation was identified in NRC Inspection
i
Report 50-112/87-01 and involved the failure to provide training in
!
radiation safety and the facility emergency _ procedures to individuals from
the Norman Fire Department who would respond to an emergency at the
facility. The licensee provided training on radiation safety to 13
4
. members of the Norman Fire Department during the period of
'
L
September 11-15, 1989.
(Closed) Violation (112/8901-01): Authority to Dismantle a Facility -
This violation was identified in NRt Inspection Report 50-112/89-01 and
,
involved the dismantling of the University of Oklahoma research reactor
i
!
facility prior to submitting a decommissioning plan and obtaining NRC
,
approval. The NRC, on June 5, 1989, issued an order authorizing
dismantling of the facility and disposition of component parts.
'
(Closed) Violation (112/8901-02):
Reactor Safety Committee Composition -
This violation was identified in NRC Inspection Report 50-112/89-01 and
involved the lack of a reactor safety committee and reactor director. The
,
NRC, on June 5, 1989, issued an order authorizing dismantling the facility
!
in accordance with the application dated October 25, 1988, as
supplemented. Appendix A to the NRC order contains the facility Technical
-
Specifications and does not require a reactor safety committee.
-!
(Closed) Violation (112/8901-03):
Reactor Safety Committee Meetings -
This violation was identified in NRC Inspection Report 50-112/89-01 and
involved the failure of the reactor safety committee to conduct semiannual
!
meetings.
The NRC order, of June 5,1989, does not require a reactor
safety committee or any scheduled meeting frequency.
,
(Closed) Violation (112/8901-04):
Reactor Safety Committee Audits - This
violation was identified in NRC Inspection Report 50-112/89-01 and
,
involved the f ailure of the reactor safety committee to perform the
recuired audits of activities related to the reactor license conditions.
'
The NRC order, of June 5,1989, does not require a reactor safety
committee or any scheduled audits of the reactor license conditions.
.
m,
.
,
-
~
,
'
j
_ *
c
'
-
-
.
'
4
!
F
!
h
(Closed) Violation (112/8901-05):
Emergency Response Training - This
L
violation was identified in NRC Inspection Report 50-112/B9-01 and
,
involved the. lack of emergency response training for the Norman Fire
i
Department.
This was a repeat violation (112/8701-03). The licensee had
provided radiation safety training for 13 members of the Norman Fire
Department during the period September 11-15, 1989.
l
3
.
3.
Release Criteria for Unrestricted Use
.
The radiation levels for release of the reactor facility for unrestricted
-
,
!
use were established in " Safety Evaluation by the Office of Nuclear
L
Reactor Regulation Dismantling of Facility and Disposition of Component
'
'
Parts Research Reactor Facility (AGN-211P) Facility License No. R-53
.
Docket No. 50-112" and supporting NRC order, dated June 5, 1989. The
i
safety evaluation states that surfaces must be decontaminated to levels
,
consistent with Table 1 of Regulatory Guide 1.86, " Termination of
Operating Licenses for Nuclear Reactors." In addition, external exposure
L
' rates must be less than 5 micro Roentgens per hour (uR/h) above natural
background at 1 meter from the measured surfaces or that no person will
receive more than 10 mrem / year.
Natural background had been defined as
radiation from naturally occurring radioisotopes as measured at a
comparable uncontaminated structure or exterior soil surface.
4.
Disposition of Material
,
-The reactor has been dismantled and the fuel has been transferred to
Martin Marietta Energy Systems, a Department of Energy (DOE) contractor.
Records maintained by the licensee indicated that radioactively
contaminated components had been transferred to the University of Oklahoma
Byproduct License (35-07466-05) for disposal via its low-level radioactive
waste program.
The radium-beryllium neutron source has not been
transferred to any facility for disposal.
The licensee is working with
the State of Oklahoma and DOE to dispose of this source.
This source is
-not licensed by the NRC.
.
A review of DOE /NRC Form 741 indicated that the fuel was transferred and
<
shipped to Martin Marietta Energy Systems on April 30, 1988, and an
acknowledgement was received on May 10, 1988.
No violations or deviations were identified.
,
.
5.
Records of Personnel Exposure
The licensee had issued personnel exposure monitoring devices,
!
thermoluminesent dosimeters and direct reading dosimeters, as part of the
University of Oklahoma's radiation safety program. This program is
administered by the university's radiation safety office.
Records of
personnel exposures are being maintained by the university.
The licensee
had not provided bioassay sampling and analysis as there was no recorded
'
<
-e
--
5
,
i-
,
.
.
m,
,
5-
p.
incident which would have suggested that an internal uptake of radioactive
material had taken place and necessitated the need for such monitoring,
,
i
i
No violations or deviations were identified.
I
6.
Licensee's Termination Survey Report
-
,
The licensee submitted the " Dismantling and Decommissioning Activities for
L
the University of Oklahoma AGN-112P Nuclear Reactor Facility Docket
. No. 50-112" on August 28, 1989. This, report summarized the results of
E
surveys and decommissioning activities in the decommissioning log book
L
during the period of May 18, 1988, . through August 1989.
The inspector reviewed the decommissioning log to determine if radiation
i
surveys and surface contamination levels were in agreement with the values
specified in the dismantling plan and NRC guidance.
No violations or deviations were identified.
L
7.
Independent Confirmatory Measurements
-The inspector performed a verification survey of the Nuclear Engineering
Laboratory Building, Room 107, Reactor Laboratory.
This survey was
performed to independently verify that the release criteria for
unrestricted use, described in paragraph 3 above, was fulfilled.
The
radiological surveys performed included direct measurements of beta and
gamma exposure rates. Measurements of removable (transferable) and
nonremovable alpha and beta contamination were also made. All components
had been removed from the reactor.
As a result, the inspector had easy
access to the empty reactor tank and east and west storage pits.
The inspector determined that the general background direct gamma
radiation levels associated with the facility were 9-14 uR/h.
The
. inspector also verified that the maximum residual radiation levels were
>
not greeter than the general background level.
No localized or activated
" hot spots" were identified.
In addition to gamma measurements, the
inspector also performed surveys to identify fixed alpha and beta
radiation levels,
No alphe or beta radiation levels above the general
background were identified.
The inspector performed surveys to identify removable alpha and beta
contamination using conventional paper smear techniques.
Smear surveys
8
were taken over a nominal 100 square centimeters (100 cm ) and analyzed
for alpha and beta disintegrations per minute (dpm/100 cm').
No removable
radiation contamination levels above background levels were found.
The specific details concerning the radiation surveys are documented in
1
Attachment 1.
No violations or deviations were identified,
n
.
.
.
.
---
--
3
.-
.
n
-.in
..
-
,
6-
h
!
- r- >
8.
Reactor Components
i
e,
The inspector surveyed the reactor components such as control rod drives,
7
L
reflector elements, core support items, and experiment transfer tubes.
L
These components had been removed from the reactor tank and held in
,
. temporary storage in the west storage pit.
Surface gamma radiation levels
,
.of about 5-20 uR/h above background were found on a bolt in the tip of
27 reflector elements.
Followup analysis by the licensee identified that
- .
the bolts contained cobalt-60. Smear surveys were-performed on the
!
elements; no removable contamination was found. The gamma radiation
,
[
1evels appeared to be the result of activation of the cobalt metal in the
>
bolts in the reflector elements. All reflector elements that indicated
'
,
radiation levels above background were segregated and transferred to the
University's byproduct license for accountability purposes.
,
,- .
No violations or deviations were identified.
l
l
9.
Exit Interview
.
The inspector net with the licensee representatives denoted in paragraph 1
[
of this report at the conclusion of the inspection on October 11, 1989.
The inspector summarized the scope and preliminary findings of the
inspection and verification survey.
<
>
1
,.
-y.,-
.- , ..---_:.-
-
, - .
,--
= _ .
., . _ , , . _ . . , ~ . , . - - ~ - - . . . - - - , ,
. - - - . -
--r-.
_.-__..,,c
_.
,..
,
_
-
_
-
-
,
9;
- -
-
.
. .
a
,
%
. 4
' ;,
-I
.:
.
ATTACHE NT~
4
.
.
~
Confirmatory Measurements Radiation-Surveys
-
.,,
1.
Instrumentation
~
'
~
.
_
Portable Survey Meters
~
Model
NRC Identification Number
Scintillation Detector
000266
'
Ludlum Model 19 Micro R meter
015535
_
Ludlum Model 19 Micro R meter
016338
Ludlum Model 14C with GM detector
012799
-
Techncial Associates Model TBM-35
018660
Eberline Model PAC-1 SAGA with AC-3
Laboratory Counters
Model
Eberline Model DC-4 Beta Counter (Eff. = 16%)
014812
Eberline Model 9AC-4 Scintillation Alpha Counter (Eff. '= 27%)
012831
2.
Survey Results -
a.
Direct Radiation Levels
(1) location
(a) Reactor Tank
Gamma (Mr/h)
Beta (arad/h)
Alpha (dps/100ca )
z
Survey
BKGD
Contact
'
Contact
Bottom - contact
10
12
<0.02
<20 .
Bottom - 1 meter
10
12
3 ft. above bottom contact
10
12
<0.02
<20
3 ft. above bottom 1 meter-
10
12-
6 ft. above bottom contact
10
12
<0.02
<20
6 ft. above bottom 1 meter
11
12-
Top, Floor Area - contact
~12
12
<0. 02 ':
<20
.
Top, Floor Area -'l meter
12
12
- - _ _ _ .
-
- _ _ _
-
_____ _ ____________ ____
_
_
~
_
_ _
~
-2-
~
s;
.:
.-
,
. . . .
~
2
(b) East Storage ~ Pit
Gasuna(Mr/h)
Beta (mrad /h)
Alpha (dpe/100cm )
g
Survey.
BKCD
Contact
Coni.act
t
'Botton - contact
10
12
<0.02
.<20
Bottom - 1 meter
10
12
0
3 ft. above bottom-contact
10
12
<0.02
0
~ 20
<
3 ft. above bottom-1 meter
- 11'
-12
0-
6 ft. above botton-contact
11
12
<0.02
0
<20
6 ft. above bottom-1 speter
11
12
0
Top, Floor Area - contact
12
12
<0.02
0
<20
Top, Floor Area - 1 meter
12
12
0
(c) West Storage Pit
Gamma (Mr/h)
Beta (arad/h)
f.lpha(dpm/100cm )
2
Survey-
BKGD
Contact
Contact
Resin lank / Pump-contact
10
12
<0.02
<20
Bottom - contact
10
12
<0.02
<20
Bottom - 1 meter
'10
12
3 ft. above bottoarcontact
10
12
<0.02
<20
3 ft. above bottom-1 meter
10
12
6 ft. above bottom-contact
11
12
<0.02
<20
6 ft. above bottom-1 meter
11
12
Top, Floor Area - contact .
12
12
<0.02
<20
Top, Floor Area - 1 meter
12
12
(d) General Area
In addition.to detailed surveys, the reactor tank, east and west storage pits, the inspector also
conduct surveys of the entire reactor facility. Some radiation level above general background were
present due to the storage of sealed calibration sources (Cs-137) and a critical assembly.
However, no radiation levels were found that were the result of reactor operations.
,
__
.
. .
.._
_
. .
. . . . .
.
.
. . -
.
.
,
.,
..
. - . - , . _ . . . - , . _
. - . - . .- n m.
.,
, .
_
..
- .
[
'
'
'
- )
.
,
-
,
'
-
-
-
m.
.
.
.
_
,
.
r..
.
-3-
_
_
,
^
2.:
- -
r. . .
..
~
..
15 .
Removable Radiation Level
,y
(1) location =
(a) Reactor Tank
Beta'
Alpha.
2
2
(dpe/100cm )
(dps/100cm )
bottom south (1)
<400'
<20
botton north (1)
'<400
< 20 ..
wall east (1)
<400
<20
wall west (1)
<400
.<20
<
(b) East Storage Pit
Beta
Alpha
(dps/100cm2)
(dpm/100cm )
2
bottom (4)
<400
<20
wall (1)
<400
<20
(c) West Storage Pit
Beta
Alpha
2
2
(dps/100cm )
(dps/100cm )
bottom (3)
<400
<20
wall (1)-
<400
<20
resin tank (1)
<400
<20
resin pump (1)
<400
<20
(d) 22 smears were taken on various pieces.of equipment including control rod' drive asseeblies,
experiment transfer tubes, support plates, reflector elements, and other miscellane6us items.
No beta or alpha levels above background levels were identified.
l
~
,; .
. .... .m
_ ...,..
..
. .s .--
. . _ _
-.
- . .
a.
.. , _ _ _ _,
. .
. . .
.
.
. .
. _ . _ . _ . , . ,