ML20140H773

Forwards RAI Re Application for NRC OL for Mcclellan Nuclear Radiation Ctr Triga Reactor.Responses Requested to Be Provided within 30 Days of Date of Ltr

ML20140H773
Person / Time
Site:	University of California-Davis
Issue date:	05/07/1997
From:	Eresian W NRC (Affiliation Not Assigned)
To:	Tattini E AIR FORCE, DEPT. OF
References
TAC-M96343, NUDOCS 9705130272
Download: ML20140H773 (4)

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May 7, 1997 Major General Eugene L. Tattini, Commander Sacramento Air Logistics Center SM-ALC/TI-1 5335 Price Avenue McClellan AFB, California 95652-2504

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M96343)

Dear General Tattini:

We are continuing our review of your application for an NRC operating -license for the McClellan Nuclear Radiation Center TRIGA reactor. During our review, 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. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of.your application.

If you have any questions regarding this review, please contact Warren J. Eresian at (301) 415-1833.

1 b-Warren J. Eresian, Reactor Engineer

, 7 0n-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Docket No. 50-607

Enclosure:

As stated cc w/ enclosure: See next page k/

DISTRIBUTION:_

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%,,,,,# May 7, 1997 Major General Eugene L. Tattini, Commander Sacramento Air Logistics Center SM-ALC/TI-1 5335 Price Avenue i McClellan AFB, California 95652-2504

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (TAC N0. M96343)

Dear General Tattini:

We are continuing our review of your application for an NRC operating license for the McClellan Nuclear Radiation Center TRIGA reactor. During our review, questions have arisen for khich 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. In accordance with 10 CFR 50.30(b), your response must be executed in a signed original under oath or affirmation. Following receipt of the additional information, we will continue our evaluation of your application.

If you have any questions regarding this review, please contact Warren J. Eresian at (301) 415-1833.

Sincerely,

_ M4l%

Warren J. E sian, Reactor Engineer Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management l Office of Nuclear Reactor Regulation l Docket No. 50-607

Enclosure:

As stated cc w/ enclosure: See next page

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McClellan AFB TRIGA REACTOR Docket No. 50-607 cc:

Dr. Wade J. Richards SM-ALC/TI-l 5335 Price' Avenue, Bldg. 258 McClellan AFB, California 95652-2504 Lt. Col. Marcia Thornton HQ AFSC/ SEW 9570 Avenue G., Bldg. 24499 Kirtland AFB, New Mexico 87117-5670 Col. Robert Capell HQ AFMC/SGC . .

> 4225 Logistics Avenue, Suite 23 Wright-Patterson AFB, Ohio 45433-5762 1

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l ENCIDSURE REQUEST FOR ADDITIONAL INFORMATION MCCLELLAN AFB NUCLEAR RADIATION CENTER DOCKET NO. 50-607

1. (SAR, page 4-14): Since control rod speed is important to the control of power during " steady-state" operation and is important with regard to a reactivity insertion accident, please provide a detailed description of how you determine the rod drive speed to be used. In addition, please provide a description of the procedures that must be followed if you decide to increase control rod drive speed to faster than 24 inches per i minute.

2. (SAR, page 9-1): Please provide the seismic design parameters for the i "in-tank" fuel storage racks. Specifically, are they designed to retain stored fuel elements in the event of your design seismic event.

3. (SAR, page 9-8): Please provide the basis for your statement that the

" heat generation" in fuel stored in the fuel storage pits will be increased by a factor of 2, given that the power is increa:2d by a factor i

of 10 (200KW to 2 MW).

4. (SAR, page 9'-13): Please provide an analysis to show that your fuel )

element transfer cask will withstand an accidental drop of approximately '

30 feet. (Preparation room access to the top of a shipping cask.) An alternate approach would be to provide your calculations to show that offsite doses from a fuel element transfer cask drop would be less than  ;

those calculated for your " Maximum Hypothetical Accident."

5. (SAR, page 11-14): Please provide a new Figure 11.1 that also defines the boundaries for the core, tank wall, and outer surface of the biological shield.

6. (SAR, pages 13-8, 9): Please provide your calculation of the

" Uncontrolled Withdrawal of a Control Rod" using the proposed Technical Specification limits for:

a. maximum withdrawal speed;  ;

b. maximum rod worth;

c. high power scram point; J

d. 0.5 second (or more realistic value) from scram signal to actual rod '

release; and

e. rod fall time of 2 seconds.  :

Of particular interest will be the value of the " maximum positive reactivity insertion." (Is this at any time greater than $2.12?)

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