ML20011E851

Forwards Request for Addl Info Re 881116 Application to Convert Licensee Reactor to Low Enriched Fuel in Accordance w/10CFR50.64

ML20011E851
Person / Time
Site:	University of Missouri-Rolla
Issue date:	02/08/1990
From:	Alexander Adams Office of Nuclear Reactor Regulation
To:	Bolon A MISSOURI, UNIV. OF, ROLLA, MO
References
NUDOCS 9002220597
Download: ML20011E851 (5)

Text

February 8, 1990

~

_, Docket No. 50-123 Dr. Albert E. Bolon, Director Nuclear Reactor Facility University of Missouri at Rolla Rolla, Missouri 65401-

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION We are continuing our review of your submittal of November 16, 1988 for conversion of the University of Missouri - Rolla Reactor to low enriched uranium (LEU) fuel in accordance with 10 CFR 50.64. During our review of your application for conversion, questions have arisen for which we require additional information and clarification. Please provide responses to the enclosed Request for Additional Information within 30 days of the date of this letter. Following receipt of the additional information we will continue our evaluation of your submittal.

If you have any questions regarding this review, please contact me at (301) 492-1121.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.

Sincerely, Original signed by:

Alexander Adams, Jr., Project Manager Non-Power. Reactor, Deconsnissioning and Environmental Project Directorate Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

See next page DISTRIBUTION aDocket J.1, lei NRC & Local PDRs PDNP r/f 2

WTravers I.

Qo EHylton ca-o AAdams Ofoi

- 88' OGC L

v8 EJordan 9

So ACRS(10) tw Plant file au

.[AA LTR2 ABolon]

oE

.t LA PDNP:P P

D AAdam:hj S"

SWeiss on 2//

/90 2/ @$7 2/q/90 m

.y-

1..

p:stg'o-UNITED STATES -

8

~g.

NUCLEAR REGULATORY COMMISSION o

. (

E.

WASHINGTON, D. C. 20666 k..... ;o February 8, 1990 Docket No. 50-123 Dr. Albert E. Bolon, Director Nuclear Reactor Facility 4

University of Missouri-at Rolla Rolla, Missouri 65401

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION We are continuing our review of your submittal of November 16, 1988 for conversion of the University of Missouri - Rolla Reactor to low enriched uranium (LEU) fuel in accordance with 10 CFR 50.64.- During our review of your application for conversion, questions have arisen for which.we require additional information and clarification.

Please provide responses to the

-enclosed Request for Additional-Information within 30 days of the date of this letter.

Following receipt of the additional information we will' continue our evaluation of your submittal.

If you have any questions regarding this review, please contact me at (301) 492-1121.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L 96-511.

(,

Sincerely,

/Aa4 %

Alexander Adams, Jr., P ject Manager Non-Power Reactor,- De issioning and z

Environmental Project Directorate Division of Reactor Projects.- III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

.See next page l

L

.q-*

5 REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY Of MISSOURI - ROLLA DOCKET NO. 50-123

)

J 1.

SAR, Sec. 3.2.5, page 3-19; Irradiation Fuel Element; Does the irradiation fuel element have fuel plates in position 11-187 i

2.

SAR, Sec. 3.4.7, page 3-28; Heat Removal; What is the " negligible" temperature drop across the fuel meat and the aluminum cladding?

3.

SAR, Sec. 9.3, page 9-4, penultimate sentence; Please explain what is meant by "---amount of heat stored in the fuel meat and cladding--."

4.

SAR, Sec. 9.6, page 9-13; the explicit mention of a fuel-handling accident presented in your SAR in 1984 is deemed appropriate and relevant.

Reinstating that discussion would provide a better basis for your accident analysis, and also for the discussion that follows on page 9-16.

5.

SAR, Sec. 9.7, page 9-23; you have arbitrarily selected an " exclusion zone" of 100 m, and also refer and compare to doses listed in 10 CFR Part 100. Neither of-these is applicable to licensed research reactors.

Please calculate the potential doses to a maximally exposed occupant in the unrestricted area associated with your reactor, and compare with 10 CFR Part 20. Theaccidentscenarios(failedfueledexperiment)are otherwise acceptable.

6.

Technical Specifications a.

Sec. 1.3 Definitions; it is NRC's position that the shutdown margin is to be defined "with the maximum worth scrammable roo and any non-scrammable control rod in their fully withdrawn positions."

l Please make that change, and also in Specification 3.1 (3), as necessary.

Verify and show that your proposed LEU core will meet that condition under any operating condition of your reactor, b.

Specification 2.1, and its bases; because of revisions made to your SAR, dated Oct. 31, 1988, some changes seem to be needed in these l.

sections.

I l

c.

Specification 5.1.2; this spec. says 17000 cubic meters, but your l

SAR says and uses 1700 cubic meters.

Please make them consistent.

d.

Specification 5.3.2; this section should be more specific about the material composition of the new U,Si fuel elements. Furthermore, you should acknowledge that NRC hMs $pproved a specific design of the fuel elements in NUREG 1313, and that it also your basis for l

using it.

I

c.

Specifications 15.3.4; your SAR includes analyso', hased on scrammable shim-safety rods, and a non-scrammable regulating rod. This specification should include those conditions.

f.

Specification 5.4.1; will the storage pit "be capable of storing the i

complete fuel inventory" in the event you have both your HEU and LEU fuel in-house simultaneously? Please explain how you will handle this or any other related event.

7.

Does conversion to LEU fuel affect your Physical Security Plan? Will the plan allow both the LEU and HEU core to be on site at the same time?

8.

Please provide a copy of the government certification that funds are available to convert the reactor.

9.

Please provide a proposed schedule for the conversion of the reactor.

10. Pleaseprovideproposedspecialnuclearmaterial(SNM)licenselimitsfor the LEU core, the HEU core, and other SNM on site after the HEU core is shipped off site.

11.

In spite of the paper work assurances, NRC ex)ects you to approach the initial loading of your new LEU fuel as thoug1 the conditions cf criticality are not known accurately. Please provide us with a plan for fuel loading, approach to criticality, loading to final excess criticality, control rod calibration, and power level determination.

..~

4'

, University' of Missouri Docket No. 50-123-

.at Rolla CC:

A-95 Coordinator Division of Planning Office of Administration P. 0. Box 809 State Capitol Building L

_ Jefferson City, Missouri 65101 Don L. Warner, Dean.

School of Mines & Metallurgy 305 McNutt Hall University of Missouri-Rolla Rolla, Missouri 65401 4

Reactor Manager Nuclear Reactor Facility University of Missouri-Rolla Rolla, Missouri 65401 4

I

.