ML20058F788

Amend 10 to R-59,revising TS to Include Definition of Term Confinement Secured

ML20058F788
Person / Time
Site:	University of Iowa
Issue date:	11/29/1993
From:	Dudley R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058F785	List: ML20058F781 ML20058F788 ML20058F792
References
R-059-A-010, R-59-A-10, NUDOCS 9312080282
Download: ML20058F788 (8)

Text

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WASHINGTON. D.C. 20555-0001 IOWA STATE UNIVERSITY DOCKET NO. 50-116 AMENDMENT TO FACILITY OPFDATING LICENSE Amendment No. 10 License No. R-59 1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to Facility Operating License No. R-59 filed by the Iowa State University (the licensee), dated June.22, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission 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 rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering th health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission; 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 regulations of the Commission and all applicable requirements have been satisfied; and F.

Prior notice of this amendment was not required by 10 CFR 2.105(a)(4) and publication of notice for this amendment is not required by 10 CFR 2.106(a)(2).

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Accordingly, 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-59 is hereby amended to read as follows:

(2) Iechnical Specifications i

The Technical Specifications contained in Appendix A, as revised through Amendment No. 10, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license rma-iment is effective as of the date of issuance.

FOR THE NUCLEAR RtGULATORY COMMISSION f

Richard F. Dudley, Acting Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical Specifications Changes Date of Issuance:

November 29, 1993 l

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't ENCLOSURE TO LICENSE AMENDMENT NO. 10 FACILITY OPERATING LICENSE NO. R-52 DOCKET NO. 50-116 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain horizontal lines indicating the areas of change.

Remove Insert 1-1 1-1 1-2 1-2 1-3 1-3 1-4 1-4 1-5 1-5 1

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1.0 DEFINITIONS The terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50.36 of 10 CFR Pan 50.

CHANNEL TEST - The introduction of a signalinto the channel for verification that it is operable CHANNEL CALIBRATION - The adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.

Calibration shall encompass the entire channel, including equipment actuation, alarTn or trip and shall be deemed to include a Channel Test.

CH ANNEL CHECK - A qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shallinclude the comparison of the channel with other independent channels or systems measuring the same variable.

CONFINEhENT BOUNDARY - The surface surrounding the reactor facility defined by the interior partition walls of offices and laboratories on the north, east and south sides of the building and by the west interior wall which isolates the basement, first floor, and the west corridor of the second floor from the central bay.

CDhTINEMENT SECURED - The confing_mmhallhc_considersd_ secured when:

LDpars 1-2 C_Sj01.101.114.113-1. CX112.112.111-1. CX111. CC110.

CE117-2.112 A-3. CE217-2E211. 209EJ10. 211. 213-1. 213-2. 214. 215 and CC201 grefloicdar_areansp_dsd_by_a_ person with the ability to Jose the door in the cent of an smergency. and b Windowton the_npfthauth 3asland west sides of the prathogse. on the west wall of IppmJj 2 App the auth wallpf room 101. on the east wall above door CX112. orLibr_

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baserpentJr_sijpgr aniljhe west conidor of the second floor from the_qgntral bay arg_

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LThnooffovning3he_cenitalhanarfa_Andacsondfoor corridors CC201. CC212. and CC2.L) is intacLand_gapab)c_ofprIfonning as a non-pItsspre ticht boundArx l

1-1 Amendment No. 10

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e CONTROL ROD - A plate fabricated with Boral as the neutron absorbing material which is used to establish neutron flux changes and to compensate for routine reactivity losses. This includes safety-type and regulating rods.

CORE - The portion of the reactor volume which includes the graphite reflector, core tanks, and control rods. The thermal column and shield tank duct are not included.

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DELAY TIME - The elapsed time between reaching a limiting safety system setpoint and the initial movement of a safety-type rod.

DELAYED NEUTRON FRACTION - When convening between absolute-and dollar-value l

reactisity units, a beta of 0.00763 is used.

DROP TIME - The elapsed time between reaching a limiting safety system setpoint and the full insenion of a safety-type rod.

EXCESS REACTIVITY - That amount of reactivity that would exist if all control rods (control, regulating, etc.) were moved to the maximum reactive condition from the point where the reactor is exactly critical.

EXPERIMENT - Any operation, hardware, or target (excluding devices such as detectors, foils, etc ) which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within the core region, on or in a beam port or irradiation facility and which is not rigidly secured to a core or shield stmeture so as to be a part of their design.

MEASURED VALUE - The value of a parameter as it appears on the output of a channel.

MEASURING CHANNEL - The combination of sensor, line, amplifier and output desices which are connected for the purpose of measuring the value of a parameter.

MOVABLE EXPERIMENT - An experiment where it is intended that the entire experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

i OPERABLE - A component or system is capable of performing its intended function.

OPERATING - A component or system is performing its intended function.

REACTIVITY LIMITS - Those limits imposed on reactor core excess reactivity. Quantities are references to a Reference Core Condition.

I 1-2 Amendment No. 10

t REACTIVITY WORTH OF AN EXPERIMENT - The maximum absolute value of the reactivity change that would occur as a result ofintended or anticipated changes or credible malfunctions that alter nperiment position or configuration.

REACTOR OPERATING - The reactor is operating whenever it is not secured or shutdown.

REACTOR OPERATOR (RO) - An individual who is licensed to inanipulate the controls of a reactor.

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REACTOR SECURED - A reactor is secured when:

(1) It contains insuflicient fissile material or moderator present in the reactor l

to attain criticality under optimum available conditions of moderation and reflection, or (2) A combination of the following:

a The minimum number of neutron absorbing control rods are fully I

inserted or other safety devices are in shutdown position, as required by technical specifications, and i

b. The magnet power keyswitch is in the off position and the key is removed from the lock, and l

c. No work is in progress involving core fuel, core structure, installed l

control rods, or control rod drives unless they are physically decoupled from the control rods, and l

d. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum value allowed for a single experiment or 0.763% Ak/k whichever is smaller.

REACTOR SHUTDOWN - The reactor is shutdown if n is subcritical by at least 0.763% Ak/k in the Reference Core Condition and the reactivity worth of all experiments is accounted for.

REACTOR SAFETY SYSTEMS - Those systems, including their associated input channels, l

which are designed to initiate automatic reactor protection or to provide information for uutiation of manual protective action.

i l-3 Amendment No. 10 I

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i READILY AVAILABLE ON CALL - Applies to an individual who:

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(1) Has been specifically designated and the designation known to the

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operator on duty, and l

(2) Keeps the operator on duty informed of where he or she maybe rapidly l

contacted (e.g., by phone, etc.), and

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(3) Is capable of getting to the reactor facility within a reasonable time under normal conditions (e.g.,30 minutes).

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REFERENCE CORE CONDITION - The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible, less than 0.23% Ak/k.

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REGULATING ROD - A low-worth control rod used primarily to maintain an intended power level that does not have scram capability. It's position may be varied manually or by the servo-controller.

i SAFETY CH ANNEL - A measuring or protective channelin the reactor safety system.

j SAFETY-TYPE ROD - A rod that can be rapidly inserted by cutting off the holding current in its electromagnetic clutch. This applies to safety #1, Safety #2, and shim-safety.

SECURED EXPERIMENT - Any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The reoraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoy.t, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as a result of credible malfunctions.

t SENIOR REACTOR OPERATOR (SRO)- An individual who is licensed to direct the activities of a Reactor Operator (RO) and to manipulate the controls or a reactor.

SHALL, SHOULD, AND MAY - The word "shall" is used to denote a requirement, the word

'should" to denote a recommendation, and the word "may" to denote permission, neither a requirement nor a recommendation.

SHUTDOWN MARGIN - The min' num shutdown reactivity necessary to provide confidence a

that the reactor can be made suberitical by means of the control and safety systems starting from any permissible operating condition although the most reactive rod is in its most reactive position, and that the reactor will remain suberitical without further operator action.

I TRUE VALUE - The actual value of.

.w ter or variable.

1-4 Amendment No. 10

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UNSCHEDULED SHUTDOWN - Any unplanned shutdown of the reactor caused by actuation I

of the reactor safety system, operating error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check-out operations.

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i 1-5 Amendment tao.10