IR 05000148/1993001

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Insp Rept 50-148/93-01 on 930408-09.Violations Noted.Major Areas Inspected:Final Radiation Survey of Nuclear Reactor Ctr/Burt Hall Site,Personnel Dosimetry,Airborne Radioactivity,Radiation Protection Surveys & Radwaste
ML20036A523
Person / Time
Site: 05000148
Issue date: 05/06/1993
From: Murray B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20036A516 List:
References
50-148-93-01, 50-148-93-1, NUDOCS 9305120032
Download: ML20036A523 (12)


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APPENDIX

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Inspection Report:

50-148/93-01 License:

R-78 Licensee: The University of Kansas 231 Strong Hall Lawrence, Kansas 66045-2223 Facility Name: Nuclear Reactor Center

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Inspection At:

Lawrence, Kansas Inspection Conducted: April 8 through April 9,1993 Inspector:

W. Holley, Senior Radiation Specialist Facilities Inspection Programs Section t

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s Inspection Date Inspection Summary

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Areas Inspected:

Special, announced inspection of the licensee's decommissioning activities as they relate to the final. radiation survey of the Nuclear Reactor Center /Burt Hall site, personnel dosimetry, airborne radioactivity, radiation protection surveys, and radioactive waste. 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:

The licensee had completed the decommissioning of the University of

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Kansas Training Reactor (Section 1).

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The licensee had completed the final radiation survey of the reactor

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site (Section 2.2).

The ORISE Survey Team completed the final confirmatory survey without

detecting any radiation above the level for site unrestricted use; however, unrestricted use is contingent upon the analysis of the collected samples (Section 2.4).

I 9305120032 930506 PDR ADOCK 05000148 PDR g

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-2-The inspector performed independent surveys and confirmed that area

radiation and contamination levels were below unrestricted use criteria (Section 2.4).

The personnel dosimetry, air monitoring, and radiation survey were

adequate (Section 2.3).

Attachments:

Attachment 1 - Persons Contacted and Exit Meeting

Attachment 2 - Survey Data

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-3-i DETAILS

- i 1 SITE STATUS

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During December 2,1992, through April 8,1993, the licensee completed the

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final phase of the decommissioning. The final report was submitted on January 4, 1993. The reactor bay in the Nuclear Reactor Center /Burt Hall was j

completely empty.

The reactor concrete monolith used for shielding and

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housing of the reactor had been removed. Three inches of the concrete floor that was under the monolith had been removed. Two holes approximately 2.5 x 4-feet deep remained where concrete directly under the reactor had been

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removed because of the radiation produced by neutron activation'of the l

concrete. All vestiges of anything pertaining to the reactor had been removed t

from Burt Hall. The licensee had one 55-gallon drum containing waste

(activated sand and re-enforcing steel bar) from the decommissioning i

activities to be shipped for burial as soon as a contract with a vendor is in place.

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2 CLOSEOUT INSPECTION AND SURVEY (83890)

The inspector coordinated ORISE confirmatory inspection activities and also performed independent surveys of the reactor facility to determine compliance

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with the Commission's decommissioning safety evaluation which includes the i

recommendations of NRC Regulatory Guide 1.86.

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2.1 Release Criteria for Unrestricted Use

The radiation levels for release of the reactor facility for unrestricted use

are established in the " Safety Evaluation by the Office of Nuclear: Reactor-

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Regulation Related to the Dismantling of_ Facility and Disposition of Component Parts, The University of Kansas Facility License No. R-78, Docket No. 50-148"-

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and supporting NRC order dated September 19, 1991. -The safety evaluation

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requires the licensee to decontaminate the facility to satisfy the e

contamination levels in Regulatory Guide 1.86, " Termination of Operating

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Licenses for Nuclear Reactors."

In addition, external exposure rates must be 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

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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.

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_2.2 Disposition of Materials

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As part of the decommissioning activities in January and February 1986, all unirradiated fuel element assemblies were shipped to the_ Oak Ridge National Laboratory in Oak Ridge, Tennessee. All irradiated-nuclear fuel elements were,

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shipped to the Savannah River Plant in Barnwell, South Carolina.

During

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1991-1992, all radioactive waste above Regulatory Guide 1.86 criteria had been transported to Barnwell for burial. The waste below Regulatory Guide 1.86

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criteria, but above background,'was transported to a vendor's site in Bennet, Colorado. The remainder. of the waste at background level or below was

transported to a site in Kansas City, Kansas. At the time of this inspection,

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all waste had been removed from the Nuclear Reactor Center /Burt Hall site, and

it was considered decontaminated to unrestricted use levels according to the

licensee's final survey.

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2.3 Reports and Records

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The inspector reviewed the personnel dosimetry records for the period December 2,1992, through April 8,1993. The dose equivalents were 26, 19, and 15 mrem for the 3 individuals receiving the highest dose equivalents during the decommissioning activities, and the total cumulative dose equivalent was 76 person-mrem.

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The airborne radioactivity was from 3.3E-12 to 5.3E-10 microcuries per milliliter ( Ci/ml) for alpha radiation during the decommissioning activities, and the beta-gamma radioactivity was from 4.5E-10 to 1.9E-09 Ci/ml.

The inspector reviewed the weekly surveys performed during the decommissioning

activities. The gamma radiation was from 8 to 14 micro Roentgens per hour (pR/h) measured at I meter from the measured surfaces.

The. alpha

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radiation contamination ranged from 0 to 10 disintegrations per minute in a 100 square centimeter area (dpm/100 cm2), and the beta contamination ranged.

from 11-117 dpm/1002

l The licensee shipped 447 cubic feet of radioactive waste to the'Barnwell. Waste Management Facility.

The Radioactive Waste Manifest Form identified the waste to be graphite blocks, aluminum liner, concrete rubble, and contaminated trash. The main radioactive contaminants in the waste were cobalt-60 and europium-152.

2.4 Confirmatory Final Survey

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NRC contracted ORISE to perform the confirmatory final survey of the Nuclear Reactor Center /Burt Hall facility. The ORISE-personnel began' survey activities the morning of April 8, 1993, and completed the survey the

afternoon of April 9,1993. The contractor performed the survey according-to

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the recommendations ~ in NUREG 5849, " Manual for Conducting Radiological Surveys

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in Support of License Termination."

i The survey included the reactor room area and the surrounding rooms and halls

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in Burt Hall. The subspace under the floor of the= reactor room was also i

surveyed. The survey included scans, direct measurements, and loose i

contamination determinations (smear / wipe). Also, soil, concrete, and water samples were collected for analysis.

ORISE'did not detect any area radiation or final contamination levels above the unrestricted use criteria.

ORISE will issue. a confirmatory final survey report for the Nuclear Reactor Center.at the University of Kansas after the

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analyses of the samples are performed.

If the results of the analyses of the samples are below unrestricted use criteria, the decommissioning will-be

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considered successful.

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'In conjunction with contractor's confirmatory final survey, the inspector performed a verification _ survey of the Nuclear Reactor. Center /Burt Hall facility which included the reactor room, surrounding rooms, and hallways.

The radiological surveys performed included direct ~ measurements of beta and gamma exposure rates. Measurements for fixed.and removable. alpha and beta contamination were also made.

The inspector determined that the general background direct gamma radiation levels associated with the facility were approximately 11 R/h at a one meter height. The inspector verified that'the maximum residual radiation-levels were not greater than the unrestricted use criteria levels. Nof" hot spots" from any type of radiation were identified.

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The inspector did not identify any radiation from the residual contamination that exceeded the unrestricted use criteria. The data from the inspector's verification survey are presented in Attachment 2.

i 2.5 Conclusions Areas surveys and fixed contamination results were below unrestricted use l

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criteria. Unrestricted release of the University of Kansas Nuclear Reactor'

Center /Burt Hall facility is contingent upon the results of the ORISE

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confirmatory final survey report which will -include the analyses _ of the soil, concrete, and water samples.

If these results are below the unrestricted

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release criteria, the decommissioning will be considered successful.

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ATTACHMENT I 1 PERSONS CONTACTED

1.1 Licensee Personnel

  • T. Muliaazzi, Ph.D., Reactor Director
  • M. R. Lemon, Assistant Radiation Safety Officer 1.2 Commission Contract Personnel
  • A.J. Ansari, Project Leader, Environmental Survey and Site Assessment Program M. Burton, Survey Technician J. Payne, Survey Technician 1.3 NRC Personnel
  • W.L. Holley, Senior Radiation Specialist
  • Denotes personnel that attended the exit meeting,

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2 EXIT MEETING

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An exit meeting was conducted on April 9, 1993. During this meeting, the inspector reviewed the scope and findings of the report. The licensee did not identify as proprietary any information provided to, or reviewed by, the inspector.

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A"ITACIlh1ENT 2 NUCLEAR REACTOR CENTER /BURT IIALL FACILITY RADIATION SURVEY l1NSTR'UMENTATION j

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Ludlum Afodel 19 hiicro R hieter 015518 Ludlum hiodel 14C with Gm Detector 012799 Technical Associates hIodel Tilal-3S 018661 Eberline hindel PAC-ISAGA with AC-d3 000266

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Eberline Afodel SAC-4 Scintillation 012891 l

Alpha Counter (Eff. = 27.0%)

j Ludlum hlodel 2200 Gamma Counter with 000285 IIP-210 (Eff. = 11.7%)

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