ML20237C599
| ML20237C599 | |
| Person / Time | |
|---|---|
| Site: | 05000134 |
| Issue date: | 12/15/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237C589 | List: |
| References | |
| R-061-A-009, R-61-A-9, NUDOCS 8712220019 | |
| Download: ML20237C599 (4) | |
Text
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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WORCESTER POLYTECHNIC INSTITUTE DOCKET NO. 50-134 AMEND!iENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. R-61 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to Facility Operating License No.
R-61, filed by the Worcester Polytechnic Institute (the licensee),
dated August 10, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and F.
Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
8712220019 B71215 DR ADDCK 0500 4
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3 2.
Accordir. gly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
R-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 9, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Lt luf Lester S. Rubenstein, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: December 15, 1987
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I ENCLOSURE TO LICENSE AMENDMENT NO. 9
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FACILITY OPERATING LICENSE NO. R-61 DOCKET NO. 50-134 1
Revise Appendix A Technical Specifications as follows:
Remove Page Insert Page 8
8
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.The change on the revised page is-identified by a marginal line.
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1 4.0- SITE AND DESIGN FEATURES
!a 4.1 ' Site j
The reactor and associated equipment is housed in the Washburn Laboratories located between West Street and Boynton Street on the campus of Worcester Polytechnic Institute in Worcester, Massachusetts.
1 4.2 Restricted Area and Exclusion Area j
t The reactor room shall constitute a restricted area as defined in 10 CFR 20 t
and shall be controlled by partitions and normally locked doors.
In addition, two' small -areas, one each on the second and third floors of Washburn Laboratories, directly above the reactor control drives, shall j
become restricted areas whenever the radiation levels in any of the rooms
, exceed those:specified in 10 CFR 20.105.. The exclusion areas, as defined in110 CFR 100, shall consist of the reactor. room and the areas above the reactors.
4.3 Reactor Building and Ventilation System The reactor shall be housed in a closed room that is designed to restrict leakage.
The ventilation system shall provide at least two changes of air j
per hour in the reactor room whenever the reactor is operating.
4.4 Reactor Core fuel Elements:
Standard fuel elements shall be flat plate type consisting of uranium-aluminum alloy clad with aluminum.
The width and depth of each fuel element shall be 3 in. x 3 in.
Each element shall have an active
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length of 24 in.
There shall be a maximum of 18 g of U-235 in each fuel l
plate and not more than 140 g or U-235 in any fuel element.
Standard fuel i
elements may be of two types:
(1) with 10 fuel plates, each plate 0.099 in. thick including a clad thickness of 0.030 in. ; (2) with 18 fuel plates, l
each plate 0.060 in. thick with a clad thickness of 0.015 in, on 'each side.
A maximum of 27 standard fuel elements may be installed in the core.
Not more than two experimental fuel elements with eight removable fuel plates similar to type (1) fuel plates and fitted with removable top end boxes may be installed in the core.
These elements may be used as part of
-the core assembly either as complete elements or as partial assemblies, loaded with from 2 to a total of 10 fuel plates each.
4.5 Reactor Safety and Control Systems The safety system shall be designed so that no single electrical f ault that partially. or completely disables the automatic scram function can, in any manner, impair or disable the manual scram function, and vice versa.
The safety system shall be fail safe with respect to loss of voltage.
8 Worcester Tech Specs i
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