ML19338F334
| ML19338F334 | |
| Person / Time | |
|---|---|
| Site: | University of Illinois, 05000356 |
| Issue date: | 09/29/1980 |
| From: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Miley G ILLINOIS, UNIV. OF, URBANA, IL |
| Shared Package | |
| ML19338F335 | List: |
| References | |
| NUDOCS 8010200099 | |
| Download: ML19338F334 (1) | |
See also: IR 05000151/1980002
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. UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 111
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799 ROOSEVELT ROAD
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GLEN ELLYN, ILLINOIS 60137 -
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SEP 2 0 10nD
Docket No. 50-151
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Docket'No. 50-356'
University of-Ill'inois-
ATTN: Dr. George ".. Miley
. Chairman
Nuclear Engineering
~ Executive Committee
' 216 Nuclear Engineering; Laboratory-
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Urbana, IL 61801
Gentlemen:
Thank you for your letter dated September 9, 1980, informing us of the
steps you have .taken to correct the noncompliance identified in our letter
dated September 2, 1980'
We will examine your corrective action during
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a future inspection.
~In your response you stated that an error was noted under Item 15 of our
report. We acknowledge this error and it'has been corrected. -Enclo' sed is
a corrected copy of Page 7 of:our Reports No. 50-151/80-02 and 50-356/80-02
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which incorporates the change.
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Your cooperation with us is appreciated.
Sincerely,
- LW
A. B. Davis,_ Chief
' Fuel Facility and
Materials Safety-Branch
cc w/ltr'.dt'd'9/9/80:
Central Files
Reproduction Unit NRC 20b
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waste'has been generated since August 1979. A review of the
licensee's response.to IE Bulletin 79-19 was performed during an
inspection;of the' University broad license in March.1980.
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14. Transfer- of Radioactive Material
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Thellicensee has not submitted a quality assurance program (10 CFR 71.51), because they have not shipped fuel and are not planning to
ship fuel in the near future. The inspector informed.the licensee
that before;any shipment of spent fuel they must submit ,a QA plan.in
accordance'with 10 CFR 71.51.
The inspector reviewed the licensee's records of transfer of licensed
material from September 1979 to date. Material is transferred to
' both'on and off campus users. During the first'six months of 1980
severa1Lshipments of irradiated Type A quantities of normal form
rad.'oactive materials were transferred to Argonne National Laboratory
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(ANL) in an ANL' shipping container. Although the licensee maintains
shipping papers on each shipment they do not maintain.a complete
certification and safety analyses demonstrating that the container-
meets' specification 7A. This is'in noncompliance with 49 CFR
173.395 (a)(1) .
No shipment of. spent fuel reactor fuel has been made since the last
inspection in August 1979.
IS.
Independent Measurements
Gamma and neutron su'rveys were made by the inspector and reactor
health ~ physicist in the reactor facility.on August 20, 1980, while
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the reactor' was: operating at 500 kilowntts.. The highest radiation.fleids
' found were 8 mrems/ hour neutron and 5' mR/hr gamma at the face of the
north beam port. All other areas were less than 3 mrems/ hour, neutron
and gamma combined.
16. Exit Interview
The$hspectormetwith-licenseerepresentatives-(denotedinParagraph
1) at the conclusioh of the' inspection on August 20, 1980.
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The~following matters were. discussed.
a.
. The purpose and scope of the inspection.
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{b.
.The item of noncomp1'iance '(Paragraph 14).
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