ML082560800

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University of Florida, Request for Additional Information, License Renewal for the University of Florida Training Reactor
ML082560800
Person / Time
Site: 05000083
Issue date: 09/22/2008
From: Robert Kuntz
Research and Test Reactors Licensing Branch
To: Vernetson W
Univ of Florida
KUNTZ R, NRR/DPR/PRTA 415-3733
References
TAC MB5804
Download: ML082560800 (6)


Text

September 22, 2008 Dr. William G. Vernetson Director of Nuclear Facilities University of Florida Department of Nuclear and Radiological Engineering 202 Nuclear Sciences Center P.O. Box 118300 Gainesville, FL 32611-8300

SUBJECT:

UNIVERSITY OF FLORIDACREQUEST FOR ADDITIONAL INFORMATION RE:

LICENSE RENEWAL FOR THE UNIVERSITY OF FLORIDA TRAINING REACTOR (TAC NO. MB 5804)

Dear Dr. Vernetson:

We are continuing our review of your request for renewal of Amended Facility License No.

R-130 for the University of Florida Training Reactor that you submitted on July 29, 2002. During our review of your request, questions have arisen for which we require additional information and clarification. Please provide a response to the enclosed request no later than November 14, 2008. 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 renewal request.

If you have any questions regarding this review, please contact me at (301) 415-3733.

Sincerely,

/RA/

Robert F. Kuntz, Project Manager Research and Test Reactors Branch A Division of Policy & Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-83

Enclosure:

As stated cc w/enclosure: See next page

University of Florida Docket No. 50-83 cc:

Dr. Alireza Haghighat, Chairman Nuclear & Radiological Engineering Department University of Florida 202 Nuclear Sciences Center P.O. Box 118300 Gainesville, FL 32601-8300 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, FL 32301 State Planning and Development Clearinghouse Office of Planning and Budgeting Executive Office of the Governor The Capitol Building Tallahassee, FL 32301 William Passetti, Chief Department of Health Bureau of Radiation Control 4052 Bald Cypress Way, Bin #C21 Tallahassee, FL 32399-1741 William G. Vernetson, Ph.D.

Director of Nuclear Facilities University of Florida 202 NSC/PO Box 118300 Gainesville, FL 32611-8300

September 22, 2008 Dr. William G. Vernetson Director of Nuclear Facilities University of Florida Department of Nuclear and Radiological Engineering 202 Nuclear Sciences Center P.O. Box 118300 Gainesville, FL 32611-8300

SUBJECT:

UNIVERSITY OF FLORIDACREQUEST FOR ADDITIONAL INFORMATION RE:

LICENSE RENEWAL FOR THE UNIVERSITY OF FLORIDA TRAINING REACTOR (TAC NO. MB 5804)

Dear Dr. Vernetson:

We are continuing our review of your request for renewal of Amended Facility License No.

R-130 for the University of Florida Training Reactor that you submitted on July 29, 2002. During our review of your request, questions have arisen for which we require additional information and clarification. Please provide a response to the enclosed request no later than November 14, 2008. 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 renewal request.

If you have any questions regarding this review, please contact me at (301) 415-3733.

Sincerely,

/RA/

Robert F. Kuntz, Project Manager Research and Test Reactors Branch A Division of Policy & Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-83

Enclosure:

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

PUBLIC PRTA r/f AAdams EBarnhill RidsNrrDpr RidsNrrDprPrta RidsNrrDprPrtb GHill (2)

ADAMS ACCESSION NO.: ml082560800 TEMPLATE No.: NRR-088 OFFICE PRTA/PM PRTA/LA PRTA/SC NAME RKuntz rfk EBarnhill/eeb KBrock kb 9/22/08 DATE 09/15/08 09/16/08

REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF FLORIDA TRAINING REACTOR DOCKET NO. 50-83 By letter dated April 7, 2008, you provided a response to the NRCs request for additional information (RAI) dated April 6, 2005. The NRC staff has reviewed your response and has determined that further information is required. The following additional information is requested related to your response to question 5-2 related to Section 5.3, Secondary Coolant System.

1. Your letter dated April 7, 2008, states that the normal operating pressure for the secondary side is not monitored, but that secondary flow rate is about 4 times higher than the primary flow rate so the dynamic pressure of the secondary system is expected to be higher than the primary system pressure. Therefore, if a significant leak is developed on the primary/secondary boundary, the resistivity of the primary water is expected to change, which is constantly monitored and controlled. The technical specifications (TSs) limits on primary flow rate are greater than 36 gpm or 41 gpm depending on fuel coolant channel spacing tolerance, and the TSs limits on secondary flow rate are greater than 60 gpm when using a well system and 8 gpm when using city water.

Is the assumption that a significant leak would be detected in the primary water resistivity valid if the reactor is operating at the TS limit of 36 gpm or 41 gpm primary flow rate (or normal primary flow rate if it is in excess of the allowed TS limit) and 60 gpm or 8 gpm secondary flow rate? In your response, address how the primary and secondary pressures are affected by the flow characteristics in the heat exchanger.

2. Your letter dated April 7, 2008, states that with conservative assumptions on sodium in the primary coolant system, irradiation time, neutron flux level, cross section, primary-to-secondary leakage and secondary diluting flow, the following values are determined for a 1 liter/hr undetected leak rate continuing for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with 1 ppm sodium assumed in the primary coolant system. Activation for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> yields ~54 mCi Na-24 in the primary coolant tank at a concentration of ~0.0895 Ci/mi before dilution by the secondary flow. For a 1 liter/hour leak rate undetected for an hour, the concentration assuming 140 gpm well water flow (minimum based on well water flow without flow warning light), the concentration becomes ~2.8E-06 Ci/ml. Public release is allowed at 5E-3 Ci/ml so we conclude that this unlikely event would not be a problem in this regard.
a. What is the basis for the assumptions of 1 ppm sodium in the primary coolant, activation for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, and 1 liter/hour leak rate for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />?
b. How is the public release limit (5E-3 Ci/ml) derived? Appendix B to 10 CFR Part 20, Table 2, Column 2, lists an average yearly concentration release limit of 5E-5 Ci/ml for water effluents, and Table 3 list a monthly average concentration release limit to sewers as 5E-4 Ci/ml.

ENCLOSURE

c. As discussed previously, the TS limit on secondary flow rate is 60 gpm when using well water and 8 gpm using city water. Therefore, provide an estimated effluent concentration assuming the allowed TS limits for secondary flow.
d. What is the basis for your conclusion that a primary to secondary leak is unlikely?