ML101890829

University of Florida, RAI License Renewal

ML101890829
Person / Time
Site:	05000083
Issue date:	07/09/2010
From:	Alexander Adams Division of Policy and Rulemaking
To:	Hintenlang D E Univ of Florida
Hardesty, D NRC/NRR/DPR/PRLB 415-3724
References
TAC ME1586
Download: ML101890829 (6)

Text

July 9, 2010

David E. Hintenlang, Ph.D.

Interim Director of UFTR Nuclear & Radiological Engineering Department 202 Nuclear Sciences Building University of Florida Gainesville, FL 32611-8300

SUBJECT:

UNIVERSITY OF FLORIDA REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE RENEWAL FOR THE UNIVERSITY OF FLORIDA TRAINING REACTOR (TAC NO. ME1586)

Dear Dr. Hintenlang:

The U.S. Nuclear Regulatory Commission (NRC) is continuing our review of your request for renewal of Facility Oper ating License No. R-56 for the University of Florida Trai ning Reactor which you submitted on July 18, 2002, as supplemented. During our review of your renewal request, questions have arisen for which we require additional information and clarification.

Please provide responses to the enclosed request for additional information no later than July 30, 2010. In accordance with Title 10 of the Code of Federal Regulations Section 50.30(b), your response must be executed in a signed original under oath or affirmation. Please send the original copy of your correspondence to the NRC Document Control Desk with a copy to your Project Manager. Following receipt of the additional information, we will c ontinue our evaluation of your license renewal request.

If you have any questions regarding this review, please contact Duane Hardesty at (301) 415-3724 or by electronic mail at duane.hardesty@nrc.gov.

Sincerely,

/RA LTran for/

Alexander Adams Jr., Senior Project Manager Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-83

Enclosure:

As stated

cc: See next page University of Florida Docket No. 50-83

cc:

Administrator Department of Environmental Regulation Power Plant of 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 Bureau of Radiation Control Department of Health 4052 Bald Cypress Way Tallahassee, FL 32399-1741

Alireza Haghighat, PhD FPL Endowed Term Professor Nuclear & Radiological Engineering Department 202 Nuclear Sciences Building University of Florida Gainesville, FL 32611-8300 Edward Dugan Interim Reactor Manager University of Florida Nuclear & Radiological Engineering Department 202 Nuclear Sciences Center P.O. Box 118300 Gainesville, FL 32611-8300

Test, Research and Training Reactor Newsletter Nuclear & Radiological Engineering Department University of Florida 202 Nuclear Science Building Gainesville, FL 32611-8300

July 9, 2010

David E. Hintenlang, Ph.D.

Interim Director of UFTR Nuclear & Radiological Engineering Department 202 Nuclear Sciences Building University of Florida Gainesville, FL 32611-8300

SUBJECT:

UNIVERSITY OF FLORIDA REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE RENEWAL FOR THE UNIVERSITY OF FLORIDA TRAINING REACTOR (TAC NO. ME1586)

Dear Dr. Hintenlang:

The U.S. Nuclear Regulatory Commission (NRC) is continuing our review of your request for renewal of Facility Oper ating License No. R-56 for the University of Florida Trai ning Reactor which you submitted on July 18, 2002, as supplemented. During our review of your renewal request, questions have arisen for which we require additional information and clarification.

Please provide responses to the enclosed request for additional information no later than July 30, 2010. In accordance with Title 10 of the Code of Federal Regulations Section 50.30(b), your response must be executed in a signed original under oath or affirmation. Please send the original copy of your correspondence to the NRC Document Control Desk with a copy to your Project Manager. Following receipt of the additional information, we will c ontinue our evaluation of your license renewal request.

If you have any questions regarding this review, please contact Duane Hardesty at (301) 415-3724 or by electronic mail at duane.hardesty@nrc.gov.

Sincerely, /RA LTran for/

Alexander Adams Jr., Senior Project Manager Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-83

Enclosure:

As stated cc: See next page DISTRIBUTION

PUBLIC DPR/PRT r/f RidsNrrDpr RidsNrrDprPrta RidsNrrDprPrtb DHardesty, NRR AAdams, NRR GLappert, NRR ACCESSION NO.:ML101890829 NRR-088 OFFICE PRLB:PM PRPB:LA PRLB:PM PRLB:BC PRLB:PM NAME DHardesty dh GLappert gkl LTran for A Adams TMcGinty for JQuichocho LTran for A Adams DATE 7/9/2010 7/9/2010 7/9/10 7/9/10 7/9/10 Official Record Copy OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE RENEWAL FOR THE UNIVERSITY OF FLORIDA TRAINING REACTOR LICENSE NO. R-56 DOCKET NO. 50-83 The U.S. Nuclear Regulatory Commission (NRC) is continuing our review of your application for renewal of Facility Oper ating License No. R-56 for the University of Florida Trai ning Reactor (UFTR) that you submitted on July 18, 2002, as supplemented by letters dated July 25, July 29, and July 31, 2002, February 25, 2003, August 8, 2006, February 2, 2007, April 7 and November 26, 2008, September 28 and October 20, 2009, February 26, March 11, March 26, May 3, and June 1, 2010. During our review of your renewal request, questions have arisen for which we require additional information and clarification. Please provide responses to the following request for additional information no later than July 30, 2010.

The below questions pertain to the most recent "draft" technical specifications (TS) for the UFTR submitted by memo dated March 11, 2010. 1. Section 1.1 Scope. The 2nd paragraph appears to redefine "safety-related" in comparison to power reactors. This paragraph is unnecessary and has no affect as a scope statement since the definition for "safety-related" is contained in 10 CFR 50.2, which is applicable to the UFTR. Further, "Reactor Safety Systems" is already defined in section 1.2 of the UFTR TS.

Please remove this paragraph. 2. Section 1.2 Definitions: (a) Please provide a definition for core configuration [used in 3.8(4) of TS].

(b) Excess reactivity - states "-at reference core condition -or- at specified core conditions." Reference core condition is the specified core condition. Please remove

"-or at specified core conditions." (c) The definition for experiment makes reference to "within the pool." UFTR does not have a pool; please update this definition to be applicable for the UFTR. (d) In the definition for "License" - replace "responsible authority" with U.S. Nuclear Regulatory Commission. (e) Please add a definition for "safety blade" and "regulating blade" as referenced in the UFTR TS. 3. Section 2.2 Objective states "To ensure that automatic protective action is initiated before exceeding the safety limit." Protective action should be initiated to "terminate the abnormal situation before the safety limit reached." Please address.

4. Per the guidance provided in ANS/ANSI 15.1, please specify the number and type of "operable" control blades applicable to section 3.2.1, specification (3). 5. Section 3.2.1 Reactor Control System, Specification (4)(e) - please revaluate the appropriateness of the "greater than" sign in the statement ">30 sec." 6. Section 3.3 Coolant Systems, Specification (2) - contrast "monitored at return line" with LSSS >41gpm. Please describe how specification provides a positive indication of flow. 7. Section 3.52 - Reactor Vent System (a) Specification (5) uses the term "airlocks." Please provide clarification and, if applicable, add a definition to section 1.2 for airlocks. (b) Specification (6), please describe backup means for quantifying radioactivity in effluent. 8. Section 3.6.2 - Materials (a) Specification (1) refers to "Explosive materials." Please define or reference a definition such as in Regulatory Guide 2.2 Technical Specifications for Experiments in Research Reactors. (b) Specification (4) for fueled experiments states "a limit should be established- for fueled experiments." This statement is too vague. If the UFTR will conduct fueled experiments a specific limit must be established and an analysis provided in the Safety Analysis Report (SAR). Guidance for the specificity that would be acceptable for fueled experiments can be found in Regulatory Guide 2.2 Technical Specifications for Experiments in Research Reactors. 9. Section 3.8 Fuel and Fuel handling, Specification (4). Core configuration is very generic. Please state the specific data, conditions, or limitations that bound system operation. 10. Table 3-2. Secondary flow and shield tank level appear as required scrams in Table 3-1; they do not appear as minimum required channels in Table 3-2. Please explain. 11. Section 4.2.1 Reactor Control System, Specification (7) provides an exemption for performing daily and weekly checkout if a reactor startup is made within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Please provide the basis and significance for the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> time period or base the exemption on a condition of the reactor. 12. Section 4.3 Coolant System. There s hould be a clear requirement for surveillance testing after replacement, repair, maintenance or modification of TS required systems (similar to TS 4.2.2(3)). Please address. 13. Section 4.4 Radiation Monitoring Systems and radioactive Effluents. There should be a clear requirement for surveillance testing after replacemen t, repair, maintenance or modification of TS required systems (similar to TS 4.2.2(3)). Please address. 14. Section 4.5 Reactor Vent System. T here should be a clear requirement for surveillance testing after replacement, repair, maintenance or modification of TS required systems (similar to TS 4.2.2(3)). Please address.

15. Section 4.7 Reactor Building Evacuation Alarm. There should be a clear requirement for surveillance testing after replacement, repair, maintenance or modification of TS required systems (similar to TS 4.2.2(3)). Please address. 16. Section 4.10 UFTR Shield Tank. There should be a clear requirement for surveillance testing after replacement, repair, maintenance or modification of TS required system (similar to TS 4.2.2(3).) Please address. 17. Table 4-1 Safety System Operability Tests. To allow operational flexibility, ANS/ANSI 15.1 allows postponement of certain surveillance tests. The statement at the bottom of Table 4-1 of your proposed TSs appears to be too general. Any deferments of surveillance requirements need to be specifically identified and justified. Please address. 18. Section 5.0 Design Features. This section of the TS needs applicability, objective and bases statements per Title 10, Code of Federal Regulations, Part 50.36 (10 CFR 50.36). Please address. 19. Section 5.1 Site and Facility Description. Please clearly describe in this TS what areas are under the jurisdiction of the reactor license (licensed area

). 20. Section 6.1.3 Staffing. The guidance provided in ANS/ANSI 15.1 recommends that the a second designated person shall be present-" TS 6.1.3(2) does not state the person is "designated." Please address. 21. Section 6.2.2 Charter and Roles indicates that the RSRS is a subcommittee of the URCC. It is not clear where the URCC is indicated on Figure 6-1. Please clarify. 22. Section 6.4 Procedures. If the UFTR intends to use or transfer byproduct material under the reactor license, this section should contain a requirement for procedures for the use, receipt, and transfer of by-product material. Please address. 23. Section 6.5 Experiment Review and Approval. The guidance provided in ANS/ANSI 15.1 states that all new experiments shall be reviewed by the review group. Section 6.5(1) references TS 3.6, which provides for review of experiments, but does not address approval.

Requirements for approval of experiments are provided in UFTR TS 6.2.3. Please reword or clarify this TS. 24. Section 6.8.3 Records to be retained for the Lifetime of the Reactor Facility. T he regulat ions in 10 CFR 50.36 require that reviews of exceeding the safety limit (§ 50.36(c)(1)(i)(A)),

reviews of the failure of the automatic safety system that protects the limiting safety system settings (§50.36(c)(1)(ii)(A)) and reviews of not meeting limiting conditions for operation

(§ 50.36(c)(2)(i)) be retained until the Commission terminates the license. Please add these items to section 6.8.3 of the TSs. 25. General Comment. For changes made to the TS (both additions and deletions) there needs to be a justification in the form of a safety evaluation. Please provide the requested evaluations or refer to where discussed in the SAR.