ML20196C578

Submits Reminder That Univ of Maryland,Maryland Univ Training Reactor,License R-70,scheduled to Expire on June 29,2000 & to Provide Guidance for Preparing for Application of Renewal of License

ML20196C578
Person / Time
Site:	University of Maryland
Issue date:	06/17/1999
From:	Alexander Adams NRC (Affiliation Not Assigned)
To:	Christou A MARYLAND, UNIV. OF, COLLEGE PARK, MD
References
NUDOCS 9906240057
Download: ML20196C578 (7)

Text

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j NUCLEAR REGULATORY COMMISSION WA8HINGToN, D.C. 2006H001 g,,+ June 17, 1999 e

Dr. Aris Christou, Chairman Department of Materials and Nuclear Engineering The University of Maryland College Park, MD 20742

SUBJECT:

RENEWAL OF OPERATING LICENSE NO. R-70

Dear Dr. Christou:

This letter is to remind you that License No. R-70 for the University of Maryland (UM)

Maryland University Training Reactor (MUTR) is scheduled to expire on June 29,2000, and to provide you guidance for preparing your application for a renewal of the license.

Tit /e 10 of the Code of FederalRegu/ations (10 CFR 2.109) allows continued operation under your current license until the Nuclear Regulatory Commission (NRC) acts upon an application for renewal provided the application is received at least 30 days prior to the expiration date of your current license.

The NRC considers the renewal of a non-power reactor operatin0 license to be equivalent to reissuing the license. Therefore, renewal is not merely a routine administrative step, but involves in-depth reviews of all documentation related to the facility, an onsite review, and publication in the Egderal Reoister of a notice of your request that provides the opportunity for public participation, as well as a notice of the results of our review of your application.

Your renewal application should address the requirements in applicable sections of Tit /e 70 of the Code of FederalRegulations, and should demonstrate that the reactor can continue to be operated safely and without adverse impact on the environment or the public. For the review of your renewal application, the NRC staff will consider the guidance contained in the NRC Division 2 Regulatory Guides for Research Reactors (reproduced in Enclosure 1), NUREG-1537, " Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors" (Enclosure 1), and the industry standards in the American Nuclear Society ANS-15 Series for research reactors.

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Dr. Aris Christou In order for us to perform an adequate review, you are requested to include, as part of your application, all of the following documentation, in accordance with 10 CFR 50.33 and 50.34:

1 11pdated Safety Analysis Reoort (SAR_1 A complete updated edition of your Safety Analysis Report (SAR) is required to be submitted with your renewal application. The SAR should include information that describes the facility and all changes made during the license period; the design bases and limits on its operation; and a safety analysis of the structures, components and systems to ensure that they will be able to continue to perform their intended l

functions. Potential and reasonable accident scenaries and their consequences should be analyzed using the best current input data and computational techniques, information should be compared, wherever possible, with facility operating experience.

Furthermore, the SAR should include, if applicable, updated information and analyses on demography, meteorology, geology, seismology, and other natural and unnatural phenomana.

2. Financial Qualifications (10 CFR 50.33(f))

This information must show that there is reasonable assurance that you will be able to obtain the funds necessary to cover estimated operating costs for the period of the requested license renewal plus the estimated costs of decommissioning the facility.

To f acilitate our review, we request that the following information be provided, appropriately certified:

a. The most recently published annual financial statement of the University.

Indicate the source of funds utilized to cover costs of operation of the MUTR.

b. The estimated annual cost to operate the reactor for the requested period of renewal, the underlying assumptions and bases of the estimate, and the sources of funds to cover these costs, ar.d

c. The estimated costs of eventually shutting down the reactor and safely disposing of it, a listing of what is included in these costs, the assumptions underlying these estimated costs, the type of shutdown contemplated, and the source of funds to cover these costs.

3. Environmental Report (10 CFR Part 51)

Your Environmental Report should include sufficient operational data, analyses, and discussions to provide a substantial basis for NRC to develop its environmental assessment.

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l Dr. Aris Christou 4. Technical SoecificaTigng The content and format of Technical Specifications should be developed considering the guidance in ANSI /ANS 15.1-1990, "The Development of Technical Specification for Research Reactors" and NUREG-1537. Any changes to the current Technical Specifications should be proposed and justified at the time of the license renewal application so they can be evaluated during the review.

5. QJzgrator Reaualification Pr920!s (10 CFR 50.54 (i-1) and 10 CFR Part 55)

A copy of your current and implemented operator requalification program will be l

reviewed with your renewal application to ensure it meets current NRC requirements for non-power reactors. Please submit an/ changes you wish to make as part of the renewal epplication.

6. Emeraencv Plan (10 CFR 50.54(q) and (r) and 10 CFR SO, Appendix E)

We will review your approved emergency plan to ensuro compliance with current NRC requirements. If you have no changes you wish to make as part of the license renewal, you need only reference those respective UM and NRC documents.

However, if you wish to modify your emergency plan, any changes should be submitted for NRC review in accordance with the above-cited regulations.

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7. Physical Security Plan (10 CFR 73.67)

You have an approved physical security plan on file with NRC which we shall review.

Accordingly, you need only reference the existing security plan. However, if you wish to modify your physical security plan, changes should be made in accordance with the requirements of 10 CFR 50.54(p) or 10 CFR 50.90.

8. Filina of Acolication The requirements for submitting your renewal application and all other formal documentation relating to your license with respect to addressee, notarization, signatory and number of copies are defined in 10 CFR 50.4 and 10 CFR 50.30,

9. Staff Visk As a part of our review of your facility, mernbers of the NRC licensing staff may visit your facility. This visit will be coordinated with you following receipt of your application for renewal.

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Dr. Aris'Christou - June 1,1999 )

l For your further guidance in preparing the proper information to be included in your license {

renewal application, we are enclosing a copy of a license package issued for a non-power reactor facility (North Carolina State University, Enclosure 2). This includes the staff's

! Safety Evaluation Report (NUREG 1572), Environmental Assessment, and the new license for the reactor. - Upon completion of our review and a favorable evaluation of your facility, similar documents will be issued in conjunction with renewal of your reactor operating j license. The Safety Evaluation Report is provided as an example of the type of find lngs we must make. 'Your documentation must provide the technical and descriptive i

mformation that will support our issuance of a similar evaluation for your facility.

If you have any questions, please contact me at (301) 415-1127.

Sincerely, ORIGINAL SIGNED BY:

Alexander Adams, Jr., Senior Project Manager Events Assessment, Generic Communications and Non-Power Reactors Branch )

Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation Docket,No.50-16S l

Enclosures:

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As stated

cc w/o enclosures: See next page

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DISTRIBUTION: w/ enclosure ,

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l Dr. Aris Christou 1 For your further guidance in preparing the proper information to be included in your license renewal application, we are enclosing a copy of a license package issued for a non-power reactor facility (North Carchna State University, Enclosure 2). This includes the staff's Safety Evaluation Poport (NIJREG 1572), Environmental Assessrnent, and the new license for the reactor. Upon completion of our review and a favorable evaluation of your facility, similar documents wil! be issued in conjunction with renewal of your reactor operating bcense. The Safety Evaluation steport is provided as an example of the type of findings we must make. Your documentation must providc the technical and oescriptive information that will support OJr issuance of a similar evaluation for your facility, if you have any questions, please contact me at (301) 415-1127.

l Sincerely, Ab M Alexander Adams, Jr., Se r Project Manager Events Assessment, G eric Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation I l

Docket No. 50-166

Enclosures:

As stated cc w/o enclosures: See next page

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, i University of Maryland Docket No. 50-166 '

cc:

Director, Dept. of Natural Resources Power Plant Siting Program Energy & Coastal Zone Administration Tawes State Office Building i Annopolis, MD 21401 l Mr. Roland Fletcher, Director Center for Radiological Health Maryland Department of Environment 201 West Preston Street 7th Floor Mail Room Baltimore, MD 21201 Mr. Vincent G. Adams Associate Director-Reactor Facility Department of Materials and Nuclear Engineering i University of Maryland College Park, MD 20742 1

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