ML20236N458

Proposed Tech Specs Re Amend 45 to Ford Nuclear Reactor License Which Would Add Condition B(5) for re-irradiation, Organization Chart Update & Formatting Chages

ML20236N458
Person / Time
Site:	University of Michigan
Issue date:	07/06/1998
From:	MICHIGAN, UNIV. OF, ANN ARBOR, MI
To:
Shared Package
ML20236N454	List: ML20236N452 ML20236N458
References
NUDOCS 9807150134
Download: ML20236N458 (42)

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l OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed License RenewalIssue With Amendments 1-32: 110384

i. Amendment: 33:080489 34: 070191 35:040792 36:050192 37:062592

! 38:100792 39:051493 40:080193 41: 111594 42: 021795 43: 080985 44: 041698 45: Proposed l 4 FORD NUCLEAR REACTOR .

1 The University of Michigan Docket 50-2 OPERATING LICENSE R-28 A. This license applies to the Ford Nuclear Reactor owned by The University of Michigan.

The facility is located in Ann Arbor, Michigan, and is described in the application dated November 30,1984, as supplemented.

l B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses The University of Michigan:

(1) Pursuant to Section 104c of the Act and 10 CFR Pan 50, " Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility at the ,

designated location in Ann Arbor, Michigan,in accordance with the procedures and l Q limitations set forth in this license, (2) Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to receive, possess and use up to a maximum of 18 kilograms of contained uranium 235 at enrichments equal to or less than 20% in connection with operation of the reactor.

i (3) Pursuant to the Act and 10 CFR Pan 70, " Domestic Licensing of Special Nuclear Material", to possess, but not to use, a maximum of 8 kg of contained uranium at greater than 20% enrichment until the existing inventory of high enriched uranium is removed from the facility.

1 (4) Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability to l Domestic Licensing of Byproduct Material," and Pan 70 " Domestic Licensing of Special Nuclear Material," to possess, but not to separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

(5) Pursuant of the Act and 10 CFR Part 30," Rules of General Applicability to 45 Domestic Licensing of Byproduct Material," to receive for irradiation in the reactor l in the amounts as required any byproduct material without restriction to chemical or i physical fami having a definite research and development purpose.

C. This license shall be deemed to contain and is subject to the conditions specified in Parts 20,30,50,51,55,70, and 73 of 10 CFR Chapter I, to all applicable provisions of the Act, and to the rules, regulations and orders of the Commission now or hereafter in effect and to the additional conditions specified below:

9807150134 900706 i PDR ADOCK 05000002 p PDR'

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed m

(d (1) Steady State and Maximum Power Levels 39 The licensee is authorized to operate the facility at a steady state power level of 2.0 megawatts (thermal). The maximum power level shall not be in excess of 2.2 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 45, are hereby incorporated m the license. The licensee shall l 45 operate the facility in accordance with the technical specifications.

(3) Physical Security Plan The licensee shall fully implement and maintain in effect all provisions of the l 37 physical security plan approved by the Commission and all amendments and changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p),

respectively. The approved plan, which is exempt from public disclosure pursuant to the provisions of 10 CFR 2.790(d)(1), is entitled " Ford Nuclear Reactor Security Plan," Revision 1, submitted by letter dated May 17,1991, and supplemented February 17,1992.

D. This license is effective as of the date of issuance and shall expire twenty years from its date ofissuance.

O FoR mE NuCtEAR REoutAToRv CouuiSSios Director Division of Licensing Date ofIssuance: July 29,1985

Enclosure:

Appendix A,TechnicalSpecifications O

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28

( Amendment 45: Proposed i

r l

l l

APPENDIX A I l

l i TO FACILITY LICENSE R-28 l

l TECHNICAL SPECIFICATIONS  ;

! l DOCKET 50-2 lO l

MICHIGAN MEMORIAL PHOENIX PROJECT <

THE UNIVERSITY OF MICHIGAN ,

Ann Arbor, Michigan l l

i l l O

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed CONTENTS 1.0 DEFINITIONS 1 2.0 SAmTY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 5 2.1 Safety Limits 5 2.1.1 Sa lety Limits in the Forced Convection Mode 5 2.1.2 Safety Limits in the Natural Convection Mode 5 2.2 Limiting Safety 5jstem Settings (LSSS) 6 2.2.1 Limiting Safety System Settings in the Forced Convection Mode 6 2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode 7 3.0 LIMITING CONDITIONS FOR OPERATION 8 3.1 Reactivity Limits 8 3.2 Reactor Safety System 10 3.3 FNR Confinement Building 14 3.4 Primary Coolant Conditions 15 3.5 Airborne Effluents 16 3.6 Liquid Effluents 17 3.7 Limitations of Experiments 18 3.8 Fission Density Limit 19 4.0 SURVEILLANCE REQUIREMENTS 20 4.1 Reactivity Limits 20 4.2 Reactor Safety System 21 4.3 FNR Confinement Building 22 4.4 Primary Coolant System 23 4.5 Airbome Effluents 24 4.6 Liquid Effluents 24 4.7 Fission Density Limits 25 5.0 DESIGN FEATURES 26 5.1 Site Description 26 5.2 Reactor Fuel 26 5.3 Reactor Building 27 5.4 Fuel Storage 27 6.0 ADMINISTRATIVE CONTROLS 28 6.1 Organization 28 6.2 Review and Audit 30 6.3 Action to be Taken in the Event of a Reportable Occurrence 31 6.4 Operating Procedures 31 6.5 Operating Records 32 g 6.6 Reporting Requirements 33

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed O i.0 nEriNIrIONS 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 channel, including equipment actuation, alarm, and trip, and shall be deemed to include the channel test.

1 Channel 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.

Channel Test - A channel test is the introduction of a signal into the channel to verify that it is operating.

Experiment - An experiment, as used herein, is any of the following:

1. An activity utilizing the reactor system or its components or the neutrons or radiation generated therein;

2. An evaluation or test of a reactor system operation, surveillance, or maintenance technique;

3. An experimental or testing activity which is conducted within the confinement or containment system of the reactor;

4. The material content of any of the foregoing, including structural components, encapsulation or confining boundaries, and contained fluids or solids.

Experimental Facility - An experimental facility is any structure or device which is intended to guide, orient, position, manipulate, or otherwise facilitate a multiplicity of experiments of similar character.

Explosive Material - Explosive material is any solid or liquid which is categorized as a severe, dangerous, or very dangerous explosion hazard in DANGEROUS PROPERTIES OF INDUSTRIAL MATERIALS by N.I. Sax, Third Ed. (1963), or is given an Identification of Reactivity (Stability) Index of 2,3, or 4 by the National Fire Protection Association in its publication 704-M,1966.

Limiting Conditions for Operation (LCO) - Lowest functional capability or performance levels of equipment required for safe operation of the reactor (10CFR50.36).

Limiting Safety System Setting (LSSS) - Settings for automatic protective devices related to those variables having significant safety functions, and chosen so that automatic protective action will correct an abnormal situation before a safety limit is exceeded (10CFR50.36).

Measured Value - The measured value of a process variable is the value of the variable as indicated by a measuring channel.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed Measuring Channel- A measuring channel is the combination of sensor, amplifiers, and output devices which are used for the purpose of measuring the value of a process variable.

Moveable Experiment - A moveable experiment is one which may be inserted, removed, or manipulated while the reactor is critical.

Operable - Operable means that a component or system is capable of performing its intended function in its normal manner.

Operating - Operating means that a component or system is performing its intended function in its normal manner.

Potential Reactivity Worth of an Experiment - The potential reactivity worth of an experiment is the maximum absolute value of the reactivity cha,;;c hat would occur as a result of intended or anticipated changes or credible malfunctions that alter equipment position or configuration.

Reactivity Limits - The reactivity limits are those limits imposed on reactor core excess reactivity. Quantities are referenced specifically to a cold core (nominally 90 *F) with the effect of xenon poisoning on core reactivity accounted for if greater than or equal to 0.05%

A K/K. The reference core condition will be known as the cold, xenon free critical condition.

Reactor Operation - Reactor operation means that the control rods installed in the core Q are not fully inserted or that the control console key is in the keyswitch. Reactor operation is not considered possible when there are less than six standard fuel elements in addition to 38 the four control elements that house the control rods on the grid plate.

Reactor Safety System - The reactor safety system is that combination of safety channels and associated circuitry which forms the automatic protective system for the reactor or provides information which requires manual protective action to be initiated.

Reactor Scram - Shutoff of electrical current to the rod holding magnets and subsequent inser: ion of the rods into the core by gravity.

Reactor Secured - Reactor Secured is def~med as follows:

1. The full insertion of all control rods has been verified;

2. The control console key is removed; and

3. No operation is in progress which involves moving fuel elements to or from the core, moving reflector elements to or from the core, the insertion or removal of secured experiments from the core, or control rod maintenance.

Readily Available on Call - Readily available on call shall mean that an individual can 42 be contacted and is within a reasonable driving time (1/2 hour) from the reactor building.

Regulating Rod - The regulating rod is a control rod of low reactivity worth fabricated from stainless steel and used to control reactor power. The rod may be controlled by the O operator with a manual switch or by an automatic controller.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed O Removabie experiment - A removabie experiment is any experiment, experimental facility, or component of an experiment, other than a permanently attached appunenance to the reactor system, which can reasonably be anticipated to be moved one or more times l during the life of the reactor.

l Reportable Occurrence - A reponable occurrence is any of the following:

1. A safety system setting less conservative than the limiting setting established in the Technical Specifications;

2. Operation in violation of a limiting condition for operation established in the Technical Specifications;

3. A safety system component malfunction or other component or system malfunction which could, or threatens to, render the safety system incapable of performing its intended safety functions;

4. Release of fission products from a failed fuel element;

5. An uncontrolled or unplanned release of radioactive material from the restricted area of the facility;

6. An uncontrolled or unplanned release of radioactive material which results in concentrations of radioactive materials within the restricted area in excess of the limits specified in Appendix B, Table 1, Column 3, Derived Air 40 O Concentration (DAC) of 10CFR20;

7. An uncontrolled or unanticipated change in reactivity in excess of 0.005 AK/K;

8. Conditions arising from natural or man made events that affect or threaten to affect the safe operation of the facility;

9. An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the operation of the facility.

Rundown - A rundown is the automatic insertion of the shim safety rods.

Safety Channel - A safety channel is a measuring channel in the reactor safety system.

Safety Limit (SL) - Limits upon important process variables which are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity (10CFR50.36).

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed Secured Experiment - Any experiment, experimental facility, or component of an experiment is deemed to be secured, or in a secured position, if it is held in a stationary position relative to the reactor by mechanical means. The restraint shall exert sufficient force on the experiment to overcome the expected effects of hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or of forces which might arise as a result of credible malfunctions.

Shim-Safety Rod - A shim-safety rod is a control rod fabricated from either borated 41 ,

stainless steel or a boron-aluminum alloy which is used to compensate for fuel burnup, temperature, and poison effects. A shim safety rod is magnetically coupled to its drive unit allowing it to perform the function of a safety rod when the magnet is deenergized.

Static Reactivity Worth - The static reactivity worth of an experiment is the absolute  ;

value of the reactivity change which is measurable by calibrated control rod comparison methods between two defined terminal positions or configurations of the experiment. For moveable experiments, the terminal positions are fully removed from the reactor and fully inserted or installed in the normal functioning or intended position.

Time Intervals - The average over any extended period for each surveillance time interval 38 shall be closer to the normal surveillance time than the extended time. Any extension of these intervals shall be occasional and for a valid reason, and shall not affect the average as defined.

Annually - 12 to 15 months.

I d Biannually - 24 to 30 months.

Biweekly - 14 to 20 days. l 38 Daily - 24 to 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.

Monthly - 30 to 40 days.

Quarterly - 3 to 4 months.

Semiannually - 6 to 8 months.

Weekly - 7 to 10 days.

True Value - The tme value of a process variable is its actual value at any instant. )

Unscheduled Shutdown - An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, ec uipment malfunction, or a manual shutdown in response to conditions which could ac versely affect safe operation, not to include shutdowns which occur during testing or checkout operations.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor i Docket 50-2, License R-28

! Amendment 45: Proposed O 2.0 siveTv timirs 4No timiTiNo sieuTv sysTsu serriNos l 2.1 safety Limits 2.1.1 Safety Limits in the Forced Convection Mode

! Applicability:

i This specification applies to the interrelated variables associated with core I thermal and hydraulic performance in the steady state with forced l convection flow. These variables are:

Reactor Thermal Power, P l I

Reactor Coolant Flow Through the Core, m i Reactor Coolant Inlet Temperature, T Height of Water Above the Top of the Core, H Obiective:

To assure that the integrity of the fuel clad is maintained.

Specification:

I

1. The true value of reactor power (P) shall not exceed 4.68 Mw and the true value of flow (m) shall not be less than 900 gpm.

2. The true value of reactor coolant inlet temperatum (T) i at 2 Mw shall not exceed 116 *F.

3. The true value of water height above the core (H) shall not be less than 18 feet while the reactor is operating.

Bases

• I The basis for forced convection safety limits is that the calculated maximum cladding temperature in the bottom of the hot channel of the most compact FNR core (25 elements) will not reach the boiling point of the water coolant.

2.1.2 safety Limits in the Natural Convection Mode Applicability:

This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the natural convection mode of operation. These variables are:

Reactor Thermal Power, P Reactor Coolant Inlet Temperature, T, Height of Water Above the Top of the Core, H O

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed J Obiective:

To assure that the integrity of the fuel clad is maintained.

Specification:

1

1. The tme value of the reactor thermal power (P) shall not exceed 380 I kw.

l l 2. The true value of the reactor coolant inlet temperature (T) 3 shall not exceed 131 "F.

3. The height of pool water above the core (H) shall not be less than 18

feet.

Bases-The basis for natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact FNR core (25 elements) will not reach the boiling point of the water coolant at a depth of I8 feet.

l Limiting Safety System Settings (LSSS) 2.2 2.2.1 Limiting Safety System Setting in the Forced Convection Mode Applicability:

This specification applies to the set points for the safety channels monitoring reactor thermal power (P), primary coolant flow (m), height of water above the top of the core (H), core exit temperature (T,) and core inlet temperature 44 (T,).

Obiective:

To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.

Specification:

1. The limiting safety system settings for reactor thermal power (P),

primary coolant flow through the core (m), height of water above the top of the core (H), and reactor coolant exit temperature (T,)

shall be as follows:

Variable LSSS P (Max) 2.60 Mw l 39 l

m (Min) 900 gpm H (Min) 19 ft

{ T,(Max) 129'F Page 6

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

2. The limiting safety system setting for reactor coolant inlet 44 temperature at thermal power levels above 1.6 Mw shall be:

T,(max) = 114 *F Bases:

The limiting safety system settings for forced convection assure that automatic protective action will correct the most severe abnormal situation anticipated before a safety limit is exceeded.

2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode Applicability:

These specifications apply to the setpoint for the safety channels monitoring reactor thermal power (P), pool water level (H), and pool water temperature (T).

Obiective:

To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.

O sycincations:

1. The limiting safety system settings for reactor thermal power (P),

height of water above the top of the core (H), and pool water temperature (T) shall be as follows:

Variables LSSS P (Max) 100 kw H (Min) 19 ft T(Max) 129'F Bases The limiting safety system settings for natural convection assure that automatic protective action will correct the most severe abnormal situation anticipated before a safety limit is exceeded.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Limits l

Applicability:

This specification applies to the reactivity of the reactor core and to the reactivity l

worths of control rods and experiments. When the reactor is operated with the heavy water reflector tank in place, the limits will not include the static reactivity worth of the tank.

Obiective:

To assure that the reactor can be controlled and shutdown at all times and that the safety limits will not be exceeded.

Specification:

1. The shutdown margin relative to the cold, xenon free, critical condition si. ell be at least .025 AK/K with all three shim safety-rods fully inserted and the regulating rod fully withdrawn and 0.0045 AK/K with the most reactive 38 shim-safety rod and the regulating rod fully withdrawn, except during the process of verifying shutdown margin.

O 2. The overall core excess reactivity including moveable experiments shall not exceed 0.0436 AK/K. l 35

3. The reactivity worth of experiments shall be limited as follows, except 38 during the process of verifying experiment reactivity:

Maximum Exneriment Reactivity Wonh Individual Moveable 0.0012 AK/K Individual Secured 0.012 AK/K Total Moveable and Secured 0.012 AK/K

4. The reactor shall be suberitical by at least 0.025 AK/K during fuel movements to and from the reactor core. l 38

5. The reactor shall be suberitical by at least 0.10 AK/K before shim-safety 38 rods are removed S am the core.

6. The reactor shall be suberitical by at least 0.10 AK/K whenever heavy water l 38 movements that can result in positive reactivity insertions are undertaken.

Q 7. The reactivity worth of the regulating rod shall not exceed 0.006 AK/K.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed O

8. Experiments that could increase reactivity by flooding, shall not remain in or adjacent to the core unless the shutdown margin required in Specification

, 3.1.1 would be satisfied after flooding.

1 Bases-The shutdown margin required by Specification 3.1.1 assures that the reactor can be shutdown from any operating condition and will remain subcritical after cooldown and xenon decay even if the rod of the highest reactivity worth should be in the fully withdrawn position.

Specification 3.1.2 limits the allowable excess reactivity to the value necessary to overcome the combined negative reactivity effects of: (1) an increase in primary coolant temperature from 90 F to 116 F; (2) fission product xenon and samarium buildup in a clean core; (3) power defect due to increasing from a zero power, cold core to a 2 Mw, hot core; (4) fuel burnup during sustained operation for 30 days; and (5) moveable experiments.

Specification 3.1.3 limits the individual reactivity worth of moveable experiments to 38 values that will not produce a stable period of less than 30 seconds and which can be compensated for by the action of the control and safety systems without exceeding any safety limits.

Specification 3.1.3 limits the reactivity worth of secured and total experiments to O values of reactivity which, if introduced as positive step changes, will not cause 38 fuel melting.

Specifications 3.1.4 and 3.1.5 provide assurance that the core will remain suberitical during fuel movements to and from the core and during shim-safety rod l 38 maintenance or inspection.

The largest positive reactivity increase that can be produced by replacing light water l 33 with heavy water in the heavy water reflector tank is 0.04 AK/K. Maintaining the core suberitical by at least 0.10 AK/K in Specification 3.1.6 during heavy water  ! 4I transfers provides adequate margin to assure that the reactor will remain suberitical during heavy water transfers that could add positive reactivity.

Specification 3.1.7 assures that failure of the automatic control system will not introduce sufficient excess reactivity to produce a prompt critical condition.

Specification 3.1.8 assures that the shutdown margin required by Specification 3.1.1 will be met in the event of a positive reactivity insertion caused by the flooding of an experiment.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed 3.2 Reactor Safety System Applicability:

These specifications apply to the reactor safety system and other safety related instmmentation.

Objective:

To specify the lowest acceptable level of performance or the minimum number of acceptable components for the reactor safety system and othu safety related instrumentation.

Specification:

The reactor shall not be made critical unless:

1. The reactor safety systems and safety related instrumentation are operable in accordance with Tables 3.1 and 3.2 including the minimum number of channels and the indicated maximum or minimum setpoints;

2. All shim-safety rods are operable;

3. The time from the initiation of a scram condition in the scram circuit until the shim-safety rods are fully inserted (release-drop time) shall not exceed 500 O milliseconds;

4. Mechanical devices are installed which prevent the lifting of fuel elements through the movement of control rods.

Basps:

Neutron flux level scrams provide redundant automatic protective action to prevent exceeding the safety limit on reactor power. The period scram limits the rate of rise of the reactor power to periods which are manually controllable without reaching excessive power levels or fuel temperatures.

Power-flow coincident scrams provide redundant channels to assure that an automatic loss of flow scram will occur in the event of a loss of flow when the reactor is operating at power levels above 100 kw.

The rod withdrawal interlock on the Log Count Rate channel assures that the operator has a measuring channel operating and indicating neutron flux levels during the approach to criticality.

The reactor coolant inlet temperature, reactor coolant exit temperature, reactor pool 44 temperature auto mndown functions and the pool level auto mndown assure that the reactor will not be operated above the safety limit for core inlet temperature and below the safety limit for pool level in either natural or forced ccavection mode. l 44 O

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor l Docket 50-2, License R-28 Amendment 45: Proposed b

b The manual scram button and the magnet power keyswitch provide two methods for the reactor operator to manually shutdown the reactor if an unsafe or abnormal condition should occur and the automatic reactor protection does not function.

The use of the area radiation monitor system assures that areas of the facility in which a high radiation area could exist are monitored.

Specifications 3.2.2 and 3.2.3 assure that the safety system response will be appropriate.

Mechanical holddown devices specified in 3.2.4 ensure that a fuel element cannot 38 be lifted from the core by withdrawal of a control rod and be released back into the core resulting in a sudden positive reactivity insertion.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed REQUIRED SAFETY CHANNELS Minimum Number Channel Setooint Required Function Log Count Rate 2 cps 1 Rod WithdrawalInterlock Log N Period I Wide range powerlevel, powerlevelinterlocks,and l 44 i input for period scram j Period Safety 5 see 1 Scram Level Safety 122.5% (2.45 Mw) 2 Scram l 39 High Power /No (a) 900 gpm 1 Scram > 100 kw Water Flow (b) holdup tank isolation valve not fully open (c) holdup tank static pressure 1 psig below full power value High Power!

O Header Down 1 Scram > 100 kw Header Up/ 900 gpm 1 Scram No Water Flow Building Exhaust 1 mrem /hr 1 Scram Radiation Level Building Alarm 1 Scram  !

Manual Switch Manual Scram Switch 1 Scram ,

4 Magnet Power Keyswitch 1 Scram Reactor Coolant 44 Inlet Temp. I14'F 1 Auto Rundown 21.6 MW Reactor Coolant Exit Temp. 129'F 1 Auto Rundown Reactor Pool 44 Temperature 129*F 1 Auto Rundown Pool Level 1 foot below pool overflow 1 Auto Rundown Bridge Not Clamped When clamps released 1 Scram Page 12

1 l

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 l Amendment 45: Proposed Table 3.2 REQUIRED SAFETY RELATED INSTRUMENTATION Minimum Number Instrumentation Setpoint Required L ... tion l Linear Level Channel As Required 1 Linear powerlevel measurement and input for the automatic control mode

)

l Power 1.evel 95% of control 1 Retum reactor to manual  :

Deviation Interlock point setting control mode if setpoint is i mached Reactor Coolant Not Applicable l' Provide information for Inlet Temperature reactor powerlevel 38 determination by heat balance Facility Radiation Monitor System l 45

1. Building Air Exhaust 1(1)6 mrem /hr 1 Alarm, scram, initiate confinement evacuation dp 2. Reactor Bridge 40(50)6 mrem /hr 1 Alarm l 45

3. NW Column, 20(50)6 mrem /hr l' Alarm l 45 Beamport Floor

4. N Wall, Beamport 5(50)6 mrem /hr l' Alarm l 45 Floor

5. NE Column, 5(50)6 mrem /hr l' Alarm l 45 Beamport Floor Footnotes: l 38

a. Not required for natural convection operation.

b. The facility radiation monitoring system consists of 5 radiation detectors which alarm and read l 39 out locally, and are recorded in the control room. The normal setpoints for this system are shown. The value in parentheses is the maximum setpoint which will be used depending on local conditions. Use of higher than normal setpoints will require approval of the Nuclear Reactor Laboratory Manager or one of the Assistant Managers. Any reactor sta adjust a setr sint lower than the normal value.

c. If facility radiation monitor 3.,4., or 5. is placed out of service for a period of more than 7 38 days, the reactor shall be shut down or the monitor shall be replaced by a locally alarming unit of similar range. Should a second of these monitors be placed out of service, the reactor will be shut down unless the monitor is retumed to service viithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or is replaced by a pd second locally starming unit of similar range.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed l 3.3 FNR Confinement Hullding Applicability:  !

This speci5 cation applies to the Ford Nuclear Reactor confinement building requirements. l Obiective:

To assure that the Ford Nuclear Reactor Building confinement integrity is 38 maintained during reactor o wration and to minimize the release of airborne radioactive materials from tie reactor building.

1 Specification:

1. When the radiation level in the Ford Nuclear Reactor ventilation exhaust 38 duct is equal to or greater than one mrem /hr:

a. The reactor building ventilation supply and exhaust fans shall automatically tum off;

b. The reactor building venti!ation supply and exhaust dampers shall automatically close; p c. The beampon exhaust damper to Stack 2 shall automatically close; and

d. The room 3103 hood exhaust damper to Stack 2 shall automatically close.

2. During reactor operation, the f ollowing conditions will be administratively controlled:

a. Personnel access doors will be closed except as necessary for the passage of personnel and/or equipment;

b. The main equipment access door onto the beamport floor will be opened only long enough to permit the passage of equipment;

c. The personnel door to the cooling tower area will remain clamped except to permit the passage of personnel and/or equipment to the cooling tower area. The door will remain closed but not clamped until all personnel have left the cooling tower area;

d. The access hatch from grade level to the beamport floor will be sealed closed;

e. The personnel exit door located in the north wall of the building will 38 be sealed; and O

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

f. The door located on the beamport floor which connects to the Phoenix Memorial Laboratory hot cave operating area will be clamped closed.

Bases:

The potential radiation exposure to persons at the operations boundary following an accident releasing fission products within the confinement building has been evaluated. The evaluation used a leakage rate from the confinement building of 10% of the building volume per day, and concluded that the accident doses would be acceptable. Conformance to Specifications 3.3.1 and 3.3.2 will assure that the building leak rate will not exc ed the leak rate used in the evaluation.

The 1.0 mrem /hr setpoint for the facility exhaust radiation monitor provides a mechanism for isolating the building vendiation system in the event of a significant release of radioactive material into the reactor building. This setpoint, for the detector location involved, represents a gamma emitting nuclide concentration of 4

10 to 10" microcuries/cc of building air.

By requiring that the access doors and equipment hatch remain closed, except for brief, attended periods to permit personnel or equipment passage, the integrity of the confinement will be maintained at or above the level assumed in the Hazards l 38 Summary Report, and the release of radioactive material will be minimized.

3.4 Primary Coolant Conditions Applicability:

This specification applies to the limiting conditions for available pool water volume, primary coolant pH, conductivity, radioactivity, and flow distribution.

l 38 Obiective:

To maintain the primary coolant in a condition to minimize the corrosion of the primary coolant system, fuel clad, and other reactor components, and to assure proper conditions of coolant for normal and emergency requirements.

Specification:

1. The primary coolant pH shall be maintained between 4.5 and 7.5.

2. The primary coolant conductivity shall be maintained at a value less than 5 38 micromho/cm except for periods of time not to exceed 7 days when the conductivity may not be greater than 20 micromho/cm.

3. For operation at power levels in excess of 100 kw in the forced convection mode, all grid positions shall contain fuel elements, reflector elements, sample holders, or experimental facilities.

l 38

4. When the reactor is in operation, the pool gate must be in its storage l 38 Q location.

Page 15

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed Experience at this and other facilities has shown that the maintenance of primary coolant system water quality in the ranges specified in Specification 3.4.1 and 3.4.2 will control the corrosion of the aluminum components of the primary coolant sp'em and the fuel element cladding.

Specification 3.4.3 that all grid positions be occupied will prevent the degradation of flow rates due to flow bypassing the active fueled mgion through an unoccupied grid plate position.

Specification 3.4.4 that the gate be stored assures that the full volume of the pool water is available to provide cooling of the core during normal operation and in the event of a loss of coolant accident.

3.5 Airborne Effluents Applicability:

This specification applies to the monitoring of airborne effluents from the Ford Nuclear Reactor.

Obiective:

To assure that the release of airbome radioactive material from the Ford Nuclear O Reactor is maintained below the limits established in 10CFR20.

l 38 l

Specification:

1. The concentration of radioactive materials in the effluent released from the facility exhaust stacks shall not exceed 400 times the concentrations i specified in 10CFR20, Appendix B, Table 2, Column 1. Air Effluent 40 Concentration (EAC), averaged over time periods permitted by 10CFR20.

2. During operation of the reactor, the following conditions shall be met:

a. The mobile air particulate monitor and the gaseous activity detector 38 for the Stack 2 exhaust shall be operating. If either unit is out of service for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, either the reactor shall be shutdown or the unit shall be replaced by one of comparable monitoring capability;  ;

b. The reactor pool floor mobile air particulate monitor and the gaseous 38 activity detector for the reactor building exhaust stack shall be operating. If either unit is out of service for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, either the reactor shall be shutdown or the unit shall be replaced by one of comparable monitoring capability;

c. The building exhaust air radiation monitor shall be operating whenever the reactor is in operation as required by Table 3.2 of Q specification 3.2.

Page 16

OPERATING LICENSE AND TECIINICAL SPECIFICATIONS l Ford Nuclear Reactor l Docket 50-2, License R-28 Amendment 45: Proposed

\ Bases-The limits established in specification 3.5.1 incorporate a dilution factor of 400 for l 38 effluents released through the exhaust stacks. This dilution factor was calculated from actual FNR site meteorological data and represents the lowest dispersion factor determined and the highest frequency of wind in any sector. Because of the use of the most conservative measured values of wind directional frequency and dispersion factors, this dilution factor will assure that concentrations of radioactive material in unrestricted areas around the FNR site will be far below the limits of 10CFR20.

The requirements of specification 3.5.2 are considered adequate to assure proper i airborne effluent monitoring. l 38 I 3.6 Liquid Effluents Applicability:

This specification supplies to the monitoring of radioactive liquid effluents from the FNR. l l

Obiectives:

The objective is to assure that exposure to the public resulting from the release of liquid effluents will be minimized.

Specification:

1. The concentration of radioactive materials in the effluent released from the facility liquid waste system to the city of Ann Arbor sanitary sewer system shall be readily soluble (or readily dispersible biological material) in water 40 and shall not exceed 315 times the concentrations specified in 10CFR20, i Appendix B, Table 3, Releases to Sewers.

2. The amount ofliquid discharged shall be limited to the equivalent of 3,000 33 1 gallons ofliquid at the concentration limit specified in 3.6.1 each day. 38

3. Liquids from the facility's radioactive liquid waste system shall not be discharged into the storm drain system.

Bases:

All radioactive liquid effluents are collected in a series of three,3,000 gallon, coated, steel retention tanks, and they are normally recycled to the reactor pool to 40 make up for surface evaporation. However, after sampling, analysis, and dilution, if the concentration of radioactivity is less than the limit of 10CFR20, liquid effluents can be discharged to the sanitary sewer system.

I f~\

v Page 17 L_ _ __ _ . . . _ _ _ _ _ _ _ _ _ _

i OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed A

V In the past, less than 50 retention tank discharges per year have been required. l 38 During 1970, the Nonh Campus water released into the sanitary sewer system averaged 946,000 gallons per day. This provides a daily dilution factor of 315 for a 3,000 gallon waste tank, which assures that there will be no significant exposure to the public from radioactive waste discharged to the sanitary sewer system.

3.7 Limitations of Experiments Applicability:

This specification applies to experiments installed in the FNR.

Objective:

To prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.

Specification:

1. Each experiment shall be designed so that the surface temperature shall be below the temperature calculated for the inception of nucleate boiling. Prior to insertion in the reactor, any capsule which is expected to operate with an internal pressure in excess of one atmosphere shall be tested at a pressure twice the calculated maximum pressure.

2. All experiments which are in contact with reactor coolant shall be either corrosion resistant or encapsulated within corrosion resistant containers.

3. Explosive materials shall not be placed in the reactor pool.

4. Neutron radiography of explosives shall be conduc .d with the explosives contained in a blast proof irradiation container, a prototype of which has been successfully tested and demonstrated not to fail by detonation of at least twice the amount of explosive to be irradiated.

5. The radioactive material content, including fission products, of any singly encapsulated experiment should be limited so that the complete release of all gaseous, paniculate, and volatile components from the encapsulation could not result in doses in excess of 10% of the equivalent annual doses stated in 10CFR20. This dose limit applies to persons occupying unrestricted areas continuously for two hours starting at time of release and restricted areas during the length of time required to evacuate the restricted area.

6. The radioactive material content, including fission products, of any doubly encapsulated experiment should be limited so that the complete release of all gaseous, particulate, or volatile components from the er. capsulation could not result in doses in excess of the equivalent annual doses stated in 10CFR20. This dose limit applies to persons occupying unrestricted areas continuously for two hours starting at the time of release and restricted areas during the length of time required to evacuate the restricted area.

%/

Page 18

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed Bases:

Specifications 3.7.1 through 3.7.4 are intended to reduce the likelihood of damage l 38 to reactor components and radioactivity releases resulting from experiment failure l and serve as a guide for the review and approval of new and untried experiments by l

facility personnel and the Safety Review Committee.

Neutron radiography is conducted in a vertical beam tube and at horizontal beamports that terminate at the heavy water reflector tank adjacent to the reactor core. In the radiography of explosives, the explosive devices will be contained, during exposure, inside a blast proof enclosure. The enclosure will not be coupled to the beamtube or beamport and will be constructed to fully contain any blast effects or missiles which might be generated by an accidental detonation.

Specifications 3.7.5 and 3.7.6 confomi to the regulatory position put forth in l 38 Regulatory Guide 2.2 issued November,1973. The calculations for experiment radioactivity limits are provided in section 14.3 of the SAFETY ANALYSIS.

3.8 Fission Density Limit Applicability:

This specification applies to fission density limits in FNR fuel.

Objective:

To prevent fuel plate swelling which could result in clad rupture and release of radioactive fission products.

Specification:

1. The FNR fission density limit shall be 1.5x10 2' fission /cc.

bases:

The fission density limit is below operational fission densities reached in other operating reactors using the same kind of fuct without failures attributed to the fuel.

An uraniumexperimental oxide (U3 0,), anddata base uranium silicide that (U 3Sisupports the up

2) fuel in the FNR safe use to the of uranium aluminid fission density limit was derived from irradiation tests performed in the Materials Test Reactor (MTR), the Engineering Test Reactor (ETR), and the Advance Test Reactor (ATR) at the Idaho National Engineering Laboratory, the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, and the Getman Karlsruhe FR2 reactor.

O Page 19

l l

l OPERATING LICENSE AND TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor Docket 50-2, License R-28 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactivity Limits i

Applicability:

This specification applies to the surveillance requirements for reactivity limits.

Obiective: l l

To assure that the reactivity limits of Specification 3.1 are not exceeded. )

)

Specification: 1

1. Shim safety rod reactivity worths shall be measured:

a. Annually; l 38

b. Whenever the fuel elements in more than three interior core locations are replaced;

c. Whenever the replacement of a fuel element in an interior core location results in an element fuel mass change of more than 10% in that location; O d. whenever the additien ef mere than three standard fuei eiements to the outer faces of the core is made to achieve the desired excess reactivity for the operation of the reactor. l 38

2. Shim safety rods shall be visually inspected and put through ajig to check for swelling at least annually.

3. The reactivity woith of those experiments whose safety review indicates a need for such a determination shall be measured prior to the experiment's initial use. That worth shall be verified if core configuration changes occur which could reasonably be expected to cause increases in ex rriment reactivity worth whereby the experiment worth could exceec the values specified in Specification 3.1.

4. The core negative reactivity required during heavy water transfers will be l 33 verified whenever heavy water transfers are to be made.

Basss:

Specification 4.1.1 will assure that shim-safety rod reactivity worths are not degraded or changed by core arrangements.

A U

Page 20

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed Shim-safety rod inspections are the single, largest source of radiation exposure to facility personnel. Furthermore, frequent inspections of shim-safety rods for swelling over the last ten years have produced no evidence of sweiheg or cracking.

In order to minimize personnel radiation exposure and provide an inspection frequency that will detect early evidence of swelling and cracking, an annuai inspection interval was selected for Specification 4.1.2.

The specified surveillance relating to the reactivity wonh of experiments will assure that the reactor is not operated for extended periods before determining the reactivity worth of experiments. This specification also prcvides assurance that experiment reactivity wonhs do not increase beyond the established limits due to core configuration changes.

Actual verification of the core negative reactivity required for heavy water transfers l 33 will assure the reactor stays suberitical under all possible circumstances during heavy water transfers.

4.2 Reactor Safety System Applicability:

This specification applies to the surveillance of the reactor safety system.

Objective:

O To assure that the reactor safety system is operable as required by Specification 3.2.

Specification:

1. A channel test of the neutron flux level safety channels, period safety channel, log count rate channels, and power-flow coincidence scrams shall be performed:

a. Prior to each reactor stanup following a period when the reactor was secured;

b. After a channel has been repaired or deenergized.

2. A channel calibration of the safety channels listed in Table 3.1, which can be calibrated, shall be performed annually. l 38

3. A channel check of the neutron flux level safety channels during reactor operation comparing the channel outputs with a heat balance, shall be performed shortly after reaching operating power level and weekly thereafter if the reactor is to be operated at a thermal power level above 500 kw.

4. The operation of the radiation monitoring system required in Table 3.2 shall be verified:

l 38 Q a. Prior to each reactor stanup following a period when the reactor was secured; 38 Page 21

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

! O b. After a channel has been deenergized. l 38 l

l c. If a channel has been repaired, an operation and setpoint verification will be performed prior to use.

l

5. The radiation monitor system required in Table 3.2 shall be calibrated semiannually. l 38 i

l 6. Shim-safety rod release-drop time shall be measured:

a. Annually; l 38

b. Whenever a shim-safety rod's core location is changed;

c. Whenever maintenance is performed that could affect the rod's drop time.

I l

Bases-1 Prestartup tests of the safety system channels assure their operability. Annual calibration detects any long term drift that is not detected by normal intercomparison of channels. The channel check of the neutron flux level channels assures that the detectors are properly adjusted to accurately monitor the parameter they are measurmg.

Radiation monitors are checked for proper operation in Specification 4.2.4.

Calibration and setpoint verification involve use of a calibration source and significant personnel radiation exposure. Semiannual calibration of radiation l 38 monitors, which have displayed excellent stability over many years of operation, is adequate to verify the setpoint unless instrument repairs have been made.

i The measured release-drop times of the shim-safety rods have been consistent since the installation of the boron / stainless steel shim safety rods in 1962 and the boron- 41 aluminum alloy shim-safety rods in 1994. Annual check of these parameters is considered adequate to detect any deterioration which could change the release-drop time. Binding or rubbing caused by rod misalignment could result from maintenance; therefore, release drop times will be checked after such maintenance.

4.3 FNR Confinement Building Applicability:

This specification applies to the surveillance of the facility openings and dampers.

Objective:

To assure that the condition of the closure devices for the building openings are in satisfactory condition to assure their ability to provide adequate confm' ement of any airbome radioactivity released into the building.

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Page 22 l i l

! I

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed O Specification:

1. Operation of the dampers described in Specification 3.3.1 shall be tested l 38 whenever a complete checkout of the reactor control system is required prior i to startup. This functional test will be a portion of the startup checklist for the facility.

2. The condition of the following gaskets shall be inspected semiannually, and l 38 the gaskets shall be replaced whenever any evidence of deterioration is found:

a. Building ventilation system intake and exhaust dampers;

b. Personnel access doors;

c. Equipment access doors;

d. Cooling tower access door Bases The prestart check of the main damper function provides assurance that the automatic function provided by these dampers will be actuated when confinement isolation is required. The semiannual inspection of gasket materials, since these O materials are not in a damaging atmosphere, will provide assurance that the gaskets will perform their function of limiting leakage through these openings in the event of a release of airborne activity into the building.

4.4 Primary Coolant System Applicability:

This specification applies to the surveillance of the primary coolant system.

Objective:

To assure high quality pool water and to detect the release of fission products from fuel elements.

Specification:

1. The pH of the primary coolant shall be measured weekly.

2. The conductivity of the primary coolant shall be measured weekly.

l 38

3. The radioactivity content of the primary coolant shall be measured biweekly. l 38

4. A record of pool makeup water shall be maintained to discover significant leakage of primary coolant from the facility.

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed Bases-Regular surveillance of pool water quality and radioactivity provides assurance that pH and conductivity changes that could accelerate the corrosion of the primary coolant system would be detected before significant corrosive damage would occur, and that the presence ofleaking fuel elements in the reactor is detected.

Routine inspection of makeup water needs over a period of time provides early l l

warning of small pool water leaks.

4.5 Airborne Effluents Applicability: l This specification applies to the surveillance of the monitoring equipment used to measure airborne radioactivity.

Obiective:

~

l The objective is to assum that accurate assessment of airbome effluents can be made. j l

Specification: 1

1. The building exhaust air radiation monitor shall be calibrated semiannually. l 38

2. The mobile air particulate monitors shall be calibrated semiannually.

l 38

3. The gaseous activity detectors shall be calibrated for Argon-41 semiannually.

'I 38

4. The operation of all airborne activity monitors shall be checked daily except when the reactor staffis not present in the facility.

Bases-Experience with the electronic reliability and calibration stability of the units used by '

i the Ford Nuclear Reactor demonstrates that the above periods are reasonable surveillance frequencies.

4.6 Liquid Effluents Applicability:

This specification applies to the surveillance of the monitoring equipment used to measure the activity in liquid effluents.

Objective:

The objective is to assure that accurate assessment ofliquid effluents can be made.

Page 24

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

1. The monitoring equipment used to measure the radioactive concentrations in the waste retention tank contents shall be calibrated semiannually when 38 releases are made to the sanitary sewer. 40

2. The contents of each tank released shall be sampled and evaluated prior to its release.

Bases Experience with the counting equipment used in measuring the radioactivity in the waste retention tanks suggests that the above period is a suitable calibration frequency. Waste water is normally recycled to the reactor pool. Consequently, 40 discharges are not normally made to the sewer and calibrations are not normally needed.

4.7 Fission Density Limits Applicability:

This specification applies to the surveillance requirements for fission density limits.

Obiective:

To assure that the fission density limits of Specification 3.8 are not exce.eded.

l 38 Specification:

1. The fission density of all fuel elements which have uranium-235 burnup shall be calculated at least quarterly.

Bases:

Determination of fission densities on a quarterly basis will ensure the th : fission density limits of Specification 3.8 are not exceeded. Fuel element s'..a m will be l 38 kept well below levels which could result in clad rupture and release oi . . aactive fission products.

O Page 25

OPEPATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 5.0 DESIGN FEATURES 5.1 Slie Description The Ford Nuclear Reactor (FNR) is located on the Nonh Campus of the University of Michigan at Ann Arbor, Michigan. The North Campus ama is under the administrative control of the Regents of the University of Michigan.

l The Nonh Campus is a tract of nearly 900 acres, about 1-1/2 miles northeast of the l

center of Ann Arbor. It is bounded on the north by Plymouth Road and on the south by Glazier Way. A VA hospital and some apartments are south of Glazier 38 Way Apanments are located north of Plymouth Road. Open land and the 40 Arborcrest Cemetery lie to the east. To the west are University athletic fields, municipal parks and a wooded ridge. The Huron River flows through land bordering the area on the west and south and some marsh land lies adjacent to the river on the south.

Tb reactor building is located near the center of the North Campus area. No 40 housing or buildings containing housing facilities are erected within 1500 feet of the reactor.

l The University of Michigan controls all the land within 1500 feet of the reactor site, with the exception of a small portion of the highway right of way along Glazier Way on the southeast and the Arborcrest Cemetery located 800 feet to the east of the l 38 site.

The reactor site consists of all the land 500 feet to the east,1000 feet to the west and north and 1200 feet to the south. The boundary of this area consists of roadways around the site whose traffic flow can be controlled should such control be desirable.

The mactor restricted area consists of the reactor building and the contiguous Phoenix Memorial Laboratory (PML). The reactor buildiag is the operations boundary and the emergency planning zone.

5.2 Reactor Fuel The fuel assemblies shall be of the MTR type, consisting of plates containing uranium aluminide (UAl,), uranium oxide (U3 0.), or uranium silicide (U3 Si 2 ) fuel l 34 enriched to less than 20% in the isotope U235 clad with aluminum. The authorized fuel assembly designs are:

l Maximum Maximum Number Plate leading Assembly Loading

! p1Phics (g U235) (g U235) 18 9.28 +/- 2% 167 +/ 2%

l 9 9.28 +/- 2% 84 +/- 2%

O Page 26 L - - - - - - _ _ _ _ _ _ _ _ -

l l

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 5.3 Reactor Bulfding The reactor building is a windowless, four story, reinforced concrete building with 12 inch walls structurally integral with the footmgs and foundation mats. The l- building is approximately 69 feet wide x 68 feet long x 70 feet high with approximately 44 feet exposed above grade. The building has the following general features:

l 1. The reactor is housed in a closed room designed to restrict leakage.

2. The reactor room is equipped with a ventilation system designed to exhaust air or other gases present m the building atmosphere into an exhaust stack which exhausts a minimum of M feet above ground level.

3. The ventilation system provides ventilation for certain storage and experimental facilities and exhaurts these a minimum of 54 feet above ground level.

4. The openings into the reactor building are an equ,ipment access door, three personnel doors, an equipment access hatch, air mtake and exhaust ducts, room 3103 fume hood exhaust duct, beamport ventilation duct, a sealed north wall door, a door between the hot cave operating face and the beamport floor, a sealed foundation tile drain to the cold sump, and a 40 r to e i t oen or a tory.

5.4 Fuel Storage

1. Irradiated fuel elements and fueled devices shall be stored in an array which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device tempeeture will not exceed 100 "C.

2. All reactor fuel elements and fueled devices shall be stored in a geometric array which assures subcriticality. The array spacings will be based on the experimental results reported in ORNL-CF-58-9-40 for stc, rage array experiments performed with Oak Ridge Reactor and Bulk Shielding Facility fuel elements, i

i j

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Page 27

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Aniendment 45: Proposed 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization

1. The organization! stnicture of the University of Michigan relating to the h Ford Nuclear Reactor (FNR) shall be as shown in Figure 6.1.

2.

The Nuclear Reactor Laboratory Manager shall be responsible for that all operations are conducted in a safe manner and within the limits prescribed by the facility license, including the technical specifict.nons and operating procedurer. During periods of his absence, his responsibilities ,

are delegated to the Assistant Man iger for Operations or to the Assistant 33

}

Manager for Research Support Activities.

3. In all matters pertaining to the operation of the plant and these technical specifications, the Nuclear Reactor Laboratory Manager shall report to and be directly responsible to the Dircctor, Michigan Memorial-Phoenix Project.

l 33

4. Qualifications, Nuclear Reactor Laboratory Manager and Assistant

} Managers: Minimum qualifications for the Nuclear Reactor Laboratory l 33 Manager and Assistant Managers shall be bachelor's degrees and at least four years of reactor operating experience in increasingly responsible positions. Years spent in graduate study may be substituted for operating 9 experience on a one for one basis up to a maximum of i co years. Within six months after being assigned these positions, the Nuclear Reactor 33 Laboratory Manager and the Assistant Managers shall apply for NRC senior operatorlicenses if they do not already hold licenses.

5. A health physicist who is organizationally independent of the Ford Nuclear Reactor operations group shall be responsible for radiological safety at the facility.

6. A licensed operator or licensed senior operator pursuant to 10CFR55 shall be present in the control room whenever the reactor is in operation as defined in these specifications. The minimum operating crew shall be 33 composed of two individuals, at least one of whom shall be a licensed anior reactor operator.

7. The Nuclear Reactor Laboratory Manager, one of the Assistant Managers, 33 or a licensed senior reactor operator shall be readily available on-call 24 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> per contacting day,supervisor the on-call seven shall days per week.

be known Theoperator to the reactor identity or of and metho shutdown watchman on duty.

8. Licensed operators are not required to be present in the facility when the l 38 reactor is secured.

9. All licensed operators at the facility shall participate in an approved operator requalification program as a condition of their continued assignment to g operator duties.

Page 28

i OPERATING LICENSE AND TECHNICAL SPECIFICA110NS Ford Nuclear Reactor Docket 50-2, License R-28

{

Amendment 45: Proposed Figure 6.1 Organization Chart for the Ford Nuclear Reactor Regents l 34 University of Michigan President

}

Provost and Executive Vice Executive Vice President 45 President for Academic Affairs and Chief Financial Officer Vice President Associate Vice President~~~~ 45 Research for Business Operations l

l s

O Director Director l Michigan Memorial-Phoenix Project Occupational Safety and i 45

- Environmental Health l 8

e i s I I i i I i

! Safety Review  !

~~

Committee Director ,,,,j Radiation Safety l 45 I

Nuclear Reactor ____________________________ Health Physicist Laboratory Manager l l l

Assistant Manager Assistant Manager Reactor Operations Research Support Activities l

\

Line Function  !

h Licensed Operators

~~~~~~~'

Safety and Licensing Function Page 29

_j

I-OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor l Docket 50-2, License R-28 Amendment 45: Proposed 6.2 Review and Audit

1. A Safety Review Committee (SRC) shall review reactor operations and advise the Director, Michigan Memorial-Phoenix Project, m matters relating to the health and safety of the public and the safety of facility operations.

2. The Safety Review Committee shall have at least eight members of whom no more than the minority shall be from the line organization shown in Figure 6.1 or shall administratively report to anyone in that line organization below the Vice President for Research. The Committee shall be made up of 43 University faculty and staff and an individual from outside the University appointed by the Vice President for Research who shall collectively provide l experience in reactor engineering, instrumentation and control systems, radiological safety, and mechanical and electrical systems.

3. The Committee shall meet at least semiannually.

4. A quorum shall consist of not less than a majority of the full conunittee and shall include the chairman or his designated altemate.

5. Those changes, experiments, and tests that require specific SRC review must be approved by a majority of the full Committee Membership. Votes l 43 may be cast at SRC meetings or via individual polling of members.

6. Minute:, of each Committee meeting shall be distributed to the Director, O- Michigan Memorial-Phoenix Project, all Safety Review Committ'ee i members, and such others as the chairman may designate. l

7. The Safety Review Committee shall: I

a. Review and approve proposed experiments and tests utilizing the j reactor facility which are significantly different from tests and i experiments previously performed at the Ford Nuclear Reactor. In  !

the event of a disagreement over approval of an experiment between the Committee and the Nuclear Reactor Laboratory Manager, the l 33 i matter shall be referred to the Director, Michigan Memorial-Phoenix Project for resolution.

b. Review reportable occurrences.

c. Review and approve proposed standard operating procedures and proposed changes to standard operating procedures. This requirement pertains to those procedures prepared pursuant to Section 6.4 of these specifications,

d. Review and approve proposed changes to the technical specifications and proposed amendments to the facility license and review proposed changes to the facility made pursuant to 10CFR50.59(c).

O e. Review the audit report provided by the consultant for reactor operations.

Page 30

l OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 l Amendment 45: Proposed l 8. A consultant will be retained by the University of Mich:gan to perform an annual audit of reactor operations and the safety of facility operations. The consultant shall be selected by the Director, Michigan Memorial-Phoenix

}ioject and shall be an individual presently or recently engaged in the mr.nagement of a research or test reactor of comparable oower level and type. He shall provide a report on the conclusions drawn from that audit to  :

the Director, Michigan Memorial-Phoenix Project. The Director shall l provide the members of the Safety Review Committee with copics of this report.

9. The audit shall be conducted with the following guidelines:

a. At least once every five years, a broad review will be made of the l 34 following areas: (1) Administration; (2) Safety Review Committee; (3) Reactor operators; (4) Procedures; (5) Surveillance; (6) Quality Assurt.nce P; agram; (7) Logs and Records; (8) Experiments; (9)

Emergency Plan; (10) Security Plan; and (11) Health physics >

support. The purposes of the review are: (1) Evaluate the adequacy l of the organization, training, plans, procedures, surveillance, and l records for safe operation of the facility; (2) Verify that the requirements of Technical Specifications are being met; (3) Establish whether plans and procedures are being implemented; and (4)

Determine whether responsibilities within the organization are appropriate.

b. Routine audits will review a limited number of systems in depth l 34 each year and will include as applicable to each system: (1)

Operating procedures and records:(2) Calibration procedures and records; (3) Equipment operation, condition, and failures; (4)

Modifications; and (5) Reportable occurrences.

6.3 Action to Be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, as defm' ed in these technical spe :ifications, the following action shall be taken:

1. The Nuclear Reactor Laboratory Manager shall be notified of the l 33 occurrence. Corrective action shall be taken to correct the abnormal conditions and to prevent its recurrence.

.. A report of such occurrence shall be made to the Safety Review Committee; the Director, Michigan Memorial-Phoenix Project; and the Nuclear Regulatory Commission in accordance with Section 6.6.2.a. The report shall include an analysis of the causes of the occurrenc:, the effectiveness of corrective actions taken, and recommended measures to prevent or reduce 38 the probability or consequences of recurrence.

6.4 Operating Procedures Written procedures, including applicable check lists, reviewed r.nd approved by the O sarety Review Committee shall be in effect md followed for the following operations:

Page 31

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

1. Startup, operation and shutdown of the reactor;

2. Installation and removal of fuel elements, conttol rods, experiments and experimental facilities;

3. Actions to be taken to correct specific and foreseen potential malfunctions of t

systems or components, including responses to alarms, suspected primary coolant system leaks, and abnormal reactivity changes;

4. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, reentry, recovery, and medical support;

5. Maintenance procedures which could have an effect on reactor safety;

6. Periodic surveillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors;

7. Facility security plan;

8. Radiation protection procedures.

Substanf.ve changes to the above procedures shall be made only with the approval l 34 of the Safety Review Committee. Temporary changes to the procedures that do not change their original intent may be made with approval of the Nuclear Rettor 33 Laboratory Manager or one of the Assistant Managers. All temporary changes to O- the procedures shall be documented and subsequently reviewed by the Safety Review Committee.

i 6.5 Operating Records i

1. The following records and logs shall be prepared and tetained by the licensee for at least five years:

a. Normal facility operation and maintenance;

b. Reportable Occurrences;

c. Tests, checks. and measurements documenting compliance with ,

surveillance requirements; )

d. Records of experiments performed;

c. Records of radioactive shipments;

f. Operator requalification program records (the five year period will j commence after termination of the assignment of the opetator to  ;

operative duties); l

g. Facility radiation ad contamination surveys. )

O Page 32 C___________._.__________.____.-______-__.-__.___...___--__.______.m. . _ _ _ . . - . . _ _ _ _ _ _ _ . _ _ _ - _ _ _ _

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed (VO 2. The following records and logs shall be prepared and retained by the licensee for the life of the facility:

a. Gaseous and liquid waste released to the environs; 3 1

b. Off site environmental monitoring surveys; l

{

c. Radiation exposures for all FNR personriel, i l

d. Fuelinventories and transfers; j 1

e. Updated, corrected, and as built facility drawings, ,

f. Minutes of Safety Review C,mmittee meetings, i

6.6 Reporting Requirements l i

In addition to reports required by Title 10, Code of Federal Regulations, the l following reports shall be submitted to the United States Nuclear Regulatory Commission. .

1 1

1. Annual Operating Repon i A written annual operating report shall be submitted by March 31 of each n

V year to the U. S. Nuclear Regulatory Commission, Attn.: Document l Control Desk, Washington, D.C. 20555 and to the Administrator, Region {

III. l The report shall include the following information for the preceding year.

a. Operations Summary A summary of operating experience having safety significance occurring during the reporting period.

1. Changes in facility design.

2. Performance characteristics (e.g., equipment and fuel ,

performance). l l

l

3. Changes in operating procedures which relate to the safety of facility operations.

4. Results of surveillance tests and inspections r :;iired by I these technical specifications.

1 5- A brief summ try of those changes, tests, and experiments which required authorization from Jie commission pursuant to 10CFR50.59(a).

k Page 33

l l OPERATING LICENSE AND TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor l

Docket 50-2, License R-28 Amendment 45: Proposed (3

V 6. Changes in the plant operating staff serving in the following positions:

a. Nuclear Reactor Laboratory Manager; l 33

b. Health Physicist;

c. Safety Review Committee members.

b. Power Generation A monthly tabulation of the thermal output of the facility during the reporting period.

c. Shutdowns A listing of unscheduled shutdowns which have occurred during the reporting period, tabulated according to cause, and a brief discussion of the actions taken to prevent recurrence. j i

d. Maintenance i A discussion of corrective maintenance, excluding preventive maintenance, performed during the reporting period on safety related systems and components.

O) q

e. Changes, Tests, and Experiments l A brief description and a summary of the safety evaluation for those changes, tests, and experiments which were carried out without prior commission approval, pursuant to the requirements of 10CFR50.59(a).

f. Radioactive Efflaent Releases A statement of the quantities of radioactive effluents released from the plant.

1. Gaseous Effluents

a. Gross Radioactivity Releases

1. Total gaseous radioactivity in curies. l 40

2. Average concentration of gaseous effluents released during normal steady state operation averaged over one year.

l 40

3. Maximum instantaneous concentration of n noble gas radionuclides released during special operations, tests, or experiments.

(J Page 34

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

4. Percent of diluted,10CFR20, Appendix B, 40 Table 2, Column 1, air effluent concentration limit.

b. Iodine Releases (Required if iodine-131 is identified in primary

- coolant samples, or if fueled experiments are conducted at the facility.)

1. Total iodine radioactivity in curies released by isotope, based on representative isotopic analyses.

2. Percent of diluted,10CFR20, Appendix B, 40 l Table 2, Column 1, air effluent concentration limit.

c. Particulate Releases

1. Total pa *ulate grocs beta and gamma l 40 radioactivity released in curies excluding background radioactivity.

2. Gross alpha radioactivity released in curies

.O. excluding background radioactivity. J (Required if the operational or experimer.tal program could result in the release of alpha emitters.)

3. Total gross radioactivity in curies of nuclides J with half lives greater than eight days.

4. Percent of diluted,10CFR20, Appendix B, 40 Table 2, Column 1, air effluent concentration limit, for particulate radioactivity with half lives greater than ei3ht days.

2. Liquid Effluents

a. Total gross beta and gamma radioactivity released in curies excluding tritium and average concentration released to unrestricted areas or sanitary sewer l 40 averaged over period of release,

b. The maximum concentration of beta and gamma radioactivity released to unrestricted areas.

l 40

-0 l

4 Page 35 I I4 m_..___._h___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..-______-_2__ _ _ . _ . _ _ - . _

l OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed

c. Total alpha radioactivity in curies released and average concentration released to unrestricted areas averaged over the period of release. (Required if the l 40 operational or experimental program could result in the release of alpha emitters.)

d. Total volume in ml of liquid waste released.

e. Total volume in ml of water used to dilute the liquid waste during the period of release prior to release from the building to the sanitary sewer system.

f. Total radioactivity in curies, and concentration averaged over the period of release by nuclide released, based on representative isotopic analyses performed for any release from a waste storage tank. l 40

g. Percent of diluted,10CFR20, Appendix B, Table 3, 40 Releases to Sewers

g. Environmental Monitoring For each medium sampled:

O V

1. Number of sampling locations and a description of their location relative to the reactor.

2. Total number of samples.

3. Number of locations at which levels are found to be significantly higher than the remaining locations.

4. Average annual concentrations or levels of radiation for the l 40 sampling point with the highest average concentration or level and the location of that point with respect to the site.

5. The maximum cumulative radiation dose which could have been received by en individual continuously present in an unrestricted area during reactor operation from:

a. Direct radiation and gaseous effluent;

b. Liquid effluent.

6. If levels of radioactive materials in environmental media, as detennined by an environmental monitoring program, indicate the likelihood of public intakes in excess of 10% of 40 those that could result from continuous exposure to the concentration values listed in 10CFR20, Appendix B, Table 2, Columns 1 and 2, estimates of the likely resultant

()' exposure to individuals and to population groups and assumptions upon which estimates are based.

Page 36

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed O

b 7. If significant variations of off site environmental concentrations with time are observed, correlation of these reruhs with effluent release shall be provided.

h. Occupational Personnel Radiation Exposure A summary of annual whole body radiation exposures greater than l 38 500 mrem (50 mrem for persons under 18 years of age) received during the reporting period by facility personnel including faculty, students, or experimenters.

2. Non-Routine Reports ,

l

a. Reportable Occurrence Reports In the event of a reportable occurrence as defined in section 1.0, 38 notincation shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and FAX to the Reactor Project Manager, Headquarters, U.S. Nuclear Regulatory Commission and to the Administrator, Region III, followed by a written report within 14 days to the U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D. C. 20555, and to the Administrator, Region III. l 38 FAX notification may be sent on the next working day in the event of a reportable occurrence during a weekend or holiday p::id The written report of a reportable occurrence, and, W the extent possible, k the preliminary telephone and FAX notification shall: l 38

1. Describe, analyze, and evaluate safety implications;

2. Outline the measures taken to assure that the cause of the condition is determined;

3. Indicate the corrective action including any changes made to the procedures and to the quality assurance program taken to 3 prevent repetition of the occurrence and of similar  !

occurrences involving similar components or systems;

4. Evaluate the safety implications of the incident in light of the cumulative experience obtained from the record of previous failure and malfunctions of similar systems und components.  !

b. Technical Specification, Safety Analysis, and System Deficiencies l 38 l

A written report shall be forwarded within 30 days to the U. S.

Nuclear Regulatory Commission, Attn: Document Control Desk, Washington D. C. 20555, and to the Administrator, Region III, in l 38 i l

the event of:

1. Discovery of any substantial errors in the transient or accident analyses or in the methods used for such analyses, C) > aeecribed ia the safety an lysis or in the bases for the techmcal specifications; Page 37

_ _ _ _ _ - ________--___---______a

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 45: Proposed l

2. Discovery of any substantial variance from performance specifications contained in the technical specifications and safety analysis.

3. Discovery of any condition involving a possible single failure which, for a system designed against assumed failures, could result in a loss of the capability of the system to perform its safety function.

I O

1 O

Page 38

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