ML20245F974
| ML20245F974 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 08/04/1989 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245F960 | List: |
| References | |
| R-028-A-033, R-28-A-33, NUDOCS 8908150149 | |
| Download: ML20245F974 (53) | |
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UNITED STATES s
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- 4 NUCLEAR REGULATORY COMMISSION 8" s?
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.e UNIVERSITY OF MICHIGAN DOCKET NO.50-002 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. R-28 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to Facility Operating License No. R-28 fileo by the University of Michigan (the licensee),
dated y 8, 1989 and supplemented by letters dated May 16, 23, and June 16, 1989, complies with the standards end requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFP. Chapter I; E.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comn:ission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be concucted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this arnendment is ir accordance with 10 CFR Part 51 of the Cormission's regulations ano all applicable requirements teve beer, satisflec; and F.
Publication of notice of this amendment is not requirea since it does not involve a significant hazards consideration nor amenament of a license of the type described in 10 CFR Section 2.106(a)(2).
8908150149 890804 PDR ADOCK 05000002 P
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Accordingly, the license is amended by changes to the Technical
. Specifications as indicated in the enclosure 'to this license amendment, and paragraph 2.C.(2) of License No. R-28 is hereby amended to read as follows:
(2) Technical Specifications
.The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license' amendment is effective as of its'date of issuance.
4 FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director.
Non-Power Reactor, Decommissioning and Environmental Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: August 4, 1989
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EhCLOSURE TO LICENSE AMENDMENT N0. 33 l
FACILITY OPEFATING LICENSE N0.~R-28 1
DOCKET 110.50-002 The Appendix A Technical Specific 6tions have been replaced in its entirety.
Apart from page number revisions, caused by retyping, the only changes that
'have been made appear in the following pages, which are identified by Amendmes;t Number and contain a vertical line indicating the area of change.
Revised P,a g 10,11,15, 21, 25, 26, 30, 33, 36, 37, 38, 39, 40, 41, and 42 I
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t' TECHNICAL SPECIFICATIONS.
Ford Nuclear Reactor Docket 50-2. License R-28 Revision i License Renewal Issue:
113084 Revisions:
1: 050189 APPENDIX A TO FACILITY LICENSE R-28 TECHNICAL SPECIFICATIONS DOCKET 50-2 MICHIGAN MEMORIAL PHOENIX-PROJECT THE UNIVERSITY OF MICHIGAN Ann Arbor, Michigan i
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TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 i
Revision i CONTENTS 1.0 DEFINITIONS 1
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 6
2.1 Safety Limits 6
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 Natural Convection Flow Mode 7
3.0 LIMITING CONDITIONS FOR OPERATION 10 3.1 Reactivity Limits 10 3.2 Reactor Safety System 12 3.3 FNR Confinement Building 16 3.4 Primary Coolant Conditions 17 3.5 Heavy Water Reflector Tank 18 3.6 Airborne Effluents 19 3.7 Liculd Effluents 20 3.8 Limitations of Experiments 21 3.9 Fission Density Limit 23 4.0 SURVEILLANCE REQUIREllENTS 25 4.1 Reactivity Lluits 25 4.2 Reactor Safety System 26 4.3 FNR Confinement Building 28 4.4 Primary Coolant System 29 4.5 Heavy Water Reflector Tank 30 4.6 Airborne Effluents 30 4.7 Liquid Effluents 31 4.8 Fission Density Limits 31 5.0 DESIGN FEATURES 33 5.1 Site Description 33 5.2 Reactor Fuel 34 5.3 Reactor Building 34 5.4 Fuel Storage 35 Contents-1
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. TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket.50-2 License R-28 Revision i 6.0 ADMINISTRATIVE CONTROLS 36 6.1.
Organization 36 6.2 Review and Audit.
37
.6. 3 -
Action.to be-Taken in the Event of a 1
Reportable 0ccurrence 40
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Operating Procedures 40 6.5 Operatina. Records 41 6.6 Reporting Requirements 42 Contents-2
L TECHNICAL SPECIFICATIONS Ford Nuclear Reactor l-Docket 50-2. License R-28 Revision 1 l
1.0
' DEFINITIONS 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.
l Channel. Check - A channel check is a qualitative verification of acceptable perf ormance 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 into the channel to verify that it is operating.
Experiment - An experiment, as used herein, is any of the f ollowing:
1.
An activity ut11121ng 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 whicn is conducted within the confinement or containment system of the reactor; 4.
The material content of any of the f oregoing, Including structural components, encapsulation or j
confining boundarles, and contained fluids or sollds.
Experimental Facility - An experimental f acility is any structure or device which is Intended to gulde, orient, position, manipulate, or otherwise f acilitate a multiplicity of experiments of similar character.
Explosive Material - Explosive material is any solid or liquid which is categor12ed as a severe, dangerous, or very danger 003 explosion hazard in DANGEROUS PROPERTIES OF INDUSTRIAL l
MATERIALS by N.I. Sax, Third Ed. (1968), or is given an j
Identification of Reactivity IStability) Index of 2,3, or 4 by l
the National Fire Protection Association in its publication 704-M. 1966.
Limiting Conditions for Operation (LCO) - Lowest functional capability or perf ormance levels of equipment required f or j
saf e operation of the reactor (10CFR50,36 ).
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TECHNICAL SPECIFICATIONS
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Ford Nuclear Reactor Docket 50-2, License R-28 Revision i l
Limiting Safety System Setting (LSSS) - Settings for automatic ~
protective devices related to those variables having significant u
safety functions, and chosen so that automatic protective action will correct an abnormal situation before a safety limit is exceeded fiOCFR50.36).
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 sensor, ampl if i e rs, and output devices which are used for the purpose of measuring the value of a process variable.
Hoveable 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 pormal manner.
Potential Heactivity Worth of an Experiment - The potential reactivlty worth of an experiment is the maximum absolute value of the reactivity change that would occur as a result of Intended or anticipated changes or credible malfunctions that alter equipment position or configuration.
Reactivity Limits - The reactivity limits are those limits imposed on reactor core excess reactivity.
Quantitles 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 0.05X Delta 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 cre 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 fuel elements loaded on the grad plate.
Reactor Safety Syttem - The reactor safety system 13 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 initlated.
Reactor Scram - Shutoff of electrical current to the rod holding magnets and subsequent insertion of the rods into the core by gravity.
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TECHNICAL SPECIFICATIONS
'3.
Ford Nuclear Reactor Docket 50-2, License R-28 Revision 1-Reactor Secured - Reactor Secured is defined as f ollows:.
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 cere, the insertion or removal of secured experiments from the core, or control rod maintenance.
Readily Available on.Cill - 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) from the reactor building when the reactor is Deing cperated by a licensed operator.
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.
Removable ExpErlsent - A removable experiment is any experiment, experimental facility, or component of an experiment, otner than a permanently attached appurtenance to the reactor system, which can reasonably be anticipated to be moved one or more times during the life of the reactor.
Reportable Occurrence - A reportable occurrence is any of the f ollowing:
1.
A Jafety 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 Tecnnical Specli1 cations; 3.
A safety system component malfunction or other i
component or system malfunction which could, or threatens to, render the safety system incapable of perf orming its intended saf ety f unctions:
4.
Release of fission products f rom a f ailed f uel element; 5.
An uncontrolled or unplanned release of rad 10 active material f rom the restricted area of the f acility; Page 3
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TECHNICAL SPECIFICATIONS H ;*
,4 Ford Nuclear Reactor T
. Docket 50-2. License R-28 Revision i b
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 of 10CFR20; 7.
An uncontrolled or unanticipated change in reactivity in excess of 0.005 delta K/K; 8.
Conditions' arising from natural or man made L
.operatiot of the f acility; events that affect or threaten to affect the safe 9.
An obserted inadequacy in the implementation of b
administrative or procedural controls such that the. inadequacy causes or threatens to cause the existence or development of an unsafe-condition in connectio:. with the operation of the facility.
l Rundown - A rundown is the automatic insertion of the Shim safety rods.
Safety Channel - A safety channel is a measuring chann?! in
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the reactor safety system.
1 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).
Secured Experiment - Any erperiment, 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 ef f ects of hydraulle, 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 borated stainless steel which is used to compensate f or f uel burnup, temperature, and polson effects.
A shim safety rod is magnetically coupled to its drive unit allowing it to perf orm the f unction of a saf ety rod when the magnet is deenergized.
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-TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28 Revision 1
' Static Beactivity Worth - The static reactivity worth of an experiment is the absolute value of the reactivity change which 15 measurable by calibrated control rod comparison methods between two defined terminal positions or configurations of the
. experiment.
For moveable experiments, the terminal positions are f ully removed f rom the reactor and f ully inserted or Installed in the normal Functioning or intended position.
Time Intervals Annually - 12 to 15 months.
B1 annually - 24 to 30 months.
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.
l Sem1 annually - 6 to 6 months.
l Weekly - 7 to 10 days.
l True Value - The true value of a process variable is its i
actual value at any Instant.
Unscheduled Shutdown - An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the I
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.
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TECHNICAL SPECIFICATIONS i'/
- Ford Nuclear Reactor-Docket 50-2. License R-28 i
l Revision 1 2.0 SAFETY LIMITS AMD L1HITING SAFETY SYSTEM SETTINGS L
2.1 Safety Llaats 2.1.1 Safcty Limits in the Forced Convection Mode Applicat111ty:
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This specification. applies to the Interrelated L
variables associated with core thermal and L
hydraulic performance in the steady state with forced convection flow.
These variables are:
l Reactor Thermal Power, P Reactor Coolant Flow Through the Core, m Reactor Ccolant Inlet Temperature. T1 Height of Water Above the Top of the Core, H Objective:
To assure that the Integrity of the fuel clad 2s maintained.
Specification:
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 temperature (T ) at 2 Mw shall nct exceed.
3 116 F.
3.
The true value of water height above the core (H) shall not be less than 18 feet while the reactor 15 operating.
Bhses:
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 FHR core (25 elements ) will not r ach the boiling point of the water coolant.
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TECHNICAL SPECIFICATIONS
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' e' Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 1
2.1.2 Safety Limits in the Natural Convection Mode.
Applicability:
j This specification applies to the interrelated variables associated with core thermal and j
hydraulic performance in the natural convection mode of operation.
These variables are:
Reactor Thermal Power, P Reactor Coolant Inlet Temperature, T1 Height of Water Above the Top of the Core, H Objective:
To assure that the integrity of the fuel clad is maintained.
Specification:
1.
The true value of the reactor thermal power (P) shall not exceed 380 kw.
2.
The true value of the reactor coolant inlet temperature (T ) shall not exceed 131 F.
3 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 bolling point of the water coolant at a depth of 18 feet.
2.2 Limiting Saf ety System Settings (LSSS) 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),
helght of water above the top of the core (H).
and core exit temperature (Te).
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a TECHNICAL SPECIFICATIONS-L,0 * '
Ford Nuclear Reactor Docket 50-2, License'R-28 j
Revision't Objective:
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 (Te) shall be as f ollows:
Variable LSSS P (Max )
2.4 Mw m (Min )
900 gpm H (Min) 19 f t Te(Max) 129 F Bases:
The limiting safety system settings for forced convection assure that automatic protective action will correct the most severe abnormal tituation 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 f or the safety channels monitoring reactor thermal power (P), pool water level (H ),
and pool water temperature (T).
Obj e ct ive:
To assure that automatic protective action is initiated to prevent a saf ety limit f rom being exceeded.
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li TECHNICAL SPECIFICATIONS Ford Nuclear Reactor.
Docket 50-2, License R-28 Revision i Specifications:
1.
The limiting safety system setting 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 11miting 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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3.0L LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Limits i
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 limits will not include the static reactivity worth in the tank.
Objective:
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 shall be at least.025 delta K/K with all three shim safety rods fully inserted and the regulating rod full with-drawn and 0.0045 delta K/K with the most reactive shim safety rod and the regulating rod fully withdrawn.
2.
The overall core excess reactivity including moveable experiments shall not exceed 0.038 delta K/K.
3.
The total reactivity worth of all experiments shall not exceed 0.012 delta K/K.
4 The reactivity worth of each experiment shall te limited as follows:
Maximum R activity Worth Experiment 1
Noveable 0.0012 delta K/K~
Secureo 0.012 delta K/K 5.
The reactor shall be subtritical by at least 0.025 delta K/K during fuel loading changes.
6.
The core shall have a negative reactivity of at least 10%
before shim safety rods are removecTTrom the core for inspection.
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7.
The core shall have a neoative reactivity of at least 101 whenever f.eavy water movementi'sh'iWcan result in positive reactivity insertions are undertaken.
_ Amendment No. 33
,9 8.
-The reactivity worth of the regulating rod shall not exceed 0.006 delta K/K.
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Experiments which could increase reactivity by flooding, shall 6
not remain in or adjacent to the core unless the shutdown margin required in Specification 3.1.(1) would be satisfied after flooding, Bases:
The shutdown margin required by Specification 3.1.1 assures that the reactor can be shutdown from any operating condition and will l
remain subtritical after cooldown and xenon decay even if the rod l
of the highest reactivity worth should be-in the fully _ withdown position.-
Specification 3.1.2 limits the allowable excess reactivity to the q
value necessary)to overcome the' combined negative reactivity to 116 F; (2)(fission product xenon and samarium buildup in a clean effects of:
1 an increase in primary coolan'. temperature from 90 F core; (3) power defect due to increasing from a zero power, cold core to a 2 Pk, hot core; (4) fuel burnup during sustained operation for 30 days; and (5) moveable experiments.
Specification 3.1.3 limits the reactivity worth of experiments to
. values.of reactivity which, if introduced as positive step changes, will not cause fuel melting.
Specification 3.1.4. limits the individual reactivity worth of experiments to values that will not produce a stable period of itss than 30 seconds and which can be compensated for by the action of the control onc safety systems without exceeding any safety limits.
Specifications 3.1.5 and 3.1.6 provide assurance that the core.will remain subcritical during fuel loading changes and shim. safety rod maintenance or inspection.
The, largest positive reactivity increase that can be produced by replacing light water with heavy water in the heavy water reflector tank is 0.04 delta K/K. Maintaining the core at a negative reactivity of at least 10% in Specification 3.1.7 during heavy water transfers provides adequate margin to assure that the reactor will remain subcritical during heavy water transfers that could add positive reactivity.
Specification 3.1.8 assures that failure of the automatic control system will not introduce sufficient excess reactivity to procuce a prompt critical condition. Amendment No. 33
TECHNICAL SPECIFICATIONS C ~ -
Ford Nuclear Reactor Docket 50-2, License R-28 Revision i Specification 3.1.9 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.
3.2 Reactor Safety System Applicability:
These specifications apply to the reactor safety system and other safety related instrumentation.
Objective:
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.
Specification:
The reactor shall not be made critical unless:
1.
The reactor safety systems and safety related Instrumentation are operable in accordan'e with Tables 3.1 and 3.2 including the minimum t'imber of channels and the indicated maximum or minimum setpoints; 2.
All shim saf ety rods are operable; 3.
The time from the initiation of a scram condition in the scram circuit until the shlm safety rods are fully inserted (release-drop' time) shall not exceed 500 milliseconds; 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 j
manually controllable without reaching excessive power levels or f uit temperatures.
Power-flow coincident scrams provide redundant channels to assure that an automatic loss of flow scram w111 occur in the event of a loss of flow when the reactor is operating at power levels above 100 kw.
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TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Revision i Table 3.1 REQUIRED SAFETY CHANNELS Minimum Number Channel Setpoint Required Function Log. Count Rate 2 cps i
Rod Withdrawal Interlock Log N Period i
Vide range power level and input for period scram Period Safety 5 see i
Scram Level Safety 120Xf2.4 Mw) 2 Scram High Power /No (a) 900 gpm i
Scram 2100 Kw Water Flow (b) holdup tank isolation valve not fully open (c) holdup tank static pressure i psig below full power value High Power /
Header Down i
900 gpm i
Scram No Water Flow Building Exhaust i mr/hr i
Scram Radiat10:1 Level l
Building Alarm i
Scram l
Manual Switch l
l Manual Scram Switch i
Scram Magnet Power Keyswitch i
Scram Reactor Coolant Exit Temp.
129 F i
Auto Rundown Pool Level i foot below pool i Auto Rundown overflow Bridge Not When clamps i
Scram Clamped released Page 13
TECHNICAL SPECIFICATIONS L 1* ~
Ford Nuclear Reactor Docket 50-2,-License R-28 Revision i Table 3.2 Required Safety Related Instrumentation Minimum Number Instrumentation Setpoint Required Function Linear Level Channel As Required i
Linear power level measurement and input for the automatic control mode Power Level Deviation 95% of control i
Return reactor to Interlock point setting manual control mode if setpoint is reached Reactor Coolant Inlet Not Applicable 1(a)
Provide Temperature Information for the heat balance determir.ation Facility Radiation Monitor System (b)
- 1.
Building Air Exhaust 1(1) mr/hr i
Alarm, scram, initiate Confinement evacuation
- 2. Reactor Bridge 30(50) mr/hr 1
Alarm
- 3. NW Column, Beamport 10(50) mr/hr 1(c)
Alarm Floor
- 4. H Wall, Beamport 5(50) mr/hr 1(c)
Alarm Floor
- 5. NE Column. Beamport 2(50) mr/hr 1(c )
Alarm Floor
- 6. Primary Deminer-20(50) mr/hr 1(c)
Alarm alizer (Hot DI)
(a) Not required for natural convection operation.
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TECHNICAL SPECIFICATIONS Ford Nticlear Reactor Docket.50-2, License R-28 Revision 1 Table 3.2 Required Safety Related Instrumentation (continued)
(b) The facility radiation monitoring system consists of 6 radiation detectors which alarm and read out locally, and are recorded in
.the control room.
The normal setpoints for this system are shown.
The value in parentheses is the maximum setpoirit which will be used depending on local conditions.
Use of higher than normal setpoints will require approval of the Huclear Reaq_ tor ji Laboratory Mapager or-one of the Assistant Managers.
Any reactor staf f member may adjust a setpoint lower than the normal value.
(c) Of the detectors labelled 3-6. 'any one unit may be.out of service f.or a-period not to exceed 7 days without requiring-reactor shutdown or replacement by a locally alarming monitor with similar range..Should a second of these units require
-repair, such repair must be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the reactor must.be shutdown or replacement of the second unit with a locally alarming monitor of similar range is required.
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TECHNICAL SPECIFICATIONS S1' N^*'
Ford Nuclear Reactor Docket-50-2 License R-28 Revision 1
.The. rod withdrawal. interlock on the Log Count Rate channel assures'that the operator has a measuring channel operating and11ndicating neutron flux levels during the approach to criticality.
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 limit for pool level.
The manual scram button and the magnet power Reyswitch
. 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.
3.3 FNR Confinement Building Applicability:
This specification applies to the FNR confinement-building requirements.
Oblective:
To minimize the release of airborne radioactive materials from the FNR.
Specification:
1.
The ventilation intake and exhaust dampers, the intake and exhaust ventilating f ans, and the dampers in the beamport exhaust system and the room 3103 exhaust hood duct shall automatically close when the radiation level in the building ventilation exhaust duct is i millirem / hour or more.
2.
During reactor oleration, the f ollowing conditions will be administratively controlled:
a.
Personnel access doors will be closed except as necessary f or the passage of personnel and/or equipment; L
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TECHNICAL SPECIFICATIONS i-Ford Nuclear Reactor.
Docket 50-2, License R-26 t
Revision i 1
i b.
The main-equipment access door onto the beamport i
floor will be opened only long enough to permit 1
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 4
tower area.
The door will remain closed but not l
clamped until all personnel have left the Cooling tower area; d.
The access hatch f rom grade level to the beamport floor will be sealed closed; e.
The personnel exit door located in the north wall of the building and the door located on the beamport floor which connects to the PML 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 f rom the conf inement 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 exceed the leak rate used in the evaluation.
The 1.0 mr/hr setpoint for the facility exhaust radiation monitor provides a mechanism for isolating the building "ent11ation system in the event of a significant 1 lease of radioactive mater 2al into the reactor building.
This setpctnt, for the detector location involved, r a gamma emitting nuclide conctntrationof10-gpresentsto 10-4 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 below the value assumed in the Hazards Summary Report, and the release of radioactive material will be minimized.
3.4 Frimary Coolant Conditions Applicability:
This specification applies to the limiting cond!tions for available pool water volume, primary coolant pH.
resistivity, radioactivity, and flow distribution.
Page 17
TECHNICAL ~ SPECIFICATIONS
' - c' Ford Nuclear Reactor Docket 50-2, License R-28 D
Revision 1 Objective:
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 resistivity shall be maintained at a value greater than 200,000 ohm-cm except for periods of time not to exceed 7 days 'fhen the resistivity may not be less than 50,000 ohm-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, grid plugs or experimental facilities-4.
For operation at powers in excess of cs, the pool gate 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 3.4.1 and 3.4.2 will control the corrosion of the aluminum components of the primary coolant system and the fuel element cladd1Lg.
j The requirement that all grid positions be occupied will prevent the degradation of flow rates due to flow i
bypassing the active fueled region through and 1
unoccupled grid plate position.
]
The requirement 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 Heavy Water Reflector Tank App l ic ab i l ity:
This specification applies to the heavy water reflector tank used in the reactor core.
Page 18
I' TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-26 Revision 1-
' Obj e c t ive:
To' assure that heavy water handling in the heavy water reflector tank does not jeopardize facility and personnel safety.
Specification:
1.
The tritium content of the heavy water reflector tank shall be no greater than 50 curies.
' Bases:
The 50 curie limit imposed on the tritium content of the heavy water reflector tank assures that offsite concentrations of tritium in the event of a tank rupture will not exceed the limit established in 10CFR20 for tritium releases to uncontrolled areas.
3.6 Airborne Effluents Applicability:
This specification appilas to the monitoring of airborne effluents from the FNR.
Objective:
To assure that containment integrity is maintained during reactor operation and that the release of airborne radioactive mate?lal from the FNR is maintained below the limits established in 10CFR20.
Spe c if ic ation:
- 1. -
1.
The concentration of radioactive materials in the I
ef fluent released f rom the f acility exhaust stacks shall not exceed 400 times the concentrations specified in 10CFR20. Appendix B, Table II, when averaged over time periods permitted by 10CFR20.
)
j Page 19
TECHNICAL SPECIFICATIONS.
W*
Ford Nuclear' Reactor Docket 50-2 License R-28 Revision 1 2.
During operation of the reactor, the following conditions shall be met:
p a.
The particulate activity monitor and'the gaseous o
activity monitor f or the. f acility exhaust stacks shall be operating.
'If either unit is to be 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
- apability; b.
.The particulate activity monitor and the gaseous activity monitor for the reactor building shall t
be operating.
Temporary shutdown of these units
'shall be limited as in specification 3.6.2.a above; c.
The building exhaust air radiation monitor shall be operating whenever the reactor is in
' operation as required by Table 3.2 of specification 3.2.
1 Bases:
The limits established in specifleation 3.6.1 incorporate a dilution factor of 400 for effluents released through the exhaust stacks.
This dilution factor was calculated from actual.FNR site meteorological data and represents the lowest dispersion factcr determined and the highest frequency of wind in any sector.
Because of the use of the most conservative
'mcasured values of wind directional frequency and dispersion factors, this dilution f actor will assure that. Concentrations of
'410 active material in unrestr.icted areas around the FNR site will be far below the limits of 10CFR20.
The requirements of specification 3.6.2 are considered adequate to assure proper airborne effluent monitoring.
3.7 Liquid Effluents
,l Applicability:
j This specificat)on supplies to the monitoring of radioactive 11guld effluents from the FNR.
Objectives:
The objective is to assure that exposure to the public resulting f rom the release of liquid effluents will be minimized.
1 Page 20 J
k.f*'..-
TECHNICAL' SPECIFICATIONS' Ford Nuclear Reactor Docket ~50-2, License R-28 Revision i 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 not exceed the concentrations specified in 10CFR20 for releases to sanitary sewer systems.
2.
The amount of liquid discharged shall be limited i
to tne equivalent of 3,000 gallons of 11guld at the concentration limit specified in 3.7.1 each day.
4 3.
Liquids f rom the f acility's radioactive 11guld waste systemishall not be discharged into the storm drain system'.
Bases:
All radioactive liquid effluents,2re collected it. a series of three, 3,000 gallons, coated, steel retention tank.
The liquid waste in the tanks is sampled and analyzed before discharge.
When the concentration is less than the. limit of 40CFR20, it is discharged to the sanitary sewer system Current experience requires discharges of less than 50 tanks per year.
During 1970, the North Campus water released into the sanitary sewer system averaged.
946.000 gallons per day.
This provides a daily dilution f actor of 315 f or 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.
3.6 Limitations of Experiments s
ApplicaL111ty:
This specification appljes 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.
Fage 21 l
\\
' TECHNICAL SPECIFICATIONS 1
Ford Nuclear Reactor r
Docket 50-2, License R-28 Revision i Specification:-
1.
Each experiment shall be aesigned 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 pocl.
4.
Neutron raalography 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 fall by detonation of at least twice the amount of explosive to be irradlated.
5.
The radioactive material content, including fission products, of any singly encapsulated experiment should be limited so that the complete release of all gaseous, particulate, and volatile ccmponents from the encapsulation could not result in doses in excess of 10% of the equivalent annual doses stated in 10CTR20.
This dose limit applies tu persons occupying unrestricted areas contt';uously for two hours starting at time of releas0 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 4
from the encapsulation co111d not result in doses in exces; of the equivalent ennual doses stated in 10CTR20.
This dose limit applies to persons occupying unrestricted areas continuously for two hours starting et the time of release and restricted areas during the length of time required to evacuate the restricted area.
1 Page 22
TECHNICAL SPECIFICATIONS e*.'-
Ford Nuclear Reactor Docket 50-2. License-R-28 Revision i
?
Bases:
Specifications 3.8.1-through 3.8.4 are intended to reduce the 11Relihood of damage to reactor components and radioactivity releases resulting from experiment failure and serve as a guide for the review and approval 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 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 3.8.5 and 3.8.6 conf orm to the 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.
3.9 F1ssion 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:
21 1.
The FNR fission density limit sha'l be 1.5x10 fission /cc.
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.
Page 23
_m_.______._-____________________________.____.____.._____________.____m___.
l 1 TECHNICAL SPECIFICATIONS
'?
Ford Nuclear Reactor-Docket 50-2 License R-28 l
Revision:1 An experimental data base which supports the safe use of UAlx and U 038 fuel-in'the FHR up to the fission density was derived from irradiation tests performed in the Materials Test Reactor (MTR), the' Engineering Test Reactor (ETR), and the Advance Test Reactor (ATR) at i
the Idaho National Engineering Laboratory, the High Flux Isotope Reactor (HFIR) at the Oak Ridge National-Laboratory, and the German Karlsruhe FR2 reactor.
l l
l-Page 24 1
e,
.E 4
4.0 ' SURVEILLANCE REQUIREMENTS 4.1 Reactivity. Limits
~
A. applicability:
This specification applies to the surveillar.ce requirements for reactivity limits.
Objective:
To assure that the reactivity limits of Specification 3.1 are notL exceed.
Specification:
1.
Shim safety rod reactivity worths shall be measured:
a.
Not less than once each calendar year; b.
Whenever.the fuel elements in more than three interior
. core locetions are replaceo; 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; c.
Whenever the addition of more than three standard fuel elements to an outer face of 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 swellino at least annually.
3.
The reactivity worth of those experiments whose safety review indicates o 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 coulc reasenably be expected to cause increases in experir.,ent reactivity worth whereby the experiment worth could exceed the values specified in Specification 3.1.
4.
The core negative reactivity required by specification 3.1.7 will te verifieu whenever heevy water transfers are to be made.
l Amendment No. 33 c_ - __- - -
i Bases:
Specification 4.1.1 will assure that shim-sefety rod reectivity worths are not degraded or changed by core arrangements.
Shim safety rod inspections are the single, largest source of rao16 tion exposure to facility personnel.
Furthermore, frequent inspections of sh.m safety rods for swelling over the last ten years
.have produceo no w idence of swelling or cracking._ In order to minimize' personnel radiatier, exposure and provide an inspection frequency that will detect early evidence of swelling and cracking, an annual inspection interval was selected for Specification 4.1.2.
The specified surveillance relating to the reactivity worth of experiments will assure that the reactor is not operated for
. extended periods before determining the reactivity worth of experiments. This specification also provides assurance that experiment reactivity worths do not increase beyond the established limits due to core configuration changes.
Actual verification of the core negative reactivity required in 1-3.1.7 will assure the reactor stays subtritRiiTuilder all possible Ecumstances during heavy water transFerE~~~~-
4.2 Reactor Safety System Applicability:
This specification applies to the surveiller.ce of the reactor safety system.
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 char.nels, period safety channel, log count rate channels, and power-flow coincidence scrams shall be perforraed; a.
Prior to each reactor startup following e. period when the reactor was secured; b.
Af ter a channel has been repaired or deenergized.
l Amendment rio. 33 j
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor
.. a
.e Docket 50-2, License R-28 Revision 1 2.
A channel calibration of the safety channels listed in Table 3.1, which can be calibrated, shall be parformed at least once each calendar year..
3.
A channel check of the neutron flux level-safety channels during reactor operation compar1nts the chhnnel outputs with a' heat balance, shall be performed shortly after reaching operating power level and weekly thereaf ter 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 Specification 3.2 shall be verified prior to every reactor startup for which 3afety system channel tests are required as in 4.2.1.
If.the system has been repaired, an operation and setpoint verification will be performed prior to use.
5.
The radiation monitor system required in Specification 3.2 shall be calibrated not less than once every six months.
I 6.
Shim safety rod release-drop time shall be measured not less than once each calendar year.
7.
Shim safety rod release-drop time shall be measured whenever the shim safety rod's core location is changed or whenever maintenance is performed which could effect the rod's drop time.
Bases:
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 measuring.
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.
It is felt that overall calibration of radiation monitors, which l
have displayed excellent stability over many 1
years of operation, every six months is adequate to verify the setpoint unless instrument repairs have been made.
l Page 27
{-
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. License R-28 Revision 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.
Annual check of these parameters Is considered adequate to detect any deterioration which could change the releate-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 FWB 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 confinement of any airborne radioactivity released into the building.
Specification:
1.
The operation of the dampers described in Specification 3.3.1 shall be tested for operability whenever complete checkout of the reactor control system is required prior to startup.
This operability test will be a portior of the startup checkout list for the facility.
2.
The condition of the following gaskets shall be inspected at intervals not to exceed six months, and 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; l
- d. Cooling tower access door.
l 1
J Page 28 L_ _ __ _ _ __
6
)
/[3 0.,7 TECHNICAL SPECIFICATIONS'
-Ford Nuclear Reactor Docket 50-2, License R-28 I
Revision 1
-l g
1 Bases:-
l 1
The prestart' check of the main damper function provides j
assurance that the automatic function provided by these l-
_ dampers will be actut.ted when confinement isolation is L
required.
.The semiannual inspection of casket materials, since these materials are not in a damaging l'
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 resistivity of the primary coolant shall be measured weekly.
3.
The radioactivity of the primary coolant shall b2 analyzed biweekly.
4.
A record of pool makeup water shall be maintained to discover significant leakage of primary coolant from (ne f acility.
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 bef ore significant corrosive damage would occur, and that the presence of leaking 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.
Page 29
TECHNICAL. SPECIFICATIONS He "-
e-Ford Nuclear Reactor Docket 50-2 License R-28 Revision 1 4.5 Heavy Water Reflector Tank Applicability:
l This specification applies to surveillance requirements regarding the heavy water reflector tank used in the reactor core.
Obj e ct ive:
To assure that the limits of Specification 3.S.are not exceeded.
Specification:
1.
The tritium content of the heavy water reflector tank shall be measured quarterly provided the reactor'has operated during the period.
Bases:
Reactor experlence during the last twenty years with the tritium production rate in the tank supports the conclusion that quarterly tritium analyses are sufficient to prevent violation of Specification 3.5.1.
4.6 Airborne Effluents Applicability:
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 not less than once every six months.
I 2.
The particulate air monitors shall be calibral d not less than once every six months.
Thegag{ousactivitymohitorsshallbecalibrated 3.
for Ar not less than once every six months.
[1 4.
The operation of all airborne activity monitors shall be checked daily except when the reactor staff is not present in the facility.
Page 30
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor L,"
Docket 50-2 License R-28 Revision 1 Bases:
Experience with the. electronic reliability and calibration stability-of the units'used by the Ford Nuclear Reactor demonstrates that the above periods are reasonable surveillance frequencies.
4.7 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 of 11guld effluents can be made.
l 1
Specification:
1.
The monitoring equipment used to measure the radioactive concentrations in the waste retention tank contents shall be calibrated not less than once every six months.
2.
The contents of ever 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 sultaDie calibration f requency.
4.8 Fission Density Limits Applicability:
This specification applies to the surveillance requirements for fission density 11mrta.
Objective:
To assure that the fission density limits of Specification 3.9 are not exceeded.
Specification:
1.
The fission density of all fuel elements which have uranium-235 burnup shall be calculated at least quarterly.
Page 31
TECHNICAL SPECIFICATIONS M i' Ford Nuclear Reactor Docket 50-2, License R-28 Revision 1 Bases:'
L Determination of fission densities on a quarterly basis will ensure that the fission density limits of Specification 3.9 are not exceeded.
Fuel element swelling w1ll-be kept well below levels which could result in clad rupture and release of radioactive l
fi.esion products.
l L
l l
l l
1 l
l l
Page 32
TECHNfCAL SPECIF2 CAT 10NS
_Foro Nuclear Reactor i
l Docket 50-2. Lacense R-28 l
Revision 1 5.0 DESIGN FEATURES 5.1-Site Description The Ford Nuclear Reactor (FNR) is located on the Norin Campus of the University of Michigan at Ann Arbor, Michigan.
The North Campus area is under the administrative control of the Regents of the University 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 Glacier Way. Open land and the Arborcrest Cemetery l
lie to the east.
To the west are University athletic fleids, municipal parks and a wooded ridge.
The Huron River flows through land bordering the area on the west and south and some marshland lies adjacent to the river
'on the south.
The reactor building is located near the center of the North Campus area.
Development of the North Campus area by the University has been done using the following guidelines:
1.
Only laboratory and research buildings will be l
constructed within 500 feet of the reactor.
l1 2.
No housing or other buildings containing housing f acilities will be erected within 1500 f eet of the reactor.
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 Glacier Way on the southeast and'the Arborcrest Cemetery located 800 f eet
- ,o the east of the site.
The reactor site consists of all the land 500 f eet 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 traf fic flow can be controlled should such control be desirable.
)
The reactor restricted area consists of the reactor building and the contiguous Phoenix Memorial Laboratory IPML).
The reactor building is the operations boundary and the emergency planning 2one.
Page 33 l
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 5.2 Reactor Fuel The fuel assemblies shall be of the MTR type, consisting of plates containing uranium aluminide (UAlx) or uranium oxide (U 0g) fuel enriched to less than 20% in the 3
isotope U235 clad with aluminum.
The authorized f uel assembly designs are:
Maximum Maximum Kumher Plate Loading Assembly Loading
.of T11tes (g U235)
(g U235) 18 9.28 +/- 2%
167 +/- 2%
9 9.28 +/- 2%
84 +/- 2%
5.3-Ecactor Building The reactor building is a windowless, four story, rejnforced concrete building with 12 inen walls structurally integral with the footings and foundation 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 f eatures:
1.
The reactor is housed in a closed room designed to restrict leakage.
2.
The reactor r00m is equipped with a ventilation 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 certain storage and experimental facilities and exhausts these a minimum of 54 f eet above ground level.
4.
The openings into the reactor building are an equipment access door, three personnel doors, an equipment access hatch, air intake and exhaust ducts, room 3103 fume hood exhaust duct, beamport ventilation duct, a sealed north wall door, a door l
between the not cave operating f ace and the beamport floor, and a pneumatic tube system f or sample l
transfer between the FHR and several laboratories in the Phoenix Memorial Laboratory, Page 34
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor I
Docket 50-2 License R-28 Revision i 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 l
that the fuel element or fueled device temperature will not exceed 100 C.
2.
All reactor fuel elements and f ueled 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 ORR and BSF fuel elements.
Page 35
TECHNICAL SPECIFICATIONS
)
L
'e E-Ford Nuclear Reactor i
Docket 50-2, License-R-28 Revision 1-
- 6. 0 -
' ADMINISTRATIVE CONTEOLS 6.1 Organization 1.
The organizational structure of the University of Michigan relating to the Ford Nuclear Reactor-(FNR) shall be as shown in Figure 6.1.
2.
-The Nuclear Reactor Laboratory Manager shall be l1 i
responsible for the safe operation oT the FNR.
He shall be responsible for assuring that all I
operations are conducted in a safe manner and within the limits prescribed by the facility license, including the technical specifications and operating. procedures.
During periods of his absence, his responsibilities are delegated to the A_ssistant Manager for Operations or to the Assistant Manager f or Research Support Activities. l1 3.
In all matters pertaining to the operation of the plant and these technical specifications, the Nuclear Reactor Laboratory Manager shall report-l1 to and be directly responsible to the Director, Michigan Memorial-Phoenix Project.
4.
Qualifications, Nuclear __ Reactor Laboratory ji Manager and Assistant Managers:
Minimum quafffications f or the Nuclear Reactor Laboratory Manager and Assistant Managits 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 experience on a one for one basis up to a maximum of two years.
Within six months after being assigned these positions, the Nuclear Reactor Laboratory Mana.ger and the Assistant Mana_gers shall apply for NRC senior operator licenses if they do not already hold a license.
5.
A health physicist who is organ 12ationally independent of the FNR operations group shall be responsible f or radiological saf ety at the f acility.
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 composed of two ji individuals,.at l e aJ t on_e_0D!bom_.JJ1AJJ_b e_ a.
licensed sen30r reactor operator.
Page 36 i
y TECHNICAL SPECIFICATIONS 3.
m..
Ford Nuclear Reactor Docket 50-2, License R-26 o
'L L
Revision l' The_Nu. clear Reactor Laboratory _Manasily-availalit e l1 er or one of 7.
the Assistant Managers shalFbe read o_n-call ~24 hours per day 1 seven days per week.
.{
The identity of and method f or rapidly contacting the on-call manager shall be known to the reactor operator or shutdown watchman on duty.
8.
Licensed senior operators or operators are not required to be present in the facility when the i
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-of operator duties.
6.2 Review and Audit 1.
A S3f ety Review Committee (SRC) shall review reactor operations and advise the Director, Michigan Memorial-Phoenix Project, in matters relating to the health and saf ety of the public and the saf ety of facility operations.
2.
The Safety Review Committee shall have at least eight members of whom no more than the mincrity shall be from the line organ 12ation shown in 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 Univer81ty staff and faculty who shall collectively provide experience in reactor engineering, instrumentation and control systems, radiological safety, and mechanical and electrical systems.
3.
The Committee shall meet at least sem1 annually.
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.
6.
Minutes of each Committee meeting shall be distributed to the Director, Michigan Memorial-Phoenix Project, all Safety Review Committee members, and such others as the chairman may designate.
Page 37
_ _ _ _ =
c' Ford Nucitar Reicter y,
Docket 90-2, License R-28 Revision i Figure 6.1 Organization Chart for the Ford Nuclear Reactor Rtgents University of Michigan President Vice President Vice President and Chief l1 Research Financial Officer I
I Director Director l1 Michigan Memorial-Phoenix Project Financial Operations and Sponsored Program Finance I
i Saf ety Review Director l1 Cormittee Occupational and Environmental Safety I
Director Radiation Control Service I
Nuclear Reactor Health Physicist ji Laboratory Manager
~
I l
Assistant Manager Assistant Manager Reactor Operations Research Support Activities Line Function Safety and Licensing Function
)
Licensed Operators Page 38
gl, $.L,
~
TECHNICAL SPECIFICATIONS-
. Ford Nuclear Reactor Docket 50-2 License R-28 Revision i 7.
The Saf ety Review Committee shall:
- a. Review and approve proposed experiments and tests
. utilizing the reactor facility which are significantly different from tests and experiments previously performed at the FNR.
In:
the event of a disagreement over approval of an experiment between the Committee and the Euclear' Reactor Laboratory Manajer, thematterl1 shall be referred to the Director, Michig.:.n Memer!al-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 ),
- e. Review the audit report provided by the consultant for reactor operations.
8.
A consultant will be retained by the University of Michigan to perform an annual audit of reactor operations and the safety of facility operations.
The-consultant shall be selected by the Director, Michigan Memorial-Fhoenix Project and shall be an Individual presently or recently engaged in the management of a research or test' reactor of.
comparable power. level and type.
He shall provide a report on the contlutions drawn.from that audit to the Director, Mich;gan Memorial-Phoenix Project.
The Director shall ;rovide the membert of the Safety Review Committee with copies of this report.
9.
The consultant f or operations shall:
- a. Audit reactor operations and reactor operational records for compliance with internal rules, procedures, and regulations and with license provisions including technical specifications;
- b. Audit existing standard operating procedures for adequacy and to assure that they achieve their intended purpose in light of any changes since their implementation; Page 39
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TECHNICAL SPECIFICATIONS L
Ford Nuclear Reactor-I 1
Docket 50-2, License R-28 Revision i
~
- c. Audit plant equipment performance with-particular attention to operating-anomalies, reportable occurrences, and.the steps taken to identify and correct.their causes.
6.3 Action to Be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, as defined.in these technical specifications, the following action-shall be taken:-
1.
The Nuclea.r Reactor Laboratory Manager shall be l1 nctified of the occurrence.
Correct 1' e action shall be taken to correct the abnormat conditions and to prevent its recurrence.
2.
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 occurrence, the. effectiveness of corrective actions taken, and recommended of measures to prevent or reduce the probability of consequences of recurrence.
6.4 Operating Procedures Written procedures, including applicable check lists, reviewed and approved by the Safety Review Committee shall be in effect and followed for the following operations:
1.
Startup, operation and shutdown of the reactor; 2.
Installation and removal of fuel elements, control rods, experiments and experimental fac211tles; 3.
Actions to be taXen to correct specific and f oreseen potential malfunctions of 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 provlsions for evacuation, reentry, recovery., and medical support; 5.
Maintenance procedures which could have an effect on reactor saf ety; 6.
Periodic surveillance of reactor Instrumentation and safety systems, area monitors, and continuous air monitors; Page 40
TECHNICAL SPECIFICATIONS I
Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 1
i l
7.
Facility security plan; 8.
Radiation protection procedures.
1 Substantive changes to the above procedure shall be 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 approval of the Nuclear Reactor Laboratory _M_an_ager or ji one of the Assistant Managers.
All temporary changes to the procedures shall be documented and subsequently reviewed by the Safety Review Committee.
6.5 Operating Records 1.
The following records and logs shall be prepared and retained by the licensee for at least five years:
a.
Normal f acility operation and maintenance; b.
Reportable Occurrences; c.
Tests, checks, and measurements documenting compliance with surveillance requirements; d.
Records of experiments performed; e.
Records of radioactive shipments; f.
Operator requalification program records (the five year period will commence after termination of the assignment of the operator to operative duties );
g.
Facility radiation and contamination surveys.
2.
The following records and logs shall be prepared and retained by the licensee for the life vf the f acility:
a.
Gaseous and liquid waste released to the environs; b.
Of f site environmental monitoring surveys; c.
Radjation exposurts for al) FNR personnel; d.
Fuel inventories and transf ers; e.
Updated, corrected, and as built facility drawings; f.
Minutes of Safety Review Committae meetings.
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- .b.
TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 6.6 Reporting Requirements The following information shall be submitted to the USNRC in addition to the reports required by Title 10.
Code of Federal Regulations.
All written reports shall be addressed to the U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D.C. 20555 with a copy to the Administrator, Region III.
1.
Annual Operating Reports A report covering the previous year shall be submitted by March 31 of each year.
It shall include the following information.
a.
Operations Summary A summary of operating experience having safety significance occurring during the report)ng period.
- 1. Changes in facility design.
2._ Performance characteristics (e.g.,
equipment and f uel perf ormance ).
- 3. Changes in operating procedures which relate to the safety of facility operations.
- 4. Results of survelljance tests and Inspections required by these technical specifications.
- 5. A brief summary of those changes, tests, and experiments which required authorization from the commission pursuant to 10CFR50.59(a).
- 6. Changes in the plant operating staff serving in the following positions:
- a. Nuclear Reactor Laboratory Manager; l1
- 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.
i Page 42 i
i -
TECHNICAL' SPECIFICATIONS Ford Nuclear' Reactor Docket 50-2. License R-28 Revision 1 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.
d.
Maintenance i
A discussion of corrective maintenance, excluding' preventive maintenance, performed' during the reporting period on safety related systems and components.
e.
Changes. Tests, and Experiments 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 Effluent Releases A statement of the quantitles of radioactive effluents released from the plant.
- 1. Gaseous Effluents a.
Gross Radioactivity Releases 1.
Total gross radioactivity in curies, primarily noble and activation gases.
E.
Average concentration of gaseous effluents released during normal steady state operation averEged over the period of Pfactor operation.
3.
Maximum instantaneous concentration of noble gas radionuclides released during special operations, tests, or experincnts.
4.
Percent of technical specification limit.
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TECHNICAL SPECIFICATIONS
-m Ford Nuclear Reactor Docket 50-2, License R-28 Revision 1 b.
Iodine Releases (Required if iodine is identified in primary coolant samples, or if fueled experiments are conducted at the facility.)
1.
Total lodine radioactivity in curies by nuclide released, based on representative isotopic analyses performed.
2.
Percent of MPC.
c.
Particulate Releases 1.
Total gross beta and 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 could result in the release of alpha emitters.)
3.
Total gross radioactivity in curies of nuclides with half lives greater than eight days.
4.
Percent of MPC for particulate radioactivity with half lives greater than eight days.
- 2. Liquid Effluents a.
Total gross beta and gamma radioactivity L
released in curies excluding tritium and l
average concentration released 10 the unrestricted area or sanitary sewer l
averaged over period of releast.
b.
The maximum concentration of beta and samma radioactivity released to the unrestricted area, c.
Total alpha radioactivity in curles released and average concentration released to the unrestricted area averaged over the period of release.
(Required if the operational or experimental program could result in the release of alpha emitters.)
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V TECHNICAL SPECIFICATIONS 1
Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 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 f rom 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 whose contents have a concentration in excess of 9xiO~4 microcuries/cc.
g.
Percent of technical specificat10!; limit for total radioactivity from the site, g.
Environmental Monitoring For each medium sampled:
- 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. Highest, lowest, and the annual average concentrations or levels of radiation for the sampling point with the highest average and the location of that point with respect to the site.
- 5. The maximum cumulative radiation dose which could have been received by an 2ndividual continuously present in an unrestricted area o.uring reactor operation f rota:
a.
Direct radiation and gaseous ef f luent; b.
Liquid effluent.
Page 45
TECHNICAL SPECIFICATIONS H ^,'
- 2 Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 6.
If levels of radioactive materials in l-environmental media, as determined by an L
environmental monitoring program, indicate L
the likelihood of public intakes in excess of 1% of those that could result from continuous exposure to'the concentration values listed in Appendix B, Table II, 10CFR20, estimates of the likely resultant L
exposure to individuals and to population groups and assumptions upon which estimates are based.
7.
If significant variations of of f site environmental concentrations with time are observed, correlation of these results with effluent release shall be provided, h.
Occupational Personnel Radiation Exposure A summary of annual radiation exposures greater than 500 mrem (50 mrem for persons under 18 years of age) received during the reporting period by f acility personnel including faculty, students, or experimenters.
2.
Non-Routine Reports a.
Reportable Occurrence Reports Notification 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 telegraph to the Director of the appropriate Regional Inspection and Enforcement Of fice f ollowed by a written report within 14 days to the U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D. C.
20555, with a copy to the Director of the Regional Inspcction and Enforcement Office in the event of a reportable occurrence, as defined in Section 1.0, Tejcgraph notification may be sont on the next working day in the event of a reportable occurrence dur)ng a weekend or holiday period. The written report of a reportable occurrence, and, to the extent possible, the preliminary telephone and telegraph notification shall:
- 1. Describe, analyze, and evalcate safety implications;
- 2. Outline the measures taken to assure that the
{
cause of the condition is determined Page 46
_ - - __ _ - -______ L
4 f"t TECHNICAL SPECIFICATIONS d.
Ford Nuclear Reactor Docket 50-2, License R-28 Revision i 3.-Indicate the corrective action including any changes made to the procedures and to the quality assurance program taken to 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 f ailure and malfunctions of similar systems and components.
b.
Unusual Events A written report shall be forwarded within 30 days to the U. S. Nuclear Regulatory _ Commission.
Attn: Document Control Desk, Washington D. C.
20555, with a copy to the Director of the Regional Inspection and Enforcement Office in the event of:
1.
Discovery of any substantial errors in the translent or accident analyses or in the methods used for such analyses, as described in the safety analysis or in the bases for the technical specifications;
- 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.
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