ML20023A850
| ML20023A850 | |
| Person / Time | |
|---|---|
| Site: | 05000142 |
| Issue date: | 10/08/1982 |
| From: | Wegst W CALIFORNIA, UNIV. OF, LOS ANGELES, CA |
| To: | Thomas C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8210200081 | |
| Download: ML20023A850 (10) | |
Text
.
UNIVEllSITY OF CALIFOllNIA, LOS ANGELES UCLA menu m nms inmr un m.n o . an ansmr so num - su e nm nw I sminimas smu ntz 2567 Boelter Hall
$CllOOLOF ENGINEEHING AND APPLIED SCIENCE
[Ds ANGEL.E%, CAlHORNIA 9p24 October 8,1982 Mr. Cecil 0. Thomas, Acting Chief Standardization & Special Projects Branch Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-142 License No. R-71
Dear Mr. Thomas:
The attached pages which bear the amendment date Oct. 10,1982 are to amend the UCLA license renewal application of February 1980. The pages are to replace the similarly numbered pages in the application which can then be removed.
The amended page 5 of the body of the application reduces the permissible inventory of reactor fuel to less than 5000 gms of U-235 (- 93% enriched).
In an unrelated change, amended pages V/3-4 and V/3-6 alter the purpose and function of the Safety High Level Radiation Monitor as stated in the Technical Specifications of the application. The instrument was origin-ally procured and installed in November 1980, in anticipation of the pos-sibility that hold-up tanks would be installed at the facility. The pur-pose was to detect an accidental or premature blow-down of the tanks to the stack, and for that reason the detector was located in the stack.
The hold-up tanks were not installed, and the instrument can now be more usefully employed to detect an unusual level of radiation that might oc-cur'in the reactor room from, for example, a dropped fuel element. The monitor will sound an alarm alerting the reactor room occupants to a po-tential emergency.
Five additional pages hereby amended to correct typographical errors are (III/A, V/5-3, V/6-10) or to improve clarity (V/l-3, V/3-3).
8210200081 P l0W ,
l Nt' CLEAR ENERGY LABORATORY IVAN CATTON, DIRECTOR l l
l
With respect to the amendment reducing the permissible quantity of fuel, note that the amendment is made in response to your letter of Sept. 27, 1982 which referenced Commission policy on the use of HEU, and of which we were only recently made aware.
I hope that those amendments will meet with your approval.
Sincerely, WFW ^
Walter F. Wegs Director, Reseach & Occupational l Safety '
l l
e
1 APPENDIX III ARGONAUT SAFETY ANALYSIS REPORT (ASAR)
Attachment A Analysis of Credible Accidents for Argonaut Reactors NUREG/CR-2079-PNL-3691 Battelle Pacific Northwest Laboratory Richland, Washington April 1981
[ incorporated by this reference]
III/A retyped 10-10-82
A. Secured Experiment. Any experiment, experiment facility or component of an experiment is deemed to be secured, or in a 3ecured position, if it is held in a stationary position re-lative to the reactor core.
B. Movable Experipent. A movable experiment is one which may be inserted, removed, or manipulated while the reactor is criti-cal.
C. Untried Experiment. An Untried Experiment is a single experi-ment or class of experiments that has not been previously eval-uated and approved by the Reactor Use Committee.
1.14 EXPERIMENT FACILITIES l An Experiment Facility is any structure, device or device or pipe system
! which is intended to guide, orient, position, manipulate, control the j environment or otherwise facilitate a multiplicity of experiments of
- similar character.
1.15 CONTROL R0D A Control Rod is a semaphore-type blade fabricated with cadmium as the neutron absorbing material which is used to compensate for fuel burnup, temperature, and poison effects. A control rod is magnetically coupled to its drive unit allowing it to perform the safety function when the magnet is de-ene: gized.
1.16 READILY AVAILABLE ON CALL q Readily available on Call means an individual who:
A. has been specifically designated and the designation known to the operator on duty, B. keeps the operator on duty informed of where he may be rapidly contacted (e.g., by phone, etc.),
C. is capable of getting to the reactor facility within a reason-able time under normal conditions (e.g., I hr. or within a 30 mile radius).
1.17 R00 DROP TIME 4
Rod Drop Time is the elapsed time between the instant a limiting safety system set point is reached and the instant that the rod is fully in-serted.
1.18 DROP-ROD SCRAM (or simply SCRAM) i All four. control rods fall by gravity into the core. Cooling water cir-cul a tion' continues .
V/1-3 retyped 10-10-82
Channel No. Operable Function Count Rate la Inhibit @ < 2 cps Core Water Level 1 Scram @ < 45 in.
Primary Coolant Flcw lb Scram @ < 10 gpm Manual Button 1 Full Scram c
Keyswitch I Scram b
Closures 6 Full Scram > 1 watt Notes: a. Operable below 0.02 W and bypassed above.
- b. May be bypassed at power levels below I watt.
- c. Loss of console power causes full scram l
3 . 2. 3.1 Bases The power level scram provides redundant automatic protective action to e revent exceeding 125% of the license limit on reactor power.
! The period scram, assisted by the intermediate rod inhibit, limits the rate of increase in reactor power to values that are controllable with-out excessive power levels or temperature. These functions are not limiting safety system response.
The inhibit on the count rate channel prevents inadvertent criticality during cold startup that could arise from lack of source neutrons and the neutron instrument response.
Reactor core low pater level scrams the reactor. This scram also pre-vents startup unt1' the minimum core water level is reached.
If the primary coolant outlet temoerature exceeds 180 F, a high tempera-ture alarm annunciates at the control room annunciator panel.
The coolant flow scrar ensures adequate coolant flow to prevent boiling in the core.
The keyswitch scram prevents unauthorized operation of the reactor.
Bypass is permitted on non-power parameters for experiments, tests, and special purposes only [ refueling].
V/3-3 retyped 10-10-82
^
3.3 RADIATION MONITORING SYSTEMS The minimum acceptable radiation and annunciating instrumentation re-i quired for reactor operation is as follows:
Max. Alarm M No. Operable Setpoint Function Safety high level 1 25 mR/hr Detect high radia-radiation monitor tion in reactor room Sound alarm audible in reactor room Exhaust Duct 1 1.8 x 10-5 Alarms with dis-Monitor (" Stack pCi/ml* plays in the con-Monitor") trol room
- In the event that the limits for Argon 41 contained in 10 CFR Part 20, Appendix B, Table II, with a reduction factor of 460 are exceeded in the stack, the ventilation fans shall be shut down and the automatic damper system closed to limit natural circulation from the reactor room to the external environment and the reactor is automatically scrammed.
Fixed Area Monitors 2 5 mR/hr Detect radiation (gamma) in key lo-cations; alarm in control room Evacuation Switch 1 ---
Alarm to initiate evacuation sequence (manual)
NOTE: For maintenance or repair, required radiation monitors may be re-placed by portable or substitute instruments for periods up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the function will still be accomplished. Interruption for brief periods to permit checking or calibration is permissible.
3.3.1 BASES The radiation monitoring system components are located and have set points to ensure that 10 CFR Part 20 requirements are not exceeded for restricted and unrestricted areas.
V/3-4 retyped 10-10-82 i
{ _ - - - - _ _
~. _ .
3.4 ENGINEERED SAFETY FEATURES These specifications apply to required equipment for the confinement of activity through controlled release of reactor building air to the at-mosphere.
3.4.1 SAFETY HIGH LEVEL RADIATION MONITOR 3.4.1.1 Specification See 3.3 3.4.1.2 Bases
~
This monitor senses excessive radiation in the reactor room and automa-tically sounds an alarm in the reactor room.
3.4.2 CONFINEMENT SYSTEM 3.4.2.1 Specification A. The exhaust fan shall have a capacity of 14,000 CFM and shall maintain a negative pressure in the reactor building and an exhaust rate from the reactor room greater than 8000 CFM.
l B. The high bay ventilation exhaust and intake fans are inter-locked to shut off simultaneously when the ventilation system is shut down.
4 C. Spring loaded, air operated damper motors automatically close the intake and exhaust dampers.
D. All doors to the reactor high bay shall be normally m1 sed while the reactor is operating. Transit is not prohn ,ced under proper supervision.
The safety rods shall automatically scram when the ventilation E.
fan is shut down.
3.4.2.2 Bases To effect _ controlled release under normal conditions of gaseous activi-i ty present in the building atmosphere, a negative pressure is required
, so that the air flow to the reactor room is non-radioactive air from
" cold" areas in the building. This serves to dilute reactor room am-bient air prior to discharge, and to prevent the flow of reactor room l air out of the reactor room to other parts of the building. Under emer-l gency conditions, the reactor room dampers will close, and the reactor will be scrammed.
V/3-6 retyped 10-10-82
5.3.2.4 Neutron Source for obtaining reliable neutron information necessary to startup from a cold shut-down condition, a radium-beryllium neutron source is perma-mently installed.
5.3.3 R0D CONTROL SYSTEM 5.3.3.1 Shim (Control) Rods Three control rods are provided for the control of core reactivity.
These rods are cadmium-tipped magnesium (see 4.3.4). Individual inte-gral worths vary from about $2.40-$2.70, depending on position and in-dividual characteristics. The rods are coupled to drive shafts through electromagnetic clutches that allow release of the rods within 12 ms after receiving a scram signal. Position indicators on the control con-sole show the extent of withdrawal for each rod. To limit the rate of reactivity increase upon startup, the rod drive speeds are limited to 7.7 c/sec. and only one rod can be withdrawn at time. These rods are l not otherwise automatically controlled, but are used to compensate for l seasonal and long-term reactivity changes.
5.3.3.2 Regulating Rod i One regulating rod is provided to aid in fine control and maintenance of constant reactor power for long periods. The rod is limited to a total worth of about $1.30 and can be either manually or servo-controlled.
The drive speed is approximately 1% (of full range) per second. In the commonly used range, this amounts to approx.matalv $0.03/second.
I i
V/5-3 retyped 10-10-82
i I
B. Any of the following:
- ' B .1 a violation of the Technical Specification or the facili-ty license; 1
B.2 an unanticipated or uncontrolled reactivity change in ex- '
cess of $0.90 or total reactivity in excess of $3.00; B.3 an uncontrolled or unanticipated release of radioactivity from the site; B.4 a safety system component malfunction or other system or component malfunction which renders or threatens to ren-der the safety system incapable of performing its intended safety function; B.5 an observed inadequacy in the implementation of either ad-ministrative or procedural controls, such that the inade-quacy causes or could have caused the existence or devel- l opment of an unsafe condition with regard to reactor oper-ation; B.6 abnormal degradation of reactor fuel as revealed by perio-dic inspection;
! B7 if the power level exceeds 135 kw.
6.5.3 WRITTEN REPORTS A written report within 30 days to the Commission of:
A. Permanent changes in the facility organization structure; B. Significant changes in the transient or accident analysis as described in the Safety Analysis Report; C. Substantial variances of safety related operating character-istics from previously predicted or measured values.
V/ 6-10 retyped 10-10-82
5
- ** N (iii) Foreign Relationships
- The applicant is in no way owned, controlled, or dominated by an alien, a for-eign corporation, or foreign government.
(4) Agent: The applicant is not acting as the agent or repre-sentative of another in filing this application. The ap-plicant is the principal party.
- e. Class of license applied for:
Class 104 license
! Use to which the facility will be put:
The reactor and its. supporting laboratories will be used for the education of senior undergraduate and graduate students in nuclear engineering and related sciences. In i addition to formal courses and demonstrations, the reactor l will be used to support research at the M.S. and Ph.D !
l evels .
Period of time for which license is requested:
Twenty (20) years, or until March 30, 2000.
Other licenses applied for in connection with this facility:
Special fluclear Material: (1) Less than 5000 gms of en-l riched U-235, and (2) 32 gms of Pu-239 as a Pu-Be sealed neutron source.
i f. Financial qualifications of the applicant:
. This item is treated in Appc.7 dix I " Financial Qualifica-tions."
- g. Deleted
- h. tiot applicable 4
, i, flot applicable i j. tio restricted data or defense information is contained in this
! application or in any material offered in support of this appli-cation.
l l
retyped. 10-10-82 i
__