ML20058H807

Forwards Request for Addl Info Re 891109 Application for Authorization to Convert to Low Enriched U

ML20058H807
Person / Time
Site:	University of Virginia
Issue date:	11/15/1990
From:	Mendonca M Office of Nuclear Reactor Regulation
To:	Mulder R VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
References
NUDOCS 9011260050
Download: ML20058H807 (5)

Text

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- November 15, 1990 4

Docket No. 50 62' Dr. R. U. Mulder, Director UVA Reactor Facility

, Department of Engineering and Engineering Physics University of Virginic Charlottesville, Virginia 22901

Dear Dr. Mulder:

i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION

~We are continuing our review of your application of November 9, 1989 for Lauthorization-to convert to low enriched uranium. During our evaluation of lyour: application, questions have arisen for which we require additional

~information and clarification. Please provide response to the enclosed request for additional information within 60 days of the date of this letter.

Following-receipt of the additional information we will centinue our evaluation of your application. If you have any questions regarding this review, please contact me at (301) 492 1128.

The reporting and/or. record keeping requirements contained in this letter affect fewer than ten respondents; therefore, Office of Management and Budget-clearance is not required under Public Law 96 51).

Sincerely, Original signed by:

• Marvin M. Mendonca, Senior Project Manager Hon Power Reactor, Decommissioning and v Environmental' Project Directorate

. Division of Reactor Projects .=III, IV, Y and Special-Projects Office of Nuclear. Reactor Regulation L

Enclosure:

Request; for Additional Information

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' "% , , , , , # - November 15, 1990 Docket No. 50-62 1

, Dr. R. U. Mulder Director UVAReactorFacility Department of Engineering and Engineering Physics

University of Virginia

' Charlottesville,. Virginia 22901

SUBJECT:

REQUEST FOR ADDITIONAL INFG % Tich We are continuing our review of your application of November 9,1989 for authorization to convert to low enriched uranium. During our evaluation of l your application, questions have arisen for which we require additional '

information ard clarification. Please provide response to the enclosed request for additicnal inforation within 60 days of the date of this letter.

'Followingreceht~oftheadditionalinformationwewillcontinueour-evaluation of your applicaticn, If you have any questions regarding this  :

review, please contact me at (301) 492-1128.

The reporting and/or record keeping're

' fewer than ten respondents; therefore,quirements contained Office of Management and Budget in this letter affect l clearance is not required under Public Law 96-511. l 4

Sincerely,

%m  % cdu u 1

l .Marvin M hdonca, Senior Project lianager '

Non-Power Reactor, Deconnissioningiand  ;

Environraental Project Directorate j Division of Peactor Projects - III, '

7 IV,.V~and Special Projects a Office of Nuclear Reactor Regulation i

Enclosure:

Request; for- Additional Information

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cc w/ enclosure:

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t University of Virginia Docket Nos. 50-62/396 CC:

Commonwealth of Virginia Council on the Environment 903 Ninth Street Office Bldg.

Richmond, Virginia 23219 s Mr. Preston Farrar-Nucinar Reactor Facility _ '

University of Virginia School of Engineering and Applied Science Charlottesville, Virginia = 22901 Dr. Paul E. Allaire, Chairman Department of Nuclear, Engineering and Engineering Physice <

University of. Virginia-l Charlottesville, Virginia -22901 l Dr. William Vernetson Director of Nuclear Facilities Department.of Nuclear Engineering-Sciences University of Florida

- 202: Nuclear-Sciences Center l Gainesville,. Florida 32611 ,

m Dr. Ratib A.:Karam, Director Neely Nuclear Research. Center Georgia Institute of Technology _

900 Atlantic Drive, NW Atlanta . Georgia .30332-Mr. Garry'D. Miller,-Associate Director Nuclear Reactor Program North Carolina State University P. O. Box 7909 Raleigh, North Carolina 27695-7909 Office.of the Attorney General 7 101 North 8th Street

Richmond, Virginia 23219-Bureau of: Radiological Health Division of Health Hazards Control

' 109 Governor Street, Room 916-  !

Richmond, Virginia 23219 4

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l:EQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF VIRGINIA DOCKET H0. 50-62 ,

'!. We understand from discussions with your staff.that because of the timing of issuance, your application did not reference or utilize NUREG-1313 for the acceptability of the Low Enriched Uranium (LEU) silicide-aluminum dispersion fuel. Provide rationale for the' technical acceptability of your LEU fuel. You may utilize and reference the evaluations in NVREG-1313 provided that you assess and show applicability to your reactor and it's operating conditions. ,

2. Provide a' description of yt initial core loading plans and testing program to assure that core grameters are consistent with your safety analysis assumptions and Technical Specificttien requirements. Include ,-

considerations for reactor coolant flow rate worth of each control rod, '

i power distribution, shutdown margin, and excess reactivity. Also, include acceptance criteria for parameters and actions to be taken when not met.  !

L Compare the planned initial LEU core with the HEU core it will replace.

3. There appear to be several inconsistencies in your epplication:

'~.- a.. Safety Analysis Report (SAR) Page 3-17 Table 3.1 - Number of plates '

per element, and U-235 centent per element appear to be incorrect.

b4 SAR Page 3-10 and Table 3.1 differ for' control rod worths in units and in value from those in reference 9 pages 8 and 27; c.. SAR Page 3-12 and the Technical Specification 3.1 (1) for shutdown margin differ in units and value;

d. SAR Page 3-23, first paragraph, last three 11nes seem to be snonsequitur, e

4 In reference to SAR. page 3-21, Section 3.10, Nuclear Regulatory Comisiion (NRC) Safety Evaluttion Reports (SERs) for specific facilities are not generally or directly applicable to support statements and conclusions for -

'other facilities.- Therefore,-provide your independent assessment r.f fission product inventory (including. plutonium) for the LEU fuel and demor. strate 7 direct applicability to any referenced document. Include-consideration of power level and distribution, fue1' configuration and composition, fuel <

rotation plans, and.othat relevant factors.

5. The proposed Technical Specifications have a safety limit based on tempera-cture of fuel cladding. This is inconsistent with the current Terhnical Specifications, ANSI /ANS 15.1, and 10 CFR 50.36. These documents define and establish safety limits as process variables.

L c. - Therefore, provide safety limits consistent with these documents, that -

l is, proctas variables, such as, rt actor coolant flow rate, reactor 1 thermal power level, poc1 water level and reactor coolant inlet temperature.

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b. Also, provide similar safety limits for the natural circulation mode of operation.

6. Implicit in the analysis of the short period transient in SAR Section 9.12 l e for the HEU core is that the maximum accidental reactivity addition will

-result in a reactor period of about three seconds. Is this valid for the l l

LEU core? Provide justification and analyses for this assessment. l

7. In order to avoid confusion, the Technical Specification changes not  !

related to the LEU conversion should be renoved from this application, q

, and if desired submitted separately. l l

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