ML110880521

University of California at Irvine - Request for Additional Information Regarding the License Renewal for the University of California Irvine Nuclear Reactor Facility

ML110880521
Person / Time
Site:	University of California - Irvine
Issue date:	04/05/2011
From:	Linh Tran Research and Test Reactors Licensing Branch
To:	Geoffrey Miller University of California - Irvine
DiMeglio A, NRR/DPR/PRTA, 301-415-0894
References
TAC ME1579
Download: ML110880521 (5)

Text

April 5, 2011 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

UNIVERSITY OF CALIFORNIA AT IRVINE - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE RENEWAL FOR THE UNIVERSITY OF CALIFORNIA IRVINE NUCLEAR REACTOR FACILITY (TAC NO. ME1579)

Dear Dr. Miller:

We are continuing our review of the application for Renewal of License No. R-116, Docket No. 50-326 for the University of California Irvine Nuclear Reactor Facility. The application was submitted on October 18, 1999, as supplemented by letters dated October 23, 1999, January 27, 2010, July 14, 2010, and October 20, 2010.

During our review of your application, as supplemented, additional questions have arisen for which we require 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 Title 10 of the Code of Federal Regulations (10 CFR), Section 50.30(b), you must execute your response in a signed original document under oath or affirmation. Your response must be submitted in accordance with 10 CFR 50.4, Written Communications. Information included in your response that is considered security, sensitive, or proprietary, that you seek to have withheld from the public, must be marked in accordance with 10 CFR 2.390, Public inspections, exemptions, requests for withholding. Following receipt of the requested information, we will continue our evaluation of your application.

If you have any questions regarding this request, please contact A. Francis DiMeglio at 301-415-0894.

Sincerely,

/RA/

Linh Tran, Senior Project Manager Research and Test Reactors Licensing Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-326 License No. R-116

Enclosure:

As stated cc: See next page

ML110880521 NRR-088 OFFICE PRLB:PM PRLB:PM PRPB:LA PRLB:BC PRLB:PM NAME ADiMeglio LTran GLappert JQuichocho LTran DATE 3/24/2011 4/5/2011 4/5/2011 4/5/11 4/5/11

University of California at Irvine Docket No. 50-326 cc:

Dr. Donald Blake, Chair Department of Chemistry University of California, Irvine Irvine, CA 92697-2025 Mr. Steve Hsu Radiological Health Branch State Department of Health Services P.O. Box 9442732 Sacramento, CA 94234-7320 Dr. Michael R. Gottfredson Executive Vice Chancellor University of California, Irvine Irvine, CA 92697-1000 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

Enclosure OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION UNIVERSITY OF CALIFORNIA IRVINE NUCLEAR REACTOR FACILITY LICENSE NO. R-116 DOCKET NO. 50-326 The U.S. Nuclear Regulatory Commission (NRC) staff is continuing the review of your application for renewal of Facility Operating License No. R-116, dated October 18, 1999, as supplemented by letters dated October 23, 1999, January 27, 2010, July 14, 2010, and October 20, 2010. During our review, additional questions have arisen for which we require information and clarification. Our review conformed to the Interim Staff Guidance on the Streamlined Review Process for Research Reactors and NUREG-1537.

Please address and provide the requested information to the following within 30 days of the date of the transmittal letter:

(1)

NUREG -1537, Chapter 7, Instrumentation and Control Systems, recommends that a description be provided of the Reactor Protection System listing the protective functions and the parameters monitored to detect the need for protective action. Chapter 7 of the SAR, as supplemented, includes the mention of a Seismic Switch and the set point for a reactor scram. However no discussions were provided for the Seismic Switch or the rationale for the reactor trip set point. In addition, the proposed technical specifications stated a Limiting Condition of Operation which requires a Seismic Switch with a trip set point different from that in the SAR. Please provide a discussion regarding the Seismic Switch and an analysis describing the reactor scram associated with the seismic switch trip set point.

(2)

NUREG-1537, Chapter 13, Accident Analysis, recommends maximum hypothetical accident (MHA) doses analysis to the public. The MHA analysis presented in the SAR, as supplemented, is incomplete in that (1) while providing considerable information, it does not provide a clear presentation of the analyzed MHA scenario, and (2) it does not discuss the dose to non-occupational occupants in unrestricted areas adjacent to the reactor facility and non-occupational occupants of Rowland Hall such as students, faculty, visitors, etc. Please provide a discussion regarding the scenario for the MHA and a dose assessment for the maximum exposed individual member of the public in the unrestricted areas of Rowland Hall and in unrestricted areas adjacent to the reactor facility. Please describe the assumptions used and any systems, plans, procedures, or stay times for which credit is taken in the analysis.

(3)

NUREG 1537, Chapter 4, Reactor Tank and Pool, recommends that consideration be given to methods for assessing and preventing corrosion to the tank exterior. From the NRCs Inspection Report dated January 13, 2011, it is noted that ground water from rain and irrigation has been observed in fuel storage pits and in monitoring wells in the in-ground spaces around the exterior of the reactor tank. Please provide a discussion describing the impact to the reactor tank liner and other structures, as applicable, associated with this groundwater incursion. Since this groundwater incursion may cause corrosion, in your discussion, please describe how corrosion can be detected for the reactor tank and other structures, as applicable. Please include a discussion regarding detection of leakage from the reactor tank.