IR 05000112/1989002
| ML19332E440 | |
| Person / Time | |
|---|---|
| Site: | 05000112 |
| Issue date: | 11/24/1989 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19332E435 | List: |
| References | |
| 50-112-89-02, 50-112-89-2, NUDOCS 8912070227 | |
| Download: ML19332E440 (9) | |
Text
,.,
%'
tw;, '
,
y7J
f,,
-APPENDIX
'N U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
'
<,
n.
?ftC' Inspection Report:
50-112/89-02 License:
R-53 y
o
,
.
.
50-112
!
,
- Docket:
'
>
-
Lic:nsee:
University of Oklahoma -
l 865 Asp Ave., Room 212 r
Norman, Oklahoma 73019 i
Facility Name:
AGN-211P, Research Reactor (100KW)
. Inspection At:
University of Oklahoma, Norman, Oklahoma i
sInspection Conducted:i 0ctober 11, 1989
.
Inspector:.
/INE MlN
'
Ronard E. Baer, Health FWysicist, Facilities Date Radiological Protection Section
,
.
.Acctmpanied By:
Blaine Murray, Chief, facilities Radiological l
Protection Section
,
Approved:l N
Bla ne Murray, Ch' ey, acilities Radiological Date Protection Section j
Inspection Summary Inspection Conducted October'11, 1989 (Report 50-112/89-02)
-Areas Inspected:. Special, announced, closeout inspection involving the review
-
cctivities associated with the decommissioning of the University of Oklahoma AGN-211P Research Reactor facility. The inspector also performed confirmatory rrdiological surveys regarding the reactor equipment and facilities.
The guidance provided in NRC Inspection Procedure 83890 was utilized.
,
s.
6912070227 691127 PDR ADOCK 05000112
-
O PDC j
.
.
,-
,
- ,
.
+
,
,
"
[
.
APPENDIX I
U.S. NUCLEAR REGULATORY COMMISSION
!
REGION IV
U NRC Inspection Report:
50-112/89-02 License:
R-53 t
Docket:.50-112
. Licensee:. University of Oklahoma 865 Asp Ave., Room 212 g
Norman, Oklahoma 73019 2 Facility Name:
AGN-211P, Research Reactor (100KW)
Inspection At:
University of Oklahoma, Norman, Oklahoma Inspection Conducted: October 11, 1989 Inspector:
MN
/
Ronal~d E. Baer, Health fmysicist, facilities Date Radiological Protection Section Accompanied By:
Blaine Murray, Chief, Facilities Radiological Protection Section Approved:
b N
Bla'ne Murray, Ch'e y, acilities Radiological Date Protection Section q
. 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 surveys regarding the reactor equipment and facilities.
The l
guidance provided in NRC Inspection Procedure 83890 was utilized.
j i
8912070227 891127 i-PDR ADOCK 05000112 l.
O PDC
C:
~~
}
..
-
,
e
.
.
- s.
'
-
.
2-i.
!
I k
[
Results: The licensee's action concerning personnel radiation protection, fuel
!
disposition, and external radiation exposure and loose contamination levels for equipment and facilities met established regulatory criteria.
Confi rmatory F
radiological surveys conducted by the inspector verified that the facility met g'
the recommended guidance in NRC Regulatory Guide 1.86 for release of the facility for unrestricted use.
'-
I Jc No violations or deviations were identified in the areas inspected.
,
F h
f
.
I
!
i i
!
I l'
p s
.I
,
'
__
m
..
,
.
I
.
-
!
<
DETAILS
,
,
,
. 1.
Persons Contacted University of Oklahoma
- Dr. D. M. Egle. Director, School of Aerospace and Mechanical Engineering
- Dr. P. Skierkowski, Radiation Safety Officer
- Denotes those present during the exit interview on October 11, 1989.
2.
Followup on Previously Identified Inspection Findings (Closed) Violation (112/8701-03):
Failure to Provide Emergency Response Yraining - This violation was identified in NRC Inspection Peport 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 members of the Norman Fire Department during the period of September 11-15, 1989.
(Closed) Violation (112/8901-01):
Authority to Dismantle a Facil_ty -
i This violation was identified in NRC Inspection Report 50-112/89 Sl~and involved the dismantling of the University of Oklahoma research reactor 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 Mestings -
'
This violation was identified in NRC Inspection Report 50-112/b9-01 and involved the failure of the reactor safety committee to conduct semiannual
.
meetings.
The NRC order, of June 5, 1989, does not require a reacter i
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 i
involved the failure of the reactor safety committee to perform the
~
' required 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.
_..
'
.
.
'
.
,
-4-i
,
I (Closed) Violation (112/8901-05):
Emeroency Response Training - This violation was identified in NRC Inspection Report 50-112/89-01 and involved the lack of emergency response training for the Norman Fire Department.
This was a repeat violation (112/8701-0*>).
The licensee had provided radiation safety training for 13 members of the Norman Fire
>
Department during the period September 11-15, 1989.
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
'
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 safety evaluation states that surfaces must be decontaminated to levels consistent with Table 1 of Regulatory Guide 1.85, " Termination of Operating Licenses for Nuclear Reactors." In addition, external exposure rates must be less than 5 micro Roentgens per hour (pR/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
.
.
.
.
l-
,
L.
..
!
'
5-i
.
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.
6.
Licensee's Termination Survey Report
'
L The. licensee submitted the " Dismantling and Decommissioning Activities for the University of Oklahoma AGN-112P Nuclear Reactor Facility Docket
,
No. 50-112" on August 28, 1989.
This report summarized the results of
,
! :.
surveys and decommissioning activities in the decommissioning log book
~
during the period of May 18, 1988, through August 1989.
The inspector reviewed the decommissioning log to determine if radiation 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.
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 reledse 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 pR/h.
The
-
inspector also verified that the maximum residual radiation levels were not greater 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 alpha 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 were taken over a nominal 100 square centimeters (100 cm ) and analyzed
for alpha and beta disintegrations per minute (dpm/100 cm ).
No removable i
radiation contamination levels above background levels were found.
The specific details concerning the radiation surveys are documented in Attachment 1.
No violations or deviations were identified.
. -
-
- -
.. -
-
-
j
.- -
,
.
- -
.
-6-8.
Reactor Components The inspector surveyed the reactor components such as control rod drives, j
reflector elements.-core support item 3, and experiment transfer tubes.
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 pR/h above background were found on a bolt in the tip of 27 reflector elements.
Fn110wup 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 levels 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.
9.
Exit Interview The inspector met 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 surve _ _ - -
_ - - - -
_
-
_,
._.
,.
,.
.
,
__
,
ATTACIMENT
-
- -
.
,
Confirmatory Measurements Radiation Surveys
,f 1.
Instrumentation Portable Survey Meters Model NRC Identification Number Scintillation Detector 000266 Ludium Model 19 Micro R meter 015535 Ludlum Model 19 Micro R meter 016338 Ludium 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 (pr/h)
Beta (orad /h)
Alpha (dpm/100cm )
j Survey BKGD Contact Contact l
l Bottom - contact
12
<0.02
<20
'
Bottom - 1 meter
12 3 ft. above bottom contact
12
<0.02
<20 3 f t. above bottom 1 meter
12 6 ft. above bottom contact
12
<0.02
<20 6 ft. above bottom 1 meter
12 Top, Floor Area - contact
12
<0.02
-<20 Top, Floor Area - 1 meter
-12
. _ _
- _ _ _ _ _ _ _ _. -
__ ________ -------------- ---.
-
_ _.
..__
__ _
_m.
_
___
. _ _
_
b
,w
'
-
-2-
.
(b) East Storage Pit Gamma (pr/h)
Beta (arad/h)
Alpha (dpm/100cm )
Survey BKGD Contact Contact.
Bottom - contact
12
<0.02
<20 Bottom - 1 meter
12
3 ft. above bottom-contact
12
<0.02
<20 3 ft. above bottom-1 meter
12
6 ft. above bottom contact
12
<0.02
<20 6 ft. above bottom-1 meter
12
Top, Floor Area - contact
12
<0.02
<20 Top, Floor Area - 1 meter
12
(c) West Storage Pit Gamma (pr/h)
Beta (arad/h)
. Alpha (dpm/100cm )
Survey BKGD Contact Contact Resin Tank / Pump-contact
12
<0.02
<20 Bottom - contact
12
<0.02
<20 Bottom - 1 meter
12 3 ft. above bottom-contact
12
<0.02
<20 3 ft. above bottom-1 meter
12 6 ft. above bottom-contact
12
<0.02
<20 6 ft. above bottom-1 meter
12 Top, Floor Area - contact
12
<0.02
<20 Top, Floor Area - 1 meter
~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 I
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.
l
.
. -
-
.
_
_
.
.
- -.
.
.
p-
-
-
.
, y
_
.q
-
-
'
-
.
,s
-
o
_.
,
,
,.,
..,
-.
-
,
-
..
.
'
-
-3-
.
.-
.
b.
Removable Radiation Level-
'
..;
(1) location (a) Reactor Tank Beta-Alpha-
2 (dpe/100cm ).
(dps/100cm ).
' bottom south (1)
<400
-<20 bottom north (1)
<400
- <20 wall east (1)
<400
<20'
'
wall west (1)
<400
<20 (b) East Storage Pit Beta Alpha
2 (dps/100cm )
(dps/100cm )
bottom (4).
<400
<20 wall (1)
<400
<20 (c) West Storage Pit Beta Alpha.
2 (dps/100cm )
(dpe/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 assemblies, experiment transfer tubes, support plates, reflector elements, and other miscellaneous items.
No beta or alpha levels above background levels were identified.
-
-