ML20052H393
| ML20052H393 | |
| Person / Time | |
|---|---|
| Site: | University of Lowell |
| Issue date: | 05/17/1982 |
| From: | Bernard H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052H390 | List: |
| References | |
| R-125-A-008, R-125-A-8, NUDOCS 8205200316 | |
| Download: ML20052H393 (7) | |
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION
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- e UNIVERSITY OF LOWELL DOCKET NO.
50-223 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 8 License No. R-125 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The filing by the University of Lowell (the licensee) dated March 25, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the provisions of the Atomic Energy Act of 1954, as amended, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the healch and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendent will not be inimical to the common defense and security or to the health and safety of the public;
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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.
Prior public notice of this amendment was not required since it did not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. R-125 is hereby amended to read as follows:
DESIGEATED ORIGINAL
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PDR ADOCK 05000223 P
i 2.C.(2) Technical Specifications t
The Technical Specifications contained in Appendix A as i
i revised through Amendment No. 8 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 REGUL" TORY COMMISSION f
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MQty Harold ernard, Ac't'~j Chief Standardization & Special Projects Branch Division of Licensing
Attachment:
Changes to the Technical 1
Specifications
.i Date of Issuance MAY 171982 f
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r ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY OPERATItt :.ICENSE NO. R-125 DOCKET NO. 50-223 Revise Appendix A Technical Specifications as follows:
I Remove Pages Insert Pages 28 28 29 29 30 30 31 31 Changes on the revised page are identified by marginal lines.
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3.
Variable-load elecent:
same as Specification 1 above but internal plates are removable.
l 5.2 REACTOR CORE 1.
The reactor core consists of a 9x7 array of 3-inch square modules with the four corners occupied by posts. The referen.ce core for these technical specifications consists of 26 standard fuel elements arranged symmetrically around four safety control blades as shown in Figure 4.23 of the FSAR.
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2.
Cores from 23 standard elements to 30 elements may be used, and cores from 24 elements to 30 elements may contain 2 half-I loaded elements.
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3.
Cores with an intern'al fuel element replaced by a radiation j
basket may be operated under forc'ed convection only after flux measurements made under natural convection' establish that no I
alteration of the LSSS's are required to preclude. violation of a SL during the transients anticipated in the FSAR.
l 5.3 REACTOR ?UILDING i
1.
The reactor shall be housed in the reactor building, l,
designed for containment. The minimum free volume in the reactor building shall be S.5x109 cm3 (300,000 ft ).
3 2.
The reactor building ventilation and containment systems shall I
be separate from the rest of the building systers and shall be designed to exhaust air or other gases from the building through s
a stack with a discharge at a minimum of 100 feet above ground
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The openings into the reactor building are.the tYuck entrance 3.
door, personnel entrance doors, and air supply and exhaust ducts.
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5.4 FUEL STORAGE l
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All reactor fuel element storage facilities shall be designed in a geometrical configuration where keff is less than 0.8 under quiescent j
flooding with water.
6.0 ADMINISTRATIVE CONTROLS 6.1 ORG-\\NIIATION AND MANAGEMENT 1.
.The reactor facility shall be an integral part of the Radiation Laboratory of the University of Icwell. The reactor shall be related to the University structure as shown in Chart 6.1 and 7i
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Chart 6.2.
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PRE 51 DENT h
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4 Vice-Pres. for Academic Services 5 s
Technical Research i
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Administrative Assist DIRECTOR.
F Af'ULTY GR ADUATE for COMPUTER CENTE R SCH00L.ETC.
Reactor 5 Accelerator l
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I ACADEMIC 0EP ARTMENTS.
SUPPORT 3TAF F AOMINISTR ATiv E FUNCTIONS.
Sy,PPO,ST FUNCTIONS ETC.
REACTOR ACCELERATOR f
l CHART 6-1.
Univ of Lowell Administrative Structure l
Chart 6-1
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Vice Pres for University Tech. Research Radiation Safety Coz:::nittee
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Administrative Assis, j
for Reactor 6 Accelerator Radiation f
Safety Officer I
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Reactor Safety Sub-Committee i
I Reactor Supervisor s
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Reactor Operations REACTOR m
Staff
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OPERATIONS
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CHART 6-2.
University of Lowell Reactor Organizational Structure Chart 6-2
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2.
Tha racctor fccility shall ba unds: tha dirsetien of th3 Admir.istrative Assistant for the Reactor i
and Accelerater, who shall be a member qf the graduate faculty, and it shall be supervised by
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the Reacter Superviser who shat 1 'be a NIC licensed senior operater for the facility. The Reactor Supervisor shall be responsible for assuring that all cperations are conducted in a safe manner and 4
j within the limits prescribed by the facility j
license and the provision of the Reacter Safety Sub-Cec:mittee.
t 3.
There shall se a Radiatien Safety Officer responsible for the safety of operations frem the standpoint of t
radiation protectic.t. He does not report to the line organization responsible for reacter cperations, i
I but rather to the Vice President for Academic Services and Technical Research.
4.
An operator er senior operator licensed pursuant
.to 10CFR 55 shall be present at the controls unless the reacter is secured as defined in these specifications.
5.
A licensed senior operator shall be readily available en call within the Pinanski Building whenever the reactor is in operation.
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There shall ha :., ilecctcr Caf; y Cubccr.r. :ae whic' shell revicw reactor Operaticns. to assure that the facility is i
operated in c ::.n. er censisten. vi:.h public safety cnd within the ter!..s of the facili:/ license.
Tha Subcon=ittee shall report :c the Ins:itute Ec.dictica Safe:y Cc::ittee wnich has everall au:hcrity in the use cf all radiation sources at the Institute.
I 2.
The responsibilities of th'e Subcot::ittee include, but are not li:.ited to, the felicuing:
t Review and cpproval of nor=al, abnor=al and energency a.
operating cnd maintenaacc.precedures cnd records.
b.
Review and approval of propcsed tests and experiments utilizing the rccc:cr fccilitics in accordance with' Paragrcph 6.L oi these specifications.
Revieu snd approval cf prcposed c.
innges to the facility syste.as cr ecuipment, procedures, and operations.-
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d.
Deterr.ination of whether n proposed change, test, or experitent would cens:itute an unreviewed safety se g
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