IR 05000262/1989001
| ML20248F238 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 04/05/1989 |
| From: | Baer R, Chaney H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20248F234 | List: |
| References | |
| 50-262-89-01, 50-262-89-1, NUDOCS 8904120532 | |
| Download: ML20248F238 (3) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Repo'rt:
50-262/89-01 License:
R-109 Docket:
50-262 Licensee:
Brigham Young University (BYU)
'Provo,. Utah 84602 Facility Name: Nuclear Laboratory (NL) - Model L-77 Reactor (Defueled)
-Inspection At: BYU, Provo, Utah County, Utah Inspection Conducted: March 2-3, 1989 Inspector:
Eh t
'4 s-H. D. Clahey, Senior Radiation Specialist Da e Facilities Radiological Protection Section 4/ 8S I
Approved:
R. Baer, thief, Facilities Radiological Date Protection Section Inspection Summary Inspection Conducted March 2-3, 1989 (Report 50-262/89-01)
Areas Inspected:
Routine, unannounced inspection of the licensee's reactor operations, radiation protection, and physical security programs.
Results: The reactor has been maintained in a secured condition.
Radiological surveillance of the facility have been performed on a routine basis. Within the areas inspected no violations or deviations were identified.
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8904120532 890405 PDR ADOCK 05000262 PDC L__ __
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l DETAILS 1.
-Persons Contacted.
Licensee.
- W. R. Hansen, Director,'BYU Campus Safety
- *E. F. Jackson, BYU Radiation Safety Officer. (RS0)-
G.~ L. Jensen, Senior Reactor Operator
~* Indicates'those present at the exit interview on March 3, 1989.
2.
Background The BYU Nuclear. Laboratory L-77 reactor.has not been operated since May 11,:1982. On May'22, 1987, the licensee submitted to the NRC a request for conversion of the Facility Operating License to a " Possession Only" lice'nse.
The licensee's request is still under.NRC Headquarter's review.
The 0.5 curie plutonium-beryllium neutron sealed source has been left installed / secured in the reactor vessel.
3.
. Reactor Operations (40750)
a.
Operations
.The licensee's logs and records were reviewed to determine compliance with the. requirements of the Facility Operating Li. cense and Appendix A to the license Technical Specifications (TS).
Currently, the reactor satisfies the TS A.1 definition of " Reactor Secured." No surveillance or equipment operation have been performed other than routine visual inspection of shield water height, and structural examination of the reactor vessel.
No violations or deviations were identified.
b.
Staffing and Qualification Only one person is-licensed by the NRC for the reactor facility and this license does not allow reactor operation. The RSO maintains radiological surveillance over the reactor facility.
No violations or deviations were identified.
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c.
Surveillance No surveillance are required by the TS.
The licensee has j
agreed to disconnect the power to the reactor console.
This will be
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accomplished by March 23, 1989.
No violations or deviations were identified.
d.
Health Physics The licensee has been performing semiannual radiation and contamination surveys, area '(environmental) dosimetry replacement, and analysis of reactor vessel shield water. These surveys satisfy the conditions of the license and Section II.D of the TS.
The NRC inspector obtained a sample of the reactor shield water for NRC
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Region IV confirmatory measurement purposes. The licensee also agreed to split any future reactor facility samples with the NRC for l
confirmatory measurement.
No violations or deviations were identified.
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Physical Security
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The licensee's physical security program was reviewed to determine compliance with the requirements of 10 CFR Parts 50.54(p) and 73.00, and the NRC approved security plan dated October 7, 1974. The licensee's last review of the security plan was March 4, 1987.
The licensee routinely verifies the operability of the intrusion alarm system for the nuclear facility.
No violations or deviations were identified.
5.
Exit Interview The NRC inspector met with licensee representatives identified in paragraph 1 at the conclusion of the inspection on March 3, 1989. The NRC inspector summarized the scope and findings of the inspection.
The NRC also requested the licensee to split all samples with NRC that are taken to evaluate reactor facility component activation or contamination.
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