ML20101F618
| ML20101F618 | |
| Person / Time | |
|---|---|
| Site: | 05000199 |
| Issue date: | 12/19/1984 |
| From: | MANHATTAN COLLEGE, RIVERDALE, NY |
| To: | |
| Shared Package | |
| ML20101F604 | List: |
| References | |
| NUDOCS 8412270242 | |
| Download: ML20101F618 (67) | |
Text
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Rev. 3 16.0 ' TECHNIC AL SPECIFICATIONS FOR THE MANHATTAN COLLEGE ZERO POWER REACTOR Dr. Jih-Perng~ Hu Bro Gabriel Kane, FSC Dr. Ronald S. Kane Revision 3 Decembe r 19, 1984 P
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Rev.3 Revision Record Revision No. Comment 0- Submitted to U. S. N. R. C. on August 26, 1983 as part of the Safety Analysis Report for the MCZPR
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Complete revision submitted on January 12, 1984 I 2 Complete revision submitted on November 15, 1984 3 Revisions as noted on pages 16-1,-16-2, 16-10,.16-11, 16-13, 16-16, 16-23, 16-25, ,and 16-28,on December 19, 1984.
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TABLE OF CONTENT _S_
Contents Page No.
Title Page 16-1 Revision Record 16-2 Table of Contents 16-3
- 1. O DEFINITIONS 16- 4 2.'O SAFETY LIMITS AND LIMITING 16 8 SAFETY SYSTEM SETTINGS
- 3. O LIMITING CONDITIONS FOR OPERATION 16 10
- 4. 0 ' SURVEILLANCE REQUIREMENTS 16 25
- 5. O DESIGN FEATURES 16 35
- 6. O ; ADMINISTRATIVE _ CONTROLS 16-53 Table 3-1, Safety System 16- 13 Figure 5-1, Cutaway of MCZPR Facility 16-36 Figure.5-2, Plan of First Floor of MCZPR 16-37 Figure 5-3, Plan of Second Floor of MCZPR 16-38 Figure 5-4, Grid Plate Stand (Plan View) 16-42 Figure 5-5, Grid Plate Stand (Section View) 16-43 Figure 5-6, Grid Plate 16-44 Figure 5-7, Lucite Holddown Rod 16 45 Figure 5-8, Fuel Element 16 47 Figure 5-9, Control Rod Assembly 16 49 Figure 5-10, Rod Drive Mechanism 16-50 Figure 6-1, Table of Organization 16-54 16-3 L
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- 1. O DEFINITIONS
! The. terms Safety Limit, Limiting Safety System Setting, and
, Limiting Condition for Operation are as defined in paragraph 50,36
. of -10 CFR Part 50.
channel - A channel is, the: combination of sensor, -line, amplifier and
' output devices which are conne'eted for the' purpose of measuring the.value of a parameter.
- channel' test - A channel test is the' introduction of a signal into the channel for verification that it is' operable, channel calibration - A channel calibration is an adjustment of the channel' such that its-output corresponds with acceptable accuracy to known values
. of the parameter which the channel measures. Calibration shall encompass
.the entire chainnel, including equipment actuaition, . alarm, or trip and
'shall be deemed to include a channel test.
- chann'el check - A channel check is a qualitative verification of acceptable -
performance by observation of channel behavior. This verification, where
. possible, shallinclude comparison of the channel with other independent channels or.-systems measuring the same variable.
control' rod - Plates fabricated with neutron absorbing material 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 fuel elements, the source, and the control rods, delayed neutron fraction -- When converting betw'een absolute - and dollar-value reactivity units, a beta of 0.00645 is used.
. drop time - The elapsed time between reaching the complete remo. val setpoint and the full insertion of a safety-type rod. (It must be less than
- 1. 0 second).
excess reactivity - Excess reactivity is that amount of reactivity that would exist if all control rods (control, regulating) were moved to the maximum reactive condition from the point where the reactor is exactly critical (K,gg = 1).
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y experiment - Any object, other than a fuel element or handling tool, which is inserted into the volume formed by projecting the grid plate vertically to the tank pool water surface is to be regarded as an experiment in the core, measured value, _- The measured value is the value of a parameter as it appears on the output of a channel.
. 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 . pool water.
- operable - Operable means a coraponent or system is capable of performing its intended function.
operating - Operating means a' component or system is performing its intended function, reactivity limits,- The reactivity limits are those limits imposed on reactor core excess' reactivity. For the MCZPR the reactivity limits are
- 0. 44% A k/k (0. 68 $ ) at 110. 6 F.
reactivity worth of an experiment - The reactivity worth of an experiment is the maximum absolute 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.
q reactor operator - (RO) - An individual who is licensed to manipulate the controls of a reactor, reactor safety systems - Reactor safety systems are 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.
reactor secured - A reactor is secured when:
- 1) It contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality under optimum available conditions of moderation and reflection, or 16-5
- 2) 1 A combination of all of the following
a)- All neutron absorbing control rods are fully inserted and other safety devices are in shutdown position', as required by the technical specifications, and b)v The console key switch 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 devices unless they are physically decoupled from the control rods, and d) No experiments are in or near the reactor.
reactor shutdown - The reactor is shut down if it is suberitical by at least one dollar in the reference' core condition and the reactivity worth of all
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experiments is accounted for, reference core condition - The condition of the core when the pool water
. temperature is between 60 F and 800 F.
r_egulating rod - A low-worth control rod used primarily to. maintain an intended power level. Its position may be varied by operator action.
research reactor - A research reactor is defined as a device designed to support a self-sustaining neutron chain reaction for research, development,
-educational, training, or laboratory ' purposes, and which may have provisions for the production of radioisotopes.
reverse trip -
' The electronic setting' within the console instrumentation which willinitiate a reverse system which will drive in an electromagnet when certain_ specified limits are exceeded.
. safety-type rod -
A rod.that can be rapidly inserted by cutting off the
. holding current in its electromagnetic clutch. This applies to both control rods, scram time - The time for the control rods (shim, regulating) acting under the force of gravity to change the reactor from a critical to a suberitical condition. This will be equal to or less than the drop time.
scram trip,- The electronic setting within the console instrumentation which will activate scram circuits when certain specified limits are exceeded.
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- senior reactor operator (SRO) An individual who is licensed to direct the activities of a Reactor Operator (RO) and to manipulate the controls
- of a- reactor.-
shall, 'should and'may ,
The, word "shall" is used to denot'e a requirement :
the word "should" to denote a' recommendation: and the word "may" to denote permission, neither a requirement nor a recommendation.
shutdown margin L Shutdown margin shall mean' the minimum shutdown reactivity necessary to provide confidence that the reactor can be made suberitical 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.
1 unscheduled shutdown - An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuatio'n of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not including shut-downs which occur during testing or check-out operations.
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' 2. 0 - SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.N Safety Limits
. The Manhattan' College Zero Power Reactor (MCZPR) shall not operate at a ' steady power level in excess of 0. I watt. No other S afety Limits need be specified since convective cooling is not required for this power level. This power level is sufficient to satisfy the educational and training purposes of the MCZPR.
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- 2. 2 - - Limiting Safety System Settings (LSSS)
- 2. 2.1 ' Applicability This specification applies to the setpoints of safety channels.
- 2. 2. 2- -Objeetive
- To assure that automatic trip action is initiated and that the operator is warned to take protective action to prevent a safety limit from being exceeded.
- 2. 2.' 3 Specifications The limiting safety system settings are the following:
A. The maximum steady state power level trip setpoints shall not exceed O. I watt.
B. When performing the high flux tests, the transient power. level trip setpoints, shall not exceed O.18 watt.
2.~ 2. 4 Bases The trip setpoints provide adequate margins for the limits of operation. Both trip setpoints, A and B,-initiate automatic scrams.
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- 3. O LIMITING CONDITIONS FOR OPERATION 3
3.' !! . Reactor Core Paramete rs
, 3. l.-l Applicability l
These specifications apply to the parameters which describe the reactivity condition of the core.
3.1,2 ' Objective To ensure that the reactor cannot achieve prompt ;
criticality.and that it can be safely shut down under any condition.
3.1. 3 Specifications The re' actor shall not be made critical unless the following conditions exist:
A. The total core excess reactivity with or without the movable experiments of section 3. 8. 3 shall not exceed O. 44% Ak/k (O.68$ ).
B. The minimum shutdown margin provided by control rods in the reference core condition shall not be less than 0.90% Ak /k (1. 40 $).
C. The lower limit of water resistivity based on the requirements for the corrosion protection system shall be set at O.1 Megaohm-cm.
.r There shall be no upper limit for the water resistivity.
D.
Any change in the experimental apparatus shall be approved by the Reactor Operations Committee.
3.1. 4 Bases Specification A is based upon the experimentally determined value for excess reactivity 0. 44% Ak/k (0.68$) at a reactor pool water temperature of 110. 6 F.
Specification B is based upon the negattve worth or tne regulating rod; that is, the control rod with the smaller negative wor th.
' Specification C provides the minimum resistivity of water in the reactor tank. If the water resistivity is less than this level of 0.1 Megaohm-cm, the resin bed in the deionizer is re placed. The resistivity of the water has little or no bearing on the corrosive effects experienced or possible other than i
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- to offer'some guarantee that catalyzing anions are excluded from the system. In the. absence of the other protective mechanisms that are in place, corrosion will occur regardless
- of the resistivity of the water. The supplemental protective
- device selected for use is a dynamic cathodic protection system operating at 10 volts and an expected current density of 25 to 50 milliamps. The lower limit of 0.1 Megaohm-cm has been selected to allow this system to provide an electron -
saturated barrier layer over the entire internal surface of the tank thus preventing the development of any galvanic L cells as a result of discrete areas becoming anodic.
' Specification D limits the changes in theexperirnental apparatus to those approved by the committee charged with review and approval of experiments.
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- 3. 2 Reactor Control and Safety System 3.' 2.1 Applicability These specifications apply to the reactor safety system and safety-relat ed instrumentation.
3.2,2 Objectives To specify the lowest acceptable. level of performance or the -
minimum number of acceptable components for the reactor -
safety system and safety-related instrumentation.
3.2.3 Specifications The reactor shall not be made critical unless the following conditions exist:
A. The reactor safety system shall be operable in accordance with Table 3-1.
B. There shall be two safety-type control rods:
A regulating rod with a negative worth of 0. 90% Ak/k (1. 40$)
and a shim rod with a negative worth of 2. 50% Ak/k (3. 88$).
C. The drop time for either safety rod should not exceed 1. 0 second: measurements of rod drop times shall be made once per semester.
D. The reactivity insertion rate for a single rod shall not exceed O. 10 % Ak /k ( 154$) per second.
3.2.4 Bases Specification A provides assurance that the reactor safety system which may be needed to shut down the reactor is operable. Each feature of the system is described in Table 3-1.
Specification B provides assurance that the reactor can be operated safely at the critical state because these negative
-worths make it possible to shutdown the reactor rapidly.
Specification C provides assurance that both reactor safety rods can be fully inserted into the core to decrease the power level within 1.0 second.
Specification D assures a safe rate of power change during startup and during power ascensions.
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l Rev. 3 Table 3-1 Safety Syste_m The following circuits shall be functioning whenever fuel is in the reactor and power is available to the control drives.
1 Scram Circuits A scram system shall be provided that will cause interruption of the magnet current to the electromagnets supporting the control rods whenever a scram trip is exceeded. Power to the magnets shall be available when the " reactor on" switch is on and there are no scram trip signals. A scram trip shall be provided for each of the conditions below, with the trip setting as specified.
- a. High neutron flux - Count Rate Channel electronic trip set for 125% or less of Full Power (Full power shall be equal to 0. I watt).
- b. High neutron flux - Linear Channel electronic trip set for 125% or less of Full Power.
- c. High gamma activity - high level signal from either of the two Gamma Channels electronically set for 10mR/hr or less,
- d. Manual scram - operates upon actuation of the manual scram button on the console.
- e. Low water level - operates when the' tank water level drops o'n e foot below the tank full position. Tank full position is defined as seven feet above the bottom of the reactor vessel.
- f. Reactor key switch off - operates when the " REACTOR ON" switch is turned to the off position,
- g. Power failure - operates whenever the power. supply to the console or to the nuclear instrumentation fails.
2 Reverne Circuits A reverse system shall be provided that will cause both control rod drives to drive the control rods into the reactor vvhenever a reverse trip is exceeded. The reverse action shall override any rod selection made by an operator and shall persist as long as a reverse trip is exceeded. Reverse trips shall be provided for each condition as below with the trip setting as specified:
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. Table 3-1 Safety System _.(continued)
- a. A Count Rate Channel reverse' trip shal1~ occur for any of Ethe following conditions:
'(1) Count Rate recorder off.
(2)' Count -Rate recorder down scale - shall occur when the recorder indicates less than 2 counts per second.
-(3)' Count Rate recorder up scale - shall occur when the recorder indicates greater than 50,000 counts per
.second,
- b. Linear Channel reverse trip'shall occur for any of the following . conditions:
(1). Linear recorder off.
_(2) - ' Linear recorder down scale - shall occur when the linear recorder is less than 5% .of full scale.
(3) Linear recorder up scale - shall occur when the linear r'ecorder is greater than 95% of full scale,
- c. Gamma Chann'el reverse trip shall occur for any of the following conditions:
(1) Gamma recorder off.
- (2) Gamma record'er down scale - shall occur when the recorder indicates less than 0. 2 mR/hr.
(It should be noted that the minimum reading on the
' recorder is 0. I mR/hr while the minimum reading
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dn the instruments on the Gamma Channels for Area . ,
4 Radiation Monitoring is . Ol' mR/hr ).
(3)_ Gamma recorder up scale . shall occur when the recorder indicates greater. than 95 mR/hr.
- d. '
Any scram condition shall cause the control rod drives to drive in the electromagnets.
!' -e.. Manual run-in-trip 'shall occur upon actuation of the "Run-In" switch on the control console.
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- 13. Bypass in Safety Systems The only bypasses in the scram or reverse circuits shall be those
- described below. - The bypasses shall be key operated switches located on the console.
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' Table 3-1 Safety System (continued)
- a. A bypass to eliminate a-reverse-as a consequence of the -
gamma recorder being down scale may be utilized
- during startup until the gamma recorder. reads on scale.
- b. A bypass to eliminate a reverse as a consequence of the linear ~ recorder being down scale may be utilized in the initial fuel loading while conducting experiments to determine suberitical multiplication.
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~3.' 3 . Coolant Condition Because of the low value of the maximum steady power
-: level (O. I watt), . no recirculating cooling equipment or -
- systems are required other than the pool of water maintained in the reactor tank. The pool water is basically.used as the moderator to' slow down the fast neutrons; however. due to its large quantity and enormous heat capacity, the pool .
~ water can also be used to dissipate heat from the reactor Core.
' 3. 3.1 Applicability This specification applies to the coolant condition of the pool water in the reactor tank.
3.3,2 Objective This specification insures that all the heat being generated in the reactor core can be dissipated by the pool water.
- 3. 3. 3 Specifications The maximum heat capacity of the pool water shall be 65 MJ/ C, with a minimum water level requi ement of ~
-seven feet as measured from the tank bottom. The minimum heat capacity of the pool water shall be 56 MJ/0C, with a water level of six feet.
- 3. 4. Bases
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This specification provides assurance that the pool water, a
. due to its large quantity and enormous heat capacity relative to the low steady power level (O. I watt), can completely remove and dissipate heat in the reactor tank.
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- 3. 4 Confinement or Containment No operations requiring confinement or containment are performed with the MCZPR.
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- 3. 5 . Ventilation System
- 3. 5.1 Applicability This specification applies to the ventilation system within the MCZPR room.
3.5.2 Objective To ensure that the air in the reactor room is always clean
. 'and free of dust.
3.5.3 Specifications A. The MCZ.PR Laboratory shall contain a forced circulation venti 1' a tion system consisting of a blower and associated duct work. There shall be no connection between this system-and any other part of the building.
B. A switch shall be provided in the reactor. room to turn the ventilating system on and off.
3.5.4 Bases Specification A shows that the ventilation system is indeper. dent of the building.
Specification B provides assurance that the ventilation system is controllable.
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'F : 3. 6 Emergency Power -
No emergency. power is supplied to the MCZPR. In the -
event of power failure while the reactor is operating, a :
scram trip shall occur.
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~ Radiation Monitoring Systems -
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. 3. 7.1- Applicability Thes'e specifications apply to the radiation monitoring systems and to the limits on the radiation detection level of each channel.
~3. 7. 2 Objective To specify the minimum number of acceptable components or -
the lowest acceptable level of performance for the radiation monitoring systems.
- 3. 7. 3 ' Specifications
_ - A. Two radiation monitoring channels shall be provided to measure gamma intensity. These channels shall also be used to monitor reactor operation and shall be used in the reactor safety system'as described in Table 3-1. Each channel consists of a Gamma Detector and Gamma Indicator Unit.
A common strip chart recorder shall be provided with a selector switch for recording the output of either channel.
- B. ~ Each Gamma Detector shall be a sealed unit containing a Geiger-Mueller tube, ' transistorized count rate amplifier, and check source. The output from the Detector shall be logarithmic with respect to the radiation level. The check source shall be exposed to the Detector by a solenoid which is actuated by a pushbutton on the control console.
-C. One of the Detectors (Gamma-1) shall be located on the reactor. platform directly over the core area while the other Detector (Gamma 2) shall be mounted on the side of the reactor tank.
D. The Gamma Indicator shall contain the power supply for the system, the alarm reset check source control, and the output connector for the Dete' c tor. Also contained on the front of the Indicator is a logarithmic meter relay for indication and alarm of the gamma level. The alarm shall be set to give audible annunciation whenever the
. radiation level exceeds 6mR/hr for Gamma 1 and 10 mR/hr for Gamma 2 E. The range of both detectors shall be from . 01 to 100mR/hr.
The system shall be designed so that if the radiation intensity is greater than 100mR/hr. the detector shall indicate full scale, 16-20 L
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3.7.4 Bases Specification A provides the functions and components of two radiation monitoring channels and provides' assurance-that these two channels can also be used as safety-related channels.
Specification B provides the composition of each detector and provides assurance that each detector can function well
- by using the check source.
Specification C provides assurance that radiation in both radial and axial directions can be detected. .
Specification D provides assurance that the safety alarm system will'be activated when radiation exceeds the allowable limit.
Specification E provides the range and design configuration of the monitoring system.
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- 3. 8 Expe riments '
. 3, 8.1 Applicability
^ These specifications apply to the experiments installed .
in the reactor.
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- 3. 8, 2 Objective To prevent damage to the reactor and release of radioactive material in the event of experiment failure,'and to avoid exceeding any safety limit.
3.8.3 Specifications Limitations on experiments and material irradiations in the reactor shall meet the following conditions:
-A. No experiment shall be installed in the reactor in such a location that any part of the apparatus will touch or in any way interfere with the action of the control rods.
- B. No experiment shall be installed in the reactor that can shadow the nuclear instruments, thereby giving erroneous or unreliable information to the reactor operator.
.C. No experiment which has explosive properties shall be irradiated.
D. Experiments containing materials whose release to the water could result in a violent chemical reaction (e. g.
Sodium) or would result in chemical or corrosive attack to the reactor components (e.g. Mercury) shall not be irradiated.
E. Experiments containing materials whose release could result in overexposure of personnel to gaseous or particulate q radioactivity shall not be irradiated.
F. Each experiment, other than laboratory exercises defined in
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Item G shall receive the specific approval of the Reactor Operations Committee. In addition, all operations leading to the production of more than one millicurie of any radioisotope outside of fuel elements shall receive the approval of the Reactor Operations Committee.
G. (
Laboratory exercises - The following laboratory exercises ~, while not requiring the presence of a Reactor Supe rvisor, require the presence of a Reactor Operator.
Laboratory exercises involving use of experiments (other than experiments used in the following exercises) shall be 16-22
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- Rev. 3 conducted in th'e presence of a Reactor-Supervisor.
L. Startup rnd Operation of Manhattan College Zero Power Reactor; ' Approach to Criticality 2 Critical Mass Determination
- 3. Reactor Period and Reactivity 4 Void Coefficient Measurement 5 Flux ~ Distribution in the Manhattan College Zero Power Reactor 6 Determination of Buckling 7; . Measurement of Diffusion Length and Age 8 . Temperature Coefficient of Reactivity
- 9. Gamma Ray Energy Spectrum in the Vicinity of the~ Reactor Core
-p H. A maximu'm of seven aluminum covered indium foils with a combined maximum negative reactivity of -1,113 X 10-4 Ak/k may be used in a laboratory exercise (Flux Distribution in the MCZPR). A void with a maximum negative worth of -10. 4 X 10-4ak/k may also be used in a-laboratory exercise (Void Coefficient Measurement).. l I. A record of each materialirradiation shall be included in the reactor log. The rec.ord shall include at least the following data:
Mate rial irradiated Position in core Reactor Power Irradiation time, time in, time'out Dose rate on contact at time of removal Supervisor's signature 3.8.4 Bases Specifications A, B. C,' D, E, F, and I are based on require-ments stated in the Standard for The Development of Technical Specifications for Research Reactors,' ANSI / ANS -15,1 - 1982.
Specification G lists all the laboratory exercises that have been performed with the MCZPR for teaching and training purposes. There are no limiting conditions for these exercises except item 5 - Flux Distribution in the.MCZPR.
With regard to Specification H, for the laboratory exercise involving the irradiation of the seven indium foils, the reactor is always scrammed before these foils are ~ removed. Also,
.in the. laboratory exercise for determination of the void coefficient, both control rods are fully inserted before the rod is fully removed, j 16 -23 i
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-3.9 Facility SpeciCc LCO No limiting conditions for operations (LCO)'mique to the facility other than those lirted above are necessary.
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- 4. 0 SURVEILLANCE REQUIREMENTS Surveillance tests, except those specifically required for safety when the reactor is shutdown, may be deferred during reactor shutdown; however, they must be completed prior to reactor startup 4.1 Reactor Core Parameters 4.1.1 Applicability These specifications apply to the surveillance activities required for reactor core parameters.
4.1. 2 Objective s These requirements give the frequency and type of testing to assure that the reactor core parameters conform to the specifications of section 3.
4.1. 3 Specifications A. Total core excess reactivity shall be checked immediately after any change in the core configuration. All core configura-tion changes shall have prior approval by the Reactor Operations Committee and the Nuclear Regulatory Commissic.n.
B. The. shutdown margin shall be checked at leact semi-annually by comparing the two control rod positions during the laboratory exercise of Approach to Criticalit y (see 3. 8. 3, G.1).
C. The water resistivity shall be measured and recorded during each checkout procedure.
D. Any change in the experimental apparatus shall be approved and documented by the Reactor Operations Committee.
4.1. 4 Bases Specification A provides assurance on the core excess reactivity.
The measurements and tests required in specifications B, C, and D are sufficient to provide assurance that the reactor core parameters are as specified in 3.1. 3, B, C, and D.
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- 4. E ' Reactor Control and Safety System -
- 4. 2; 1 Applicability ,
- These specifications apply to the surveillance activities required for the. reactor control and safety system. ;
4.2,2 ' Objective J To specify the frequency and type of testing or calibration to
. assure that the reactor control and safety system conforms to the specification of section 3 of these Specifications.
4,2.3 Specifications A. It is' assumed that the worth of the control rods remains unchanged. However, the relative worths of the control rods
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shall be checked annually by comparing the criticality positions of the control rods with the criticality positions of previous years.
B. The rod withdrawal speeds shall be measured at least twice
- a year, and shall be such that the maximum speed is no greater than 12 inches per minute in the MCZPR.
C. The operability of the control rods and driving mechanism "
shall be tested daily when the reactor is operating.
D. An operability test,' including trip action, of each safety channel
-listed in Table 3-1 that provides a scram function shall be .:
completed prior to each reactor startup following a period when the reactor has been secured for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or '
at least weekly during continuous operating periods. .
E. A calibration of the channels listed in Table 3-1 shall be performed at least annually and whenever any maintenance on a channel which may affect its performance is completed.
4.2.4 Bases Specification A provides assurance that relative worths of the control rods will be checked annually.
The rod withdrawal and insertion time measurement intervals required in specification B verify the limits in specification 4
3.2. 3 D and are appropriate to detect abnormal performance.
Specification C verifies the operability requirements in specification 3. 2. 3 C during each day of operation, 16 -26 k
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y In specification D each channel capable of generating a, scram signalis tested during the pre-critical procedure, prior to startup, so that the conditions of specification 3.2.3 A are satisfied.
. Specification E requires calibration of safety and safety-related channels at an interval which is appropriate and justified by prior experience at this facility.
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- 4. 3 Coolant Condition There is no coolant or coolant system in this facility other than the pool water.
- 4. 3.1 Applicability This specification applies to the surveillance activities required for the rea ctor coolant condition.
- 4. 3. 2 . Objective These requirements specify the frequency and type of testing-to assure that the coolant condition conforms to the speci-fication of section 3. 3.
4.3.3 Specifications A. The pool water sampling analysis shall be performed by the Health Physicist. The result of the sampling analysis shall be reviewed by the Reactor Operations Committee.
B. The water level in the reactor oool shall be maintained at - seven feet from the tank bottom and shall be checked and recorded every day that the reactor is operated.
4.3.4 Bases Specification A provides assurance on the quality of the pool wate r.
Specification B provides assurance on the amount of pool water in the reactor tank.
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- 4. 4 Confinement or Containment There is no confinement or containment system.
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- 4. 5 Ventilation Systems
- 4. 5.1 Applicability This specification applies to the surveillance activities required for the reactor ventilation system.
' 4. 5. 2 Objective To specify the frequency and type of testing to assure that the ventilation system conforms to the specifications of section 3. 5 of these Specifications.
- 4. 5. 3 Specification The blower and switch of ventilation system shall undergo testing fdr normal operation at least once per year.
4.5.4 Bases This specification requires that the blower and switch of ventilation system be tested to verify that they can be operated when needed. The testing interval is adequate to verify operability, based on experience at this facility.
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- 4. 6 Emergency Power This specification does not apply to this facility since there is no emergency power supply.
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' 4. 7 Radiation Monitoring System *
- 4. 7.1 Applicability These specifications apply to the surveillance activities required for the radiation monitoring system.
4.7.2 Otjective To n,pecify the frequency and type of testing to assure that the radiation monitoring system conforms to the specification of section 3. 7 of these Specifications.
4.7.3 Specifications These'surve111ance activities are required for safety.
A. A calibration of the two radiation monitoring channels shall be performed at least annually and whenever any maintenance on a channel which may affect its performance is completed.
' This calibration shall be performed by comparing the readings of these instruments with those on a portable beta-gamma survey meter. The latter shall be calibrated annually by a recognized diagnostic laboratory.
B. An operability test, including source checks, of the radiation monitoring channels shall be performed at least quarterly (and recorded in the reactor checkout sheets).
C. Readings of the radiation levels of allinstruments shall be recorded hourly during operation with the reactor being c ritical.
D. The environmental film badge and smear surveys in and around the reactor enclosure shall be performed at least twice a year.
E. An ALARA program shall be established and monitored l by a Radiation Safety Officer (RSO).
4.7.4 Bases ,
Based on experience at this facility and the average usage pattern of the reactor, specifications A-E are adequate to verify that the operations conform to the specifications of
- 3. 7. 3. The usage pattern will be subject to review by the Reactor Operations Committee, 16-32
y
- J >
E 4, 8 Expe riments
- 4. 8.1 - Applicability These specifications apply to the surveillance activities required for experiments installed in the reactor.
4.8.2 ~ Objective To specify the frequency and type of testing to assure that the experiments conform to the specifications of section
- 3. 8 of these Specifications.
4,8.3 Specifications A. The identification and location of all installed experiments shall be recorded prior to each reactor startup.
B. . Other specific surveillance activities shall be established during the review and approval process specified in section 6. 0, 4.8.4 Bases-Specification A requires that the reactor operator verify that the installed experiments are approved.
Specification B recognizes that detailed surveillance require-ments will vary among experiments, and that the Reactor O perations Committee specifies the appropriate type and frequency of surveillance.
16-33
- 4. 9 Facility Specific Surveillance No Facility Specific Limiting Conditions for Operations are provided in section 3. 9, 16 34
r ,
e 5 5. 0 DESIGN FEATURES
- 5. I- Site and Facility Description The Manhattan College Zero Power Reactor (MCZPR) is located in the Leo Engineering Building of Manhattan College at 3825 Corlear Avenue, Bronx, New York.
The laboratory. room where the reactor is located is considered a restricted area as defined in paragraph
- 20. 3(a), 14, of 10 CFR 20.
The principal activities carried on within the site are those related to the educational program of Manhattan College. The reactor may be utilized in this program for instructional use and may be used in laboratory exercises for teaching and training purposes.
The Leo Engineering Building of Manhattan College is a four story, brick building providing space for Engineering and Science Laboratories. The building provides classrooms, computer facilities, and laboratories for an estimated 1800
- students at any one time, as well as office space for the Dean of the School of Engineering, chairmen, and faculty members using the building.
The laboratory housing the Manhattan College ZPR is completely separated from the remainder'of the Reactor Laboratory as shown in figure 5-1 Security locked doors provide the only access to the Reactor Laboratory,
- The MCZPR laboratory has the following penetrations:
- a. Electrical conduits
- b. Air circulation system
- c. Door (secured with locks and a security system)
- d. Window (sealed with plywood)
The MCZPR is located in the laboratory as shown in figures 5-2 and 5-3. The reactor tank rests on a concrete slab in the first floor and extends upward through the second floor. The first floor, room housing the reactor has concrete walls extending from the floor to the ceiling on three sides and a metal partition from the retainer wall to the ceiling on the fourth side. The 16-35 l
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only access to the reactor from the first floor is through1 a metal door which penetrates the metal partition as shown in figure 5_-2 . The metal door is kept locked at all times when there is fuel in the reactor. The only unlocked access to the first floor of the MCZPR room when fuel is in the reactor is from the second floor through a trap door in the
~
reactor platform and down a vertical steel ladder adjacent ~
' to the reactor. tank 'as shown in figure 5-3 The reactor platform is-located on the 'second floor above the tank whenever fuelis located in the reactor. The platform is surrounded by a link fence to prevent personnel from inadvertently approaching the open areas in the platform.
In addition to the concrete walls extending from floor to ceiling on three sides of the first floor room housing the reactor, a concrete be rm has been constructed on the fourth' side sufficiently. high to contain all the water in the reactor p tank.
The window to the MCZPR Laboratory has a window guard that 1
has been seated to prevent unauthorized entry into the room.
The door into the facility is locked whenever a reactor operator is not in attendance in the room.
During times when an operator is not in attendance in the MCZPR Laboratory, the MCZPR Laboratory is under electronic surveillance.
The reactor vessel consists of a cylindrical aluminum tank eight feet high and ten feet in diameter. The tank wall is one L
quarter of an inch thick. ' The only tank wall penetration is a 3/4 inch diameter aluminum coupling located near the tank bottom with a 3/4 inch diameter short nipple and a 3/4 inch aluminum gate valve. The inlet to the domineraliser is connected to this gate valve. The outlet of the demineraliser feeds into a pipe which rises vertically and forms a gooseneck loop over the edge of the tank.
!' The reactor vessel is located as in figure 5-2 and is held in place by five aluminum brackets welded to the sides of the tank near the bottom. These brackets are bolted to the concrete floor.
l 16-39 i
- 5. 2 Reactor Coolant System There is no reactor coolant or coolant system other than the reactor pool.
16-40
r w
- 5. 3 ~ Reactor Core, Fuel, and Safety System-
' 5.3.l. Reactor Core A grid plate stand as shown in figures 5-4 and 5-5 is welded to the bottom of the reactor tank.
A grid ' plate is bolted to the grid plate stand. The design of the plate including attachments thereto are as shown in figure 5-6, Fuel element hold down rods are threaded into the grid plate unless an approved program requires their removal. The holes in the support cylinders for the in-core fuel elements are plugged.
~ The shafts of tiiese hold-down rods are made partly of aluminum and partly of lucite as shown infigure 5-7
.The lucite portion consists of a solid rod one inch in diamete r. The threaded base of the hold-down rod is made
~
of aluminum tubing having a one eighth inch wall thickness.
The broad top of the hold-down rod, which extends over the
. top of the fuel element is also made of aluminum. The aluminum portions of the hold-down rod are securely fastened to the lucite by aluminum pins and epoxy cement.
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- 5.3.'2 Re acto r' F6el -
The design of a fully loaded element is as shown on figure 5-8. The fuel portion of such elements consists of six concentric cylinders formed by mechanically joining and positioning eighteen curved fuel plates within grooves
- of 3 ' spacer webs. .The fuel plates are mechanically held on -
- the grooves by roll bonding: the bonding provides joint strengths of at least 200. pounds per linear inch. The fueled
_ portion of the element is 24 inches long and is located within
~
a 1/8 inch thick, 3. 51 inch OD support cylinder which is 37 inches long. The support cylinder extends 6-1/2 inches beyond the fueled region on either end; this axial position is maintained by 3 plug welds joining the spacer webs and the support cylinder. _ Three lugs are provided on the inside of
~
the suppo'rt cylinder at each end. ~ At one _ end, these lugs position the cylindrical fuel element in the slots in the
" positioning lug" attached to the grid plate and at the other end are used to mate with a fuel handling tool. Partially loaded elements, except for the number of fuel plates,- ~are .
designed in accordance with this paragraph.
t
-The cylindrical fuel plate _ consists _.of 0. 020 inch thick U- Al alloy of 92% enriched uranium, clad on both sides with 0. 015 inches of aluminum making the total plate thickness-0. 050 inches. The nominal U-235 content of each full fuel element-
. is 200 grams. The inner diameter of the innermost cylinder is about 1. 25 inches and the spacing between adjacent cylinders (water channel width) is 0,118 inches. A maximum of 15 fuel elements plus one partial fuel element, which may.
have.some fuel plates missing, is used in the facility. - The _-
weight of a complete fuel element is 4. 505 kg, and the weight of the' partial fuel element is 2. 527 kg.
In each full fuel element, the weight percent of U-235 is 4. 45% ,
and in the partial fuel element , the weight percent of U-235 is 0.95%. These are percentages of the entire element including
, the uranium-aluminum alloy,' the aluminum casing, and the n aluminum cladding.
S
, 16-46
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Figure 5-8, Fuel Element 16-47
5.- 3.' 3 ' ' Reactor Safety System The. critical assembly is controlled by two Y-shaped control blades which pass in the clearance between adjacent fuel elements. Construction details and dimensions are as shown i n. figure 5-9. One. control rod (the shim rod) is constructed so that the blades ~are formed by sandwiching a 1/16 inch sheet of _ cadmium between 1/16 inch layers of ' stainless steel.
- The other control rod _is an all stainless ' steel regulating rod.
Either one of these.contro1 rods-is capable of preventing the
~
reactor from becoming critical.
Each control blade is guided by a guide assembly for the full length of the control rod stroke. These guide assemblies prevent any bearing of the control bla' des on the fuel elements.
The' guide assemblies, which are positioned on the grid by pins, ralso act as sway bracing for the guide tubes. Details -
of the guide assembly, the methods for positioning on the grid plate, and the method for connection to the guide tube are as shown in figure 5-10. The guide _ tube is bolted at the upper end to the control rod drive units.
Each control rod is attached to its associate'd drive mechanism by an electromagnet and falls by gravity to the.
least reactive position upon decrease of magnet current as a result of scram action. . A system is provided to give indication at the control console that a control rod is in contact with the magnet.
A reactor platforta is located over the reactor tank on the.
second floor of the ZPR laboratory. The platform is bolted to the concrete floor of this room. The neutron and gamma-ray detectors are suspended from this platform. The control rod drive mechanisms as shown in f'igure 5-10 are bolted to the structural members of the reactor platform.
The control rod drive system is designed in accordance with these
, _ specifications. Each control rod drive system is a cantilever drive with a design drive speed no greater than 12 inches' per minute. -Rod motion is controlled from the console by individual momentary contact toggle switches having an IN-OFF-OUT selection. Driving the control rods. into the core by a reverse action as described in section 3. 2.3 vverrides any manual selection. . Each drive also has position indication from the " full-in'.' to the " full-out" position.
16-48
~ ~
END PIATE i
ICATING PIN' CCCROL ROD CONTROL ROD GUIDE GUIDE nlBE FIANGE' #
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1 CO.NTROL ROD GUIDE SECTION B-B SECTION A-A SECTION C-C Figure 5-9, Control Rod Assembly 16-49
- RACK HOUSING g LIMIT SWITCH w
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Figure 5-10, Rod Drive Mechanism 16-50
The position. sensing element is a potentiometer located in each' rod drive mechanism. Coarse position readout is provided on the control console in the form of two indicators reading from 0% (full-in) to 100% (full-out). The system
- indicates' rod position with an accuracy of 2%. A fine position indication system is also provided to indicate rod position with an accuracy of 0.1%.
The control console for the reactor is located as shown on figure 5-1. The control console contains all the necessary-switche s,. lights, . and indicating instrumentation required to operate the reactor. . Motion of the control rods out'of the reactor is possible only by actuation of console control swit che s. A moderator demineralizer system is located on the first floor of the MCZPR laborato ry. The system is a
. closed _ loop containing a pump and demineralizer. The flow rate through the demineralizer bed is valve controlled to be between 5 and 20 gallons / min /ft2, The startup source is a Pu-Be source encapsulated in tantalum. The minimum source strength is one (1) curie (approximately 106neutrons per second).
F 16-51 l'
lhi' rp ta t
, 5. 41 ' Fissionable Material Storage Fissionable' Material Storage Fuel elements are permanently stored on the reactor grid plates-with the exception that three-fue1~ plates are= permanently stored in a locked steel container fastened to the floor of the first floor:of the MC ZPR: Laborato ry, 1
I
+
4 e
i 16-52
- 6. 0 ' ADMINISTRATIVE CONTROLS L 6.1 Organization 6.1.1 Structure The organization for the management of the reactor _ facility shall be _ structured as shown in figure _6.1. Levels of authority indicated divide responsibility as follows:
Level 1: Responsible for the facility license and site administration.
Level 2: Responsible for the reactor facility operation and management.
Level' 3: Responsible for daily operations The Reactor Operations Committee shall be appointed by the Reactor Administrator and shall be responsible to him for the review and evaluation of all proposed operations and procedures in order to insure that the reactor facility shall be operated in a safe and competent manner.
6.1. 2 Re s ponsibility
. Individuals at the various management levels shown in Figure 6-1, in addition to having responsibility for the policies and operation of the facility, shall be responsible for safe-guarding the public and facility personnel from undue radiation exposures and for adhering to all requirements of the Operating License and the ~ Technical Specifications.
In all instances, responsibilities of one level may be assumed by designated alternates, or by higher levels, conditional upon appropriate qualifications.
The detailed description of duties of each individual in Level 2-and Level 3 are as follows:
A. The Reactor Administrator will provide final policy decisions on all phases of reactor operation and on regulations for the facility as a whole. _ He will be advised in all matters concern-ing the safe operation of the reactor by the^ Reactor Operations Commititee. The Reactor Administrator shall be responsible for the overall administration and supervision of the reactor 16 -:, _
MANHATTAN COLLEGE CORPORATION BOARD OF TRUSTEES Level 1 l
l PRESIDENT OF THE COLLEGE l l
l EXECUTIVE VICE PRESIDENT l l
l PROVOST l l
lDE AN OF THE SCHOOL OF ENGINEERING l REACTOR ADMINISTRATOR Level 2 RADIATION RE ACTOR OPER.ATIONS SAFETY OFFICER COMMITTEE l HEALTH PHYSICIST l CHIEF REACTOR SUPERVISOR Level 3 l REACTOR SUPERVISORS l f
REACTOR OPERATOR Level 4 CLERICAL STAFF, MAINTENANCE AIDES, ASSISTANTS PERSONNEL Figure 6-1, Table of Organization 16-54
4
, facility. He shall appoint qualified members to the Reactor Operations Committee from time to time as necessary 'He:shall designate Reactor Supervisors,
-name the Chief Reactor Supervisor, and appoint.the Radiation Safety Officer. The Reactor Administrator.
shall approve and promulgate all regulations, instructions.
.and-procedures governing the operation of the reactor facility.
The Reactor Administrator shall be appointed by the Provost of Manhattan College.
B. The Reactor Operations Committee shall be responsible to the Reactor Administrator for the review and evaluation of all proposed operations and procedures in order to insure that the reactor facility shall be operated in a safe and competent manner. - Particular emphasis shall be placed on the examina-
~
tion of new and untried operations and procedures, and the Committee shall take action on proposed new experiments.
The Committee shall review and evaluate all proposed changes in the reactor system. The Reactor Operations Committee shall advise on and be . available for advice and assistance on any problems relative to the safe operation of the reactor facility.
C. The Radiation Safety Officer shall be responsible for the promulgation and enforcement of rules, regulations and operating procedures which conform with the regulations set-
~
forth in 10 CFR, Part 20. The Radiation Safety Officer in conjunction with the Reactor Operations Committee shall approve suggested procedures for the purchase, possession, storage, use ,and disposition of all radioisotopes, consistent with general or specific licenses for use of by-product material' j- issued to Manhattan College. . The Radiation Safety Officer in conjunction with the Reactor Operations Committee, shall be available for advice and assistance on problems involving -
1 radiological safety arising from the operation of the reactor
, facility. The Reactor Operations Committee shall evaluate
[ and. approve all proposed procedures leading to the production of radioisotopes with a half life longer than one (1) hour. All
- operations leading to the production of more than one (1) millicurie of radioactivity, with any half life, must receive prior-approval of the Reactor Operations Committee, t
I 16-55
~ -. .
D.- The Health Physicist shall be responsible for monitoring _
records of exposure on film badges, maintenance of a log on radiation tests and exposure records. He also shall review the reactor log. -Periodic radiation surveys of the critical reactor laboratory, the suberitical laboratory and the counting room, and other areas where radioactive materials are being used, shall be made by the Health Physicist under the direction of the Chief Reactor Supervisor. The Radiation Safety Officer. shall'be notified if an abnormal radiation problem is encountered. . Results of these surveys shall be recorded or filed in the log. The Health Physicist shall also be responsible for proper disposal of samples and radioactive materials. The Health Physicist shall be appointed by the Reactor Administrator after consultation with the Reactor Operations Committee.-
E. The Reactor Supervisors'sha11 be appointed by_the Reactor
. Administrator. These individuals shall have general competence in reactor technology and associated fields. Each supervisor shall hold a Senior Operator's License issued by the Nuclear Regulatory Commission. The Reactor Supervisors shall be responsible to the Reactor Administrator, through the Chief Reactor Supervisor, for the preparation and submission of complete detailed proposed procedures, regulations and administrative rules to insure the maintenance, safe operation, proper and competent use, and security of the reactor equipment.
.~ Appointment as a Reactor Supervisor shall in all cases be accompanied by appointment to the Reactor Operations Committee.
The Reactor Supervisors shall be responsible for the preparation and submission of operating schedules of the reactor facility, and shall insure that all activities and experiments involving the facility conform to both local and Commission regulations.
They shall establish in coordination with the Reactor Operations Committee, procedures for activities to be performed with the reacto r. They shall establish procedures and be responsible for the keeping of adequate, complete and currently accurate-records for the operation and maintennnce of the facility.
A Reactor Supervisor shall be in charge of the facility and shall witness the startup and intentional shutdown procedures.
In addition, he shall be responsible for prompt execution of emergency procedures.
16-56 4
.. . ,l
-l F. -
The Chief Reactor Supervisor shall hold a valid Senior . 1 Operator's-License issued by the Commission. He shall l
- be responsible for the' promulgation and enforcement of administrative- rules, regulations and ope' rating- procedures.
He'shall inform the Reactor Operations Committee of any unusual operations proposed to be performed on the reactor, or any proposed changes in procedure. He_ shall not authorize the operation or proceed with the proposed changes until appropriate evaluation and approval has been made by the Reactor _ Operations Committee, and authorization given by the Reactor Administrator. The Chief Reactor Supervisor shall have the authority to authorize any' activities or procedures which have received prior approval of the-Reactor Operations Committee. ~He shall be directly responsible for enforcing operating procedures and insuring that the reactor facility is. operating in a safe, competent and authorized manner at all times. In addition, he shall be directly responsible for the preparation, authentication and storage of all prescribed logs and operating records.
_G. The Reactor Operators shall hold a valid Operator's License issued by the Commission. They must conform to the rules, instructions-and procedures for the start-up, operation, and 7 shut-down of the reactor facilities. They must also conform to the specifications of the Emergency Plan. Within the constraints of the administrative and supervisory controls out-lined above, a reactor operator shall be in charge of the control-
~
console at all times that the reactor is operating. ' The reactor operator shall be required to maintain complete and accurate records of all reactor operations in the operational logs.
H. All other personnel using the facility shall be instructed in the
., hazards involved, and given a copy of the' laboratory regulations p concerning use of radioactive material. All personnel working in the vicinity of the reactor shall wear film badges.
'6. l. 3 Staffing 7 1. The minimum staffing when the reactor is not secured
- shall be:
- a. A licensed Reactor Operator in the control room.
i-
- b. A licensed Senior Reactor Operator present in the Leo Engineering Building,
- c. A health physi'es - qualified individual contactable .
by phone.
16-57 u , . - ~ - . :-. . . - ,.. _. . - - . . - - . . , . - . .
1
-2 Operating Personnel Requirements a'. The controls of the reactor _shall be operated only (the reactor controls are to be regarded as operating if the " Reactor-On" switch is turned to "ON" and fuel is present in the core tank) with the specific authorization of a Reactor Supervisor.
The Reactor Operator shall be responsible for o btaining the authorizing signature of a reactor supervisor at the top of the checkout sheet. The Reactor Supervisor signing the authorization is the supervisor "in charge".
- b. Whenever the reactor controls are operated, a.
licensed Reactor Operator shall be present and in the immediate vicinity of the console. An up-to-date list of licensed reactor operators will be posted near the reactor console. A person is considered "present" if he is in the console room within view of the instruments on the console.
- c. A Reactor Supervisor shall be present in the Leo Engineering Building at all times that the reactor controls are operated and shall be cognizant of the reactor operation at all times. If the supervisor in charge of the operation must leave the building, the reactor controls must either be turned off and locked or another supervisor must accept responsi-bility. The Reactor Operator shall be informed of such a transfer of authority. A list of Reactor Supervisors will be posted near the reactor console.
- 3. Personnel Requirements for Fuel and Experimental Loading
- a. Any movement of fuel elements or of material into or out of the reactor core can be done only on specific written authorization of or in the presence of a Reactor Supervisor,
- b. At least two persons, one a licensed Reactor Operator, shall be in the ZPR laboratory when any fuel elements or any experiment is moved in the reactor core.
One person shall be at the reactor console.
16-58
- c. Whenever-the final fuel element necessary for attainment of criticality is transferred into the -
core, a Reactor Supervisor shall be present,
- d. ' A Reactor Supervisor.shall be present in the ZPR room during the . loading of an experiment into the core for the first time, or its removal from the core. A Supervisor shall be present in the ZPR room or give his written authorization for repetitive insertions of an experiment.
' 6.1. 4 Selection and Training of Personnel The selection, training, and requalification of operators personnel shall meet or exceed the reg'tirements of American National Standard for Selection and Training of Personnel for Research Reactors ANSI /ANS 15.4 - 1967, or its successor, and be in accordanc'e with the Requalification Plan approved by the Nuclear Regulatory Commission.
I6-59
F r
- 6, 2 Review and Audit The Reactor Operations Committee shall perform the independent review and audit of the safety aspects of reactor facility ope rations.
- 6. 2.1 Composition and Qualifications The Reactor Operations Committee shall be composed of the Reactor Administrator and the Health Physicist, both ex officio, and at least three other members having expertise in reactor technology. Committee members shall be appointed by the Reactor Administrator.
6.2.2 Charter and Rules
- 1. The Reactor Operations Committee shall meet at least semiannually and more frequently as circumstances warrant, consistent with effective monitoring of facility activities. Written records of its meetings shall be kept.
2 The Reactor Operations Committee may appoint one or more qualified individuals to perform the audit function.
6.2.3 Review Function The following items shall be reviewed:
1 Determination that proposed changes in equipment, systems, tests, experiments, or procedures do not
, involve an unreviewed safety question.
2 All new procedures and major revisions thereto having safety significance and proposed changes in reactor facility equipment, or systems having safety significance.
- 3. All new experiments or classes of experiments that could affect reactivity or result in the release of radioactivity.
4 Proposed changes in the Technical Specifications or the Operating License.
- 5. Audit reports.
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l 6.2.4 The Audit Function
-The Audit Function shall include selective (but comprehensive) examination of operating records, logs, and other documents.
' The following items shall be ' audited:
- 1. Facility operations for conformance to the Technical Specifications and applicable Operating License conditions,
at least once a year.
2 The retraining and requalification program for the ope rating st aff. -
- 3. The results of action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operation that affect reactor safety, at least once per calendar year.
4 The reactor facility - Emergency and Physical Security Plans and implementing procedure at least once every a other calendar year.
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- 6. 3 Procedure s Written procedures shall be- prepared, reviewed and approved prior to initiating any of the activities listed in this section. The procedures shall be reviewed by the Reactor Operations Committee and approved by the Reactor Administrator. The following activities, not already described in the Technical Specifications, may be included in a set of procedures,
- 1. Startup, operation, and shutdown of the reactor.
2 Fuel loading, unloading and movement within the reactor.
- 3. Routine maintenance of major components of systems that could have an effect on reactor safety.
4 Surveillance tests and calibrations required by the Technical Specifications or those that may have an effect on reactor safety.
5 Personnel radiation protection consistent with
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applicable regulations.
- 6. Administrative controls for operations and maintenance and for the conduct of irradiations and use of experiments that could affect reactor safety or core activity.
7 Implementation of the Emergency and Physical Security Plans.
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- 6. 4 - Experimental Review and Approval Approved laboratory exercises 'shall be carried out in accordance
.with established and approved procedure.
- 1. All new exercises shall be reviewed by the Reactor Operations Committee and approved by the Reactor Administ rator prior to initiation.
2 Substantive changes to previously approved experiments shall be made only after they are reviewed by the Reactor Operations Committee and approved by the Reactor Administrator.
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- 6. 5 Required Actions
. 6. 5.1 Action to be Taken in Case of Safety Linut Violation 1 The reactor shall be shut down and reactor operations shall not be resumed until authorized by the Nuclear
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Regulatory Commission (NRC).
- 2. The safety limit violation shall be promptly reported to the Reactor Administrator or a-designated alternate.
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- 3. The safety limit violation shall be reported to Nuclear Regulatory Commission.
4 A safety limit violation report shall be prepared.
The report, and any follow-up report shall be reviewed by the Reactor Operations Committee and shall be submitted to the Nuclear Regulatory Commission when authorization is sought to resume operation of the reactor. The report shall describe the following:
- a. Applicable circumstances leading to the violation including, when known, the cause and contributing factors.-
- b. Effect of the violation upon reactor facility components, systems,' or structures and on the health and safety of personnel and the public,
- c. Corrective action to be taken to prevent recurrence.
6.5.2 Action to be Taken in the Event of an Occurre'nce of the Type Identified in 6. 6. 2-1. b and 6. 6. 2-1, c.
- 1. Reactor conditions shall be returned to normal or the reactor shall be shut down. If it is necessary to shut down the reactor to correct the occurrence, operations shall not be resumed unless' authorized by the Reactor Administrator or a de'signated alternate.
2 Occurrence shall be reported to the Reactor Administrator or a designated alternate and to the Nuclear Regulatory Commis sion.
- 3. Occurrence shall be reviewed by the Reactor 3-Operations Committee at its next scheduled meeting.
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- 6. 6 Reports 6.6.1 Operating Reports Internal reports are kept as minutes of the semiannual meetings of the Reactor _ Ope rations Committee.
Reports to the Nuclear Regulatory Commission (NRC) are made in response to-reports made after inspection by NRC to the' Reactor Administrator. Reports to the Nuclear Regulatory Commission may include:
- 1. A narrative summary of reactor operating experience.
- 2. ' A description of unscheduled shutdowns including where applicable, corrective action taken to preclude recurrence.
- 3. Tabulation of major preventive and corrective maintanance operations having safety significance.
- 4. Tabulation of major changes in the reactor facility and procedures, and tabulation of new tests or experiments, or both,- that are significantly different from those performed previously and are not described in the Safety Analysis Report, including conclusions that no unreviewed safety questions were involved.
5 A summarized result of any radiation surveys performed by the facility personnel.
- 6. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percent of that allowed or recommended.
6.6.2 Special Reports
- 1. There shall be a report not l'ater than the rollowing working day by telephone and confirmed in writing by telegraph or similar conveyance to Nuclear Regulatory Commission to be followed by a written report that describes the circumstances of the event within 14 days of any of the following:
a, Violation of safety limits (sec 6. 5.1).
,. b. Release of radioactivity from the site above allowed limits (see 6. 5. 2).
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- 4) An unanticipated or uncontrolled change in reactivity greater than the licensed excess reactivity. or one dollar, whichever is smaller.
- 5) Abnormal and significant degradation in reactor fuel, or cladding, or both which could result in exceeding prescribed radiation exposure limits of personnel or environment, or both.
- 6) An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations.
2 A written report within 30 days to the Nuclear Regulatory Commission concerning the following:
- a. Permanent changes in the organization involving the Reactor Administrator, Chief Reactor Supervisor, or Radiation Safety Officer.
- b. Significant changes in the transient or accident
, analysis as described in the Safety Analysis Re po rt,
- c. Any of the following (see 6. 5,2): i:
- 1) Operation with actual safety system settings for required systems less conservative than the limiting safety system settings specified in the Technical Specifications.
- 2) Operation in violation of limiting conditions for operation established in the Technical Specifications unless prompt remedial action is taken.
- 3) A reactor safety system component malfunction which renders or could render the system incapable of performing. Its intended safety function unless the malfunction or condition is discovered during maintenance tests or periods of reactor shutdown.
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- 6. 7 LRecords 6.7.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component if Less than Five Years 1 ~ Normal reactor' facility operation (but not including supporting documents such as checklists, log sheets, etc. . .which shall be maintained for a period of at
> least one year).
2 Principal maintenance operations.
- 3. Reportable occurrences.
. 4. - - Surveillance activities req'uired by the Technical
. Specifications.
- 5. Reactor facility radiation and contamination surveys-where required by applicable regulations.
-6. Laboratory exercises performed with the reactor..
- 7. Fuel inventories,' receipts, and _ shipments.
8 Approved changes in operating procedures.
- 9. Record- af meetings and audit reports of the Reactor Operations Committee.-
- 6. 7. 2 Records to be Retained for at Least One Training Cycle Retraining and requalification of licensed operators:
Records of the most recent complete cycle shall be
. maintained at all times the individual is employed.
6.7.3 Records to be Retained for the Lifetime of the Reactor Facility Applicable annual reports, if they contain all of the required information, may be used as records in this section.
1.- Gaseous and liquid radioactive effluents, if any, released to the environs.
2 On-site environmental monitoring surveys required by the Technical Specifications.
- 3. Radiation exposure for all personnel monitored.
4 Drawings of the reactor facility.
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