ML20155G692

Forwards Request for Addl Info in Order to Continue Evaluation of 860912 Application for Amend to License R-103, Authorizing Use of Extended Life Aluminide Fuel in Reactor

ML20155G692
Person / Time
Site:	University of Missouri-Columbia
Issue date:	06/10/1988
From:	Alexander Adams Office of Nuclear Reactor Regulation
To:	Brugger R MISSOURI, UNIV. OF, COLUMBIA, MO
References
NUDOCS 8806200058
Download: ML20155G692 (5)

Text

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June 10,1988 ,

Docket No. 50-186 j I

Dr. Robert fl. Brugger, Director  !

Research Reactor Facility  ;

University of Missouri Columbia, Missouri 65211

SUBJECT:

NRC REVICW 0F EXTENDED LIFE ALVMINIDE FUEL (ELAF) AMENDMENT APPLICATION We are continuing our review of your application to Facility License No. 9-103 for permission to use ELAF in your reactor. The application was submitted by letter dated September 12, 1986, as supplemented. During our review of the information you had submitted, 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 request. 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.95-511.

Sincerely.

Originni signed By:

Alexander Adams, Jr. Project Manager l Standardization and Non-Power Reactor Project Directorate l Division of Reactor Projects III, ,

IV, V and Special Projects l Office of Nuclear Reactor Regulation i

Enclosure I As stated  !

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• June 10, 1988 Docket No. 50-186 i

Dr. Robert M. Brugger, Director Research Reactor Facility University of Missouri Columbia, Missouri 65211

SUBJECT:

NRC REVIEW OF EXTENDED LIFE ALUMINIDE FUEL (ELAF) AMENDMENT APPLICATION We are continuing our review of your applic.: ion to Facility License No. R-103 for permission to use ELAF in your reactor. The application was submitted by letter dated September 12, 1986, as supplemented. During our review of the information you had submitted, 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 request. 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, OfiB clearance is not required under P.L.95-511.

Sincerely, 00 ,

Alexander Adams, Jr. Pri et Manager Standardization and Non- ower l Reactor Project Directorate i Division of Reactor Projects III, IV, Y and Specia) Projects Office of Nuclear Reactor Regulation i

Enclosure As stated cc: See next page I

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University of Missouri Docket No. 50-186 at Columbia cc: University of Missouri Associate Director Research Reactor Facility Columbia, Missouri 65201 A-95 Coordinator Division of Planning Office of Administration P. O. Box 809, State Capitol B'ldg.

Jefferson City, Missouri 65101 l

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• Docket No. 50-186 REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF MISSOURI - COLUMBIA The MURR submittal of March 11, 1988 has been reviewed and the following concerns have been identified where additional information is required to assess the technical basis. The areas are:

(1) In Table 4.1 on enthalpy rise, safety limits basis, an overall product of 8.81 is reported. This appears to be a typographical '

error. Please address.

(2) In the last sentence of page 16, the sentence reads, "...by changing the maximum acceptable DNBR:. This appears to be a typographical error. Please address. It is suggested that the corresponding COBRA DNBR be given for the new fuel design. Table 4.2 indicates that COBRA is predicting approximately a 6 percent greater margin than the BOLERO safety limits. Will the COBRA minimum DNBR reflect this difference?

(3) The responses by MURR of September 11, 1987 and March 11.,1988 address the response to a reactivity perturbation with increased oxide. These discussions indicate that more severe results are obtained with a particular inlet temperature, two PARET/ANL channels, original PARET CHF code, and the Bergles and Rohsenon correlation for the onset of nucleate boiling and transition to fully developed nucleate boiling. -

To aid in the evaluation o' ',he new fuel acceptability for 10 MW operation, it is requested that sensitivities be reported for the following variables:

l (a) CHF correlation l (b) Onset of nucleate boiling correlation 1

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i' (c) Inlet temperature (d) Coolant flow velocity (benchmarking reported for PARET/ANL is for natural convection flow)

(e) Modeling of new fuel with hot plate (4) as channel 1, and remainder as channel 2.

(f) Moderator direct heating percent.

(4) It is requested that the deviation of the PARET/ANL feedback input for channel 7 and channel 2 be submitted as a part of the request for approval. The void feedback is strongly dependent on fuel element coolant channel position and the PARET results are derived only with 6 k/% void.

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