ML20099M322

Rev 4 to Tech Specs for Manhattan College Zero Power Reactor,Facility License R-94

ML20099M322
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Issue date:	03/15/1985
From:	MANHATTAN COLLEGE, RIVERDALE, NY
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1 APPENDIX A TECHNICAL SPECIFICATIONS 1

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'FOR THE a

1 MANHATTAN COLLEGE ZERO POWER REACTOR FACILITY LICENSE R-94 l

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Rev. 4 Revision Record Revision No.

Comment i

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Submitted to U. S. N. R. C. on August 26, l83 i

as part of the Safety Analysis Report for the MCZPR.

.1 Complete revision submitted on January I?.,

1984.

2 Complete revision submitted on November 15, 1984 3_

Revisions as noted on.pages 16-1, 16-2, 16 - 10, 16 r11, 16 - 13, 16-16, 16-23, 16-25, and 16-2 8,.

on December 19, 1984 4

Page numbering changed from 16-1 to 1 - 1, etc.

Cover sheet revised from section 16 to Appendix A per USNRC reque st.

Revisions as noted on pages i, ii, iii, 1 - 1, 2 - 1, 2 -2, 3 - 1, 3 -2, 3 -3, 3 -4, 3-7, 4-1, 4-2, 4-4, 4-8, 4-11, 5-1, 5 -2, 5 -3, 5 -4, 5 -5, 6 - 1, 6 -6, ' 6 -8, 6-9, 6-11,6-13, and 6-14 on March 15, 1985 f.

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Rev. 4 TABLE OF CONTENTS Contents Page No.

Title Page i

't Revision Record ii Table of Contents iii j

1. O bEFINITIONS 1

-1

2. 0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1

3. 0 LIMITING CONDITIONS FOR OPERATION 3 -1

4. O SURVEILLANCE REQUIREMENTS 4-1

5. 0 DESIGN FE ATURES 5-l'

6. O ADMINISTRATIVE CONTROLS -

6-1

- Table 3 - 1, Safety System 3-4 Figure 6 - 1, Table of Organization 6-2 I

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Rev. 4

1. O DEFINITIONS The terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50. 36 s

of 10 CFR Part 50 ALARA -

ALARA is a concept introduced by the Nuclear Regulatory Commission (NRC) to all reactor facilities. The basis of ALARA is that all exposure to radiation should be kept "as low as reasonably achievable" (ALARA).

l channel -

A ch_annel is the combination of sensor, line, amplifier and output devices which are connected for the purpose of measuring the value l

i of a parameter.

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channel calibration - A channel calibration is an adjustment of the channel

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such that. its output corresponds with acceptable accuracy to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deerried to include a channel test.

channel check - A channel check is a qualitative verification of acceptable

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performance by observation of channel behavior. This ve rification, where po s sible, shallinclude comparison of the channel with other independent channels or systems measuring the same cariable.

channel te st_-

A channel test is the introduction of a signal into the channel for verification that it is operable.

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.

The portion of the reactor volume which includes the fuel elements, core -

the source, and the control rods, delayed neutron f racti_o_n_- When converting between absolute - and dollar-value reactivity units, a beta of 0.00645 is used.

drog ti_me -..The elapsed time between reaching the complete removal setpoint and the full insertion of a safety-type rod. (It must be less than

1. 0 second).

exce s s _ re activity-Excess reactivity is that amount of reactivity that would exist if all control rods vontrol, regulating) were moved to the maximum reactive condition from the point where the reactor is exactly critical l

(K

= 1).

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c_xyeri, ment - Any object, other than a fuel element or handling tool, e

which is inserted into the volume formed )y projecting the grid plate L

vertically to the tank pool water surface is to be regarded as an experiment in the core.

meas _ured 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 reacto r pool water.

o_y_e r ab le - Operable means a component or system is capable of performing its intended function.

operatint-Ophrating 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% Ak/k (O. 68 $ ) at 110. 6 F.

reactivity worth of an exgeriment - The reactivity worth of an experiment is the maximum absolute value of the reactivity change that would occur as a resuit of intended or anticipated changes or credible malfunctions that alter experiment position or configuration.

reactor operating - The reactor is operating whenever it is not secured or shutdown.

reactor operator - (RO) - An individual who is licensed to manipulate the controls of a reactor, reactor _ safety syst_ ems - Reactor safety systems are those systems, including e

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 mode ration and reflection, or 1-2

2)

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) 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 shutdohn - 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 experiments is accounted for.

reference core condition - The condition of the core when the paol water temperatu're is between 60 F and 80 F.

r_egulating ro_d_ - 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 laborato ry purposes, and which may have provisions for the production of radioisotopes.

reverse trit-The electronic setting within the console instrumentation which will initiate 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 i.ts 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 subcritical 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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senio r reactor _ ope rato r - (S RO) - 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 denote a requirement :

the word "should" to denote a recommendation:

and the word "may" to denote permission, neither a requirement nor a recommendation.

shutdown margh - Shutdown margin shall mean the minimun$ 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 suberitical without further ope rator action.

unscheduled shhtdown - An unscheduled shutdown is defined as any unplanned

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shutTown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual ;hutdown 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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1-4

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Rev. 4

2. O SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits 2.1.1 Applicability -

This specification applies to the melting temperature of the fuel cladding.

i 2.1. 2_ Objective e

To assure that the integrity of the fuel is mai,ntnined.

2.1. 3 Specific'ations The safety limit shall be on the temperature of the fuel element cladding, which shall be less than 1220 F.

2.1. 4 Bases The melting temperature of the aluminum used as cladding on the fuel elements is 1220 F.

Therefore,in order to maintain fuel element integrity, the cladding temperature must not exceed 1220 F.

As reported in Appendix G of the Safety Analysis Report for the MCZPR, the maximum core temperature that can ever be reached is only 221 F and reaches this level only during the Maximum Hypothetical Accide nt.

The specification,therefore, provides assurance on the integrity of the fuel within'the cladding.

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I Rev. 4

2. 2 Limiting Safety System Settings (LSSS) 2, 2.1 Applicability This specification appliesto the setpoints of safety channels which monitor reactor power level.

2.2.2 Objective To assure that automatic trip action is initiated and that the operator is warned to take protective action against exceeding a safety limit.

2.2.3 Spe cifications l

The liniiting safety system setting shall be on reactor maximum power level not exceeding 0.125 watt, or 125% of full powe r.

2.2.4 Bases Since there is no forced circulation cooling, the reactor core is cooled by the water surrounding the reactor core.

Therefore, the only parameter which could be used as a l-limit for the fuel cladding temperature is the reactor power.

t The analysis in Appendix G of the Safety Analysis Report l

shows that evenfor the M aximumHypothetica1 Accident (a reactor power excursion of 147 kilowatts), the maximum core temperature reaches only 221 F.

(The tank water i

temperature would rise less than 10 F. ). This temperature is much lower than the temperature (1220 F) at which I

cladding damage could occur.

The refo re, a large safety margin exists between the limiting safety system set point and the fuel safety limit.

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Rev. 4

3. 0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactor Core Parameters 3.1. I Applicability These specifications apply to the parameters which describe the reactivity condition of the c. ore, 3.1. 2 Objeetive i

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To ensure that the reactor cannot achieve prompt criticality and that it can be safely shut dow.n,under

.any condition.

Spe' ifications 3.1. 3 c

The reactor shall not be made critical unless the following conditions exist:

A.

The total core excess reactivity with or without the movable Ak experiments of section 3. 8. 3 shall not exceed O. 44%

/k (O. 68 $ ). at 110. 6 F.

B.

The minimum shutdown margin provi'ded by control rods shall not be less than 0. 46%Ak/k (0. 72 $). at 110. 6 F.

C.

Any change in the experimental apparatus shall be approved by the Reactor Orerations Committee.

3.1.4 Bases Specification A is base-1 upon the' ex crimentally determined value for excess reactivity O. 44% A /k (O. 68$) at a reactor pool water temperature of 110. 60F.

Specification B is based upon the negative worth of the regulating rod:

that is, the control rod with the smaller negative worth.

l Specification C limits the changes in the experimental apparatus to those approved by the committee charged with l

review and approval of experiments.

3-1

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Rev. 4

3. 2 Reactor Control and Safety System

3. 2.1 Applicability These specifications apply to the reactor safety system and safety-related instrumentation.

3.2.2 Objective s i

To specify the lowest ar eptable level of performance or the minimum number or 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 ope rable in accordance with Table 3 -1.

B.

There shall be two safety-type control rods:

Ak A regulating rod with a negative worth of 0. 90%

/k (1. 40$)

and a shim rod with a negative worth of 2. 50% A k /k(3. 88$).

C.

The drop time for eithe r safety rod sliall not exceed 1. 0 l

second; measurements of rod drop times shall be made once semi-annually.

D.

The reactivity insertion rate for a single rod shall not exceed O. 10 % Ak /k (.154$) pe r second.

3.2.4 Bases Specification A provides assurance that the reactor safety system which may be needed to shut down the reactor is o pe rable. Each feature of the system is described in Table 3-1.

- A scram system is provided that causes interruption of the magnet current to the electromagnets, should a scram trip be exceeded. The control rods then fall into the reactor core under the force of gravity. This system provides a conservative response to an instrumentation system failure, electric powe r failure, low water level, high neutron flux, and high gamma activity.

3-2

Rev. 4 A reverse system is provided that lowers the control rods into the reactor should a reverse trip be exceeded. This system provides a conservative response to the high/ low power reading from each channel's recorder, and to the power being off on each r,ecorder.

A bypass system is provided that causes the elimination of reverse circuit in the linear chan,nel or i

the gamma channel. This system provides a special controllable function for the reactor operation during initial fuel loading and during reactor startup., -

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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Rev. 4 Table 3-1 Safety Systeny 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 providedthat shall 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 i

no scram trip signals. A scram trip shall be provideifor each of the conditions below, with the trip setting as specified, a.

,High neutron flux - Count Rate Channel elec'tronic trip set dor 129/o 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 t' nk water level drops a

one 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 "RE ACTOR 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 Reverse Circuitsi x

A reverse system shh11 be provided that shall cause both control rod drives to drive the cont'ec.l rods into the reactor whenever a reverse trip is exceeded. The rev'erse action shall override any rod selection made by an operator and sha'll persier as long as a reverse trip is exceeded. Reverse trips shal'isbe rerovided for each condition as below with the trip setting as sphetfied:

3-4 L

l Table 3-1 Safety System (continued) a.

A Count Rate Channel reverse trip shall occur for any of the 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.

g 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 recorder is greater than 95% of full scale, c.

Gamma Channel reverse trip shall occur for any of the following conditions:

(1)

Gamma recorder off.

(2)

Gamma recorder down scale - shall occur when the recorder indicates less than Oi 2 mRIhr.

(It should be noted that the minimum reading on the recorder is 0. I mR/hr while the minimum reading on the instruments on the Gamma Channels for Area Radiation Monitoring is. 01 mR/hr ).

(3)

Gamma recorder up scale - shall occur when the r,ecorder indicates greater than 95 mR/hr.

d.

Any sdram condition shall cause the control rod drives to j

drive in the electromagnets.

e.

Manual run-in-trip shall occur upon actuation of the "Run-In" switch on the control console.

3.

Bypar,s in Safety Systems e--

The only bypas es in the scram or reverse circuits shall be those The bypasses shall be key operated switches described below.

located on the console.

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Table 3-1 Saf_ety_Systern (continued) a.

A bypass to eliminate a reverse es 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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Rev. 4

3. 3 Coolt.nt Condition Because of the low value of the maximum steady p,wer 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; howeve r,_due.

to its large heat capacity.othe pool. water can also be used to dissipate heat from the~ reactor} ore]

3. 3.1 Applicability i

,3 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 A.

The maximum heat capacity of the pool water shall be 65 MJ/ C, with a minimum water level requirement of seven feet as measured from the tank bottom. The minimum heat capacity of the pool water shall be 56 MJ/oC, with a water level of six feet.

B.

The lower limit of water resistivity %ased on the require -

ments for the corrosion protection system shall be set at 0.1 Megohm-cm.

There shall be no upper limit for the 4

water resistivity.

3.,3. 4 Bases l

o i-Specification, A provi<iers assuran.ce that the pool water,

• We to itsylarge heat capacity. relative to the low' m.;-,

steady power level (O. I vratt), can completely remove and dissipate heat in the reactor tank.

Specification B provides the minimum resistivity of water in the reactor tank. If the water resistiirity is less than this level of 0,1 Megohm-cm, the resin bed in the deionizer is replaced. The resistivity of the water has little or no bearing on the corrosive effects experienced or possible other than to offer some guarantee that catalyzing anions are excluded from the system. In the absence of the other protective mechanisms that are in place, co rro sion will obcur 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 Megohm-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 cells as a result of discrete areas becoming anodic.

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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 Obje ctive To ensure that the air in the reactor room is always clean i

und free of dust.

3.5.3 Specifications A.

,The JACZPR Laboratory shall contain a forceti birculation veni11ation 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 i

the ventilating system on and off.

3.5.4 Bases Specification A shows that the ventilation system is independent of the building.

Specification B provides assurance that the ventilation system is controllable.

3-9 i

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3.6 Eme rgency Powe r 1

l No emergency powpr is supplied to the MCZPR, In the event of power failure while the reactor is operating, a scram trip shall odeur.

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3. 7 Radiation Monitoring Systems

3. 7.1 Applicability These 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 besprovided to measure gamma intensity. These channels sG11 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 Ganuna 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 Detector. 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 der.lgned so that if the radiation intensity is greater than 100mR/hr. the detector shall indicate full scale.

3 - 11

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 ea'ch 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 siaf'ety alarm

' system will be activated when radiation exceeds the allowable

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limit.

Specification E provides the rance and design configuration of the monitoring system, s

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3 - 12

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3.~ 8 Expe riments 3, 8.1 Applicability These. specifications apply to the experiments installed in the reactor.

l' 3,8.2 Objeetive 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 "N

o Limitations on experiments and material irradiations in the reactor shall meet the following conditioyg A.

No experiment shall be installed in the reactor in such a location that any part of the apparatus will touch or in any l

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 irradiate d.

2 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 radioactivity shall not be irradiated.

L F.

Each experiment, other than labo,ratory exercises defined in 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.

Labolatory exercises - The following laboratory i

exercises, while not requiring the presence of a Reactor Supervisor, require the presence of a Reactor Operator, Laboratory exercises involving use of experiments (other j

than experiments used in the following exercises) shall be 3 - 13

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_ _. _ _ _ _ _. _ _ _ _ _ - _., ~ _ _ _ _.. _, _ _,, _ _ _ _ _ _ _.. _ _

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. conducted in the presence of a Reactor Supervisor.

1.

Startup and 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 Manhatten College Zero Power Reactor 6

Determination of Buckling 7.

Measurement of Diffusion Length and Age 8

Temperature Coefficient of Reactivity:,

n 9.

Gamma Ray Energy Spectrum in the Vicinity of the Reactor Core H.

A maximum of seven aluminum covered ind'iuEfoils with a combined

. haximum negative reactivity of -1.113 X 10-4 Ak/k may be used in g

a laboratory exercise (Flux Distribution in the MCZPR). A void with a maximum negative worth of -10. 4 X 10-44k/k may also be used in a laboratory exercise (Void Coefficient Measurement).

I.

A record of each material irradiation shall be included in the reactor log. The record 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

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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 albays 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 r6d is fully removed.

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3. 9 Facility Specific LCO No limiting conditions for operations (LCO) mique to the facility other than those listed above are necessary.

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Rev.4

4. 0 SURVEILLANCE REQUIREMENTS Surveillance tests, except those specifically required for safety when the reactor is shutdown, may be defe rred during reactor shutdown; however. they must be completed prior to reactor startup.

4.1 Reactor Core Parameters 4.1. 1 Applicability j

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 ptrameters conform to the specifications of section 3.

r 4.1. 3 Specifications A.

Total core excess reactivity shall be checked immedia'ely 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 Commission.

B.

The shutdown margin shall be checked at least 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.

Any change in the experimental apparatus shall be approved and i

documented by the Reactor Operations Committee.

4.1. 4 Bases Specification A to preclude operating the reactor without adequate shutdown capability provides assurance on the core excess reactivity.

Visual confirmation and the expe rimental measurements of Specifications A, B, and C are sufficient to provide assurance that the reactor core parameters are as specified in 3.1. 3 A, B, and C.

4-1

Rev. 4

4. 2 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 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.

i 4.2.3 Specifications A.

It is assumed that the worth of the control rod,s' remains unchanged. However, the relative worths of the control rods shall be checked annually by comparing the criticality positions of the control rods with the criticality positions of previous yea m.

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 i.s 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 Icast weekly during continuous operating periods, f

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 assures that relative worths of the control rods shall be checked annually in order to

, maintain the required shutdown margin.

This speci-fication also provides means for determining the relative' wo rth of experiments inserted into the reactor core.

The rod withdrawal and insertion time measurement inte rvals i

required in specification Il ve rify the limits in specification l

3. 2. 3 D and are appropriate to detect abno rmal performance, i

4-2 i

1

l Specification C verifies the operability requirements in specification 3. 2. 3 C during each day of ope ration.

In specification D cach channel capable of generating a scram signal is tested during the pre-critical procedure, prior to startup, so that the conditions of specification,3.2.3 A are s atis fied.

Specification E requires calibration of safety and safety-related channels at an interval which is appropriate and g

justified by prior experience at this facility.

f, r

A 43 i

i

Rev. 4

4. 3 Coolant Condition This specification applies to the surveillance of the pool water condition.

4. 3.1 Applicability This specification applies to the surveillance activities required for the reactor coolant condition.

4.3.2 Objective g

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

'S pecifications A.

The water level in the reactor pool shall be maintained at seven feet from the tank bottom and shall be checked and recorded every day that the reactor is operated.

B.

The lower limit of water resistivity shall be checked and recorded every day that the reactor is operated.

A pool water sampling analysis shall be pe rformed semi-annually by the Health Physicist. The result of the samp!1ng analysis shall be reviewed by the Reactor Operations Committee.

4.3.4 Bases Specification A provides assurance on the amount of pool water in the reactor tank.

Specification B provides assurance on the water resistivity of the pool water. Te st re sults on the reacto r pool wate r showing no indication of radioactivity provide evidence that there has been no breach in the fuel cladding and no corrosion of the cladding by the pool water.

4-4

l-

4. 4 Confinement or Containment The re is no confinement or containment system.

)

l 4-5

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 i ~

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 for 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.

f.

t 4-6

o I

4. 6 Emergency Powe r This specification does not apply to this facility since there is no emergency power supply.

s f.

t 4-7

Rev. 4

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 Objective To specify 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 Spe cific ation s.

These surveillance activities are required for safety.

A.

A calibration of the two radiation monitoring channels shall

.he performed at least annually and whenever any maintenance on a channel which may affect its performance is completed.

l This calibration shall be performed by comparing the readings j

of these instruments with those on a portable beta-gamma

i survey meter. The latter shall be calibrated annually by t

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 all instruments shall be recorded hourly during operation with the reactor being critical.

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 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 slull be subject to review by l

the Reactor Ope rations Committee.

4-8

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.

l B.

Other specific surveillance activities shall be established during l

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 detailep surveillance require-ments will_ vary among experiments, and that the Reactor O perations Committee specifies the appropriate type and frequency of surveillance.

f.

s 3

4-9

4. 9 Facility Specific Surveillance No Facility Specific Limiting Conditions for Operations are provided in section 3. 9.

t O

e r

1 1.

1 i

4-10

Rev. 4 4.10 Frequency of Testing 4.10.1 Applicability This specification applies to all surveillance requirements of Section 4 of these Technical Specifications.

4.10. 2 Objecrive i

The objective of this specification is to establish maximum time intervals for surveillance periods. It is intended that this specification provide operational flexibility and not reduce surveillance frequency.

4.10.3 Specifications 4.10.3.1 Time intervals used elsewhere in these specifications shall be defined as follows:

A.

Biennially Interval not to exceed 30 manths.

B.

Annually

- Interval not to exceed 15 months.

C.

Semi-annually - Interval not to exceed 32 weeks.

D.

Quarte rly

- Interval not to exceed 18 weeks.

E.

Monthly

-. Interval not to exceed 6 weeks.

F.

Weekly

- Interval not to exceed 10 days.

G.

Daily

- Must be done prior to the first startup of the calendar day following a shutdown greater than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

f.

t 4 - 11

Rev. 4 5.0 DESIGN FEATURES 5.1 Site and Facility Description 5.1.1 The Manhattan College Zero Power Reactor (MCZPR) shall be located in the Leo Engineering Building of Manhattan College at 3825 Corlear Avenue, B ro nx, New York.

1 5.1. 2 A total of fifteen full fuel elements and one partial element shall be permanently mounted upon the reactor grid plate, which shall be located at the center of the reactor tank bottom. Due to the extremely low power rating of the MCZPR (O. I watt), periodic fuel replacement is not necessary.

Hence, no built-in provision is made for the storage of spent fuel.

5.1. 3 The control system shall consist of two safety-type control rods, that is, a shim rod and a regulating rod.

The control rods shall be attached to their associated drive mechanisms by an electromagnet and shall fall by I

gravity to the least reactive position upon a decrease of magnet current following scram action.

5.1. 4 The MCZPR Laboratory shall be provided with a forced circulating ventilation system. This ventilation system shall be independent of the Leo Engineering Building and shall be controlled by a switch located on the west wall of the MCZPR room.

5.1. 5 The MCZPR shall be designed to operate at a full power of 0. I watt. There shall be no fission product release or gaseous effluent under such low power rating.

5-1

Rev. 4 i

5. 2 Reactor Coolant Condition Because of the extremely low power rating of the reactor (O. I watt), there is no recirculating coolant or coolant system in the reactor other than the reactor pool wate r.

Water lost due to evaporation shall be replenished with New York City water. The water from the city system shall pass through a demineralizer at a flow rate of two to three gallons per hour.

Under the reference core condition, the water level in the reactor tank s, hall be l'

maintained at seven (7) feet as measured from the tank bottom.

i I

I'('

5-2

Rev. 4

5. 3 Reactor Core, Fuel, Control Rods, and Startup Source 5.3.1 Reacto r Core A grid plate stand is welded to the bottom of the reactor tank. Bolted to the grid plate stand is a grid plate. Fuel element hold-down rods are passed axially through the center of the fuel elements to hold the latter rigidly in position. These hold-down rods, each with total length of 35 inches, are threaded into the grid plate. The shaft of i

these hold-down rods are made partly of aluminum and partly of lucite. The lucite portion, which consists of a solid rod one inch in diameter, is 24 inches'Igns. The

' lower portion of the hold-down rod is made out of aluminum tubing having a wall thickness of 1/8 inch and total length of 5-1/2 inches.

The bottom 1-1/2 inches is threaded and secures the hold-down rod to the grid plate. The broad top of the hold-down rod, which extends over the top of the fuel element is also made of aluminum with thickness of 3 /8 inch.

The aluminum portions of the hold-down rod are securely fastened to the lucite by aluminum pins and epoxy cement.

5.3.2 Reactor Fuel The fuel portion of the elements consists of six concentric cylinders formed by mechanically joining and positioning eighteen curved fuel plates within grooves of three spacer webs.

The cylindrical fuel plate consists of 0. 020 inch-thick U-Al alloy of 92% enriched uranium, clad on both sides with

0. 015 inch of aluminum, making the total plate thickness

0. 05 inch.

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. I18 inch. A maximum of 15 full fuel elements plus one partial fuel element (containing a nominal 24 grams of U-235), is used in the facility.

The partial fuel element has one cylinder.

5-3

Rev. 4 5.3.3 Reactor Control Rods A.

Control Rods - The reactor is controlled by two Y-shaped control rods which pass in the clearance between adjacent fuel elements. 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 control rods is capable of preventing 5

the reactor from becoming critical.

+

B.

Control Rod Drive Mechanisms - Each control, rod drive

,sys em is a cantilever drive with a design drive speed no t

greater than 12 inches per minute.

5.3.4 Reactor Startup Source The startup source is a Pu-Be source encapsulated in tantalum. The source strength is one (1) curie 6

(approximately 10 neutrons per second).

f.

5-4

Rev. 4

5. 4 Fissionable Material Storage Fuel elements are permanently stored on the reactor l

grid plates with the exception that three fuel plates are permanently stored in a locked steel container fastened to the floor of the first floor of the MCZPR Laboratory.

1 j

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Rev. 4

6. O ADMINISTRATIVE CONTROLS 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.

i 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 i

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 shit provide final policy decisions l

' 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 Committee. The Reactor Administrator shall be responsible for the overall administration and supervision of the reactor 6-1

MANHATTAN COLLEGE CORPORATION 4

BOARD OF TRUSTEES Level 1 I

l PRESIDENT OF THE COLLEGE l l

l EXECUTIVE VICE PRESIDENT l I

l PROVOST l l

l DEAN OF THE SCHOOL OF ENGINEERING l.

i s

RE ACTOR ADMINISTRATOR Level 2 RADIATION

' REACTOR OPERATIONS SAFETY OFFICER COMMITTEE i

l HEALTH PHYSICIST l

~

~

CHIEF REACTOR SUPERVISOR Level 3 l REACTOR SUPERVISORS) f' REACTOR OPERATOR Level 4 CLERICAL STAFF, MAINTENANCE' AIDES, ASSISTANTS PERSONNE L l

Figure 6-1, Table of Organization 6-2

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 Office r.

The Reactor Administrator shall approve and pron.lgate all regulations, instructions, and procedures governicg the operation of the reactor facility.

The Reactor Administrator shall be appointed by the Provost of Manhattan College.

i 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 saf6 and competent

' man ne r. 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 eriforcement 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 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 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.

l 6-3

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. Pe riodic radiation surveys of the critical reactor laboratory, the subcritical 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 t,hese surveys shall be recorded or filed in the log. The Health Physicist shall also be responsible for proper disposal of samples and i

radioactive materials. The Health Physicist shall be appointed by the Reactor Administrator after consultation with the Reactor Ope rations Committee.

E.

The Reactor Sugervisors shall be appointed by tihe Reactor Administ rato r.

These individuals shall have general competence an 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 con. form 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 maintenance of the facility.

A Reactor Supervisor shall be in charge of the facility and shall witness the startup and intentional shutdown procedure s.

In addition, he shall be responsible for prompt execution of emergency procedures.

6-4

l F.

The Chief Reactor Superviso_r shall hold a valid Senior Operator's License issued by the Commission. He shall be responsible for the promulgation and enforcement of administrative rules, regulations and operating 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 Ope rations Committee. He shall be d,irectly 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 _R_eactor 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 shut-down of the reactor fa-cilities. 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 cencerning use of radioactive material. All persdnnel working in the vicinity of the reactor shall wear film badges.

6.1. 3 Staffing 1.

The minimum staffing when the reactor is not secured shall be:

a.

A licensed Reactor Operator in the control room.

b.

A licensed Senior Reactor Ope rator present in the l

Leo Engineering Building.

qualified individuaf contactable l

c.

A health physics by phone.

1 6-5 y

~

Rev. 4 2

Operating Personnel Requirements o

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

-g the supervisor "in charge".

b.

Whenever the reactor controls are operated, a licensed Reactor Operator shall I e present and in the immediate vicinity of the console'. An up-to-date list of licensed reactor operators shall 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, A Reactor Supervisor shall be present in the Leo c.

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 shall be posted near the reactor console.

l 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.

6-6

. _ - _ _, -. - - - _ =,__ -

Whenever the final fuel element necessary for c.

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 requirements of Am~erican National S,tandard for Selection and Training of Personnel for Research Reactors ANSI /ANS 15,4 - 1967, or its successor, and be in accordance with the Requalification Plan approved by the Nuclear Regulatory Commission.

8 9

6-7

Rev. 4

6. 2 Review and Audit The Reactor Operations Committee shall perform the independent review and audit of the safety aspects of reactor facility o pe rations.

6. 2.1 Composition and Qualifications The Reactor Operations Committee shall be composed of the Reactor Administrator and the Health Physicist, both ex i

officio, and at least three other members having expertise in reactor technology. Committee members shall be appointed l

by the Reactor Administrator.

I 6.2.2 Qharter and Rules 1.

The Reactor Ope rations Committee shall meet at least semiannually and more frequmtly as circumstances warrant, consistent with effective monitoring of facility activities. Writ ten 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 1

1.

Determination that proposed changes in equipment, l

systems, tests, experiments, or procedures do not t

involve an unreviewed safety question, f

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 exp_riments 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.

Reports of external (NRC, state and local authorities, and insurors) inspectors and auditors.

6-8

Rev. 4 l

l 6.2.4 The Audit Function The Audit Function shall include selective (but comprehensive examination of operating records, lo g s, and other documents.

The audit will be performed biennially by an outside individual or group familiar with the research reactor j

ope rations. They shall submit a report to the, Reactor i

Administrator and the Reactor Operations Committee. The' follo.ving items shall be audited:

.t 1.

Facility operations for conformance to the Technical Specifications and applicable Operating License conditions, at least once. a year.

'2 The retraining and requalification p'rogram for the operating staff.

3.

The results of action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of ooeration 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 eve ry other calendar year.

f.

e i

6-9 L

6. 3 Procedures 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 activitie s, not already described in the Technical Specifications, may be included in a set of procedures.

l.

Startup, ope ration, and shutdown of the reactor.

2 Fuel loading, unl oading and moveme,nt.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

{

applicable regulations.

6 Administrative controls for opqrations 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.

e 6 - 10

Rev. 9

6. 4 Experiments; Review and Approval Approved laboratory exercises shall be carried out in accordance with established and approved procedure.

l 1.

All new exercises shall be reviewed by the Reactor Operations Committee and approved by the Reactor Administrator 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.

e t

6 - 11

r

6. 5 Required Action's

6. 5.1 Action to be Taken in Case of Safety Limit Violation 1

The reactor shall be shut down and reactor operations shall not be resumed until authorized by the Nuclear Regulatory Commission (NRC).

2 The safety limit violation shall be prornptly reported to the Reactor Administrator or a designated alternate.

t 3.

The safety limit violation shall be reported to Nuclear Regulatory Commission.

4.

A safety limit violation report shall be.piepared.

The report, and any follow-up report shall be-reviewed by the Reactor Operations Committee and shall be subrr.itted 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 i

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 Occurrence 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 designated alternate.

2.

Occurrence shall be reported to the Reactor Administrator or a designated alternate and to the Nuclear Regulatory l

Commis sion.

l 3.

Occurrence shall be reviewed by the Reactor l

. Operations Committee at its next scheduled meeting.

6 - 12 l

. ~

. ~

Rev. 4 l

6. 6 Re po rt s

6. 6.1 Ope rating Reports Internal reports are kept as minutes of the semiannual meetings of the Reactor Ope rations Committee.

A report summarizing facility operations will be prepared annually where the reporting period ends August 31.

A copy of this report shall be submitted to the Nuclear Regulatory Commission (NRC) Region I office by October 15 of each year, with a copy to the Director, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission. The report shall include the following:

1.

A narrative summary of reactor operating experience.

7,.

A description of unscheduled shutdow'ns -including where applicable, corrective action taken to preclude recurrence.

3.

Tabulation of major preventive and corrective maintanance operations having safety significance.

p 4.

Tabulation of majar 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.

l l

6 A summary of exposures received by facility personnel l

and visitors where such exposures are greater than l

25 percent of that allowed or recommended.

6.6.2 Special Reports 1

There shall be a report not later than the following 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 (see 6. 5.1).

b.

Release of radioactivity from the site above allowed limits (see 6,5. 2).

6 - 13

Rev, 4 c.

Any of the following (see 6. 5. 2):

1) Operation with actual safety system settings for required systems less conservative than the limiting safety system settings specified in the Technical Specifications.

2) Operation in violation of limiting conditions for operation established in tha 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.

4) An unanticipated or uncontrolled change in reactivity greater than the licensed excess reactivity, or one dollar, whichever is smalle r.

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 Supe rvisor, or Radiation Safety Office r.

b.

Significant changes in the transient or accident analysis as described in the Safety Analysis Re po rt.

6 - 14

6. 7 Records

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.

t 3.

Reportable occurrences.

4 Surveillance activities required 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 inve nto rie s, receipts, and shipments.

8.

Approved changes in operating procedures.

9.

Records of meetings and audit reports of the Reactor Operations Committee.

6.7.2 Records to be Retained for at Least dne 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 s e c. tion.

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.

6 - 15

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