ML20217H302
| ML20217H302 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 03/30/1998 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217H291 | List: |
| References | |
| R-59-A-12, NUDOCS 9804030264 | |
| Download: ML20217H302 (7) | |
Text
as p tM4 9 y t UNITED STATES j
s* NUCLEAR REGULATORY COMMISSION
- - WASHINGTON. D.C. 20066-0001
. . . . . ,o IOWA STATE UNIVERSITY DOCKET NO. 50-116 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.12 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 December 22,1997, as revised on February 10,1998, 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 1; 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 that (i) the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) 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, and publication of notice for this amendment is not required by 10 CFR 2.106, j 1
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- 2. 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) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.12, 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ u Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: March 30, 1998
4 ENCLOSURE TO LICENSE AMENDMENT NO.12 FACILITY OPERATING LICENSE NO. R-59 DOCKET NO.' 50-116 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. Pages 1-2,1-3, and 1-5 have been reformatted without any Technical Specification change. The Technical Specification addition is underlined on page 1-4.
Remove Insert 1-2 1-2 1-3 1-3 1-4 1-4 1-5 1-5
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..o.
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.
-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 converting between absolute- and dollar-value reactivity units, a beta of 0.00763 is used.
. DROP TIME - The elapsed time between reaching a limiting safety system setpoint and th:: full
- insertion of a safety-type rod.
ENCESS 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 criticalc -
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 structure 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 devices 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.
OPERABLE - A component or system is capable of performing its intended function.
- OPERATING - A component or system is performing its intended function.
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' REACTIVITY LIMITS - Those limits imposed on reactor core excess reactivity, Quantities are references to a Reference Core Condition.
REACTIVITY WORTH OF AN EXPERIMENT - The maximum absolute value of the reactivity L change that would occur as a result ofintended or anticipated changes or credible malfunctions that alter experiment position or configuration.
REACTOR OPERATING - The reactor is operating whenever it is not secured or shutdown.
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REACTOR OPERATOR (RO) - An individual who is licensed to manipulate the controls of a reactor.
REACTOR SECURED - A reactor is secured when:
(1) It contains insufficient fissile material or moderator present in the reactor 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 inserted or other safety devices are in shutdown position, as required by technical specifications, and
- b. The magnet power keyswitch is in the off position and the key is removed from the lock, and
- c. No work is in progress involving core fuel, core structure, installed
'; control rods, or control rod drives unless they are physically decoupled from the control rods, and
- 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.
I REACTOR SHUTDOWN - The reactor is shutdown ifit is suberitical 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, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.
READILY AVAILABLE ON CALL- Applies to an individual who:
(1) Has been specifically designated and the designation known to the operator on duty, and
- (2) Keeps ne operator on duty informed of where he or she maybe rapidly contacted (e.g., by phone, etc.), and I
(3) Is capable of getting to the reactor facility within a reasonable time under normal conditions (e.g.,30 minutes).
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L 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.
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.
SAFETY CHANNEL - A measuring or protective channelin the reactor safety;ystem.
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 restraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, 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.
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 pennission, neither a requirement nor a recommendation.
SHUTDOWN MARGIN - The minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical 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 subcritical without further operator action.
SURVEILLANCE TIME INTERVALS - The average over any extended oeriod for each surveillance time interval shall be closer to the identified rurveillance time than to the maximum ,
allowed time. e.e.. for the annual interval the averace shall be closer to 12 months than to 13 l months.
Biennial- once every 2 years (interval not to exceed 25 months)
Annual- once every 12 months (interval not to exceed 13 months) l Bi-annual- once everv 6 months (interval not to exceed 7 months)
Ouarterly - once every 3 months (interval not to exceed 4 months)
Monthly - once every 30 days tinterval not to exceed 6 weeks)
Any extension of these intervals shall be occasional and for a valid rease' and shall not affect the average as defined.
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- TRUE VALUE - The actual value of a parameter or variable.
- UNSCHEDULED SHUTDOWN - Any unplanned shutdown of the reactor caused by actuation 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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