ML20151R977
| ML20151R977 | |
| Person / Time | |
|---|---|
| Site: | 05000538 |
| Issue date: | 07/27/1988 |
| From: | Hosey C, Kuzo G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151R974 | List: |
| References | |
| 50-538-88-01, 50-538-88-1, NUDOCS 8808150002 | |
| Download: ML20151R977 (5) | |
See also: IR 05000538/1988001
Text
-
-. ..
E UNITED STATES
'Mouq*
, :i: *
.-
.
.o NUCLEAR REGULATORY COMMISSION
REGION ll
[
-
g. g
-
,
101 MARIETTA STREET N.W.
- '- K ATLANTA. GEORGIA 30323
\; .- . ,o#
....
JUL29 M
Report No.:- 50-538/88-01
Licensee: Memphis State University
Memphis, TN- 38152
Docket No.: 50-538 License No.: R-127
Facility Name: Memphis State University AGN-210 Training Reactor
j. Inpsection Conducted: June 23-24, 1988
Inspector: MWM bn %N OD
G. B' Kuzo Date Siigned
Approved by: M
C. M. Hosey, Section Chief
7b M
Date Sighed
Division of Radiat'on Safety and Safeguards
SUMMARY
Scope: This special announced closecut inspection involved the review of
licensee radiation protectioni activities associated with decommissioning of the
Memphis State University (MSU)'AGN-201 Training and Research Reactor facility,
and also the performance of confirmatory radiological surveys for the reactor
equipment and facilities.
Results: The licensee's actions concerning personnel radiation protection,
fuel disposition, and equipment and facilities external radiation exposure and
loose contamination levels for equipment and facilities met established
regulatory criteria. Supplemental survey results for fixed surface
radioactive contamination levels for equipment and facilities conducted
subsequent to the onsite inspection and reviewed by the NRC, met the established
release criteria for unrestricted use of the facilities.
No violations or deviations were identified in the areas inspected.
i
8808150002
680729
O ADOCK 05000338 *
PDC j
,
_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
E d
<
'
s:
- 's
.
REPORT DETAILS
1. Persons Contacted
R. Collier, Director, Public Service
- V. Oliphant, Vice President, Planning and Public Service
- R.-Riley, Radiation Safety Officer, Safety Services
- Attended exit interview
, 2. Closecut Inspection and Survey (83829)
a. Request for Confirmatory Radiological Surveys
The Memphis State University (MSU) AGN-207 Nuclear Research and
Training Reactor was operated at the University from December 10,
1976 through March 31, 1985.
In an application to the Office of Nuclear Reactor Regulation (NRR)
dated March 15, 1985, the licensee requested conversion of its
3
license to a possession only status while plans were being developed
for decommissioning and license termination. Amendment No. 5, to the
MSU Facility Operating License No. R-127 was issued on June 17, 1985,
authorizing possession only status of the reactor at MSU. Initial
plans for accomplishing the dismantlement, disposal and
decontamination of the MSU AGN-201 Reactor and its associated
facilities were forwarded by the licensee to NRR by letter dated
November 10, 1986. Additional informatior, regarding the plans was
detailed to NRR in letters dated June 10, 1987, and August 21, 1987.
Plans included discussion of decontamination methods, radiological
monitoring and surveys to be performed, and residual radiological
contamination and exposure limits to be established for release
and/or unrestricted use of the equipment and MSU facilities associated
with the reactor.
The NRC issued an Order on January 26, 1988, authorizing the
dismantling of the facility and disposition of the component parts.
By letter dated March 24, 1988, the licensee forwarded to NRR, a
request for verification of their radiological surveys, and for the
issuance of an order to terminate License No. R-127. NRR requested
the NRC Region II office to provide a final radiological survey of
the facility to verify that residual radiation and contamination
levels met the requirements of Regulatory Guide 1.86 Table 1, the
maximum dose rate was 5 microRoentgens per hour (uR/hr) above
background at a one meter distance from all materials and all fuel
was removed from the MSU facilities.
y .
'
-
,
- . :
e
2
b. Disposition of Special Nuclear Materials
The MSU AGN-201 Training and Research Reactor facility operated from
approximately December 1987, through March 1985. The reactor
operated at a maximum power level of 0.1 watt thermal.
Status of all fuel utilized for operation of the facility and a
Radium-Beryllium (Ra-Be) startup source authorized by license
No. R-127 were reviewed by the inspector. All fuel originall
received onsite was shipped to the Department of Energy (DOE)y
facilities, Oak Ridge, TN, during February 1987. The inspector
reviewed 00E/NRC Form 741, Nuclear Material Transaction Reports,
dated February 18, 1987, and corractions thereto, dated March 31,
1988, verifying shipment of fuel to the DOE facility. In addition,
tours of the reactor facilities confirmed that the reactor components
were dismantled and all fuel materials were shipped.
The 10 millicurie (mci) Ra-Be startup source originally authorized by
HRC License R-127 was retained and was stored at the facility.
Authorization for possession of the Ra-Be source material was
transferred to the State of Tennessee License No. R-79177-C-89. The
inspector reviewed and discussed the State license with cognizant
personnel to verify that the startup source could be retained under
the State license.
No violations or deviations were identified.
4. Personnel Exposure
The inspector reviewed exoosure records for personnel involved with fuel
movement and handling, and dismantlement and surveys of the MSU reactor
equipment and associated f acilities. For fuel movement and handling
activities , both whole body and extremity (finger ring) dosimeters were
utilized. All results were reported as less than 10 millirem (mrem), the
- vendor's minimum measurable quantity dose equivalent. During radiation
i surveys, only whole body dose monitoring was performed. All results were
reported as not exceeding the minimum dose equivalent.
The cognizant licensee representative stated that the records required by
10 CFR 20.401(c) would be maintained indefinitely by the MSU radiation
safety office which will continue to monitor campus radiation safety
activities not associated with the NRC license.
5. Termination Radiation Contamination Surveys
The NRR Safety Evaluation Report (SER) for decommissioning of the MSU
AGN-201 facilities located in Building 113 of the MSU south campus was sent
as an enclosure to a letter from NRR to MSU dated January 26, 1988, which
also transmitted the Order authorizing dismantling of the reactor and
disposition of component parts. Section 4.5 of the SER requires that for
,
unrestricted use of the facility or materials, the facility and/or
materials must meet or be less than the surface contamination levels
I
_.
.. _
..
. .
.
3
detailed in Regulatory Guide 1.86, Table 1, and must not exceed an
exposure rate limit of 5 microroentgens per hour (uR/hr) above natural
background at 1 meter from the measured surface.
The inspector reviewed the licensee's final contamination survey results
which were provided as an enclosure to a letter from the licensee to the
NRC Region 11 office dated March 24, 1988. Background exposure levels
measured approximately 18 uR/hr. Excluding Room 147, exposure results
measured at one meter above selected surface areas in Building 113 ranged
from 6 to 22 uR/hr throughout the reactor facility and associated rooms
within the building. The elevated exposure reading noted for Room 147
resulted from the storage of the Ra-Be startup source and other
radioactive source material maintained under the State of Tennessee
license. This area was being maintained as a controlled area by the
campus radiation safety office.
The inspector noted that the licensee reported smearable (removable)
surface contamination results for equipment at the facility as counts per
minute (cpm) for both beta / gamma and alpha analyses. Furthermore, the
licensee's report did not indicate the efficiency of the survey instrument
utilized to conduct the measurements nor listed the area of the surveys.
Regulatory Guide 1.86 established acceptable fixed and removable surface
contamination levels in units of disintegrations per minute per 100 square
centimeters (dpm/100 cm2). The inspector noted that the licensee needed
to report their smearable contamination results in the appropriate units
and also needed to conduct additional surveys of fixed and smearable
contamination levels on selected equipment and building surfaces within the
facilities. Licensee representatives stated that the appropriate surveys
would be conducted to meet the established criteria for unrestricted
release or use of the facilities. They agreed to conduct the appropriate
surveys and provide the information to the NRC as an addendum to their
initial termination survey report.
The inspector performed radiation exposure surveys throughout the reactc'
room, control room and adjacent rooms in the Building 113. NRC values
were slightly lower than licensee values, background measurements
indicating 7 uR/hr and survey measurements ranging from 3 to 7 uR/hr
for all areas, excludirg Room 147 where the sources were maintained. In
addition, the inspector took approximately 28 swipes of selected facility
and equipment surface areas to verify that the limits for removable
(smearable) contamination were not excced. All NRC results were less than
the limits specified in Regulatory Guide 1.86. During the inspection, the
inspector did not conduct surveys of fixed alpha or beta / gamma contamination
levels.
6. Exit Interview
The inspection scope and findings were summarized on June 24,1988, with
those persons indicated in Paragraph 1. The inspector discussed the areas
inspected and noted that supplemental surveys for fixed alpha and beta
surface contamination levels associated with the equipment and selected
facility areas were needed to meet the release and/or unrestricted use
t
_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _
..
w 5
.
4
criteria specified in the decomissioning plans submitted by the licensee.
NRC review and verification of these supplemental radiation contamination
surveys, were considered necessary subsequent to a decision being made
regarding termination of the license. In letters dated July 14, 1988, and
July 26, 1988, from MSU to NRR, the licensee provided supplemental
information regarding their final survey report. All results for the
fixed and removable alpha and beta / gamma surveys conducted were below the
limits specified in Regulatory Guide 1.86. The licensee did not identify
as proprietary any of the material provided to or reviewed by the
inspector during this inspection. Dissenting coments were not received
from the licensee.
. ..