ML19256A202
| ML19256A202 | |
| Person / Time | |
|---|---|
| Site: | 05000113 |
| Issue date: | 10/12/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256A199 | List: |
| References | |
| R-052-A-013, R-52-A-13, NUDOCS 7811030228 | |
| Download: ML19256A202 (17) | |
Text
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UNITED STATES e 's.
'e NUCLEAR HEGULATORY COMMISSION 3 J,.
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W ASHING TON, D. C. 20555
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THE UNIVERSITY OF ARIZONA p0CKET N0. 50-113 AMENDMENT TO FACILITY LICENSE Amendment No.13 License No. R-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The' application for amendment by the University of Arizona (the licensee) dated July 14, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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 (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 Commission's regulations; 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 Commission'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).
7812.03o;g3
. Accordingly, the license is amended by changes to the Technical 2.
Specifications as ind:cated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility License No. R-52 is hereby amended to read as follows:
(2) Techni_ cal Sp_ecifi_ca_tions The Technical Specifications contained in Appendix A as revised through Amendment No.13, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This licente amendment is effective as of the date 'of its issuance.
3.
F6R THE NUCLEAR REGULATORY C0t@ilSSION g,/Wl ll' 0 e }*
O We Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: October 12, 1978 6
ATTACHMENT TO LICENSE AMENDMENT NO.13 4
FACILITY LICENSE NO. R-52 DOCKET N0. 50-113 Replace the following pages of the Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Replace Table of Contents, second page Table of Contents, second page 2
2 6
6 9
9 11 11 17 17 23 23 25 25 26 26 27 27 28 28 29 29 30 30 33 33 M
M 5.0 DESIGN FEATURIS 20 5.1 Reactor Fuel 20 5.2 Reactor ".uilding 21 22 5.3 Fuel Storage 6.0 ADMINISTRATIVE CONTROLS 23 6.1 Organization 23 6.2 Review 24 6.3 Operating Procedures 25 6.4 Action to be Taken in the Event a Safety Limit 26 is Exceeded
~ '6.5 Action to be Taken in the Event of a Repe table 27 l
Occurrence 6.6 Plant Operating Records 28 6.7 Reporting Ecquirements 29 6.8 Review of Experiments 33 Amendment No. 13
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.2-1.10 Experiment - An experiment is:
Any apparatus, device or material placed in the reactor core a.
region, in an experimental facility, or in-line with a beam of radiation emanating from the reactor, b.
Any operation designed to measure reactor characteristics.
1.11 Untried Exper,iment - An untried experiment is any experiment not previously performed in this reactor.
1.12 Ejgytrimental_ Facilities - Experimental f acilitics are the beam port, thermal columns, pneumatic transfer systems, central thidble, rotary specimen rack, beam tube, and the in-core f acilities.
1.13 Reportab1_ej0ccurrence - A reportable occurrence is any of the following: [
a.
Operation with any safety system setting 1 css conservative than specified in Section 2.2, Limiting Safety System Settings; b.
Violation of a limiting condition for operation; c.
An engineered safety system component failure which could render the system incapab1c of performing its intended safety function; d.
Release of fission products from a fuel element; An uncontrolled or uaanticipated change in reactivity greater than e.
$1.00; and f.
An observed inadequacy in the impica.catation of cither admin-istrative or procedura1
,trols, such that the inadequacy could have caused th_ existence or development of an unsafe condition in connection with the operation of the reactor.
1.14 Measured Value - The measured value of a process variable'is the value of the variabic as it appears on the output of a channel.
1.15 Measuring Channc1 - A measuring channel is the coibination of sensor, lines, amplifiers and output device which are connected for the purpose of measuring the value of a process variabic.
1.16 Kenetor Safety System - The reactor safety system is that combination of channels and associated circui try which forms the automatic protective system for reactor or provides information which requires manual protessive action to be initiated.
1.17
,0_pc_ rating - Operating means a component or system is performing its intended function in its normal manner.
1.18 Channel Check _ - A channel check is~a qualitative verification of acceptabic performance by observation of channel behavior. This verification shall include comparison of the channel with other independent channels-or methods mea,suring the same variabic.
Amendment No. 13
6-3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Applicability These specificat 'ns apply to the reactivity condition of the reactor, and the reactivit y worths of control rods and experiments, and apply for all modes o' acactor operation.
' Objective The objective is to assure that the rcactor can be shut down at all times and to assure that the fuel temperature safety limit will not be exceeded.
_ Specifications The reactor shall not be operated unicss the following conditions exist:
The shutdown margin referred to the cold' xenon-free condition is greater a.
than $0.50 with the highest work rod fully withdrawn and with the highest worth non-secured experiment in its most positive reactivity state.
b.
Any experiment with a reactivity worth greater than $1.00 is securely fastened so as to prevent unplanned removal from or insertion into the reactor; c.
The reactivity available to be inserted by the pulse rod shall be determined and limited by a mechanical block to a maximum of $2.50.
I d.
The reactivity worth of an individual experiment is not more than $3.00; The total of the absolute values of the reactivity worth of c.
all experiments in the reactor is less than $5.00; f.
A ramp or oscillating rod placed in the reactor 'cannot add more than $1.50 of reactivity nor can it add that amount at a rate exceeding $10.00 per second;
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Amendment No. 13
9-3 3 Pulse operatien_
Applicability te specifications apply to operation of the reactor in the pulse rede.
Oojective 2e objective is to pavent the fuel temperatum safety lir.it from being exceeded daring pulse rode operation.
Srecifications a
Ee mactor shall not be operated in the pulse rode unless, in addition to the mquimmnts of Secticn 31, the following con-ditions exist:
a.
Se trr.sient red is set such that the mactivity worth upon withdrawal is not smater than $2.50; and g
b.
Se tenperature of the fuel i=ediately prior to the pulse is essentially in equilibrium with the bulk water temperatum.
Eis is contmlied by limiting the reactor power prior to pulsing.
Basis te specifications 3.3.a and 3 3.b are based en Fig. A-4 fmm the SAR v.tich shows the reasumd raxir.um te:q,3ratum -of the fuel after a
$2.50 pulse to be approximately 500'C above the bulk pool temperatum, j and thus well below the 1000 C fuel safety critericn.
Amendment No. 13
. 3.5 Reactor Safety System Applicability This specification applies to the reactor safety system channels.
Objective The objective is to require the minimum number of reactor safety system channels that must be operable in order to assure that the fuel temperature safety limit is not exceeded.
Specification The reactor shall not be operated unless the safety system channels described in the following table are operable.
Minimum Operating Mode Nunber in which Measuring Channel Operable Function Required Reactor Power Level 2
scram Ste;dy State Mode Reactor Power Level 1
Prevent transient Pulse Mode rod withdrawal
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when power is
>10 kW Peak Reactor Power 1
Scram Pulse Mode Manual Button 1
Scram All Modes
'.mendment No. 13
. ~
'4.3 Reactor Safety System f, olicability Thic specification applies to the surveillance requirements for the censuring channels of the reactor safety system.
Objective The objective is to assure that the safety syste= will remain operable and will prevent the fuel temperature safety limit from being exceeded.
Specifications a.
A channel 'est of each of the reactor safety system channels
{
required in the operating mode to be followed shall be per-formed prior to each day's operation or prior to each operation extending more than one day.
b.
A diannel check of the power leve] measuring channels required in the operating mode to be followed shall be performed daily whenever the reactor is in operation.
A channel calibration by the calorimetric method shall be c.
made of the power level monitoring channels annually, but at intervals not to exceed 16 months.
Basis The daily tests and channel checks will assure that the safety channels are operable.
The annual calibrations and verifications will permit any long-term drift of the channels to be corrected.
Amendment No. 13
. 6.0 ADMINIST MTIVE CCSTROLS 6.1. Organization a.
The reactor facility shall be an integral part of the Nuclear Engineering Departe.ent of the College of Engineering at the University of Arizona as shown in the diag;ran below.
b.
The reactor facility shall be under the supervision of the Reactor Laboratory Head who shall have been qualified as g
a licensed senior operator for the reactor. He shall be respon-sible for assuring that all operations are conducted in a safe canner and within the limits procribed by the" facility license and the provisions of the Nuclear Reactor Committee.
c.
There shall be a Health Physicist responsible for assuring the safe'ty of reactor operations from the standpoint of radiation protection.
I College of Director of "E'"* #'"E Radiation Safety Dean i ____._.
__ _. I' 7
Department of l
Radiation Nuclear Engr.
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Safety Office i
l l
Reactor Committee l
l 1
i Reactor
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tJniversity
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- Y Health Physicist
. Head i
1 Rea 1or, J
Sspervisor I
j (Sr. Reactor Operator)
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__I Reactor l.
Operations Amendment No. 13
. 6.3 Operating Procedures Written procedures, reviewed and approved by the Reactor Conmittcc, shall be in effect and followed for the following itcas.
The procedures shall be adequate to assure the. safety of the reactor, but should not preclude the use of independent judgment and action should the situation require such, Startup, operation, and shutdown of the reactor.
a.
Installation or removal of fuel elements, control rods, experi-b.
ments, and experimental facilities.
c.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or component.e including responses to alarms,- suspt:ted primary coolan t, system leaks, and abnormal rear a, ty changes.
Emergency conditions involving potential or actual reicase of d.
radioactivity, including provisions for evacuation, re-entry, recovery, and medical support, Maintenance procedures which could have an effect on reactor c.
safety.
f.
Periodic surveillance of reactor instrumentation and safet; systems, area monitors and continuous air monitors.
Substanti re changes to the above procedures shall be made only with the approval of.the Reactor Committee. Temporary changes to the change their original intent cay be made with procedures that do not the approval of the Reactor Laboratory Head.
All such temporary l
changes to procedures shall be documented and subsequently reviewed
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by the Reactor Committee.
Amendment No. 13
- 26..
6.4 Action to_be Taken in the Event a Safety Limit is Exceeded In the event a safety limit is ?xceeded, or thought to have been exceeded:
The reactor shall be shut down and reactor operation shall not a.
I be resumed until authorized by the NRC.
b.
An inmediate report of the occurrence shall be made to the Chairman of the Reactor Conmittee and reports shall be made to the NRC in accordance with Section 6.7 of these specifications.
l A report shall be r:ade which shall include an analysis' of the c.
causes and extent of possibic resultant damage, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability-of recurrence.
This report shall be I
submitted to the Reactor Com.:ittee for review, and a similar report subaitted to the NRC when authorization to resume opera-g tion of the reactor is sought.
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Amendnent No. 13
6.5 Action to be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, as defined in Section 1.13 l
of the specifications, the f ollowing action shall be taken:
a.
The Reactor Laboratory Head shall be notified and corrective l
action taken prior to resumption of the operatior, involved, b.
A report shall be cade which shali include an analysis of the cause of the occurrence, efficacy of corrective action and reconmendations for measures to prevent or reduce the probability of reoccurrence.
This report shall be submitted to the Reactor Conmittee for review.
c.
A report shall be submitted to the NRC in accordance with
'l Section 6.7 of these specifications.
m Amendment No. 13
- 28 6.6 Plant Operating Records In addition to the requirements of applicable regulations, and in a
no way substituting therefor, records and logs shall be prepared and retained for a period of at least 5 years (except as otherwise specified in the Commission's regulations) of the following items, as a minimum:
a.
Normal plant operation; J
b.
Principal maintenance activities; c.
Reportable occurrences;
- d.. Equipment and component surveillance activities; e.
Experiments performed with the reactor; f.
Gaseous and liquid radioactive effluents released to the environs; g.
Of f-site environmental monitoring surveys; h.
Fuel inventories and transfers; 1.
Facility radiation and contamination surveys; j.
Radiation exposures for all personnel; and k.
Updated, corrected, and as-built drawings of the facility.
(Items f through k shall be retained for the life of the facility.)
m.
Amendment No. 13 s
3 6.7 Reporting Requirements In addition to the requirements of applicable regulations, and in
[
no way substituting therefor, reports shall be made to the NRC as folicws:
A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the a.
appropriate regional USNRC Office of Inspection and Enforcenent of:
Any accidental offsite release of radioactiv1ty above 1.
permissible limits, whether or not the release resulted in property damage, personal injury, or exposure; 2.
Any violation of a Safety Limit; and Any reportable occurrencesas defined in Section 1.13 3.
of these specifications in writing.
b.
A report within ten days (in writing to the appropriate regional USNRC Office of Inspection and Enforcement, with copies to the Director, Office of Inspection and Enforcement, USNRC, Washington, D. C.
20555 and to the Director, Office of Management and Program Analysis, USNRC, Washington, D. C.
20555) of:
1.
Any significant variation of measured values from a cor-responding predicted value of previously measured value of safety-connected operating characteristics occurring during operation of the reactor; 2.
Incidents or conditions relating to operation of the f acility which prevented or could have prevented the performance of engineered safety features as described in these specifications; Any reportable occurrences as defined in Section 1.13 of l
3.
these specifications; and 4.
Any violation of a Safety.imit.
A report within 30 days (in writing to the appropriate c.
regional USNRC Office of Inspection and Enforcement, with copies to the Director, Office of Inspection and Enforcement, USNRC, Washington, D. C.
20555 and to the Director, Office of Management and Program Analysis, USNRC, Washington, D. C.
20555) of:
Amendment No. 13
. 1.
Any substantial variance from performance specifications contained in these specifications or in the Safety Analysis Report; 2.
Any significant change in the transient or accident analyses as described in the Safety Analysis Report; 3.
Any changes in facility organization; and 4.
Any observed inadequacies in the implementation of administrative or procedural controls.
d.
A report within 60 days af ter completion of startep testing of the reactor (in writing to the appropriate regional USNRC Office of Inspection and Enforcement, with copies to the Director, Office of Inspection and Enforcement, USNRC, Washington, D. C.
20555) upon receipt of a new facility license, or an amendment to the licens authorizing an increase in reactor power level, describing the measured values of the operating conditions or characteristics of the reactor under the new conditions including:
1.
An evaluation of facility performance to date in comparison with design predictions and specifications; and 2.
A reassessment of the safety analysis submitted with the license application in light of measured operating character-istics when such measurements indicate that there may be substantial variance from prior analysis.
An annual report within 60 days following the 30th of June each c.
year (in writing to the appropriate regional USNRC Office of Inspection and Enforcement, with copies to the Director, Office of Inspection and Enforcement, USNRC, Washington, D. C.
20555) providing the following information:
1.
A brief narrative summary of (1) operating experience (including experiments performed), (2) changes in facility design, per-formance characteristics, and operating procedures related to reactor safety and occurring during the reporting period, and (3) results of surveillance tests and inspections; 2.
Tabulation of the energy output (in megawatt days) of the reactor, amount of pulse operation, hours reactor was critical, and the cumulative total energy output since initial criticality; Amendment No. 13 m
33 -
6.8 Revic,w of Experiments All proposed new experiments utilizing the reactor shall be a.
evaluated by the experiucater and the Reactor Committu. The evaluation shall be reviewed by a licensed senior operator of the facility (and the llealth Physicist when appropriate) to assure compliance with the provisions of the utilization license, the Technical Specifications, and 10 CFR 20.
If, in his jud;-
ment, the experiment meets with the above provisions and does not constitute a threat to the integrity of the reactor, he shall s ubmi t it to the Reactor Supervisor for scheduling or to the Reactor Conmittec'for final approval as indicated in Section 6.2 above.
L' hen pertincat, the evaluation shall include:
1.
The reactivity worth of the experiment; 2.
The integrity of the experiment, including the effects of changes in temperature, pressure, or chemical composition; 3.
Any physical or chemical interaction that could occur with the reactor components; and 4.
Any radiation hazard that may result from the activation of catcrials or from external beams.
b.
Prior to the performinc of an experiment not previously performed in the reactor, it shall be revieued and approved in writing by the Reactor Committee. Their review shall consider the follouing information:
1.
The purpose of the experiment; 2.
A procedure for the performance of the experiment; and 3.
The evaluation approved by a licensed senior operator.
c.
For the irradiation of materials, the applicant shall submit an
" Irradiation Request" to the Reactor Supervisor who shall have been qualified as a licensed senior operator for the reactor. This request shall contain information on the tarbet material including the amount, chemical form, and packaging.
For routine irradiations (which do not contain nuclear fuel or known explosive materials and which do not constitute a significant threat to the integrity of the reactor or ->
the safety of individuals) the approval for the Reactor Committee may be made by the Reactor Supervisor.
Amendment No. 13
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