ML20033F053
| ML20033F053 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 02/21/1990 |
| From: | IOWA STATE UNIV., AMES, IA |
| To: | |
| Shared Package | |
| ML20033F049 | List: |
| References | |
| NUDOCS 9003150325 | |
| Download: ML20033F053 (11) | |
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PAGE REVISIONS FOR TECHNICA'.-SPECIFICATIONS c::' ; ;-
1 Revision Set # 1
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.. t REACTIVITY LIMITS - Those limits imposed on reactor core excess reactivity.
Quantities are referenced to a Reference Core Condition.
o REACTIVITY WORTH OF AN EXPERIMENT - The eaximum absoiute value of the reactivity change that would occur as a result of intended 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.
REACTOR OPERATOR (RO) - An individual who is licensed to manipulate the controls of a reactor.
REACTOR SECURED - A reactor is secured wher,:
(1) It contains insufficient fissile material or moderator present in the reactor to attain criticality under optimum availible 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 l
. required by technical specifications, and
- b. The magnet power keyswitch _is in the off position and the key-L -
is removed from the lock, and
- c. No work is in progress involving core fuel, core structure, L
installed control rods, or control rod driver. unless they are physically decoupled from the control rods, and I'
- 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 t single experiment or 0.763%
Ak/k whichever is smaller.
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(rev1,2/21/90) 1-3 r
a REACTOR SHUTDOWN - The reactor is shutdown if it 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, 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 i
(2) -Keepe, the operator on duty informed of where he or she may be rapidly contacted (e.g., by phone, etc.), and (3)
Is capable of getting to the reactor facility within a reasonable time under nor.nal conditions (e.g., 30 minutes).
. REFERENCE CORE CONDITION - The condition of the core when it is at ambient temperature (cold) and the ree.ctivity worth of xenon is negligible, less than 0.23%Ak/k.
REGULATING R0D - A low-worth control rod used primarily to maintain an intended power level that'does not have scram capability.
Its position may be f
varied manually or by the servo-controller.
SAFETY CHANNEL - A measuring or protective channel in the reactor safety system.
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SAFETY-TYPE R00 - 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.
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. 3.0 LIMITING CONDITIONS FOR OPERATION.
3.1 Reactor farg Parameters t
3.1.1 Applicability These specifications apply to the prameters which describe' the reactivity condition of the core, a
'3.1.2.0bjective To ensure that the reactor can not achieve prompt criticality and that it.can be. safely shut down under any condition.
3.1.3 Specifications ll IThe-reactor shall not be made critical unless the following conditions-
' exist:
I:
'A. The total core excess reactivity with or without experiments shall not exceed 0.50% Ak/k.
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l B. The minimum shutdown margin provided by control rods in the.
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reference core co6dition shall~ not be less than 0.35% Ak/k.
C. The fuel loading pattern and experiment apparatus inserted in the.
core shall' be approved by the Reactor Use Committee.
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3.1.4 Bases Specifications A and B are based on values used in the power transient analysis (SAR: 6.3) where it is assumed that all-of the excess reactivity, (rev 1, 2/21/90) l 3-1 I
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0.50% Ak/k, is suddenly inserted as a positive step function.
The safety system response 1:, assumed to result in the minimum shutdown margin, 0.35% Ak/k, being supplied by rapidly inserted safety-type control rods,
- assuming the rod with the greatest worth is not available.
. Specification C limits the changes in core configuration to those
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appcoved by the committee charged with review. and approval 'of experiments.
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vf 3.0 LIMITING..?.[f,^NSFOROPERATION(Continued) 3.2 ReaEtor Control and Safety System 3.2.1 Applicability These specifications apply to the reactor safety system and safety-related instrumentation.
3.2.2 Objective
~ To specify the lowest acceptable level of performance or the minimum N
number of. acceptable components for the-reactor safety system and safety-related instrumentation.-
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'3.2.3~ Specifications The' reactor shall not be made critical unless the following conditions exist:
l-l A. The reactor safety' channels and safety-related measuring channels L
shall be operable.in accordance with Table 3-1, including the minimum number of channels and the indicated maximum or minimum setpoints.
B. All three safety-type control rods shall be operable and have the following response time capabilities:
-(1)
Delay time shall not exceed 100 milliseconds.
.(2)
Drop time shall not exceed 600 milliseconds.
C. The reactivity insertion rate for a single control rod shall not L
exceed 0.019% Ak/k/sec.
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3.0 LIMITING CONDITIONS-FOR OPERATION'(Continued)
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3.8 Exoeriments 3.8.1 Applicability These specifications a;, ply to the experiments installed in the reactor.
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and its experiment facilities.
3.8.2 Objective p
To prevent damage to the reactor and excessive release of radioactive j
material in the event of experiment failure, and to avoid exceeding any safety.
l limit.
o 3.3.3 Specifica'tions l
Experiments installed in the reactor shall meet.the following conditions:.
L A. Prior to initiation, each type of experiment utilizing the-reactor shall be approved by the Reactor Use Committee.
B. Operational limits peculiar to an; experiment shall be included in instructions to the reactor operator.
C..The reactivity worth of any single experiment, or group of experiments, installed in the core-shall be limited to
-0.48% Ak/k to +0.14% Ak/k.
1 D. Significant amounts of special materials used in experiments, includingtfissionable material, explosives or metastable materials capable of significant energy release, or materials that are corrosive to reactor components or highly reactive with i
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.. i Jthe coolant,_ shall conform to established special requirements.
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E. Credible failure of-any experiment shall _ not result in releases or exposures in excess of established limits nor in excess of the annual limits established in 10 CFR Part'20.
l F. Experiments shall be designed so that' they will not contribute to -
the failure of other experiments, core components, or principle physical barriers to uncontrolled release of. radioactivity.
Also, no credible reactor transient.shall cause an experiment to fail in such a way as to contribute to an accident..
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3.8.4 Bases 4
'i' Specification A, B,-0, E, and F are based:on requirements stated in the' standard for The Development of Technical Specifications for Research 3
Reactors,-ANSI /ANS-15.1-1982.
Specification C is-based on the effect of the failure on an experiment, or' group of experiments, on the reactivity of the reactor.
In the case-of an experiment failing with +0.14%'Ak/k inserted as a step function, j
I the resulting~ period would be 30 seconds, which-can be easily managed:with control rod movement.
If the -0.48% Ak/k step insertion occurs because of y
experiment failure, the reactor excess reactivity would drop to 0.02% Ak/k, an amount sufficient to maintain criticality.and to continue operation if necessary.
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- 5.0 DESIGN FEATURES (Continued) 5.3_ Reactor Core f.ufl 104 Safety System Core A graphite reflector surrounds the core tanks, 'except a water reflector of no less than 13 cm thickness is maintained above the fuel assemblies during reactor operation. The composition of the region between the core tanks (the coupling region) can be changed by removal of graphite
. blocks and insertion of other materials, and small-volume experiments can be placed in the water gap between plates in' the fuel assembly, or in the water reflector above or beneath the fuel, subject to specifications 3.8.3 (Experiments).
A rabbit tube, no larger than 10 cm outside diameter, penetrates the graphite reflector at the west face of the north core tank. A neutron source, providing a minimum of 1.0 E+6 neutrons /second is inserted into the coupling region by means of the source positioner during the startup
- operation (Ref: Drawings Rl-E-154 and R1-E-161).
4 Fuel
~ Reactor fuel is contained in aluminum-clad flat plates, similar to q
argonaut-type fuel.
Fuel meat is U S1, enriched to 19.75% in the U-235 3 2 isotope, dispersed in aluminum to achieve a umium density of 3.47 g/cc. : The fuel meat, 0.51 mm thick, is clad with 0.38 mm alumiram.
Each fuel plate
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contains~12.5 grams of U-235. The core contains 12 assemblies each with E'
approximately 24' fuel plates depending upon the measured critical-configuration.
Solid aluminum plates and assemblies with missing fuel plates, j
for experimental purposes, are used to adjust the core fuel-loading for the licensed excess reactivity of 0.50% Ak/k. (Ref: Drawing Rl-A-121-1) 4 (rev1,2/21/90) 5-5 I
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- a. A licensed reactor operator in the control room.
- b. A licensed' senior reactor operator readily available on call.
- c. A health physics-qualified individual readily available on call.
(2) Events requiring the direction of a senior reactor operator:
- a. Recovery from unplanned or unscheduled shutdown (in this instance, docuuented verbal concurrence from a SR0 is required).
- o. Fuel transfer operations.
- c. Any maintenance activity involving the reactor safety system that could cause a significant increase in the reactivity of the l
reactor.
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- d. Relocation of any in-core experiment with a reactivity worth greater than 0.763% Ak/k.
(3) Event requiring the presence of a health physics-qualified individual:
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- a. Fuel transfer operations, b.-Installation, changing locations, or removal of an experiment that l-involves removal of a si:teld plug or closure.
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- c. Any maintenance activity involving the reactor _ safety system that could cause an abnormal release of radioactive materials.
f-L 6.1.4 Selection and Training of Personnel The selection, training and requalification of operations personnel shall meet or exceed the requirement of American National Standard for Selection and Training of Personnel for Research Reactors, ANSI /ANS-15.4-1977, or its successor, and be in accordance with the Requalification Plan approved by the Nuclear Regulatory Commission.
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. 6'.6'.2 Special Reports t
(1)~ There will-be a be a report not later than the following working day by telephone to the appropriate NRC Regional Office and
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H confirmed in writing by telegraph or similar conveyance to the appropriate NRC Regional Office with a copy to the Director of Inspection and Enforcement to be followed by a wr.itten report that describes the circumstances of the event within 14 days of any of L
th~e following:
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- a. Violation of safety limits (see 6.5.1).
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- b. Release of radioactivity from the site above allowed limits i
(see6.5.2).
- c. Any of the following (see 6.5.2):
(1)
Operation with actual safety system settings for required'
-systems less conservative than the limiting safety system settings specified in the Technical Speci.fications e
L' (ii)
Operation in violation of limiting conditions for operation established in the Technical Specifications unless prompt remedial action is taken.
(iii)
A reactor safety system component-malfunction which renders or could render the system incapable of performing its intended safety function unless the ralfunction or-condition is discovered during maintenance tests or periods of reactor shutdown.
(iv)
An unanticipated or uncontrolled' change in reactivity greater than:the licensed excess reactivity, or.
I 0.763% Ak/k, whichever is smaller.
(v)
Abnormal' and significant degradation in reactor fuel, or cladding, or both, or coolant boundary which could result in exceeding prescribed radiation exposure limits of personnel or environment, or both.
(vi).
An observed inadequacy in the implementation of i
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