ML19246C081
| ML19246C081 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 07/16/1979 |
| From: | Bolz R WORCESTER POLYTECHNIC INSTITUTE, WORCESTER, MA |
| To: | Ramos S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907200311 | |
| Download: ML19246C081 (2) | |
Text
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WORCESTER Worcester d
POLYTECHNIC Massachusettc 01609
[
INSTITUTE (617)753-1411 July 16,1979 United States fiuclear Regulatory Commission Attention:
Mr. Steve Ramos Division of Operating Reactors Washington, DC 20555 Re:
Docket #50-134 License #R-61 Gentlemen:
Facility License R-61 for the Worcester Polytechnic Institute fluclear Reactor was issued December 16, 1959 and is scheduled to expire or.
tiovember 23, 1979.
In accordance with 10CFR-2.109, we hereby request a 20-year extension of this license.
The WPI Open Pool Reactor first achievad criticality on December 18, 1959 at which time it was licensed for a maximum steady power output of 1 kw.
On flovember 14, 1967 Amendment 4 to License R-61 was issued to authorize a maximum steady state power level of 10 kw and to incorporate Technical Specifications into the license.
The reactor has been used since 1959 primarily as an instructional device.
Laboratory work utilizing the reactor is an integral part of three nuclear engineering courses offered at least annually and is used extensively in two additional courses offered in alternate years.
A vital part of the WPI educational program requires each student to complete a
" Major Qualifying Project" and the facility is used in this connection for studies of an operating reactor, as a neutron activation analysis tool, and as a neutron radiography device.
Since the power increase in 1967 the WPI Reactor has been operated approximately 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> and the total power generated since 1959 is approx-imately 6300 kw hr.
The total consumption of U235 in the WPI core since 1959 is approximately 0.32 g.
The mechanical and electronic components of the reactor control and safety systems have been frequently and systemati-cally inspected and have been repaired or replaced promptly as necessary.
The pool demineralizer system has consistently worked well and has kept the pool pH ve.y close to 7.0 at all times, thereby keeping corrosion of all aluminum components to a minimum in keeping with the requirements for a 40 year lifetime.
We do not plan any substantive changes in Reactor Facility operation in the foreseeable future.
Our Safety Analysis and Technical Specifications are being revised to reflect the current flRC recommended format and to integrate changes and license provisions added to our original license by 566071
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- e United States fluclear Regulatory Commission Page Two amendments over the years.
These supporting documents for our renewal request will be forwarded before the end of September by the Facility Director, Professor Leslie C. Wilbur.
If there are any questions or concerns relative to our license renewal, please contact Professor Wilbur at 617-753-1411, extension 276.
Sincerely yours, W/
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R. E. Bo REB /ns Vice Rrq#z N
sident and cc:
L. C. Wilbur Dean ohFaculty k)
D. fl. Zwiep SE9072