IR 05000020/1993001
| ML20034F580 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 02/24/1993 |
| From: | Albert R, Keimig R, Galen Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20034F577 | List: |
| References | |
| 50-020-93-01, 50-20-93-1, NUDOCS 9303040023 | |
| Download: ML20034F580 (3) | |
Text
.
U.S. NUCLEAR REGULATORY COMMISSION.
REGION I
Report No.: 50-20/93-01 Docket No.: 50-20 License No.: E-32 Licensee:
Massachusetts Institute of Technolony 138 Albany Street Cambridee. Massachusetts 02135 Facility Name:
MIT Research Center k
Inspection Conducted:
Februtry 7 and 8.1993 Inspectors:
^d 2!AY!93-G. C. Smith, Senior Security Specialist
/ _ Dite
!
-
f
,,7,2 4 73
jR. J. Albert, SeTc ns Date Approved By:
-
J-J '/ 81 J[R. Keimig, ChieTSafe (I'ds Section Date
/ Division of Radiation Saf and Safeguards A_reas Inspected: Examination of conformance to the general requirements for shipments of irradiated fuel at the point of origin and in-transit.
Results: The licensee was in compliance with NRC requirements in the areas examined.
No safety concems or violations were identified.
.
9303040023 930226 PDR ADOCK 05000020 G
PDR J
f
..,
DETAILS 1.0 Kev Personnel Contacted J. Bernard, Director, Reactor Operations, Massachusetts Institute of Technology (MIT).
E. Lau, Assistant Superintendent for Reactor Operations, MIT T. Newton, Assistant Superintendent for Reactor Engicering, MIT E. Block, Mechanical Maintenance Supervisor, MIT F. McWilliams, MIT Radiation Protection OfDeer M. Austin, Assistant MIT Radiation Protection Officer J. Cappucci, Lt. MIT Police B. Haven, Officer MIT Police D. O'Connel, City of Cambridge Emergency Management Department
,
J. Galles, Driver / Escort, Tri-State Motor Transport Company
'
G. Ragain, Driver / Escort, Tri-State Motor Transport Company 2.0 Backcround Region I was notified by the licensee in a letter dated January 26,1993, that.a shipment.
of irradiated reactor fuel would be made over land from the MIT Research Reactor,
,
!
Cambridge, Massachusetts, to the U.S. Department of Energy (DOE), Savannah River Plant, Aiken, South Carolina. The route for this shipment was approved by the NRC
on January 8,1993. The inspection was conducted to ensure conformance to the NRC's
general requirements for shipments of irradiated _ reactor fuel.
3.0 Iransportation of Irradiated Reactor Fuel (General Recutrementsl During the inspection on February 7 and 8,1993, the inspectors determined, as described below, that the licensee followed established procedures and NRC regulatory requirements for the physical protection of the irradiated reactor fuel shipment.
- a.
The inspectors determined that there were two driver / escorts with the transport vehicle. The inspector verified that these two driver / escorts and the transport
-
vehicle were qualified for the transport ofirradiated reactor fuel. Interviews were conducted with the two driver / escorts relative to their training, knowledge of procedures and contingency preparedness. No deficiencies were noted, b.
The inspectors examined the tamper seals on the shipping cask and found that all seals were intact.
c.
The inspector observed that the transport vehicle was equipped with the required communications equipment. The inspectors also reviewed the trip plan log and discussed the frequency of the required calls to the dispatcher with the driver / escorts.- There was some confusion as to whether the NRC's 2-hour -
.
call-in requirement'or DOE's 4-hour call-in requirement to the dispatcher was-applicable. The licensee determined, and the inspectors concurred, that the
a
3
'
NRC's requirement was applicable. The driver / escorts adjusted the trip plan to reflect this requirement and scheduled calls to the transport company's dispatcher every two hours.
d.
The inspectors also verified through interviews of the driver / escorts and by-observation that the transport vehicle was equipped with an immobilization device that was approved by the NRC and that the driver / escorts were familiar with its operation.
e.
The inspectors verified through direct measurements that radiation readings on and around the shipment cask were within NRC regulatory limits. He inspectors also reviewed the licensee's radiation survey reports for the cask and transport vehicle and found them to be complete with all readings within regulatory limits.
f.
The inspectors reviewed the shipping papers for completeness and found them to be in order. Shipping papers reviewed included the Bill of Lading, the Boston Permit for Transportation of Hazardous Materials and the NRC Form-741, Nuclear Material Transaction Report.
g.
The inspectors observed that both the transport vehicle end the trailer were equipped with " Radioactive * placards on both sides, front and rear of the trailer, as required.
.
h.
The inspectors observed that there were two Radioactive Yellow III labels affixed i
to the shipment cask, as required.
i.
The inspectors reviewed a draft press release that had been prepared by the licensee for the shipment. After the inspectors' review, the licensee deleted portions of the press release that contained sensitive unclassified information (Safeguards Information).
4.0 Exit Meetine The inspectors discussed the results of the inspection with the Director of Reactor Operations on February 8,1993 and by telephone on February 11,1993.
!
.