NUREG-1537, Part 2 - NRC

1 INTRODUCTION
By letter (with supporting documentation) dated November 14, 1986, as supplemented
on June 2, 1987, August 14, 1987, April 29, 1988, and January 10, 1989,
the Dow Chemical Company (Dow/licensee) submitted to the U.S. Nuclear Regulatory
Commission (NRC/staff) a timely application for a 20-year renewal of the Class
104c Facility Operating License R-108 (NRC Docket io. 50-264) and an increase
in operating power level, from the existing 100 kilowatts thermal [kW(t)] to
300 kW(t), for its TRIGA Mark I research reactor facility. The research reactor
facility is located in the 1602 Building on the groaunds of the Michigan
Division of the Dow Chemical Company in Midland, Michigan. The licensee currently
is permitted to operate the Dow TRIGA Research Reator (DTRR) within the
conditions authorized in past amendments in accordance with Title 10 of the
Code of Federal Requlations (10 CFR), Section 2.109, until NRC action on the
renewal request is completed.
The staff's review, with respect to issuing a renewal operating license to Dow,
was based on the information contained in the renewal application and supporting
supplements plus responses to requests for additional information. The renewal
application included financial statements, the Safety Analysis Report, an Environmental
Report, the Operator Requalification Program, the Emergency Plan, and
Technical Specifications. This material is available for review at the Commission's
Public Document Room located at 2120 L Street, NW, Washington, DC 20555.
The approved Physical Security Plan is protected from public disclosure under
10 CFR 2.790.
The purpose of this Safety Evaluation Report (SER) is to summarize the results
of the tafety review of the DTRR and to delineate the scope of the technical
details considered in evaluating the radiological safety aspects of continued
operation. This SER will serve as the bas-is for renewal of the license for
operation of the OTRR at thermal power levels up to and including 300 kW. The
facility was reviewed against the requirements of 10 CFR Parts 20, 30, 50, 51,
55, 70, and 73; applicable regulatory guides; and appropriate accepted industry
standards [American National Standards Institute/American Nuclear Society
(ANSI/ANS) 15 series). Because there are no specific accident-related regulations
for research reactors, the staff has compared calculated dose values
with related standards in 10 CFR Part 20, the standards for protection against
radiation, both for employees and the public.
This SER was prepared by Alexander Adams, Jr., Project Manager, Division of Reactor
Projects III, IV. V, and Special Projects, Office of Nuclear Reactor Regulation,
U.S. Nuclear Regulatory Commission. Major contributors to the technical
review were the Project Manager and R. E. Carter, C. Cooper, and R. Carpenter
of the Idaho National Engineering Laboratory under contract to the NRC.