ML20059M314

Proposed Tech Specs Accommodating Implementation of New 10CFR20

ML20059M314
Person / Time
Site:	University of Michigan
Issue date:	08/01/1993
From:	MICHIGAN, UNIV. OF, ANN ARBOR, MI
To:
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ML20059M309	List: ML20059M308 ML20059M314 ML20059M316
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NUDOCS 9311190026
Download: ML20059M314 (49)

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{{#Wiki_filter:_. OPERATING LICENSE AND TECHNICAL SPECIFICATIONS i Ford Nuclear Reactor '{ Docket 50-2, License R-28 Amendment 40:080193 l APPENDIX A TO FACILITY LICENSE R-28 TECHNICAL SPECIFICATIONS DOCKET 50-2 l MICHIGAN MEMORIAL PHOENIX PROJECT i THE UNIVERSITY OF MICHIGAN Ann Arbor, Michigan i 9 9311190026 931027 {M[ PDR ADOCK 05000002 P PDR hi

- - ~ ? i OPERATING-LICENSE AND. TECHNICAL SPECIFICATIONS Ford Nuclear Reactor-i Docket 50-2, License.R-28 Amendment 40:080193' CONTENTS I -f 1.0 DEFINITIONS 1 2.0-SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS .6 i 2.1 Safety Limits 6 j 2.1.1 Safety Limits in the Forced Convection Mode 6 2.1.2 Safety Limits in the Natural Convection Mode-7 + 2.2 Limiting Safety System Settings (LSSS) 7 [ 2.2.1 Limiting Safety System Settings in the Forced Convection Mode 7 2.2.2 Limiting Safety System Settings in the l Natural Convection Flow Mode 8 i 3.0 LIMITING CONDITIONS FOR OPERATION 10 7 3.1 Reactivity Limits 10 j 3.2 Reactor Safety _ System 12 3.3 FNR Confinement Building 16.- 3.4 Primary Coolant Conditions 18 3.5 Airborne Effluents 19 3.6 Liquid Effluents 20 3.7 Limitations of Experiments 21 j 3.8 Fission Density Limit' 23' F i 4 4.0 SURVEILLANCE REQUIREMENTS 24 4.1 Reactivity Limits 24 1 4.2 Reactor Safety System 25 j 4.3 FNR Confinement Building 27 4.4 Primary Coolant System 28 [ 4.5 Airborne Effluents 29 4.6 Liquid Effluents 29 7 4.7 Fission Density Limits 30 { 5.0 DESIGN FEATURES 31 l f 5.1 Site Description 31 5.2 Reactor Fuel 32 5.3 Reactor Building 32 v 5.4 Fuel Storage 33 [ e C i 1 i' Contents-1 )

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS- 'l Ford Nuclear Reactor: 'l DocketL50-2, License R-28. Amendment 40.:080193-6.0 -ADMINISTRATIVE CONTROLS 34 6.1 Organization 34-6.2-Review and Audit. 35 6.3 ' Action to be Taken in the Event of a Reportable. Occurrence 38 -l 6.4 Operating Procedures. 38 l 6.5 Operating Records 39 t 6.6 Reporting Requirements 40. j f I ) i ~ 5 A ? n.. b 6 .l Contents-2 i l

n r_.. =. -~_ OPERATING LICENSE ANDETECHNICAL SPECIFICATIONS' i Ford Nuclear Reactor 1 Docket 50-2, License R-28 l Amendment 40:080193-j i 1 1.0 -DEFINITIONS .i l l Channel Calibration - A channel calibration is an adjustment of the channel such.that its output corresponds with acceptable l 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. ( Channel Check - A channel' check is a qualitative verification-of acceptable performance by observation of channel behavior. .? This verification where'possible shall include 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. .l 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; l confining boundaries, and contained fluids or j solids. i Experimental Facility - An experimental facility is~any structure or device which is intended to guide, orient, i position, manipulate, or otherwise facilitate a multiplicity of experiments of similar character. 'i Explosive Material - Explosive material is any solid or liquid which is categorized as a severe, dangerous, or very =1 dangerous explosion' hazard in DANGEROUS PROPERTIES iOF INDUSTRIAL MATERIALS by N.I. Sax, Third Ed. (1968), or is given an' Identification of Reactivity (St_ ability) Index of 2,3, or 4 by the National Fire Protection Association in its publication 704-M, 1966. Limiting Conditiores for Operation (LCO) - Lowest. functional capability or performance levels of equipment required for safe operation of the reactor (10CFR50.36). Page 1

i OPERATING LICENSE.AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 l Limiting Safety System Setting (LSSS).- Settings for automatic j protective devices related to those variables having significant i safety functions, and chosen so that automatic protective action j will correct an abnormal situation before a safety limit is j exceeded (10CFR50.36). j i Measured Value - The measured value of a process variable is the value of the variable as indicated by a measuring channel. Measuring Channel - A measuring channel is the combination of l sensor, amplifiers, and output devices which are used-for the i purpose of measuring the value of a process variable. ? ? Moveable Experiment - A moveable experiment is one which may I be inserted, removed, or manipulated while the reactor is critical. Operable - Operable means that a component or system is capable. j of performing its intended function in its normal manner. Operating - Operating means that a component or system is l performing its intended function in its normal manner. Potential Reactivity Worth of an Experiment - The potential f reactivity worth of an experiment is the maximum absolute value of the reactivity change that would occur as a result of intended or anticipated changes or credible malfunctions ~ that l 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% Delta K/K. The reference core condition will be known as the cold, xenon free critical j condition. ' l Reactor Operation - Reactor operation means that the control rods installed in the core are not fully inserted or that the control console key is in the keyswitch. Reactor operation is j not considered possible when there are less than six standard 38 fuel elements in addition to the four control elements that house the control rods on the grid plate. l l Reactor Safety System - The reactor safety system is that j combination of safety channels and associated circuitry which f forms the automatic protective system for the reactor or provides information which requires manual protective action to be initiated. i Reactor Scram - Shutoff of electrical current to the rod i holding magnets and subsequent insertion of the rods into the core by gravity. I Page 2 i

OPERATING. LICENSE AND TECHNICAL' SPECIFICATIONS. Ford Nuclear Reactor: Docket 50-2, License R-28 j Amendment 40:080193 h Heactor Secured - Reactor Secured is defined as follows: 1. The full insertion of all control rods has been I

verified, 2.

The control console key is removed: and I ~i 3. No operation is in progress _which involves moving j 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 Availabic on Call - Readily available on call shall mean a licensed senior operator shall insure that he can be contacted and is within a reasonable driving time (1/2 hour) l from the reactor building when the reactor is being operated-l by a licensed operator. 't 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 operator with a manual switch or by an automatic controller. { l Removable Experiment - A removable experiment is any l experiment, experimental facility, or component of an i experiment, other than a permanently attached appurtenance to the reactor system, which can reasonably be anticipated to be l moved one or more times during the life of the< reactor. 'i l Reportable Occurrence - A reportable occurrence is any of [ the following: i 1. A safety system setting less conservative than the limiting setting established in the l 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 l i 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 j material from the restricted area of the facility; 4 Page 3

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OPERATING' LICENSE AND_TECHNICALESPECIFICATIONS - l] Ford. Nuclear Reactor Docket 50-2,-LicenseLR-28= Amendment 40:080193-1 6. An uncontrolled or unplanned-release of radioactive l material which results in concentrations of radioactive materials within the restricted area in } cxcess of the limits specified in Appendix B, l Table 1, Column 3 Derived Air Concentration 40 i (DAC) of 10CFR20; l 7. An uncontrolled or unanticipated change in j reactivity in excess of 0.005 delta K/K; i -? 8. Conditions arising.from natural or man made l events that affect or threaten to affect the safe operation of the facility; 9. An observed inadequacy in the implementation of-f administrative or procedural controls such that the_ inadequacy causes or threatens to--cause.the t existence or development of an unsafe condition in j connection with the operation of the facility. Rundown - A rundown is the automatic insertion of the shim i safety rods. l Safety Channel - A safety channel is a measuring channel in the reactor safet> oystem. Safety Limit (SL) - Limits upon important process variables which are found to-be necessary to reasonably protect the: 1 integrity of certain of the physical barriers that guard'against t the uncontrolled release of radioactivity (10CFR50.36). Secured -Experiment - Any experiment, experimental facility, or component of an experiment is deemed'toLbe secured, or in a f secured position, if it is held in a stationary position l 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 i forces which are normal to the operating environment of the experiment, or of forces which might arise as a result of credible malfunctions. l Shim-Safety Rod - A shim-safety rod is a control-rod [38 fabricated from borated stainless steel which is used to compensate for fuel burnup, temperature, and poison effects. A 1 shim safety rod is magnetically coupled to its drive unit-j allowing it to perform the function of a safety rod when the j magnet is deenergized. J b l 1 ( i page 4 o

- ~... OPERATING' LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor i Docket 50-2, License R-28 Amendment 40:080193 i 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-38 cach surveillance time interval shall be-closer to the normal surveillance time than the extended time. Any extension of i these intervals shall be occasional and for a valid reason, and shall not affect the average aus defined. l t Annually - 12 to 15 months. Biannually - 24 to 30 months. Biweekly - 14 to 20 days l38 [ Daily - 24 to 32 hours. l t Monthly - 30 to 40 days. l 1 Quarterly - 3 to 4 months. l l Semiannually - 6 to 8 months. l Weekly - 7 to 10 days. l True Value - The true value of a process variable is its actual value at any instant. l Unscheduled Shutdown - An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not to include shutdowns which occur during testing or checkout operations, i I f 5 I I k 8 Page 5

.. _ _ ~. _. OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor- -Docket 50-2, License R-28 -Amendment 40:080193 ~i 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 l Reactor Coolant Inlet Temperature, Ti Height of Water Above the Top'of the Core, H i objective: To assure that the integrity of the fuel clad is maintained. I Specification: l l 1. The true value of the reactor thermal power i (P) shall not exceed 380 kw. j i 2. The true value of the reactor coolant inlet i temperature (Ts ) shall not exceed 131 oF. 3. The height of pool water above the core (H) .l shall not be less than 18 feet. Bases: t i The basis for natural convection safety limits 1 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-i depth of 18 feet. j 2.2 Limiting Safety System Settings (LSSS) 2.2.1 Limiting Safety System Setting in the Forced Convection Mode + Applicability: J I This specification applies to the set points for the safety channels monitoring reactor thermal power (P), primary coolant flow (r), height of water'~above the top of the core (H). j and core exit teiperature (T.). l i page 7 +-. -

i i OPERATING LICENSE'AND1 TECHNICAL SPECIFICATIONS Ford Nuclear Reactor j Docket.50-2, License R-28 -j Amendment 40:080193 Objective: j To assure that automatic protective action is l' initiated to prevent a safety limit from being exceeded. i Specification: 1 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 j coolant exit temperature (T ) shall be as i follows: l 1 Variable LSSS P (Max) 2.40 Mw m.(Min) 900 gpm H (Min) 19 ft i Te(Max) 129 0F ] Bases: The limiting safety system settings for l forced convection assure that automatic protective action will' correct the most-i severe abnormal situation anticipated before a safety limit is exceeded. 'f 2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode Applicability: These specifications apply to the setpoint for l the safety channels monitoring reactor thermal -i power (P), pool water level (H), and pool water temperature (T). l Objective: i To assure that automatic protective action is initiated to prevent a safety limit from i being exceeded. n-i ) i Page 8 -m

l OPERATING LICENSE AND TECHNICAL' SPECIFICATIONS 1 Ford Nuclear Reactor-I ~ Docket 50-2,_ License R-28 I . Amendment 40:080193 Specifications: 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: -{ -t Variables LSSS i i P (Max) 100 kw. H (Min) 19 ft T (Max) 129 o F i Bases: The limiting safety system settings for natural convection assure that-automatic protective. -l action will correct the most severe abnormal situation anticipated before a safety limit is j exceeded. .i 't t i t h'I t l 1 i Page 9

~ i OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 i 3.0 LIMITING CONDITIONS FOR OPERATION-i 1 3.1 Reactivity Limits Applicability: This specification applies to the reactivity of the reactor core and to the reactivity' worths of control ~ rods and experiments. When the reactor is operated with the heavy water reflector tank in place, the J imits will l not include the static reactivity worth of the tank. r Objective: r To assure that the reactor can be controlled and l shutdown at all times and that the safety limits will not be exceeded. Specification: l l 1. The shutdown margin relative to the cold, xenon f free, critical condition shall be at least.025 delta K/K with all three shim safety-rods fully inserted and [ 7 i the regulating rod fully withdrawn and 0.0045 delta K/K with the most reactive shim-safety rod and the regulating rod fully withdrawn, except during the 38 process of verifying shutdown margin. 2. The overall-core excess reactivity including i moveable experiments shall not exceed 0.0436 l35 i delta K/K. [ 3. The reactivity worth of experiments shall be limited i as follows, except during the process of verifying 38 experiment reactivity: } I Maximum . Experiment Reactivity Worth Individual Moveable 0.0012 delta K/K Individual Secured 0.012 delta K/K i Total Moveable and Secured 0.012 delta K/K f 4. The reactor shall be suberitical by at least ] 0.025 delta K/K during fuel movements to and 38 l from the reactor core. ? 5. The reactor shall be suberitical by at least 38 l 0.10 delta K/K bef6Fe shim-safety rods are l removed from the core. I .I a 4 l Page 10 l

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor. Docket 50-2, License R-28 Amendment 40:080193 y 6. The reactor shall be.suberitical by at least-38 0.10 delta K/K whenever heavy water movements that can result in positive reactivity insertions -l are undertaken. j l 7. The reactivity worth of the regulating rod shall not. I exceed 0.006 delta K/K. l 8. Experiments that.could increase reactivity by l flooding, shall not remain in or adjacent to the i core unless the shutdown margin required in Specification 3.1.1 would be satisfied after flooding.

l Bases:

The shutdown margin required by Specification 3.1.1. i assures that the reactor can be shutdown from any operating condition and will remain.suberitical 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

l 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 i

(5) moveable experiments. [ t Specification 3.1.3 limits the individual reactivity 1 worth of moveable experiments to values that will not l38 produce a stable period of'less than 30 seconds and which can be compensated for by the action of the control j and safety systems'without exceeding any safety limits. Specification 3.1.3 limits the reactivity. worth of. 38 secured and total experiments to values of-reactivity which, if introduced as positive step changes, will not cause fuel melting. Specifications 3.1.4 and 3.1.5 provide assurance that the core will remain suberitical during fuel movements 38 to and from the core and during shim-safety rod maintenance or inspection. The largest positive reactivity increase thatican be l33 i produced by replacing light water with heavy water in the heavy water reflector tank is 0.04 delta K/K. Maintaining the core suberitical by at.least 0.010 38 delta'K/K in Specification 3.1.6.during heavy water transfers provides adequate margin to assure that. Page 11 j

' OPERATING LICENSE AND-TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2,' License R-28 Amendment 40:080193 l the reactor will remain suberitical during heavy water j transfers that could add positive reactivity. j i Specification ~3.1.7 assures that failure of the l 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 i event of a positive reactivity insertion caused by the flooding of an experiment. .j i 3.2 Reactor Safety System l Applicability: l t These specifications apply to the reactor safety system and other safety related instrumentation. } Objective: l To specify the lowest acceptable level of performance or the minimum number of acceptable components for the reactor safety system and other safety related instrumentation. I i Specification: j i The reactor shall not be made critical unless: l 1. The reactor safety systems and safety-related l instrumentation are operable in accordance with Tables 3.1 and 3.2 including the minimum number of i channels and the indicated maximum or minimum setpoints, I 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 i exceed 500 milliseconds; l 4. Mechanical devices are installed which prevent the ) lifting of fuel elements through the movement of control rods. Bases: 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. Page 12

OPERATING LICENSE AND-TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 .j Amendment' 40:080193 Table 3.1 REQUIRED. SAFETY. CHANNELS Minimum Number Channel Setpoint Reauired Function Log Count Rate 2 cps 1 Rod Withdrawal Interlock Log N Period 1 Wide range power .j level and input-for period scram Period Safety 5 see 1 Scram ) i Level Safety 120%(2.4 Mw) 2 Scram j j High Power /No (a) 900 gpm 1 Scram 1100 kw Water Flow (b) holdup tank i isolation valve not fully open j (c) holdup tank static pressure [ 1 psig below full power value i High Power / r Header Down 1 Scram-2100 kw Header Up/ 900 gpm 1 Scram l No Water Flow Building Exhaust 1 mrem /hr 1 Scram Radiation Level Building Alarm 1 Scram Manual Switch Manual Scram Switch 1 Scram Magnet Power Keyswitch 1 Scram i Reactor Coolant Exit Temp. 129 oF 1 Auto Rundoen l Pool Level 1 foot below pool 1-Auto Rundown' overflow Bridge Not When clamps 1 Scram d Clamped released Page 13 -~

OPERATING LICENSE.AND TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor j Docket 50-2, License-R-281 i Amendment 40:080193 i Table 3.2-l REQUIRED SAFETY RELATED INSTRUMENTATION Minimum i Number Instrumentation Setpoint Reauired Function I Linear Level Channel As Required 1 Linear power level measurement and input j for the automatic control mode Power Level Deviation 95% of control 1 Return reactor'to Interlock point setting manual control mode if setpoint j is reached E' Reactor Coolant Inlet Not Applicable la provide information-Temperature for reactor power 38 level determination i by heat balance l Facility Radiation Monitor System (b) [ 1. Building Air Exhaust 1(1)b mrem /hr 1 Alarm, scram, initiate confinement. evacuation i r 2. Reactor Bridge 40(50) mrem /hr.1 Alarm l34 l 3. NW Column, Beamport 20(50) mrem /hr Ic Alarm {34 Floor [ 4. N Wall, Beamport 5(50) arem/hr 1 Alarm + Floor

5. NE Column, Beamport 5(50) mrem /hr 1 Alarm l34 Floor l38 Footnotes:

a. Not required for natural convection operation. 4 b. The facility radiation monitoring system consists of 5 radiation ]39 detectors which alarm and read oct locally, and are recorded in v' 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 j i I Page 14 J l

OPERATING: LICENSE AND TECHNICAL SPECIFICATIONS-Ford Nuclear Reactor Docket 50-2, License R-28 Amendment-40:080193 i Table 3.2 (Continued) REQUIRED SAFETY RELATED INSTRUMENTATION' i Footnotes: normal setpoints will require approval of the Nuclear Reactor l33 Laboratory Manager or one of the Assistant Managers. Any reactor staff member may adjust a setpoint lower than the normal value. c. If facility radiation monitor 3., 4., or 5. is placed out of 38 service for a period of more than 7 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 returned to service within 24 hours or is replaced by a second locally alarming unit of similar range. E 3 I 5 t t t 4 Page 15 +

.~ OPERATING LICENSE AND' TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor l Docket 50-2, License R-28 l Amendment 40:080193 Power-flow coincident scrams provide redundant channels i to assure that an automatic loss of flow scram will l occur in the event of a loss of-flow when the reactor is operating at power levels above 100Ekw. l 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. l The core exit temperature auto rundown function and ) response of the operator to the pool level alarm assure that the reactor will not be operated above the safety limit for core inlet temperature and below the safety i limit for pool level. l The manual scram button and the magnet power keyswitch l provide two methods for the reactor operator to l manually shutdown the reactor if an unsafe or abnormal condition should occur and the automatic reactor-l 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. i Specifications 3.2.2 and 3.2.3 assure that the safety system response will be appropriate. l Mechanical holddown devices specified in 3.2.4 ensure 38 i that a fuel element cannot 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. k 3.3 FNR Confinement Building i Applicability: i This specification applies to the Ford Nuclear Reactor confinement building requirements. l ) Objective: l To assure that the Ford Nuclear Reactor Building 38 { confinement integrity is maintained during reactor l operation and to minimize the release of airborne radioactive materials from the reactor building. t l Page 16

OPERATING LICENSE AND TECHNICAL S 2CIFICATIONS ] Ford " clear Reactor: . Docket 50-2, License R-28 Amendment 40:080193 Specification: 1. When the radiation level in the Ford Nuclear 38 Reactor ventilation exhaust duct is equal to or greater than one mrem /hr-i a. The reactor building ventilation supply and exhaust fans shall automatically turn off; s b. The reactor building ventilation supply and exhaust dampers shall automatically close; l 1 c. The beamport 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 following conditions will be administratively controlled: a. personnel access doors will be closed except as necessary for the passage of personnel and/or equipment; i b. The main equipment access door onto the beamport-floor will be opened only long enough to permit _ the passage of equipment; l c. The personnel door to the cooling tower area will remain clamped except to permit the passage i of personnel and/or equipment to the cooling l tower area. The door will remain closed but not l clamped until all personnel have left the l cooling tower. area; l d. The access hatch from grade level _to the beamport floor will be sealed closed, -6 e. The personnel exit door located in the north wall of the building _will be sealed; and l38 f. The door located on the beamport floor which connects to the Phoenix Memorial Laboratory hot cave operating area will be~ clamped closed. _j i { Bases: r The potential radiatiod'^ exposure to persons at the-l operations boundary following an accident releasing -i fission products within the confinement building has l 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 Page 17

i i OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 3.3.1 and 3.3.2 will assure that the building leak l rate will not exceed the leak rate used in the' evaluation. f The 1.0 mrem /hr setpoint for the facility exhaust i radiation monitor provides a mechanism for isolating i the building ventilation system in the event of a j significant release of radioactive material into the reactor building. This setpoint, for the detector i location involved, represents a gamma emitting'nuclide concentration of 10- 3 to 10-4 microcuries/cc of building i F air. 1 i 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 38 level assumed in the Hazards Summary Report, and the release of radioactive material will be minimized. 3.4 primary Coolant Conditions I Applicability: i This specification applies to the limiting ccnditions for available pool water volume, primary coolant pH, i conductivity, radioactivity, and flow distribution. l38 i Objective: To maintain the primary coolant in a condition to minimize the corrosion o? the primary coolant system, fuel clad, and other reactor components, and to i assure proper conditions of coolant for normal and .?' emergency requirements. 4 Specification: 4 1. The primary coolant pH shall be maintained between 4.5 and 7.5. 2. The primary coolant conductivity shall be 38 maintained at a value less than 5 micromho/cm a except for periods of time not to exceed 7 days when the conductivity may not be greater than 20 micromho/cm. n. i Page 18 ~

L OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 l 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. l38-4. When the reactor is in operatiori, the pool gate l38 must be in its storage location. Bases: =, Experience at this and other facilities has shown that the maintenance of primary coolant system water quality in the ranges specified in Specification i 3.4.1 and 3.4.2 will control the corrosion of the aluminum components of the primary coolant system and the fuel element cladding. r Specification 3.4.3 that all grid positions be occupied will prevent the degradation of flow rates due to flow bypassing the active fueled region 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 i effluents from the Ford Nuclear Reactor. i Objective: i To assure that the release of airborne radioactive l38 l material from the Ford Nuclear Reactor is maintained below the limits established in 10CFR20. I Specification: l i l 1. The concentration of radioactive materials in the t effluent released from the facility _ exhaust stacks shall not exceed 400 times the concentrations specified in 10CFR20, Appendix B. Table 2, 40. l Column 1, Air Effluent Concentration (EAC), j averaged over time periods permitted by 10CFR20. n. 1 i 1 1 Page 19 i

~... ~ OPERATING LICENSE ~AND TECHNICALLSPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 l Amendment 40:080193 t 2. During operation of the reactor, the following conditions shall be met: a. The mobile air particulate monitor and'the 38 gaseous activity detector for the Stack 2 l exhaust shall be operating. If either unit is out of service for more1than 24 hours, either the reactor shall be shutdown or the unit shall be replaced by one of comparable monitoring capability; y b. The reactor pool floor mobile air particulate 38 monitor and the gaseous activity detector for i the reactor building exhaust stack shall be j operating. If either unit is out of service for i more than 24 hours, 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 i be operating whenever the reactor is in operation as required by Table 3.2 of i specification 3.2. Bases: i The limits established in specification 3.5.1 l38 incorporate a dilution factor of 400 for effluents l l-released through the exhaust stacks. This dilution Li factor was calculated from actual FNR site -i meteorological data and represents the lowest dispersion factor determined and the highest frequency of wind in j any sector. Pecause of the use of the most conservative i measured values of wind directional frequency and I dispersion factors, this dilution factor will assure that concentrations of-radioactive material in unrestricted areas around the FNR site will be far l below the limits of 10CFR20. 4 l effluent monitoring.l38 The requirements of specification 3.5.2 are considered adequate to assure proper airborne 3.6 Liquid Effluents i Applicability: This specification supplies-to the monitoring of radioactive liquid effluents from the FUR. Objectives:

f The objective is to assure that exposure to the publ'ic resulting from the release of liquid effluents will be

[ minimized. i Page 20 ~2 m.

r OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment. 40:080193 ( i Specification: l .i 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 40 dispersible biological material) in water and shall not exceed 315 times the t concentrations specified in 10CFR20, Appendix B, Table 3, Releases to Sewers. 2. The amount of liquid discharged shall be limited l33 to the equivalent of 3,000 gallons of liquid at the concentration limit specified in 3.6.1 each day. l38 l 3. Liquids from the facility's radioactive liquid waste r system shall not be discharged into the storm drain system. i Bases: j 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 40 i reactor pool to make up for surface evaporation. However, after sampling, analysis, and dilution, if the [ concentration of radioactivity is less than the limit l of 10CFR20, liquid effluents can be-discharged to the sanitary sewer system. In the past, less than 50 retention tank discharges 38 3 per year have been required. During 1970, the North l 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, l which assures that there will be no significant exposure -i to the public from radioactive waste discharged to the l sanitary sewer system. l 3.7 Limitations of Experiments l l Applicability: J This specification applies to experiments installed in i the FNR. Objective: To. prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure. 1 Page 21 1 l

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS I Ford Nuclear Reactor I Docket 50-2, License R-28 l Amendment 40:080193 f Specification: 1. Each experiment shall be designed so that the surface-temperature shall be below the temperature calculated for the inception of nucleate boiling. i prior to insertion in the reactor, any capsule which l is expected to operate with an internal pressure in excess of or.e atmosphere shall be tested at a pressure twice the calculated maximum pressure. f 2. All experiments which are in contact with reactor. j coolant shall be either corrosion resistant or i encapsulated within corrosion resistant containers. j 3. Explosive materials shall not be placed in the reactor pool. 4. Neutron radiography of explosives shall be conducted 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. t t 5. The radioactive materia) tent, including fission I products, of any singly x ipsulated experiment l should be limited so that _ne complete release of all gaseous, particulate, and volatile components from the encapsulation could not result in doses in excess of 10% of the equivalent' annual doses f stated in 10CFR20. This dose limit applies to i a persons occupying unrestricted areas continuously for two hours starting at time of release and [ restricted areas during.the length of time required 'I to evacuate the restricted area. } 3 ~ 6. The radioactive material content, including fission products, of any doubly encapsulated experiment I should be limited so that the complete release of j all gaseous, particulate, or volatile components i from the encapsulation could not result in doses in. j excess of the equivalent annual doses stated in 10CFR20. This dose limit applies to persons i occupying unrestricted areas continuously for two [ hours starting at the time of release and restricted i areas during the length of time required to evacuate i the restricted area. 1 Bases: i l Specifications 3.7.1 through 3.7.4 are intended to. l38 reduce the likelihood of damage to reactor components -j and radioactivity releases resulting from experiment page 22 l

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS I Ford Nuclear Reactor i Docket 50-2, License R-28 Amendment 40:080193 I failure and serve as a guide for the review and approval i of new and untried experiments by 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 i will be contained, during exposure, inside a blast proof l enclosure. The enclosure will not be coupled to the l beamtube or beamport and will be constructed to fully i contain any blast effects or missiles which might be generated by an accidental detonation. i Specifications 3.7.5 and 3.7.S conform to the l38 regulatory position put forth in 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: l This specification applies to fission density limits f in FNR fuel. j Objective: To prevent fuel plate swelling which could result in l clad rupture and release of radioactive fission I products. ( Specification: } 1. The FNR fission density limit shall be 1.5x1021 f fission /cc. j Bases: The fission density limit is below operational fission densities reached in other operating reactors using the same kind of fuel without failures attributed to the fuel. An experimental data base that supports the safe use of uranium aluminide (UAlx), uranium oxide ( U3 0s ), and l uranium silicide (U3 Siz ) fuel in the FNR up to the l34 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 . the j Laboratory, the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory, and the German Karlsruhe l FR2 reactor. i Page 23 .m..

~ OPERATING LICENSE:AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor .i Docket 50-2, License R-28 Amendment 40:080193 4.0 SURVEILLANCE REQUIREMENTS 4.1' Reactivity Limits i Applicability: i This specification applies to the surveillance requirements for reactivity. limits. Objective: ? To assure that the reactivity limits of Specification 3.1 are not exceeded. 1 Specification: 1. Shim safety rod reactivity worths shall be measured: 1 a. Annually; l38' ^!l -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; d. Whenever the addition of more than three standard fuel elements to the outer faces of l38 the core is made to achieve the desired excess reactivity for the operation of-the reactor. 2. Shim safety rods shall be visually inspected and-put through a jig to check for swelling at least annually. 3. The reactivity worth of those experiments whose-i safety review indicates a need for such a i r determination'shall be measured prior to the j experiment's initial use. That worth shall be l verified if core configuration changes occur 5 which could reasonably be expected'to cause increases in experiment reactivity worth whereby the. 'i experiment worth could' exceed the values specified j in Specification 3.1. 3 J 4. The core negative reactivity required during j33 heavy water transfers will be-verified whenever J heavy water transfers are to be made. l Page 24

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS . Ford Nuclear Reactor i Docket 50-2, License R-28 Amendment-40:080193 l Bases. s Specification 4.1.1 will assure that shim-safety-rod reactivity worths are not degraded or changed ~by core arrangements. Shim-safety rod inspections are the single, largest' source of radiation exposure to facility' personnel. Furthermore, fregaent inspections of shim-safety rods for swelling over ti.e last ten years have produced no evidence of swelling or cracking. In order to minimize personnel radiation exposure and provide an inspection l frequency that will detect early evidence of swelling t and cracking, an annual inspection interval was selected for Specification 4.1.2. l The specified surveillance relating to the reactivity worth of experiments will assure that the reactor is i not operated for extended periods before determining i the reactivity worth of experiments. This specification j also provides assurance that experiment reactivity worths do not increase beyond the established limits due to core configuration changes. [ i Actual verification of the core negative reactivity l33 l required for heavy water transfers will assure the reactor l stays subcritical under all possible circumstances during heavy water transfers. 4.2 Reactor Safety System i 4 L Applicability: I f This specification applies to the surveillance of the i reactor safety system. 1 Objective: ) 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: i a. Prior to each reactor iwartup following a period-when the reactor was secured; j b. After a channel has been repaired or deenergized. l Page 25 l

i' OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 l 2. A channel calibration of the safety channels listed i in Table 3.1, which can be calibrated, shall be performed annually. [38 i 3. A channel check of the neutron flux level safety channels during reactor operation comparing the channel outputs with a heat balance, shall be r 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. l t 4. The operation of the radiation monitoring system required in Table 3.2 shall be verified: l38 a. Prior to each reactor startup following a 38 period when the reactor was secured; b. After a channel has been deenergized. [38' c. If a channel has been repaired, an operation [ and setpoint verification will be performed prior to use. 5. The radiation monitor system required in Table 3.2 shall be calibrated semiannually. {38 6. Shim-safety rod release-drop time shall be measured: a. Annually; l38

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

't changed; I c. Whenever maintenance is performed that could affect the rod's drop time. l 1 Bases: Prestartup tests of the safety system channels assure their operability. Annual calibration detects any long term drift that is not detected by normal j intercomparison of channels. The channel check of the neutron flux level channels assures that the detectors are properly adjusted to accurately monit'or the parameter they are measuring. Radiation. monitors are checked for proper operation in. Specification 4.2.4. Calibration and setpoint verification involve us'e of a calibration source and significant personnel radiation exposure. . Semiannual 38. calibration of radiation monitors, which have displayed excellent stability over many years of operation,.is adequate to verify the setpoint unless instrument repairs have been made. Page 26

l OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor' Docket 50-2, License R-28. Amendment-40:080193 'i The measured release-drop times of the shim safety rods j have been consistent since the installation of-the boron / stainless steel shim safety rods in 1962. Annual j check of these parameters is considered adequate to detect any deterioration which could change the j 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 [ i Applicability: This specification applies-to the surveillance of the facility openings and dampers. l ' 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 confinement of i any airborne radioactivity released into the~ building. j Specification: f 1. Operation of the dampers described in-l38 Specification 3.3.1 shall be tested whenever a complete checkout of the reactor control system: is required prior to startup. This functional test will be a portion of the startup checklist for the j facility. t t 2. The condition of the following-gaskets shall be 1 inspected semiannually, and the gaskets shall;be [38 i replaced whenever any evidence of deterioration is i found: l a. Building ventilation system intake and exhaust i dampers; j b. Personnel access doors; f c. Equipment access doors;

d. Cooling tower access door.

l i i l i f Page 27

1 OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 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 materials are not in a damaging atmosphere, will provide assurance that the gaskets i will perform their function of limiting leakage through l these openings in the event of a release of airborne activity into the building. [ t 4.4 Primary Coolant System Applicability: i This specification applies to the surveillance of the i primary coolant system. i I Objective: To assure high quality pool water and to detect the release of fission products from fuel elements. Specification: l 1. The pH of the primary coolant shall be measured weekly. 2. The conductivity of the primary coolant shall be l38 measured weekly. 3. The radioactivity content of the primary coolant 38 shall be measured biweekly. 4. A record of pool makeup water shall be maintained to discover significant leakage of primary coolant from the facility. i Bases: I Regular surveillance of pool water quality and radioactivity provides assurance that pH and l conductivity changes that could accelerate the corrosion of the primary coolant system would be detected before significant corror,ive damage would occur, and that the presence of J aking fuel elements in the reactor is detected. ~ Routine inspection of makeup water needs over a period of time provides early warning of small pool water leaks. v Page 28 m

.--- - _ - m a, w e :m.u a _2, e ,c _ -- - s OPERATING LICENSE'AND TECHNICAL SPECIFICAT' IONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 4.5 Airborne Effluents Applicability: i This specification applies to the surveillance of the monitoring equipment used to measure airborne radioactivity. Objective: The objective is to assure that accurate assessment of airborne effluents can be made. Specification: 1. The building exhaust air radiation monitor shall be. calibrated semiannually. l38 2. The mobile air particulate monitors shall'be 38 calibrated semiannually. r t 3. The gaseous activity detectors shall be calibrated for Argon-41 semiannually. l38 4. The operation of all airborne activity monitors shall be checked daily except when the reactor staff I is not present in the facility. Bases: j Experience with the electronic reliability and calibration stability of the units used by the Ford Nuclear Reactor demonstrates that the above periods are 1 reasonable surveillance frequencies. 4.6 Liquid Effluents t Applicability: This specification applies to the surveillance of the monitoring equipment used to measure the activity in i liquid effluents. I Objective: The objective is to assure that accurate assessment of liquid effluents can be made. Specification: 1. The monitoring equipment used.to measure the radioactive concentrations in the waste retention tank contents'shall be calibrated semiannually 38 when releases are made to the sanitary sewer. 40 Page.29

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-26 Amendment 40:080193 2. The contents of each tank released shall be sampled and evaluated prior to its release. I Bases: i Experience with the counting equipment used in measuring the radioactivity in the waste retention l tanks suggests that the above period is a suitable calibration frequency. Waste water is normally 40 recycled to the reactor pool. Consequently, discharges are not normally made to the sewer and' calibrations are not normally needed. 4.7 Fission Density Limits i Applicability: i This specification applies to the surveillance requirements for fission density limits. Objective: [ To assure that the fission density limits of Specification 3.8 are not exceeded. -l38 i Specification: 1. The fission density of all fuel elements which have uranium-235 burnup shall be calculated at least quarterly, a .t Bases: } Determination of fission densities on a quarterly basis will ensure that the fission density limits of Specification 3.8 are not exceeded. Fuel element l38 swelling will be kept well below levels which could result in clad rupture and release of radioactive fission products. i b en t t j l Page 50 i

-4. j , -. p. u-e m-o -, ,2 G.s.w w v.he @ 9,M J J.c.f.*w.. i OPERATING LICENSE'AND TECHNICAL SPECIFICATIONS Ford-Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 i 5.0 DESIGN FEATURES l 5.1 Site Description i The Ford Nuclear Reactor (FNR) is located on the North j Campus of the University of Michigan at Ann Arbor, Michigan. The North Campus area is under the i administrative control of the Regents of the University 1 of Michigan. The North Campus is a tract of nearly 900 acres, about 1-1/2 miles northeast of the 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 38 apartments are south of Glazier Way. Apartments are. 40 located north of plymouth Road. Open land and the 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. The reactor building is located near the center of the 40 coReference to North Campus area. No housing or buildings containing buildings widiin housing facilities are erected within 1500 feetLof the 500 feet deleted. reactor. The University of Michigan controls all the land within-1500 feet of'the reactor site, with the exception of a l small portion of the highway right of way along j Glazier Way on the southeast-and the Arborcrest l38 i Cemetery-located 800 feet to the east of the site. i The reactor site consists of all-the land 500 feet to l 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. l The reactor restricted area consists of the reactor building and the contiguous Phoenix Memorial j Laboratory (PML). The reactor building is'the operations boundary and the emergency planning zone. i s l l ' t i I Page 31

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS-Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 f 5.2 Reactor Fuel The fuel assemblies shall be of the MTR type, consisting of plates containing uranium aluminide (UAlx ), uranium oxide (U303), or uranium silicide (U3 Si2 ) fuel enriched l.34 = l to less than 20% in the isotope U235 clad with aluminum. l The authorized fuel assembly designs are: l Maximum Maximum Number Plate Loading Assembly Loading. of Plates (e U235) (c U235) P 18 9.28 +/- 2% 167 +/- 2% 9 9.28 +/- 2% 84 +/- 2% 5.3 Reactor Building [ The reactor building is a windowless, four story, reinforced concrete building with-12 inch walls structurally integral with the footings and foundation i mats. The 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: 1. The reactor is housed in a closed room designed to f restrict leakage. 2. The reactor room is equipped with a ventilation. l system designed to exhaust air or other gases present in the building atmosphere into an exhaust stack which exhausts a minimum of 54 feet above ground level. 3. The ventilation system provides ventilation for 1 certain storage and experimental facilities and a exhausts these a minimum of 54 feet above ground-level. -l i 4. The openings into the reactor building are an equipment access door, three personnel doors, an equipment access hatch, air intake and exhaust i ducts, room 3103 fume hood exhaust duct, beamport ventilation duct, c' sealed north wall door, a door between the hot cave operating face and.the beamport floor, a sealed foundation tile drain to the 40 cold sump, and a pneumatic tube system for sample transfer between the FNR and several laboratories in the Phoenix Memorial Laboratory. j J page 32

1 I OPERATING LICENSE AND TECHNICAL SPECIFICATIONS i Ford Nuclear Reactor -Docket 50-2, License R-28 Amendment 40:080193 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 temperature will not exceed 100 oC. 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 storage array experiments performed with Oak Ridge Reactor and Bulk Shielding. Facility fuel elements. ) 1 l 4 .i l i 'l i Page 33

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 t 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization 1. The organizational structure-of the University of Michigan relating to the Ford Nuclear Reactor (FNR) l shall be as shown in Figure 6.1. 2. The Nuclear Reactor Laboratory Manager shall be l33 l responsible for the safe operation of the Ford Nuclear Reactor. He shall be responsible for assuring that all operations are conducted in a safe manner and within the limits prescribed by the facility license, including the technical specifications and operating procedures. During i periods of his absence, his responsibilities are delegated to the Assistant Manager for Operations 33 or to the Assistant Manager for Research Support Activities. 3. In all matters pertaining to the operation of the [ plant and these technical specifications, the l Nuclear Reactor Laboratory Manager shall report l33' to and be directly responsible to the Director, l Michigan Memorial-Phoenix Project. 4. Qualifications, Nuclear Reactor Laboratory l33 7 Manager and Assistant Managers: Minimum qualifications for the Nuclear Reactor Laboratory '{ l Manager and Assistant Managers shall be bachelor's degrees and at least four years of reactor i operating experience in increasingly responsible positions. Years spent in graduate study may be substituted for operating experience on a one for j one basis up to a maximum of two years. Within six months after being assigned these positions, 'i the Nuclear Reactor Laboratory Panager and the l33 Assistant Managers shall apply for NRC senior operator licenses if they do not already hold i

licenses, j

l 1 l 5. A health physicist who is organizationally i independent of the Ford Nuclear Reactor operations-l group shall be responsible for radiological safety l at the facility. 6. A licensed operator or licensed senior operator l pursuant to 10CFR55 shall be present in the control j room whenever the rbactor is -in operation as defined in these specifications. The minimum l operating crew shall be composed of two l 33-individuals, at least one of whom shall be a l licensed senior reactor operator. page 34 f I t

t OPERATING LICENSE.AND TECHNICAL SPECIFICATIONS i Ford Nuclear Reactor l Docket 50-2, License R-28 Amendment 40:080193 i l i 7. The Nuclear Reactor Laboratory Manager or one of l33 i J the Assistant Managers shall be readily available on-call 24 hours per day, seven days per week. The identity of and method for rapidly contacting l the on-call manager shall be known to the reactor operator or shutdown watchman on duty. 8. Licensed operators are not required to be presentl38 in the facility when the 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 operator duties. 6.2 Review and Audit 8 ~ 1. A Safety Review Committee (SRC) shall review reactor operations and advise the Director, Michigan Memorial-Phoenix Project, in matters relating to the health and safety of the public and the safety of l facility operations. l 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 l Figure 6.1 or administratively report to anyone in that line organization below the Vice President for Research. The Committee shall be made up of l University staff and faculty who shall collectively l 4 provide experience in reactor engineering, instrumentation and control systems, radiological l safety, and mechanical and electrical systems. l 3. The Committee shall meet at least semiannually. 4. The quorum shall consist of not less than a majority of the full committee and shall include the chairman or his designated alternate. 5. Five votes are required to approve those changes,. experiments, and tests which require specific SRC approval. Votes may be cast at SRC meetings or via individual polling of. members. l t 6. Minutes of each Committee meeting shall be distributed to the-Director,. Michigan Memorial-1 Phoenix Project, all Safety Review Committee-I members, and such others as the chairman may j designate. 1 Page 35 I l

OPERATING LICENSE AND-TECHNICAL SPECIFICATIONS Ford Nuclear Reactor i Docket 50-2, License'R-28 Amendment' 40:080193 Figure 6.1 Organization Chart for the Ford Nuclear Reactor Regents University of Michigan President Vice President Vice President and Chief Research Financial Officer l l-Director Director Michigan Memorial-Phoenix Project Financial Operations and 4 Sponsored Program Finance I Safety Review Director Comittee Occupational and Envirormental Safety i Director Radiation Safety Service I Nuclear Reactor . Health Physicist Laboratory Manager I I Assistant Manager Assistant Manager Reactor Operations Research Support Activities Line Function -l Safety and- -) Licensing Function i Licensed Operators Page 36

= _. _ OPERATING LICENSE AND TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 i 7. The Safety Review Committee shall: l a. Review and approve pr(posed experiments and tests l utilizing the reactor facility which are i significantly.different from tests and i experiments previously performed at the Ford l Nuclear Reactor. In the event of a disagreement over approval of an experiment between-the l Committee and the Nuclear Reactor Laboratory 33 Manager, the matter shall be referred.to the i Director, Michigan Memorial-Phoenix Project for resolution. l

b. Review reportable occurrences.

c. Review and approve proposed standard operating procedures and proposed changes to standard operating procedures. This-requirement pertains 3 to those procedures prepared pursuant to Section j 1 6.4 of these specifications. i i d. Review and approve proposed changes to the i technical specifications and proposed amendments to the facility license and review proposed changes to the facility made pursuant to 3 10CFR50.59(c). e. Review the audit report provided by the l consultant for reactor operations. l 8. A consultant will be retained by the University of l Michigan to perform an annual audit of reactor operations and the safety of facility operations. The consultant shall be selected by the Director,.

i Michigan Memorial-Phoenix. Project and shall be an individual presently or recently engaged in the j

management of a research or test reactor of comparable power 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 provide the members of the Safety Review Committee with copies of this report. i 9. The audit shall be conducted with the following [ guidelines. i

a. At least once every five years, a broad l34 review will be made of the following areas:

(1) Administration; (2) Safety Review Committee; (3) Reactor operators; (4) Procedures; (5) j Surveillance; (6) Quality Assurance Program; (7) r 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 of the organization, Page 37 4

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2,. License R-28 Amendment 40:080193 3 training, plans, procedures, surveillance,.and records for safe operation of the facility; (2) Verify that the requirements of Technical i ~ Specifications are being met; (3) Establish whether plans and procedures are being implemented; and (4) Determine whether i responsibilities within the organization are appropriate. l t

b. Routine audits will review a limited number j34 of systems in depth each year and will include l

as applicable to each system: (1) Operating l procedures and records; (2) Calibration procedures and records; (3) Equipment operation,. -l ' condition, and failures; (4) Modifications; and (5) Reportable occurrences. l 6.3 Action to Be Taken in the Event of a Reportable j Occurrence i In the event of a reportable occurrence, as defined in these technical specifications, the following action t shall be taken: 1. The Nuclear Reactor Laboratory Manager shall be. j33 notified of the occurrence. Corrective action shall be taken to correct the abnormal conditions and to prevent its recurrence. i t 2. A report of such occurrence shall be made to the Safety Review Committee; the Director, Michigan l Memorial-Phoenix Project; and the Nuclear Regulatory Commission in accordance with Section 6.6.2.a. i s The report shall include an analysis of the causes 1 of the occurrence, the effectiveness of corrective l actions 1taken, and recommended measures to 38 prevent or reduce the probability or i consequences of recurrence. lt 6.4 Operating Procedures I Written procedures, including applicable check lists, reviewed and approved'by.the Safety Review Committee shall be in effect and followed for the following l' operations: 1. Startup,' operation and shutdown of the reactor; 1 2. Installation and removal of fuel: elements, control j rods, experiments and experimental facilities; l l ) f Page 38 l

r OPERATING LICENSE AND TECHNICAL SPECIFICATIONS I Ford Nuclear, Reactor Docket.50-2, License R Amendment' 40:080193 { 3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, l including responses to alarms, suspected primary l coolant system leaks, and abnormal reactivity changes; 4. Emergency conditions involving potential or actual release of radioactivity, including provisions for a evacuation, reentry, recovery, and medical support; 5. Maintenance procedures which could have an effect on j reactor safety, i 6. periodic surveillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors; } I 7. Facility security plan; i 8. Radiation protection procedures. Substantive changes to the above procedures shall be l34 j made only with the approval of the Safety Review Committee. Temporary changes to the procedures that do not change their original intent-may be made with. l approval of the Nuclear Reactor Laboratory Manager l33 or one of the Assistant Managers. All temporary changes to the procedures shall be documented and subsequently reviewed by the Safety Review Committee. I 6.5 Operating Records j i 1. The following records and logs shall be prepared and l retained by the licensee for at least five years: a. Normal facility operation and maintenance;. j b. Reportable Occurrences; j i c. Tests, checks, and measurements documenting j compliance with surveillance requirements;- i d. Records of experiments performed; j t e. Records of radioactive shipments; t i f. Operator requalification program. records (the five year period will commence after termination u of the assignment of the operator to' operative duties); g. Facility radiation and contamination surveys. Page 39

~ OPERATING LICENSE AND TECHNICAL SPECIFICATIONS l Ford Nuclear Reactor Docket 50-2, License'R-28 Amendment 40:080193 2. The following records and: logs shall be prepared and retained by the licensee for the life of the facility: l t a. Gaseous and liquid waste released to the i environs; j .i b. Off site environmental monitoring surveys; j c. Radiation exposures for all FNR personnel; i d. Fuel inventories and transfers; j i e. Up;4ted, corrected,-and as built facility l drawings; ) t e f. Minutes of Safety Review Committee meetings. 6.6 Reporting Requirements j t i In addition to reports required by Title 10,. Code of Federal Regulations, the following reports shall be submitted to the United States Nuclear Regulatory Commission. 1. Annual Operating Report } .I A written annual' operating report shall be submitted f by March 31 of each year to the U S. Nuclear Regulatory i Commission, Attn: Document Control Desk, Washington,. D.C. 20555 and to the Administrator, Region III. . ii L The report shall include the following information-for j the preceding year, j t a. Operations Summary A summary of operating experience having safety ] significance occurring during the reporting i period. ?

1. Changes in facility design.

I i

2. Performance characteristics (e.g.,

equipment i and. fuel performance). ~ t

3. Changes'in operating procedures which relate

} to the safety of facility' operations. i [

4. Results of surveillance tests and j

inspections required by these technical pecifications. l i ? Page 40 I = ?--- w -se e e -r- .am r e-9 w-,w

-~ -. ~ i OPERATING LICENSE AND TECHNICAL SPECIFICATIONS i Ford Nuclear Reactor-1 Docket 50-2, License R-28 l Amendment 40:080193 t

5. A brief summary of.those changes, tests, and experiments which required. authorization from i

the commission pursuant to 10CFR50.59(a).

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

j i a. Nuclear Reactor Laboratory Manager; -j33

b. Health Physicist; 9

c. Safety Review Committee members. b. Power Generation j A monthly tabulation of the thermal output of f .the facility during the reporting period. i c. Shutdowns A listing of unscheduled shutdowns which'have occurred during the reporting period, tabulated. according to cause, and a brief discussion of j the actions taken to prevent recurrence. q 13 d. Maintenance ['l A discussion of corrective maintenance, l excluding preventive maintenance, performed j during the reporting period on safety related -r systems and components. e. Changes, Tests, and Experiments [ l A brief. description and a summary of theLsafety evaluation for those changes, tests, and-experiments which were carried out without prior. j commission approval, pursuant to.the requirements of 10CFR50.59(a). i f. Radioactive Effluent Releases j P A statement ~of the quantities of radioactive

l effluents released from the plant.

-l 1. Gaseous Effluents f a. Gross Radioactivity Releases _ 1. Total gaseous radioactivity in {40 l curies. I i l t l u .Page 41 1 'f 5

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 2. Average concentration of gaseous effluents released during normal steady state operation averaged i over one year. l40 3. Maximum instantaneous concentration of noble gas radionuclides released during special operations, tests, or I experiments. 4. Percent of diluted, 10CFR20, 40 Appendix B. Table 2, Column 1, l air effluent concentration limit. b. Iodine Releases + (Required if iodine-131 is consistently identified in primary [40 coolant samples, or if fueled experiments are conducted at the facility.) 1. Total iodine radioactivity in curies released _, based on l40 representative isotopic analyses. 2. Percent of diluted, 10CFR20, 40 Appendix B, Table 2, Column 1, i air effluent concentration limit. r c. Particulate Releases 1. Total particulate gross beta and j40 gamma radioactivity released in curies excluding background radioactivity. 2. Gross alpha radioactivity released in curies excluding background radioactivity. (Required if the operational or experimental program ) is expected to result in the l40 release of alpha emitters.) 3. Total gross radioactivity in curies nuclides present in samples _ 40 .ited within two weeks of sample s collection. 4. Percent of diluted, 10CFR20, 40 Appendix B, Table 2, Column'1, air effluent concentration limit. Page 42 [

OPERATING LICENSE AND~ TECHNICAL SPECIFICATIONS i Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 2. Liquid Effluents ( a. Total gross beta and gamma radioactivity released in curies excluding tritium and average concentration released to l40 unrestricted areas or sanitary sewer averaged over period of release. b. The maximum concentration of beta and gamma radioactivity released to unrestricted areas. l40 c. Total alpha radioactivity in curies released and average concentration released to unrestricted areas l40 averaged over the period of release. (Required if the operational or j experimental program is expected to [40 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. i t 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

• • Reference to a specific 10CFR2D storage tank.

[40 u-concentraticm limit deleted. I' g. Percent of diluted, 10CFR20, ' 40 Appendix B, Table 3 Releases to Sewers i g. Environmental Monitoring For each medium sampled:

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

2. Number of locations at which levels are.

found to be significantly higher than the remaining locations. l r 4 i Page 43 2 w-. 4 y v

OPEPATING LICENSE AND TECHNICAL SPECIFICATIONS . Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 40:080193 .i

3. Average annual concentrations or levels of~-l40 l

radiation.for the sampling point with the highest average concentration or level and the location of that point with respect to the site.

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

i a. Direct radiation and gaseous effluent; i b. Liquid effluent. 5. If levels of radioactive materials in environmental media, as determined by an environmental monitoring program, indicate the likelihood of public intakes in excess 'l of 10% of those that could result from -l40 continuous exposure to the concentration I values listed in 10CFR20, Appendix B, Table 2, Columns 1 and 2, estimates of .[40 the likely resultant exposure to individuals' i and to population groups and assumptions upon which estimates are based. i 7. If significant variations of off site f environmental concentrations with time are observed, correlation of these results with effluent release shall be provided. y h. Occupational Personnel Radiation Exposure [ ~ A summary of-annual whole body radiation-l38 I exposures greater than 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 .i a. Reportable Occurrence Reports 'I r In the event of a reportable occurrence 38

l as defined in section 1.0, notification-shall be made within-24 hours by telephone and FAX to the Reactor Project 38

'l Manager, Headquarters, U.S. Nuclear-Regulatory Commission and to the j Administrator, Region III, followed by-a written report within 14 daysfto the U. S. i Nuclear Regulatory Commission, Attn: Document i Control Desk, Washington, D. C. 20555, and to. the Administrator, Region.III. FAX- . l38 Page 44 ti o;

~ OPERATING LICENSE AND TECHNICAL SPECIFICATIONS j ~ -Ford Nuclear Reactor-1 Docket 50-2, License R-28 ' Amendment.- 40:080193-1 L .l t 1 i i 'l -i i I h t ~I C i I t ? -i . t t:l .? i i i 1 i I -l 4 + 4 .i 1 1 Page 46 l l .5}}