ML20236D207
| ML20236D207 | |
| Person / Time | |
|---|---|
| Site: | 05000054 |
| Issue date: | 03/14/1989 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236D206 | List: |
| References | |
| R-081-A-025, R-81-A-25, NUDOCS 8903220527 | |
| Download: ML20236D207 (9) | |
Text
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sua . 'l 4 0 UNITED STATES I
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l NUCLEAR REGULATORY COMMISSION WASHINGTON, D, C. 20655
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l CINTICHEM, INC. ,
DOCKET NO. 50-54 g AMENDMENT TO~ FACILITY OPERATING LICENSE Amendment No. 25 License No. R-81 1
- 1. The Nuclear Regulatory Comission (the Comission) has found that: i A. The application for amendment to Facility Operating License No. R-81,. .
.filedbyCintichem,Inc.-(thelicensee),datedDecember 12, 1988, l complies with the standards and requirements of the Atomic Energy ;
Act of 1954, as amended (the Act), and.the Comission's regulations 1 as set forth in 10 CFR Chapter I; B. The facility will o)erate in conformity with the application, the provisions of t1e 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 Comission's regulations. set forth in 10 CFR Chapter I; D. The issuance of this amendment will not'be inimical to the comon 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 Comission'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).
8903220527 890314 I PDR ADOCK 05000054:
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- 2. Accordingly, the license is amended by changes to the Technical q Specifications as indicated in the enclosure to this license. j amendment,.and paragraph 2.C(2) of License No. R-81 is hereby J amended to read as follows: '
t (2) Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 25, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Charles L. Miller, 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: March 14, 1989 i
, ..p' ENCLOSURE TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. R-81 DOCKET NO. 50-54 Replace.the following pages of the. Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Pages Insert Pages 2 2.
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Reactor Secured: The reactor is secured when:
- a. The core contains insufficient fuel to attain criticality under optimum conditions of moderation and reflection, or
- b. The moderator has been removed, or
- c. (1) minimum number of control rods fully inserted as required by Technical Specifications, and (2) the console key switch is in the OFF pos' tion and the key is removed from the lock, and (3) 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 (4) no in-core experiments are being moved or serviced with a '
i reactivity worth exceeding the maximum value allowed for a single experiment or one dollar, whichever is smaller.
Reactor Safety System: The reactor safety system is a combination of safety channels and associated circuitry that forms the automatic protective system for the reactor, or provides information that requires the initiation of manual protective action.
Reactor Shutdown: The reactor is shut down when the negative reactivity of ,
the cold, clean core, including the reactivity worths of all experiments, is ;
equal to or greater than the shutdown margin.
Readily Available on Call: Readily available on call is applicable to an individual who (1) has been specifically designated and the designation has been informedmade knownhetomay of where the operator be rapidlyon duty, (2)(e.g.,
contacted keepsby the operator phone, etc.), on duty (3) is capable of getting to the reactor. facility within a reasonable time under normal conditions (e.g., I hour or within a 30-mile radius).
Reporting Interval: In all instances where the specified frequency is annual, the interval between tests is not to exceed 14 months; when semiannual, the interval should not exceed 7 months; when monthly, the interval shall not exceed 6 weeks; when weekly, the interval shall not exceed 10 days; and when daily, the . interval shall not exceed 3 days. ,
l Reportable Occurrence: A reportable occurrence is any of those conditions i described in Section 6.5.2 of these specifications.
Safety Channel: A safety channel is a measuring or protective channel in the reactor safety system.
Safety Limit: Safety limit is a limit on important process variables that is found to be necessary to reasonably protect the integrity of certain physical barriers that guard against release of radioactivity. The principal physical barrier is the fuel cladding.
Scram Time: Scram time is the elapsed time between the instant a limiting safety system setpoint is reached and the instant that the slowest control rod is fully inserted.
1 2 Amendment No. 25
i Secured Experiment: A secured experiment is any experiment,. experiment facility, or component of an experiment that is held in a stationary position l relative to the reactor core by mechanical means. The restraining forces must be substantially greater that those to which the experiment might be '
subjected by hydraulic, pneumatic, or other forces that are norral to the operating environment of the experiment or by forces that can arise as a result of credible malfunctions. I True Value: The true value of a process variable is its actual value at any instant in terms of the instrument reading.
1 Unscheduled Shutdown: An unscheduled shutdown is any unplanned shutdown of the reactor after startup has been initiated.
Untried Experiment: An untried experiment is an experiment or class of l experiments that has not been previously evaluated and approved by the Nuclear l Safeguards Committee.
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(1) )ower in NW (2) 1eight of water above the core
, Objective: The objective is to ensure that the integrity of the fuel cladding is maintained.
Specification: In the natural convection mode of operation (1) the safety limit shall be 6.7 MW I (2) the pool water level shall not be less than 20 ft above the top of the core.
Basis: -The analysis is given in Section A2 of Appendix 2 of the SAR. The homo-geneous' method of Gambill and Bundy (Final Hazards Summary Report, April 1977) used tion burnout in this inanalysis Oak Ridge has Reactor been emp(loyed ORR) andsuccessfully to predict High Flux Irradiation natural convec-Reactor.
(HFIR) fuel to be 6.7 MW. The former fuel is close in design to Union Carbide .
fuel. A safety factor of 1.24 is applied to account for random variations and uncertainties. A pool temperature near the high end of the operating range (120'F)isassumed. The safety system settings on power and pool level ensureadherencetothesespecifications'(seeSection2.2.2ofthese specifications). Maintaining a maximum power level during convection flow of 0.5 MW permits a significant safety factor between operation and burnout.
2.2 Limiting Safety System Settings 2.2.1 Safety Channel Setpoints in Forced Cooling Mode .
A) placability: This specification applies to the setpoints of the safety
. ciannels.
Objective: The objective is to ensure that automatic protective action is initiated to prevent a safety limit from being exceeded. .;
Specification: For operation in the forced cooling mode, the limiting safety system settings shall be j power level at any flow rate not to exceed 7.5 MW (nominal) coolant flow shall not be less than 1,800 gpm for powers above 250 KW pool level shall not be less than 20 ft above the top of the core Basis: Safety limits have been shown previously (Section 2.1.and SAR) to lie at a low flow-to-power ratio. To provide adequate assurance.that these limits are not a>proached too closely, the LSSS are chosen conservatively so-as to minimize t1e chance of boiling in the core. This results in a much larger flow / power ratio. In Section A3 of Appendix 2 of the SAR, power levels derived using conservative correlations for incipient boiling are tabulated for various values of pool temperatures and flow rates to '
illustrate the resulting temperature margins.
5 Amendment No. 25
' Coolant' flow rate and AT instruments allow the operator to calculate reactor-
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power and calibrate the neutron flux channels in terms of power.
Rod' position indicators show the operator the relative positions of control rods, and enable rod reactivity calibrations to be made.
Pool temperature information allows the operator to adjust the cooling system to keep pool temperature within a preferred range.
3.3.5. Safety Channels The minimum number and type of channels providing autcmatic action that are i required for reactor operation are given in Table 3.2. :
l Table 3.2 Minimum number, function, and operating mode of safety channels Operating-Minimum no. mode Channel- operable Function required
^
Pow E evel (normal) 2 Scram 9 7.5 MW All Power level (intermediate) 1 Scram 9 <3-sec period All Reverse 9 <10-sec period All f
' ' Inhibit 9 <30-sec period Al'1 )
a Startup Count rate l Inhibit 9 <2 cps-Inhibit 9 <30-sec period Startup i
Pool water level 1 Scram 9 <22 ft. All Pool temperature 1 Alarm 9 >120'F' All i b Scram 9 (1800 gpm Forced Coolant flow l .
cire.
Manual button 1 Scram All ;
Bridge lock 1 Scram All l
Guide tube lift 1/ rod Scram All Flapper valve 1 Scram (above 250 kW w/ All.
valve open)
Keyswitch 1 Scram All a
0perable below 50 W.
b Operable above 250 kW.
1 9 /m ndment No. 25 l i
4.0 SURVEILLANCE REQUIREMENTS Applicability: The requirements listed below genera,lly prescribe tests or inspections of systems and components.
Objective: The objective is to periodically verify that the performance of required systems is in accordance with specifications given above in Sections 2.0 and 3.0.
Specifications: The specifications are as follows:
4.1 Heasuring and Safety Channel Calibration A channel calibration of each measuring and safety channel shall be performed annually (see Sections 3.3.4 and 3.3.5).
4.2 Reactivity Surveillance (1) The reactivity worth of each control rod (including the regulating rod) and the shutdown margin shall be determined whenever operation requires a reevaluation of core physics parameters, or annually, whichever occurs first. The rod worth will be determined using the reactivity-period or rod-drop methods.
(2) The reactivity worth of an experiment shall be estimated, or measured at low power, before conducting the experiment.
(3) Boron carbide rods shall be gauged quarterly and any dimensional changes reported promptly to the Commission. Silver / indium / cadmium control rods shall be gauged annually, or, in the case of newly installed rods, at the end of the first 6 months. If any Ag/In/Cd or boron aluminum alloy rod does not meet the acceptance criteria, it shall be removed form service.
In addition, all other rods manufactured from the same batch shall be inspected.
4.3 Control and Safety System Surveillance (1) The scram time shall be measured annually. If a control rod is removed from the core temporarily, or if a new rod is installed, its scram time shall be measured before reactor operation. If the bridge is moved, the scram time will be measured before subsequent reactor operation.
(2) A channel test of each measuring channel in the reactor safety system shall be performed monthly or prior to each reactor operating period, whichever occurs first, unless the preceding shutdown period is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less. A channel test before startup is, however, required on any channel receiving maintenance during the shutdown period.
(3) A channel check of each measuring channel (except for the pool level) in the reactor safety system shall be performed daily when the reactor is in operation.
23 Amendment No. 25
. 5.5.3 Exhaust Duct Monitor (" Stack Monitor")
Air in the exhaust duct is continuously sampled for particulate; iodine and
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gaseous activities, each being read by separate detectors. The relative pro-portions of each type of activity can thus be determined. The results are indicated on chart records, with repeaters in the control room. Detection or indication of a~ release is not dependent on all three detectors being opera-tional, for any. release will have associated with it all three types of activ-ity or will affect each detector to some extent. When setpoints are exceeded, alarms are given at the monitor and repeated in the control room.
5.6 Fuel Storage 5.6.1 New Fuel 4 Unirradiated new fuel elements are stored in a vault-type room security area l equipped with intrusion alarms in accordance with the security plan.
Elements are stored upright in metal racks in which the separation between elements is a minimum of 2 in. With such an arrangement, subcriticality is assured (" Critical Experiments With SPERT-D Fuel Elements" (July 14,1965)).
5.6.2. Irradiated Fuel .
Irradiated fuel is stored upright under water'in the storage pool within-the reactor building in criticality-safe racks. Each rack accommodates 5E16 "Su elements Informationintowells Final with center-to-center Hazards spacing Summary Report" (Aprilof 6 in.28,1961)pplementary states that an I infinite number of elements so stored would be subcritical. Each well has a hole at the bottom to allow the water to circulate for cooling.
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30 Amendment No. 25 I