ML20035C579
| ML20035C579 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 04/02/1993 |
| From: | Mendonca M Office of Nuclear Reactor Regulation |
| To: | Karam R Neely Research Reactor, ATLANTA, GA |
| References | |
| NUDOCS 9304080137 | |
| Download: ML20035C579 (6) | |
Text
%
S
,p tag
.8 g%
e UNIT i 'iTATES NUCLEAR rec"t %(ORY COMMISSION o
3 45 WAbe
..dTON, D. C. 20555 k..... #
April 2, 1993 Docket No. 50-160 Dr. Ratib A. Karam, Director Neely Nuclear Research Center Georgia Institute of Technology Atlanta, Georgia 30332
Dear Dr. Karam:
SUBJECT:
PROPOSED RENEWAL OF FACILITY OPERATING LICENSE l'0. R-97 This letter is to remind you that the License No. R-97 for the Georgia Institute of Technology Research Reactor is scheduled to expire on June 6, 1994, and to provide you with guidance for preparing your application for renewal of the license, if you so choose.
The NRC considers the renewal of a non-power reactor operating 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 Federal Reaister of a notice of the renewal application that provides the opportunity for public participation, as well as a notice of the results of our review of the application.
A renewal application must address the requirements in applicable sections of Title 10 of the Code gf Federal Reaulationi, and must demonstrate that the reactor can continue to be operated safely and without adverse impact on the environment or the public.
Title 10 of the Code qf federal Reaulations (10 CFR 2.109) would allow continued operation under the current license until the U.S. 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 the current license.
In order for us to perform an adequate review, all of the following documentation should be included as part of a renewal application in accordance with applicable portions of 10 CFR 50.33 and 50.34:
1.
Uo_ dated Safety Analysis Report (SAR)
A complete updated edition of the Safety Analysis Report (SAR) is required to be submitted with the renewal application. The SAR should include information that describes the facility with 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 functions.
Potential and reasonable accident scenarios and their consequences should be analyzed using the best current input data and computational techniques, and should be compared, wherever possible with facility operating experience.
93040B0137 930402 g g PDR ADDCK 05000160 pgp r g 7 ygg p q gy j
P PDR 5uu 6 h A
.T 4
i
v Dr. Ratib A. Karam,
Furthermore, the SAR should include updated information and analyses on demography, meteorology, geology, seismology, and other site characteristics.
2.
Financial Oualifications to Continue Operation (10 CFR 50.33(f))
This information must show that there is reasonable assurance-that the funds necessary to cover estimated operating. costs for the period of the requested license renewal plus the estimated costs of permanently shutting L
down the facility and decommissioning will be available. To facilitate our review, we request that the following be provided, and appropriately certified:
a.
the most recently published annual financial statement of the licensee and the source of funds utilized to cover costs of operation of the reactor facility; b.
the estimated annual cost to operate the reactor for the requested period of renewal, the underlying assumptions and bases of the estimate, and certification that future budgets will include these funds; and c.
the estimated costs of eventually shutting down the reactor and safely disposing of it, the option of decommissioning contemplated, a' listing of what is included in the costs, the assumptions underlying these estimated costs, ar.d the source of funds to cover these costs.
3.
Environmental Report (10 CFR Part 51)
The Environmental Report (ER) should include sufficient operational data, analyses, and discussions to provide a substantial basis for NRC to develop its environmental assessment.
k 4.
Technical Specifications The conten' and format for Technical Specifications should be in conformance with ANSI /ANS 15.1-19?0, "The Development of Technical Specifications for Research Reactors." Any substantive 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.
Operator Reaualification Prooram (10 CFR 50.54 (1-1) and 10 CFR Part 55)
A copy of the current and implemented operator requalification program must be submitted to ensure that it is reviewed with the renewal application and meets current NRC requirements for non-power reactors.
4 Dr. Ratib A. Karam 6.
Emeraency Plan (10 CFR 50.54(q) and (r) and 10 CFR 50, Appendix E)
As the Emergency Plan (EP) has been approved by NRC, only references to the licensee submittals and NRC approval documents need be provided.
i However, if the EP is to be modified, any changes must be submitted for NRC review in accordance with the above-cited regulations.
7.
Physical Security Plan (10 CFR 73.67)
The approved Physical Security Plan on file will be reviewed.
Accordingly, the renewal application need only reference the license amendment containing that documentation. However, if the Physical Security Plan is to be modified, changes should be made in accordance with the requirements of 10 CFR 50.54(p) or 10 CFR 50.90.
7 The requirements for submitting the renewal application and all other formal documentation relating to the license with respect to addressee, notarization, signatory and number of copies are defined in 10 CFR 50.4 and 10 CFR 50.30.
As a part of our review of the facility, members of the NRC licensing staff will expect to visit the facility for a few days. This visit will be coordinated with the licensee following receipt of the application for renewal.
4 For the review of a renewal application, the NRC staff will consider the guidance contained in the NRC Division 2 Regulatory Guides for Research Reactors (Enclosure 1) and the industry standards in the American Nuclear Society ANS-15 Series for research reactors., a copy of a license packages issued for the University of Texas research reactor, may provide further guidance in preparing information to be included in your potential license renewal application. This includes' the staff's Safety Evaluation Report and Environmental Assessment, and the new license for the reactor. We emphasized that these enclosures, except for the Technical Specifications, were developed and issued by the staff and are provided as examples of the type of findings-we must make to renew a license for a non-power reactor. Therefore, if you choose to apply for renewal of the license for your research reactor, your documentation must provide the technical and descriptive information that will support our issuance of similar evaluations.
i P
-=
3* + _
e 1s J
s Dr. Ratib A. Karam If you have any questions, please contact me at (301) 504-1128.
Sincerely, Marvin M. Mendonca, Sr. Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating-Reactor Support Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/o enclosures:
See next page DISTRIBUTION;. (w/o enclosure) [KARAMLIC.REN] [Mendonca diskette]
ONDD R/F Region II BGrimes CBassett, RIl SWeiss EMcAlpine, RII EHylton TMichaels MMendonca 3
OND ONDD:PM IV' OND : 7 Efi n
MMendonca:lb SWeiss t{/g/93
)C/f/93
[k/ ~Lf 93
'l
+
la..a.
u_
t-E Dr. Ratib A. Karam',
If you have any questions, please contact me at (301) 504-1128.
Sincerely,
~ >M~
~
ur Marvin M. Mendonca, Sr. Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support-Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/o enclosures:
See next page l
t
(
6 m.
Jtn s
4 Georgia Institute of Technology Docket No. 50-160 cc:
Charles H. Badger Dr. Bernard Kahn, Chairman NSC -
Office of Planning and Budget Nuclear Engineering Room 608 Georgia-Institute of Technology 270 Washington Street, S.W.
Atlanta, Georgia 30332-0425 Atlanta, Georgia 30334 Dr. John P. Crecine, President Mayor of City of Atlanta Georgia Institute of Technology Atlanta, Georgia 30301 Carnegie Building Atlanta, Georgia 30332-0325 Dr. G. Pohlein Vice President for Interdisciplinary Programs Georgia Institute of Technology 225 North Avenue Atlanta, Georgia 30332 Dr. William Vernetson Director of Nuclear Facilities Department of Nuclear Engineering Sciences University of Florida 202 Nuclear Sciences Center Gainesville, Florida 32611 Mr. Pedro B. Perez, Associate Director Nuclear Reactor Program North Carolina State University P. O. Box 7909 Raleigh, North Carolina 27695-7909 Dr. R. U. Mulder, Director Reactor Facility University of Virginia Charlottesville, Virginia 22901 James G. Ledbetter, Commissioner Department of Human Resources 47 Trinity Avenue Atlania, Georgia 30334 Mr. James C. O'Hara Neely Nuclear Research Center Georgia Institute of Technology 900 Atlantic Drive Atlanta, Georgia 30332-0425
,