IR 05000192/1993001
| ML20035G695 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 04/21/1993 |
| From: | Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20035G694 | List: |
| References | |
| 50-192-93-01, 50-192-93-1, NUDOCS 9304290088 | |
| Download: ML20035G695 (10) | |
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APPENDIX
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
l Inspection Report:
50-192/93-01 j
License: R-92
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i Licensee: Nuclear Engineering Teaching Laboratory I
10100 Burnet Road c
j The University of Texas at Austin l
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Facility Name:
TRIGA - MARK 1 Research Reactor / Taylor Hall
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i Inspection At: Austin, Texas l
l Inspection Conducted: April 5 through April 6, 1993 l
l Inspector:
W. Holf'ey, Senior Radiation Specialist l
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i Approved:
/f M}Mk
B. Murray, Chief, Facilitips Inspection Date l
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l Programs Section G
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Inspection Summary
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l Areas inspected:
Special, announced inspection of the licensee's
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decommissioning activities as they relate to the final radiation survey of the
Taylor Hall reactor site, personnel dosimetry, area dosimetry, training, and
water sample analyses.
The inspector coordinated confirmatory surveys
performed by the NRC contractor, Oak Ridge Institute for Science and
Education (0 RISE), and also performed independent surveys.
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Results:
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The personnel dosimetry, area dosimetry, and water analyses
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i programs were adequate (Section 2.3).
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The ORISE Survey Team found contaminated areas that were not j
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l identified during the licensee's final radiation survey (Section 2.4).
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The confirmatory survey was not completed, because a concern was
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identified involving possible contam,iation between the liner and l
concrete support structure (Section 2.4).
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The inspector performed independent surveys (Section 2.4).
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9304290088 930422
'I PDR ADOCK 05000192
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-2-Attachments:
Attachment 1 - Persons Contacted and Exit Meeting
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Attachment 2 - Survey Data
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-3-l DETAILS
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1 SITE STATUS
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During December 11, 1992, through April 5,1993, the licensee completed the
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final phase of the decommissioning which included the final radiation survey
of the reactor site and surrounding area in Taylor Hall.
After the completion l
of the final radiation survey, no activities were performed at the site except
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the removal of water that had seeped into the reactor tank liner area where a
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portion of the liner and concrete had been removed during decommissioning to l
remove neutron activated materials.
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2 CLOSE00T INSPECTION AND SURVEY (83890)
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The inspector coordinated ORISE confirmatory inspection activities and also f
performed independent surveys of the reactor facility to determine compliance l
with NRC's decommissioning safety evaluation which included the l
recommendations of NRC Regulatory Guide 1.86.
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2.1 Release Criteria for Unrestricted Use
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i The radiation levels for release of the reactor facility for unrestricted use
are established in " Safety Evaluation by the Office of Nuclear Reactor
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Regulation, Supporting Order Authorizing Dismantling of Facility and
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Disposition of Component Parts for Facility Operating License No. R-92 The
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University of Texas at Austin, The University of Texas Triga Reactor, Docket No. 50-192" and supporting NRC order dated March 9, 1987. The safety i
evaluation requires the licensee to decontaminate the facility to satisfy the
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contamination levels in Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear peactors."
In addition, external exposure rates must be
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less than 5 micro Roentgens per hour (pR/h) above natural background at
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I meter from the measured surfaces or that no person will receive more than l
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.
2.2 Disposition of Materials l
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During 1991-1992, the reactor had been dismantled and the fuel moved from Taylor Hall to the Balcones Research Center.
Also, the cobalt-60 irradiator and reactor components and equipment were transferred to Balcones Research
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Center. All radioactive waste had been transported to Barnwell, South
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Carolina, for burial. At the time of this inspection, all waste had been
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shipped from the Taylor Hall site, and it was considered decontaminated to unrestricted release levels according to the licensee's final survey.
2.3 Reports and Records j
The inspector reviewed the personnel dosimetry records for the period December 11, 1992, through April 5, 1993.
The maximum dose equivalent recorded by an individual working at Taylor Hall was 80 mrem.
However, it is believed that this dose was actually received during activities at the new
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reactor site Balcones Research Center, since the area dosimetry in Taylor j
Hall indicated the radiation was at background levels.
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The inspector reviewed the summary report of the personnel monitoring
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information for 1992 submitted to NRC. The decommissioning / decontamination
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activities occurred in 1992, and only three individuals were in the 0.1 - 0.25 l
rem range, and all other personnel were below this range.
i A bottom portion of the reactor tank liner and supporting concrete had been
removed during the decontamination activities because of the radioactivity i
present in this area caused by neutron activation.
Some ground water had i
intruded into the reactor tank through the liner hole and had been pumped into
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storage barrels. This water had been sampled and analyzed for cobalt-60 and
The inspector determined that the radioactivity concentration in r
these samples was 2.5E-4 to 7.2E-4 pico curies per milliliter (PCi/ml).
I 2.4 Confirmatory Final Survey
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NRC contracted ORISE to perform the confirmatory final survey of the Taylor
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Hall facility. Thd'ORISE personnel began survey activities the morning of l
April 5, 1993.
The contractor performed the survey according to the
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recommendations in NUREG 5849, " Manual for Conducting Radiological Surveys in Support of License Termination."
The areas surveyed included the reactor room and the surrounding rooms and I
halls in Taylor Hall. The reactor tank liner and the subspace under the floor i
of the reactor room were also surveyed.
The survey included scans, direct
measurements, and loose contamination determinations (smear / wipe).
Soil, concrete, and water samples were also collected for analysis.
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A " hot spot" of 47,000 disintegrations per minute in a 100 square centimeter l
area (dpm/100 cm2) of beta radiation was found on the floor in the former i
Chemistry Room 125.
This area was decontaminated immediately by the licensee
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during this inspection.
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j Contamination was found on the top surface between the interface of the l
l reactor tank liner and the concrete floor.
The beta radiation from this fixed
contamination was 11,000 dpm/100 cm2 Other contamination emitting beta l
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radiation was found on the reactor room floor in proximity to the reactor tank liner. This radiation ranged from 19,000 to 46,000 dpm/100 cm2 The source of this contamination was water overflowing the reactor tank onto the floor i
that had occurred on several occasions during the operation of the reactor.
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l This contaminated water was contained in a primary / secondary dam system.
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primary dam was constructed around the top of the reactor tank at floor level.
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This dam had overflow openings about 1.5 inches above floor level-.
Water had
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flowed through these openings, and a portion of the contamination was found i
outside the primary dam.
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The licensee found contamination in the subspace below the reactor room floor during their final survey. The floor contained a visible crack and evidently I
the contaminated water traversed this crack and deposited the radioactivity.
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Visual inspection of the interface between the aluminum reactor tank liner and I
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the concrete floor could not validate the seal between these two surfaces; l
therefore, water may have leaked between the tank liner and the concrete
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support similar to the leak in the crack in the floor.
Since the
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contamination found on the floor close to this interface exceeded the
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unrestricted release criteria, it was determined that the licensee would need
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to remove the reactor tank liner to demonstrate a successful decommissioning.
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In conjunction with ORISE's confirmatory final survey, the inspector performed
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a verification survey of the Taylor Hall facility which included the reactor l
room, surrounding rooms, hallways, and the subspace under the reactor room
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floor.
The radiological surveys performed included direct measurements of
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i beta and gamma exposure rates. Measurements for fixed and removable alpha and
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beta contamination were also made.
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The inspector determined that the general background direct gamma radiation l
levels associated with the facility were 9-11 R/h at a one meter height.
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inspector verified that the maximum residual radiation levels were not greater
than the general background level.
No " hot spots" from gamma radiation were
identified.
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I The inspector did not identify any radiation from the residual contamination i
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j that exceeded the unrestricted use criteria except for those areas on the i
j reactor room floor discussed above.
The data from the inspector's independent l
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survey are presented in Attachment 2.
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s 2.5 Conclusions i
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Unrestricted release of the Texas University Research TRIGA - MARK I j
Reactor (Taylor Hall) will not be completed until the reactor tank liner
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is removed and the confirmatory final survey verifies that contamination
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does not exceed release criteria.
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I When the licensee completes the removal of the reactor tank liner and i
performs a final survey, ORISE will perform confirmatory measurement
l surveys.
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ATTACHMENT 1 l
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1 PERSONS CONTACTED
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1.1 Licensee Personnel
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1.1.1 Nuclear Engineering Teaching Laboratory
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+B.W. Wehring, Director
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- T.L. Bauer, Assistant Director l.1.2 Of fice of Environmental Health and Safety l
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J.C. White, Radiation Safety Officer
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L.W. Hamlin, Assistant Radiation Safety Officer
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1.2 Contract Personnel
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- A.J. Ansari, Project Leader, Environmental Survey and Site Assessment
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l Program, ORISE
M. Burton, Survey Technician, ORISE J. Payne, Survey Technician, ORISE
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1.3 NRC Personnel l
- W.L. Holley, Senior Radiation Specialist
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j B. Murray, Chief, Facilities Inspection Programs Section
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- Denotes personnel that attended the exit meeting.
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2 EXIT MEETING l
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j An exit meeting was conducted on April 6, 1993.
During this meeting, the l
inspector reviewed the scope and findings of the report.
The licensee stated l
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that the reactor tank liner will be removed and a final survey radiological survey performed on the liner and concrete support structure. The licensee j
did not identify as proprietary any information provided to, or reviewed by,
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the inspector.
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ATTACHMENT 2
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Taylor Hall Facility Radiation Survey (
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Instrumentation
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Portable Survey Meters f
Model NRC ID Number
Ludlum Model 19 Micro R Meter 015518 l
Ludlum Model 14C with Gm Detector 012799 l
Technical Associates Model TBM-3S 018661 l
Eberline Model PAC-ISAGA with AC-d3 000266
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Laboratory Counters
Model Eberline Model BC-4 Beta Counter 014812 (Eff. - 17.5%)
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Eberline Model SAC-4 Scintillation 012891 Alpha Counter (Eff. = 26.9%)
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Ludlum Model 2200 Gamma Counter 000285 (
with HP-210 (Eff. - 11.9%)
l 2.
Survey Results - Direct Radiation levels i
location Gamma ( R/h @ Im)
Beta (mR/h)
Alpha (cpm)
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at 1 m Contact Contact l
Reactor Room NW Corner
<0.02
t W Side Center
<0.02
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SW Corner
<0.02
i S Side Center
<0.02
SE Corner
<0.02
i E Side Center
<0.02
l NE Corner
<0.02
N Side Center
(0.02
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N Side 10' from Wall
<0.02
l W Side 10' from Wall
<0.02
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l S Side 10' from Wall
<0.02
E Side 10' from Wall
<0.02
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Top of Secondary Dam
<0.02
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Top of Primary Dam
<0.02
i Around Top of Rx Ik
<0.02
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Control Room
<0.02
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Control Room SW Office 11
<0.02
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Control Room SE Office 11
<0.02
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Entry Hallway
<0.02
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2.
Survey Results - Direct Radiation levels (cont')
location Gamma (gR/h @ Im)
Beta (mR/h)
Alpha (cpm)
at 1 m Contact Contact Chemistry Laboratory NW Corner
<0.02
W Wall Center
<0.02
SW Corner
<0.02
S Wall Center
<0.02
SE Corner
<0.02
E Wall Center
<0.02
NE Corner
<0.02
N Wall Center
<0.02
i Center of Lab.
<0.02
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N Hallway
<0.02
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Room E of Lab.
<0.02
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Maintenance &' Repair
<0.02
l Shop l
Fan Room
<0.02
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S Office
<0.02
SW Office
<0.02
SE Office
<0.02
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3.
Survey Results - Removable Contamination Location Alpha Beta Gamma (dpm/100 cm2)
(dpm/100 cm2)
(dpm/100 cm2)
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Reactor Room j
l N Center Floor
<MDA (MDA
<MDA
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W Center Floor
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S Center floor
<MDA
<MDA
<MDA l
E Center Floor
<MDA
<MDA
<MDA i
NW Corner Floor
Floor Between Secondary <MDA
<MDA
<MDA l
Dam and Control Room
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Pump Platform (MDA
<MDA (MDA i
Top of Secondary Dam
Floor Between Primary
<MDA
<MDA i
and Secondary Dams l
N of Rx Cavity Floor Between Primary
<MDA
61 and Secondary Dams
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E of Rx Cavity i
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3.
Survey Results - Removable Contamination (cont')
location Alpha Beta Gamma (dpm/100 cm2)
(dpm/100 cm2)
(dpm/100 cm2)
Floor Between Primary
<MDA (MDA
and Secondary Dams NE Corner of Rx Cavity 3' High on N Wall
<MDA
<MDA
3' High on W Wall
<MDA
<MDA Valve 1 W Wall
<MDA
<MDA
<MDA Valve 2 W Wall
<MDA
<MDA (MDA (MDA 8" above Floor Floor Control Room
<MDA
<MDA (MDA Floor Control Room
Floor Control Room
<MDA (MDA (MDA SE Office Subspace Below Reactor Room Floor Floor SW Side of
<MDA
<MDA (MDA Concrete Shield Ceiling Crack (Reactor
<MDA (MDA Room Floor)
Ceiling N of Shield
<MDA
(MDA j
Ceiling SW of Shield
' adder Entry to (MDA
<MDA
<MDA Subspace Floor Fan Room
54 112 Floor Maintenance Shop <MDA (MDA
<MDA Work Bench Surface
<MDA
<MDA
<MDA Maintenance Shop Floor S Office (MDA (MDA (MDA Floor SW Office
<MDA (MDA
<MDA Floor SE Office
<MDA
(MDA Chemistry Laboratory Floor NW Corner
<MDA (MDA
<MDA Floor SW Corner
<MDA
<MDA (MDA (MDA Floor NE Corner
<MDA (MDA (MDA Floor Center of Lab
<MDA'
<.MDA
<MDA Floor S Center
<MDA
(MDA l
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Survey Results - Removable Contamination (cont')
i Location Alpha Beta Gamma (dpm/100 cm2)
(dpm/100 cm2)
(dpm/100 cm2)
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Sink (MDA
<MDA (MDA l
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Hood
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<MDA
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l Floor Room E of Lab (MDA
<MDA
<MDA I'
MDA(Alpha) = <1 cpm
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MDA(Beta) = <5 cpm l
MDA(Gamma) = <5 cpm i
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