IR 05000148/1990001
| ML20006E254 | |
| Person / Time | |
|---|---|
| Site: | 05000148 |
| Issue date: | 02/08/1990 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20006E253 | List: |
| References | |
| 50-148-90-01, 50-148-90-1, NUDOCS 9002220451 | |
| Download: ML20006E254 (5) | |
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APPENDIX
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U.S;' NUCLEAR REGULATORY COMMISSION
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REGION IV
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'NRC Inspection Report:
50-148/90-01 License:
R-78 Docket:
50-148 zLicensee: The University of Kansas-(KU)
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Lawrence, Kansas-66045-2223 l
Facility Name: Nuclear React'or Center (Defueled Bendix Pool Type Reactor)
i Inspection'At: Nuclear Reactor Center (Burt Hall), KU
Inspect 1on Conducted: January 19, 1990
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' Inspector:
R( E. Baer, Radiation Protection Specialist Dite '
Facilities Radiological Protection Section Approved:
48 MlMdM N
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B.Murra~y,' Chief, Fappities Radiological Dat'e /
Protection Section/
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Inspection'~ Summary:
' Inspection-Conducted January 19, 1990 (Report 50-148/90-01)
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. Areas Inspected:
Nonroutine, announced inspection of the reactor facilities-L
,to confirm the radiological conoitions documented during the licensee's October 16,-1989, survey. The inspector used'the guidance provided in NRC
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Inspection Procedure 83890 in the performance of the confirmatory radiological surveys.
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Results: The licensee had removed all equipment from the southeast and-southwest' corners of the lower floor of the. nuclear reactor building and
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performed-an initial survey on October 16, 1989. A confirmatory radiological
- survey conducted.by the inspector verified that the facility met the guidance
. in NRC Regulatory Guide 1.86 for release of these areas for unrestricted use.
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PDR. ADOCK 05000148
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DETAILS
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1.
Persons Contacted
- H. F. Rosson, Reactor Director
- M. R. Lemon, Assistant Radiation Safety Officer
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- Indicates those individuals present at the exit interview on January 19, 1990.
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2.
Class II Operation and Procedures (40750)
a.
-Background The KU reactor had been defueled and is awaiting a final decommissioning plan. The_ reactor status had been previously discussed in NRC Inspection Reports 50-148/86-01 and 50-148/89-01.
The licensee had in October 1989 surveyed the reactor control center (southeast) and demineralizer and storage-pool (southwest) areas
located on the lower floor of the nuclear reactor building.
Figure 1 depicts the area locations.
The licensee requested through Office of-Nuclear Reactor Regulation (NRR) on November 15, 1989, that an NRC confirmation survey be made to avoid potential problems at the time of final decommissioning about the radiological status of these areas-as they plan to place a new concrete floor and retention curb over
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the existing floor and construct a storage facility for low-level and
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mixed radioactive waste.
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b.
Release Criteria for Unrestricted Use The radiation levels for release of a reactor facility for unrestricted use must be. reduced to levels consistent with Table 1 of Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors." In addition, external exposure rates must be less than 5 micro Roentgens per hour (uR/h)'above natural background at I meter i
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from the measured surfaces or that no person will receive more than
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10 mrem / year. Natural background has been defined as radiation from naturally occurring-radioisotopes as measured at a comparable j
uncontaminated structure or exterior soil surface.
'l The inspector used Regulatory Guide 1.86 criteria as a basis for l
comparison of the confirmatory survey with the understanding that the
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area will not be released for unrestricted use at this time, but l
rather for the storage of low level and mixed radioactive waste.
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c.
Independent Confirmatory Measurements The' inspector performed a verification survey of the areas depicted
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in. Figure 1 of the nuclear reactor building. This survey was l
performed to independently verify the radiological status of the area. The radiological surveys performed included direct measurements of beta and gamma radiation _ levels.
Measurements of i
removable (transferable) and nonremovable alpha and beta contamination were also made. All components except the aluminum
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storage pool.. liner had been removed from these areas.
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The inspector determined that the general background direct gamma L
radiation levels associated with the facility were 7 to 10 uR/h inside'the storage poo.1 liner and 10 to 14 uR/h on the operating g
floor level. The inspector also verified that the maximum residua'l gamma radiation levels were not greater than the general background-
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levels No localized " hot spots" were identified.
In addition to gamma measurements, the inspector also performed surveys ~to identify
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c fixed beta radiation levels.
One small area, less than 100 square centimeters (100 cm2) was identified where radiation levels were approximately 350 counts per minute above background. This area was
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decontaminated to background levels before the inspector left the-T f ac ;11ty.
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i The inspector performed surveys to identify removable alpha and beta contamination using conventional paper smear techniques. Smear y
surveys were taken over a-nominal'100 cm2 and analyzed for alpha and
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beta radioactivity. No removable radioactive contamination levels above background levels were identified.
4 Instrumentation'used are. documented in the attachment to this report.
No violations or deviations were identified.
3.
Exit. Interview
'The inspector met with'the licensee representatives denoted in paragraph 1 of this report at the conclusion of the inspection on January 19, 1990.
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The inspector summarized the. inspection findings and verification sur'vey results. The licensee did not identify as proprietary any of the o
materials provided te or reviewed by the inspector during the inspection.
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ATTACHMENT
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-Instrumentation Portable NRC Identification Survey Meters Model-Number
.Ludlum Model 19' Micro R Meter 015545
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XetextModel 3058 011601 Technical Associates Model TBM-35 018662 Laboratory NRC Identification Counters Model Number
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Eberline Model DC-4 Beta Counter (Eff. = 16%)
014812 Eberline Model 9AC-4 Scintillation Alpha Counter 012831
(Eff. = 27%)
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