IR 05000262/1987002
| ML20214N670 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 05/28/1987 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20214N668 | List: |
| References | |
| 50-262-87-02, 50-262-87-2, NUDOCS 8706030006 | |
| Download: ML20214N670 (4) | |
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.n APPENDIX U.S. NUCLEAR REGULATORY COMMISSION -
REGION IV
NRC Inspection Report: 50-262/87-02 License: 'R-109 Docket: 50-262 Licensee: Brigham Young University (BYU)
Provo, Utah 84602 Facility Name: Nuclear Laboratory - Model L-77 Reactor (10 watt)
- Inspection At
- BYU Campus, Provo, Utah County, Utah Inspection Conducted: May 4-5, 1987 Inspector: s f!28/#7 H. D. Chaney, Radiation Spec (alist, Facilities
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Dat'e Radiological Protection Section-Approved: hk/ &lMOU S. Murray, Chief. Facilities Radiological
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Protection Section Inspection Summary Inspection Conducted May-4-5, 1987 (Report 50-262/87-02)
Areas Inspected: Routine, announced inspection of the licensee's defueling of the L-77 reactor and packaging and shipment of the fuel. The inspection-involved reactor maintenance, radiation protection, and transportation of radioactive material Results: Within the areas inspected, no violations or deviations were identifie '06030006 870029 '"
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-2-DETAILS I Persons Contacted Licensee
- R. Hansen, Director, BYU Campus Safety
- L. Jensen, Senior Reactor Operator
- R. Dixon, Senior Reactor Operator (Retired)
- F. W. Nelson, BYU Radiation Safety Officer
- R. W. Kelshaw, Chief of BYU Police Department R. E. Sundquist, Supervisor, BYU Receiving Stores S. Hatch, BYU Receiving Stores D. Evans, Patrol Sergeant, BYU Police Department Others
- Olson, Westinghouse Idaho Nuclear Company C. R. Hillman, NRC material Transfer Licensing Branch J. A. F. Kelly, Senior Security Specialist, NRC Region IV
- Indicates those present at the exit intervie . Background Information The BYU L-77 (Atomic International) reactor has not been operated since May 11, 198 NRC Inspection Reports 50-262/84-01 and 50-262/87-01 l
discuss the licensee's decision to decommission the reactor. Since the 1984 inspection, the licensee has obtained NRC approval to ship the used l reactor fuel to a Department of Energy (00E) facility. Reactor operator licenses, covering fuel unloading and reactor maintenance, were issued to the two senior reactor operators in May 1985. The licensee has received authority from DOE to ship the fuel to the DOE fuel processing facility in l Idaho Falls, Idaho. The licensee developed detailed procedures and J checklists for: (1) drcining the fuel (approximately 30 liters of less
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than 20 percent enriched uranyl sulfate) from the reactor core, and (2) handling several spare fuel containers (less than 1 liter total) that were stored in the Nuclear Laboratory. The licensee constructed a vacuum operated drain-down system and performed walkthrough training of the procedures with a mock core and the spent fuel containers. The licensee performed the defueling on May 4, 1987, without incident, including flushing of the cor The uranyl sulfate containers were packaged in NRC certified shipping containers. On May 5, 1987, the material was shipped via common carrier to the DOE facility in Idaho in accordance with the requirements of 10 CFR Parts 71, 73, and 49 CFR Part 173.401 through 47 The shipment was received intact at the DOE facility on May 6, 198 .
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-3- Follow-up on Previous Inspection Findings (Closed) Violation 262/8701-03: Failure to Properly Secure Nuclear Laboratory Door - This violation was discussed in NRC Inspection Report 50-262/87-01 and involved the failure to properly secure the inner door to the Nuclear Laboratory. The NRC inspector verified that the -
licensee had taken action to ensure that, when the inner door was not fully closed, the burglar alarm would sound. This item is considered close . Program Areas Inspected The following program areas were inspecte The inspection included interviews with cognizant individuals, observation of activities, independent measurements, and' record reviews. The depth and scope of these activities were consistent with past findings and with the current status of the facilit Except as noted, the inspection revealed no. violations, deviations, deficiencies, unresolved items, or open items. Notations after a specific inspection item identify the following: I = item not inspected or only-partially inspected, V = violation, D = deviation, H = deficiency, U =
unresolved item, and 0 = open ite Procedure Inspection Requirements 40750 Class II Research and Test Reactors Operations Procedure 02.01 - Initial Interview 02.02 - Initial Walkthrough or Site Tour 02.03 - Records Review 02.04 - Observations
~85102 Material Control and Accounting - Reactors 02.01 - Possession and Use of SNM (Special Nuclear Material)
02.02 - Control and Accounting of SNM 86740 Inspection of Transportation Activities 02.01 - Management Controls 02.02 - Indoctrination and Training Programs 02.03 - Audit Program - I 02.04 - Quality Assurance Program 02.05 - Procurement and Selection of Packagings 02.06 - Preparation of Packages for Shipment 02.07 - Delivery of Completed Packages to Carriers 02.08 - Receipt of Packages 02.09 - Periodic Maintenance of Packagings - NA 02.10 - Records and Reports i
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-4-7. Exit' Interview The NRC inspector met with the licensee representatives denoted in paragraph 1 on May 5, .1987, and sumarized the scope and findings of the inspection as presented in this report.
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