ML20036B976
| ML20036B976 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 05/26/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036B975 | List: |
| References | |
| R-028-A-038, R-28-A-38, NUDOCS 9306070429 | |
| Download: ML20036B976 (51) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20655
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UNIVERSITY OF MICHIGAN DOCKET N0. 50-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. R-28 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to Facility Operating License No. R-28, filed by the University of Michigan (the licensee), dated October 29, 1992 as supplemented by letters dated March 1, and April 15, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter 1:
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and F.
Prior notice of this amendment was not required by 10 CFD 2.105(a)(4) and publication of notice for this amendment is not required by 10 CFR 2.106(a)(2).
9306070429 930526 DR ADOCK 0500 2
3
, 2.
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 Facility Operating 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. 38, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION EDs Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Enclosure:
Appendix A Technical Specifications Changes Date of Issuance: May 26, 1993
ENCLOSURE TO LICENSE AMEN 0 MENT NO. 38 FACILITY OPERATING LICENSE NO. R-28 DOCKET NO. 50-2 The Appendix A Technical Specifications 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 Amendment Number and contain a vertical line indicating the area of change.
Revised Pacel 2
4 5
10 11 14 15 16 17 18 19 20 21 22 23 24 26 27 28 29 30 31 35 38 l
44 45 b
f 1
1 d
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7 OPERATING LICENSE AND TECHNICAL SPECIFICATIONS' Ford Nuclear Racetor Docket 50-2, Licenso R-28 Amendment 38:100792 APPENDIX A TO FACILITY LICENSE R-28 TECHNICAL SPECIFICATIONS DOCKET 50-2 MICHIGAN MEMORIAL PHOENIX PROJECT THE UNIVERSITY OF MICHIGAN Ann Arbor, Michigan 4
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclocr Rasctor Docket 50-2, Liconse R-28 Amendment 38:100792 CONTENTS 1.0 DEFINITI_QIi1 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 8
3.0 LIMITING CONDILIONS 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 18 3.5 Airborne Effluents 19 3.6 Liquid Effluents 20 3.7 Limitations of Experiments 21 3.8 Fission Density Limit 23 4.0 SURVEILLANCE REQUIREMENTS 24 4.1 Reactivity Limits 24 4.2 Reactor Safety System 25 4.3 FNR Confinement Building 27 4.4 Primary Coolant System 28 4.5 Airborne Effluents 29 4.6 Liquid Effluents 29 4.7 Fission Density Limits 30 5.0 DESIGN FEATURES 31 5.1 Site Description 31 5.2 Reactor Fuel 32 5.3 Reactor Building 32 5.4 Fuel Storage 33 Contents-1
,,e-OPERATING LICENSE'AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket-50-2, Licence R-28 Amendment 38:100792 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 38-6.4 Operating Procedures 38 6.5 Operating Records' 39 o
6.6 Reporting Requirements 40 I
4 Contents-2
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Racetor Docket 50-2, Licenso R-28 Amendment 38:100792 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.
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 into the channel to verify that it is operating.
Experiment - An experiment, as used herein, is any of the following:
1.
An activity utilizing the reactor system or its components or the neutrons or radiation generated therein; 2.
An evaluation or test of a reactor system operation, surveillance, or maintenance technique; 3.
An experimental or testing activity.which is conducted within the confinement or containment system of the reactor; 4.
The material content of any of the foregoing, including structural components, encapsulation or confining boundaries, and contained fluids or solids.
i Experimental Facility - An experimental facility is any structure or device which is intended to guide, orient, position, manipulate, or otherwise facilitate a multiplicity of experiments of similar character.
Explosive Material - Explosive material is any solid or.
liquid which is categorized as a severe, dangerous, or very dangerous explosion hazard in DANGEROUS PROPERTIES'OF INDUSTRIAL MATERIALS by N.I.
Sax, Third Ed. (1968), or is given an Identification of Reactivity (Stability) Index of 2.3, or 4 by_
the National Fire protection ~ Association in its publication 704-M, 1966.
l Limiting Conditions for Operation (LCO) - Lowest functional capability or performance levels of equipment required for i
safe operation of the reactor (10CFR50.36).
H
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Page 1
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OPERATZNG LICENSE AND TECHNICAL SPECIFICATIONS-Ford Nuclear Reactor Docket 50-2,~ License R-28 Amendment 38:100792 Limiting Safety System Setting (LSSS) - Settings for automatic protective devices related to those variables having significant safety functions, and chosen so that automatic protective action will correct an abnormal situation before a safety limit is exceeded (10CFR50.36).
Measured Value - The measured value of a process variable is the value of the variable as indicated by a measuring channel.
Measuring Channel - A measuring channel is-the combination of sensor, amplifiers, and output devices which are used for the purpose of measuring the value of a process variable.
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 normal manner.
Potential Reactivity Worth of an Experiment - The potential reactivity worth of an experiment is the maximum absolute value of the reactivity change that would occur as a result of intended or anticipated changes or credible malfunctions that alter 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 condition.
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 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.
Reactor Safety System - The reactor safety system is tha't combination of safety channels and associated circuitry which forms the automatic protective system for the reactor or provides information which requires manual protective action to be initiated.
Reactor Scram - Shutoff of electrical current to the rod holding magnets and subsequent insertion of the rods into the core by gravity.
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Recctor Docket 50-2, License R-28 Amendment 38:100792 Reactor Secured - Reactor Secured is defined as follows:
1.
The full insertion of all control rods has been verified; 2.
The control console key is removed; and 3.
No operation is in progress which involves moving fuel elements to or from the core, moving reflector elements to or from the core, the insertion or removal of secured experiments from the core, or control rod maintenance.
Readily Available on Call - Readily available on call shall mean 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 being operated by a licensed operator.
Regulating Rod - The regulating rod is a control rod of low reactivity worth fabricated from stainless eteel and used to control reactor power.
The rod may be controlled by the operator with a manual switch or by an automatic controller.
Removable Experiment - A removable experiment is any experiment, experimental facility, or component of an experiment, other 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 following:
1.
A safety system setting less conservative than the limiting setting established in the Technical Specifications; 2.
Operation in violation of a limiting condition for operation established in the Technical Specifications; 3.
A safety system component malfunction or other component or system malfunction which could, or' threatens to, render the safety system incapable of performing its intended safety functions; 4.
Release of fission products from a failed fuel element;
- 5..An uncontrolled or unplanned release of radioactive material from the restricted area of the facility; page 3
OPERATING LICENSE AND TECHNICAL' SPECIFICATIONS Ford Nucloor Renctor Docket 50-2, Licensa R-28 Amendment 38:100792 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 events that affect or threaten to affect the safe operation of the facility; 9.
An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the operation of the facility.
Rundown - A rundown is the automatic insertion of the shim safety rods.
Safety Channel - A safety channel is a measuring channel in the reactor safety system.
Safety Limit (SL) - Limits upon important process variables which are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity (10CFR50.36).
Secured Experiment - Any experiment, experimental facility, or component of an experiment is deemed to be secured, or in a secured position, if it is held in a stationary position relative to the reactor by mechanical means.
The restraint shall exert sufficient force on the experiment to overcome the expected effects of hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or of forces which might arise as a result of credible malfunctions.
Shim-Safety Rod - A shim-safety rod is a control rod l38 fabricated from borated stainless steel which is used to compensate for fuel burnup, temperature, and poison effects.
A shim safety rod is magnetically coupled to its drive unit allowing it to perform the function of a safety rod when' the magnet is deenergized.
Page 4
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS' Ford Nuclear Reactor Docket 50-2, License'R-28 Amendment 38:100792 Static Reactivity Worth - The static reactivity worth of an experiment is the absolute value of the reactivity change which is measurable by calibrated control rod comparison methods between two defined terminal positions or configurations of the experiment.
For moveable experiments, the terminal positions are fully removed from the reactor and fully inserted or installed in the normal functioning or intended position.
Time Intervals - The average over any extended period for each surveillance time interval shall be closer to the norma' surveillance time than the extended time.
Any extension of a
these intervals shall be occasional and for a valid reason, and shall not affect the average as defined.
Annually - 12 to 15 months.
Biannually - 24 to 30 months.
Biweekly - 14 to 20 days l38 Daily - 24 to 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
Monthly - 30 to 40 days.
Quarterly - 3 to 4 months.
Semiannually - 6 to 8 months.
Weekly - 7 to 10 days.
True Value - The true value of a process variable is its actual value at any instant.
Unscheduled shutdown - An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, 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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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Rocctor Docket 50-2, Licenco R-28 Amendment 38:100792 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limits 2.1.1 Safety Limits in the Forced Convection Mode Applicability:
This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the steady state with forced convection flow.
These variables are:
Reactor Thermal Power, P Reactor Coolant Flow Through the Core, m Reactor Coolant Inlet Temperature, Ti 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 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 (Ti) at 2 Mw shall not exceed 116 0F, 3.
The true value of water height above the. core (H) shall not be less than 18 feet while the reactor is operating.
Bases:
i The basis for forced convection safety limits is that the calculated maximum cladding temperature in the bottom of the hot channel of the-most compact FNR core.(25 elenents) will not reach the boiling point of the water cool. ant.
3 Page 6
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclocr-Racetor Docket 50-2, Liconao R-28 Amendment 38:100792 2.1.2 Safety Limits in the Natural Convection Mode Applicability:
This specification applies to the' interrelated variables associated with core thermal and hydraulic performance in the natural convection mode of operation.
These variables are:
Reactor Thermal Power, P Reactor Coolant Inlet Temperature. Ti 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 (TI) shall not exceed 131
- F.
3.
The height of pool water above the core (H) shall not be less than 18 feet.
Bases:
The basis for natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most compact FNR core (25-elements) will not reach the boiling point of the water coolant at a depth of 18 feet.
2.2 Limiting Safety System Settings (LSSS) 2.2.1 Limiting Safety System Setting in the Forced Convection Mode Applicability:
This specification applies to the se't points for the safety channels monitoring reactor thermal power (P), primary coolant flow (m),
height of water above the top of the core (H).
and core exit temperature (T.).
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nucloor R3cetor Docket'50-2,.Liconce R-28 Amendment 38:100792 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 (T.) shall be as follows:
Variable LSSS P (Max) 2.4 Mw m (Min) 900 gpm H (Min) 19 ft T.(Max) 129 oF Bases:
The limiting' safety system settings for forced convection assure that automatic protective action will correct the most severe abnormal situation anticipated _before a safety limit is exceeded.
2.2.2 Limiting Safety System Settings in the Natural Convection Flow Mode Applicability:
These specifications apply to the setpoint for the safety channels monitoring reactor thermal power (P), pool water level (H), and pool water temperature (T).
Objective:
To assure that automatic protective action is initiated to prevent a safety limit from being exceeded.
page 8
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nucloor Rsactor Docket 50-2 Licenso R-28 Amendment 38:100792 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:
Variables LSSS P
(Max) 100 kw l'
H
('.oin) 19 ft T
(Max) 129 oF Bases:
The limiting safety system settings for natural convection assure that automatic protective action will correct the most severe. abnormal situation anticipated before a safety. limit is exceeded.
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reector Docket 50-2, License R-28 Amendment-38:100792 3.0 LIMITING CONDITIONS FOR OPERATION 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 limits'will not include the static reactivity worth of 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 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 moveable experiments shall not exceed 0.0436 l35 delta K/K.
3.
The reactivity worth of experiments shall be limited as follows, except during the process of verifying 38 experiment reactivity:
Maximum Experiment Reactivity Worth Individual Moveable 0.0012 delta K/K Individual Secured 0.012 delta K/K Total Moveable and Secured 0.012 delta'K/K 4.
The reactor shall be suberitical by at least 0.025 delta K/K during fuel movements to and 38 from the reactor core.
5.
The reactor shall be suberitical by at least 38 0.10 delta K/K before shim-safety rods are removed from the core.
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o OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 38:100792 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 are undertaken.
7.
The reactivity worth of the regulating rod shall not exceed 0.006 delta K/K.
8.
Experiments that could increase reactivity by flooding, shall not remain in or adjacent to the core unless the shutdown margin required in Specification 3.1.1 would be satisfied after flooding.
Bases:
The shutdown margin required by Specification 3.1.1 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 reactivity to the value necessary to overcome the combined negative reactivity effects of: (1) an increase in primary coolant temperature from 90 F to 116 F; (2) fission product xenon and samarium buildup in a clean core; (3) power defect-due to increasing from a zero power, cold core to a 2 Mw, hot core; (4) fuel burnup during sustained operation for 30 days; and (5) moveable experiments.
Specification 3.1.3 limits the individual reactivity worth of moveable experiments to 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-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.
9 Specifications 3.1.4 and 3.1.5 provide assurance that the core will remain suberitical during fuel movements 38 i
to and from the core and during shim-safety rod maintenance or inspection.
The largest positive reactivity increase that can be l33 produced by replacing light water with heavy water in
)
the heavy water reflector tank is 0.04 delta K/K.
j
~
Maintaining the core suberitical by at least 0.10 38 delta K/K in Specification 3.1.6 during heavy water i
transfers provides adequate margin to. assure that
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OPERATING LICENsL4 awl 0 6
'c c.-
Ford Nuclocr Racetor Docket 50-2, License R-28.-
~
AmendmentE38:100792 the reactor will remain suberitical during heavy water transfers that could add positive reactivity.-
Specification 3.1.7 assures that failure of the, automatic control system will not introduce sufficient excess reactivity.to produce a prompt critical condition'.
Specification 3.1.8 assures that the shutdown marginL required by Specification 3.1.1 will be met.in the event of a positive reactivity insertion' caused byfthe:
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 accordance with.
Tables 3.1 and 3.2 including the minimum number'of channels and the indicated maximum or' minimum setpoints; 2.
All shim-safety rods are operable; 3.
The time from the initiation of a scram condition-in the' scram circuit until the. shim-safety ~ rods are fully inserted (release-drop time) shall'not exceed 500 milliseconds; 4.
Mechanical devices are installed which prevent the lif ting of fuel elements through the move.nent 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 which1are manually controllable without reaching excessive power levels or fuel temperatures.
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclocr Reactor Docket'50-2, Licon o R-28 Amendment-38:100792 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 level and input for period scram Period Safety 5 see 1
Scram Level Safety 120%(2.4 Mw) 2 Scram High Power /No (a) 900 gpm 1
Scram 1100 kw Water Flow (b) holdup tank isolation valve not fully open (c) holdup tank static pressure 1 psig below full power value High Power /
Header Down 1
900 gpm 1
Scram No Water Flow Building Exhaust 1 mrem /hr 1
Scram Radiation Level Building Alarm 1
Scram Manual Switch Manual Scram Switch 1
Scram Magnet Power Keyswitch 1
Scram Reactor Coolant Exit Temp.
129 oF 1
Auto Rundown Pool Level 1 foot below pool 1
' Auto Rundown overflow Bridge Not When clamps 1
Scram Clamped released
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Rocctor Docket 50-2, Licon:o R-28 Amendment 38:100792 Table 3.2 REQUIRED SAFETY RELATED INSTRUMENTATION Minimum Number Instrumentation Setroint Required Function Linear Level Channel As Required 1
Linear power level measurement and input for the automatic control mode Power Level Deviation 95% of control 1
Return reactor to Inter],ck point setting manual' control mode if_setpoint is reached Reactor Coolant Inlet Not Applicable la Provide information Temperature for reactor power 38 level determination by heat balance Facility Radiation Monitor System (b) 1.
Building Air Exhaust 1(1)b mrem /hr 1 Alarm, scram, initiate confinement evacuation 2.
Reactor Bridge 40(50) mrem /hr 1 Alarm l34 3.
NW Column, Beamport 20(50) mrem /hr Ic Alarm l34 Floor
- 4. N Wall, Beamport 5(50) mrem /hr i Alarm Floor 5.
NE Column, Beamport 5(50) mrem /hr 1 Alarm l34 Floor l38 Footnotes:
a.
Not required for natural convection operation.
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 setpoint which will be used depending on local conditions.
Use of higher than Page 14
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 38:100792 Table 3.2 (Continued)
REQUIRED SAFETY RELATED INSTRUMENTATION 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or is replaced by a second locally alarming unit of similar range.
t e
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclecr Rosctor Docket 50-2, Licenso R-28 Amendment 38:100792 Power-flow coincident scrams provide redundant channels to assure that an automatic loss of flow scram will occur in the event of a loss of flow when the reactor is operating at power levels above 100 kw.
The rod withdrawal interlock on the Log Count Rate channel assures that the operator has a measuring channel operating and indicating neutron flux levels during the approach to criticality.
The 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 keyswitch provide two methods for-the reactor operator to manually shutdown the reactor if an unsafe or abnormal condition should occur and the automatic reactor protection does not function.
The use of the area radiation monitor system assures that areas of the facility in which a high radiation area could exist are monitored.
Specifications 3.2.2 and 3.2.3 assure that the safety system response will be appropriate.
Mechanical holddown devices specified in 3.2.4 ensure 38 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.
3.3 FNR Confinement Building Applicability:
This specification applies to the Ford Nuclear Reactor confinement building requirements.
Objective:
To assure that the Ford Nuclear Reactor Building' 38 confinement integrity is maintained during reactor operation and-to minimize the release of airborne radioactive materials from the reactor building.
Page 16
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Racetor Docket'50-2, Licence R-28 Amendment 38:100792 Specification:
1.
When the radiation level in the Ford Nuclear 38 Reactor ventilation exhaust duct is equal to or greater than one mrem /hr:
a.
The reactor building ventilation supply and exhaust fans shall automatically turn off;-
b.
The reactor building ventilation supply and exhaust dampers shall automatically close; 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 administrative 1y controlled:
a.
personnel access doors will be. closed exceptans necessary for the passage of personnel and/or equipment; b.
The main equipment access door onto the beamport floor will be opened only long enough.to permit' the passage of equipment; The personnel door to'the cooling tower area c.
will remain clamped except to permit the passage of personnel and/or equipment to the cooling tower area.
The door will remain closed but not clamped until all personnel have left the cooling tower area; d.
The access hatch from grade level to the beamport floor will be sealed closed; The personnel exit door located in the north e.
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.
Bases:
The potential radiation exposure to persons at the operations boundary following an accident. releasing fission products within the confinement building has been evaluated. The evaluation used a leakage rate from the confinement building of 10% of the. building volume per day, and~ concluded that the accident doses would be acceptable. Conformance to-Specifications Page 17
3 OPERATING LICENSE AND TECHNICAL' SPECIFICATIONS Ford Nuclear Reactor-Docket 50-2, License R-28
-Amendment' 38:100792 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 mrem /hr-setpoint for the facility exhaust l
radiation monitor provides a mechanism for isolating the building ventilation system in the event of a significant release of radioactive material into the reactor building.
This setpoint, for'the detector location involved, represents a gamma emitting nuclide concentration of 10- 3 to 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 above the 38 level assumed in the Hazards Summary Report, and the release of radioactive material will be minimized.
3.4 primary Coolant Conditions Applicability:
This specification applies to the limiting conditions for available pcol water volume, primary coolant pH, co'nductivity, radioactivity, and flow distribution.
l38 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 conductivity shall be 38 maintain?d at a value less than 5 micromho/cm except for periods of time not to exceed 7 days when the conductivity may not be greater than 20 micromho/cm.
i page 18
a OPERATING LICENSE AND TECHNICAL. SPECIFICATIONS Ford Nucloer Racetor Docket 50-2, License R-28 Amendment 38:100792 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 operation, 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 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.
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 j
unoccupied grid plate position.
Specification 3.4.4 that the gate be stored assures that' the full volume of the pool water is available to provide cooling of the core during normal operation and in the event of a loss of coolant accident.
3.5 Airborne Effluents Applicability:
This specification applies to the monitoring of airborne effluents from the Ford Nuclear Reactor.
Objective:
To assure that the release of airborne radioactive l38 material from the Ford Nuclear Reactor is maintained below the limits established in 10CFR20.
Specification:
1.
The concentration of radioactive materials in the effluent released from the facility exhaust. stacks shall not exceed 400 times the concentrations specified in 10CFR20, Appendix B, Table'II, when averaged over time periods permitted by 10CFR20.
Page 19
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS.
. Ford Nuclacr R2cetor Docket 50-2, Licenzo R-28 Amendment' 38:100792 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 exhaust shall be operating.
If.either unit is out of service for more'than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,'
either the reactor.shall. be shutdown.or the unit shall be replaced by one.of comparable monitoring capability; b.
The reactor pool floor mobile air particulate 38 monitor and the gaseous activity detector for the reactor building exhaust stack shall be operating.
If either unit is out of service for-more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, either the reactor'shall be shutdown or the unit shall be replaced by one of.
comparable monitoring capability; c.
The building exhaust air radiation monitor shall be operating whenever the reactor is in operation as required by Table 3.2 of specification 3.2.
Bases:
The limits established in specification 3.5.1 l38 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 factor determined and the highest frequency.of wind in any sector.
Because of the use of the most conservative measured values of wind directional-frequency and dispersion factors, this dilution factor will assure that concentrations of radioactive material in unrestricted areas around the FNR site will be far below the limits of 10CFR20.
The requirements of specification 3.5.2 are considered.l38 adequate to assure proper airborne effluent monitoring.
3.6 Liquid Effluents Applicability:
This specification supplies to the monitoring of radioactive liquid effluents from the FNR.
Objectives:
The objective is to assure that exposure to the public.
resulting from the release of liquid effluents will be minimized.
Page 20
OPERATING LICENSE AND-TECHNICAL SPECIFICATIONS Ford Nuclear Rametor Docket 50-2, Licenea R-28 Amendment 38:100792 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 l33 to the equivalent of 3,000 gallons of liquid at the concentration limit specified in 3.6.1 each day.
l38 t
3.
Liquids from the facility's radioactive liquid waste system shall not be discharged into the storm drain system.
Bases:
All radioactive liquid effluents are collected in a series of three, 3,000 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 10CFR20, it is discharged to the sanitary sewer system.
In the past, less than 50 retention tank discharges 38 per year have been required.
During 1970, the North Campus water released into the sanitary sawer' system averaged 946,000 gallons per day.
This provides a daily dilution factor of 315 for a 3,000 gallon waste tank, which assures that there will be no significant exposure to the public from radioactive waste discharged to the sanitary sewer system.
3.7 Limitations of Experiments Applicability:
This specification applies to experiments installed in the FNR.
Objective:
To prevent damage to the reactor or excessive release df radioactive materials in the event of an experim'ent failure.
page 21
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 38:100792 Specification:
1.
Each experiment shall be designed so that the surface temperature shall be below the temperature calculated for the inception of nucleate boiling.
Prior to insertion in the reactor, any capsule which is expected to operate with an internal pressure in excess of one atmosphere shall be tested at a pressure twice the calculated maximum pressure.
2.
All experiments which are in contact with reactor coolant shall be either corrosion resistant or encapsulated within corrosion resistant containers.
3.
Explosive materials shall not be placed in the reactor pool.
Neutron radiography of explosives shall be conducted 4.
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.
I 5.
The radioactive material content, including fission i
of any singly encapsulated experiment
- products, should be limited so that the 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 stated in 10CFR20.
This dose limit applies'to persons occupying unrestricted areas continuously for two hours starting at time of release and restricted areas during the length of time required 1
to evacuate the restricted area.
6.
The radioactive material content, including fission products, of any doubly encapsulated experiment I
should be limited so that the complete release of l
f all gaseous, particulate, or volatile components from the encapsulation could not result in doses in j
j excess of the equivalent annual doses stated in l
This dose limit applies to persons occupying unrestricted areas continuously fo.r two hours starting at the time of release and restricted areas during the length of time required to evacuate the restricted area.
Bases:
Specifications 3.7.1 through 3.7.4 are intended to l38 reduce the likelihood of damage to reactor components and radioactivity releases resulting from experiment Page 22
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 38:100792 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 3.7.5 and 3.7.6 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:
This specification applies to fission density limits in FNR fuel.
Objective:
To prevent fuel plate swelling which could result in clad rupture and release of radioactive fission products.
Specification:
1.
The FNR fission density limit shall be 1. 5x1021 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.
An experimental data base that supports the safe use of uranium aluminide ( UAlx ), uranium oxide ( U3 0s ), and uranium silicide (U3 Si2 ) 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 Laboratory, the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, and the German Karlsruhe FR2 reactor.
Page 23
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Rocctor Docket 50-2, Liconeo R-28 Amendment 38:100792 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactivity _ Limits Applicability:
This specification applies to the survoillance requirements for reactivity limits.
Objective:
To assure that the reactivity limits of Specification 3.1 are not exceeded.
Specification:
1.
Shim safety rod reactivity worths shall be measured:
a.
Annually;
[38-b.
Whenever the fuel elements in more than three interior core locations are replaced; c.
Whenever the replacement'of a fuel element-in an interior core location results in an element fuel mass change of more than 10% in that location;
?
d.
Whenever the addition of more than three standard fuel elements to the outer faces of l381 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 safety review indicates a need for such a determination shall be measured prior to the experiment's initial use.
That worth shall be verified if core configuration changes occur which could reasonably be expected to cause increases in experiment reactivity worth whereby the experiment worth could exceed the values specified in Specification 3.1.
4.
The core negative reactivity required during l33 heavy water transfers will be verified whenever heavy water transfers are to be made.
page 24
.=.
w OPERATING LICENSELAND' TECHNICAL SPECIFICATIONS;
, Ford Nuclear Rasctor Docket.50-2, License R-28
- Amendment 38:100792-Bases:
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, frequent inspections of shim-safety' rods for swelling over the last. ten years have produced no-evidence of swelling or cracking.- In. order to minimize personnel radiation exposure and provide an inspection frequency that will detect early evidence of, swelling and cracking, an annual inspection interval was selected 7
for Specification 4.1.2.
The specified surveillance relatingLto the reactivit'y worth of experiments will assureLthat 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.
i Actual verification of the core negative reactivity-l33 required for heavy water transfers will assure:the reactor stays suberitical under all possible' circumstances during;'
heavy water transfers.
42 Reactor Safety System Applicability:
This specification appliesLto the surveillance 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 channels, period safety channel, log count rate channels, and power-flow coincidence' scrams'shall-be performed:
I Prior to each reactor startup following a = period a.
when the reactor was secured; b.
After a channel has been repaired or deenergized.
Page 25 e-m
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor.
Docket 50-2, Licenne R-28 Amendment 38:100792 i
i 2.
A channel calibration of the safety channels listed in Table 3.1, which can be calibrated, shall be performed annually.
[38 3.
A channel check of the neutron flux level safety channels during reactor operation comparing the channel outputs with a heat balance, shall be-performed shortly after reaching operating power level and weekly thereafter if the reactor is to be operated at a thermal power level above 500 kw.
4.
The operation of the radiation monitoring system required in Table 3.2 shall be verified:
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 changed; c.
Whenever maintenance is performed that could affect 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.
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
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclocr Racetor Docket 50-2, License R-28 Amendment 38:100792
~
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 release-drop time.
Binding or: rubbing caused by. rod misalignment could result from maintenance; therefore, release' drop times will be checked after such maintenance.
4.3 FNR Confinement Building Applicability:
This specification applies to the surveillance of the facility openings and dampers.
Objective:
To assure that the condition of the closure devices for the building openings are in satisfactory condition to their ability to provide adequate confinement.of assure any airborne radioactivity released into the building.
Specification:
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 facility.
2.
The condition of the following gaskets shall be inspected semiannually, and the gaskets shall be l38.
replaced whenever any evidence of deterioration is found:
Building ventilation system intake and exhaust a.
dampers; b.
Personnel access doors; c.
Equipment access doors; d.
Cooling tower access door.
Page 27
OPERATING LICENSE AND TECHNICAL-SPECIFICATIONS Ford Nuclear Roactor Docket 50-2, Liconna R-28 Amendment 38:100792 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 will perform their function of limiting leakage through-these openings in the event of a release of airborne activity into the building.
4.4 Primary Coolant System Applicability:
This specification applies to the surveillance of the primary coolant system.
Objective:
To. assure high quality pool water and to detect the release of fission products from fuel elements.
Specification:
1.
The pH of the primary coolant shall be measured weekly.
2.
The conductivity of the primary coolant shall be 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 coolar.t from the facility.
Bases:
Regular surveillance of pool water quality and radioactivity provides assurance that pH and conductivity changes that could accelerate the corrosjon of the primary coolant system would be detected before significant corrosive damage would occur, and that the presence of leaking fuel elements 2n the reactor is detected.
Routine inspection of makeup water needs over a period of time provides early warning of small pool water leaks.
Page 28
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford-Nucloor Rac6 tor Docket 50-2, Liconeo R-28 Amendment 38:100792 4.5 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 semiannually.
[38 2.
The mobile air particulate monitors shall be 38 calibrated semiannually.
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 is not present in the facility.
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.
4.6 Liquid Effluents Applicability:
This specification applies to the surveillance of the monitoring equipment used to measure the activity in liquid effluents.
Objective:
The objective is to assure that accurate assessment 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.
l38 Page 29
iOPERATING LICENSE ~AND1 TECHNICAL ~SPECIFICATIONSL Ford NuclearcRacetor
. Docket 50-2,:Licanao R a-3
~Amendnent 38:100792 2.
The' contents'of'each tank released shall'be sampled and evaluated prior to'itsLrelease.-
i Bases:
Experience with the counting l equipment used in..
measuring the' radioactivity in~the waste retention tanks' suggests that'the above period is a suitable calibration frequency.
4.7 Fission Density Limits Applicability:
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.
]38' Specification:
1.
The fission density of all fuel elements which have-
[
~
uranium-235 burnup shall be calculated at least.
quarterly.
Bases:
Determination.of fission: densities on al quarterly.
basis will ensure that-the fission density limits =of Specification 13.8 are not exceeded.. Fuel' element
^ l 38 swelling will be kept well'below levels which could result in clad rupture and release of radioactive fission products.
j a
i f
Page 30
_ ~,
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reector Docket 50-2, Licenno R-28 Amendment 38:100792 5.0 DESIGN FEATURES 5.1 Site Description The Ford Nuclear Reactor (FNR) is located on the North 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 Glazier Way. Open land and the Arborcrest Cemetery l38 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 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 constructed within 500 feet of the reactor.
[33 2.
No housing or other buildings containing housing facilities will be erected within 1500 feet 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 Glazier Way on the southeast and the Arborcrest
[38 Cemetery located 800 feet to the east of the site.
The reactor site consists of all the land 500 feet to the east, 1000 feet to the west and north and 1200 feet to the south.
The boundary of this area consists of roadways around the site whose traffic flow can be controlled should such control be desirable.
The reactor restricted area consists of the reactor building and the contiguous Phoenix Memoria'l Laboratory (PML).
The reactor building is the i
operations boundary and the emergency planning zone.
Page 31 i
i
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Racetor Docket 50-2, Licenno R-28 Amendment 38:100792 5.2 Reactor Fuel The fuel assemblies shall be of the MTR type, consisting of plates containing uranium aluminide (UAlx), uranium oxide (Us os ), or uranium silicide (U3Si2) fuel enriched l34 to less than 20% in the isotope U235 clad with aluminum.
The authorized fuel assembly designs are:
Maximum Maximum Number Plate Loading Assembly Loading of plates (c U235)
(a U235) 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 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 restrict leakage.
2.
The reactor room 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 feet 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 between the hot cave operating face and the beamport floor, and a pneumatic tube system for sample transfer between the FNR and several laboratories in the Phoenix Memorial Laboratory.
Page 32
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 38:100792 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 *C.
2.
All reactor fuel elements and fueled devices shall be stored in a geometric array which assures suberiticality.
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.
Page 33 i
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2,. License R-28 Amendment 38:100792 6.0 ADMINISTRATIVE CONTROLS 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 l33 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 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 Nuclear Reactor Laboratory Manager shall report l33 to and be directly responsible to the Director, Michigan Memorial-Phoenix Project.
4.
Qualifications, Nuclear Reactor Laboratory l33 Manager and Assistant Managers:
Minimum qualifications for the Nuclear Reactor Laboratory Manager and Assistant Managers shall be bachelor's degrees and at least four years of reactor operating experience in increasingly responsible positions.
Years spent in graduate study may be substituted for operating 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 Manager and the l33 Assistant Managers shall apply for NRC senior operator licenses if they do not already hold licenses.
5.
A health physicist who is organizationally independent of the Ford Nuclear Reactor operations group shall be responsible for radiological. safety at the facility.
6.
A licensed operator or licensed senior operator pursuant to 10CFR55 shall be present in the control room whenever the reactor is in operation as defined in these specifications.
The minimum operating crew shall be composed of two l33 individuals, at least one of whom shall be a licensed senior reactor operator.
Page 34
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS-Ford Nuclear Reactor Docket 50-2 License R-28 Amendment 38:100792 7.
The Nuclear Reactor Laboratory Manager or one of l33 the Assistant Managers shall be readily available on-call 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, seven days per week.
The identity of and method for rapidly: contacting 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 operatorsRat the facility shall t
participate in an approved operator-requalification program as a condition of their continued assignment to operator duties.
6.2 Review and Audit 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 facility operations.
2.
The Safety Review Committee shall have at least eight members of whom no more than the minority shall be from the line' organization.shown in Figure 6.1 or administratively report to anyone in that line organization below the Vice President for Research.
The Committee shall be'made up of University staff and faculty who shall collectively provide experience in reactor engineering, j
instrumentation and control systems, radiological i
safety, and mechanical and electrical systems.
J 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.
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 35
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuc1scr Raccter Dockst 50-2. Liconss R-28 Amandront 38:100792 Figure 6.1 Organization Chart for the Ford Nuclear Reactor Regents University of Michigan President Vice President Vice President and Chief Research Financial Officer i
I Director Director Michigan Memorial-Phoenix Project Financial Operations and Sponsored Program Finance i
I I
I L---
Safety Review Director.
Committee Occupational and Environmental Safety
}
Director Radiation Safety Service Nuclear Reactor Health Physicist Laboratory Manager I
I Assistant Manager Assistant Manager Reactor Operations Research Support Activities Line Function
Safety and Licenuing Function Licensed Operators Page 36
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS
-Ford' Nuclear Racetor Docket'50-2 Licongo R-28 Amendment 38:100792 7.
The Safety 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 Ford Nuclear Reactor.
In the event'of a disagreement over approval of an experiment between'the Committee and the Nuclear Reactor Laboratory 33 Manager, the matter shall be referred to the Director, Michigan Memorial-Phoenix _ Project for resolution.
b.
Review reportable occurrences, c.
Review and approve proposed standard operating procedures and proposed changes to standard-operating procedures.
This requirement pertains to those procedures prepared pursuant to Section 6.4 of these specifications.
- d. Review and approve proposed changes to the technical specifications and-proposed amendments to the facility license and review proposed changes to the facility made pursuant to 10CFR50.59(c).
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-Phoenix 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 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.
9.
The audit shall be conducted with the following-guidelines:
a.
At least once every five years, a broad l34 j
review will be made of the following areas:
(1) Administration; (2) $afety Review Committee; (3) Reactor operators; (4) Procedures; (5) j Surveillance; (6) Quality Assurance Program; (7) i 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
OPERATING LICENSE AND TECHNICAL. SPECIFICATIONS Ford Nuclear Roactor.
Docket 50-2, License R-28 Amendment 38:100792 training, plans, procedures, surveillance, and records for safe operation of the1 facility; (2)
Verify that the requirements of Technical Specifications are being met; (3). Establish whether plans and procedures are being implemented; and (4) Determine whether responsibilities within the organization are appropriate.
in depth each year and will include l34 Routine audits will review a limited number b.
of systems as applicable to each system: (1) Operating procedures and records; (2) Calibration procedures and records; (3) Equipment. operation, condition, and failures; (4 ) Modifications; and (5) Reportable occurrences.
6.3 Action to Be Taken in the Event of a. Reportable Occurrence In the event of a reportable occurrence, as defined in these technical specifications, the following action shall be taken:
1.
The Nuclear Reactor Laboratory Manager shall be, l33 notified of the occurrence.
Corrective action shall be taken to correct the abnormal 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 measures to 38 prevent or reduce the probability or 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 facilities;-
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclecr Recetor Docket 50-2, Licence R-28 i
Amendment 38:100792 I
3.
Actions to be taken to correct specific and foreseen 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 provisions for evacuation, reentry, recovery, and medical support; 5.
Maintenance procedures which could have an effect on reactor safety; 1
6.
Periodic surveillance of reactor instrumentation and safety systems, area monitors, and continuous air monitors; 7.
Facility security plan; 8.
Radiation protection procedures, t
substantive changes to the above procedures shall be l34 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 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.
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 facility 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, page 39
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS
' Ford Nuclear Racctor Docket 50-2,~ Licence R-28 Amendment 38:100792 2.
The following records and logs shall be prepared and retained by the licensee for the life of the facility:
a.
Gaseous and liquid waste released to the environs; b.
Off site environmental monitoring surveys; c.
Radiation exposures for.all FNR personnel; d.
Fuel inventories and transfers; e.
Updated, corrected, and as built facility drawings; f.
Minutes of Safety Review Committee meetings.
6.6 Reporting Requirements In addition to reports required'by Title 10, Code off Federal Regulations, the following reports shall be submitted to the United States Nuclear Regulatory Commission.
1.
Annual Operating Report A written arnual operating report shall be submitted by March 31 of each year to the U.
S.
Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D.C.
20555 and to the Administrator, Region:III.
The report shall include the following information for the preceding year.
a.
Operations Summary A summary of operating experience having safety significance occurring during the reporting-period.
1.
Changes in facility design.
2.
performance characteristics-(e.g., equipment' and fuel performance).
3.
Changes in operating procedures which relate to the safety of facility operations.
4.
Results of surveillance tests and inspections required by these technical specifications.
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclecr:Racctor Dockat 50-2, Licence R-28 Amendment 38:100792
- 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; l33
- b. Health Physicist; c.
Safety Review Committee members, b.
Power Generation A monthly tabulation of the thermal output of the facility during the reporting period.
c.
Shutdowns A listing of unscheduled shutdowns which have occurred during the reporting period, tabulated according to cause, and a brief discussion of the actions taken to prevent recurrence.
d.
Maintenance 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 quantities 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.
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclecr Recctor Docket 50-2, Liconea R-28 Amendment 38:100792 2.
Average. concentration of gaseous effluents released during normal' steady state operation averaged-over the period of' reactor operation.
3.
Maximum instantaneous concentration of noble gas radionuclides released
~
during special operations, tests, or experiments.
4.
Percent of technical specification limit.
b.
Iodine Releases (Required if iodine is identified in primary coolant samples, or if fueled experiments are conducted at.the facility.)
1.
Total iodine radioactivity in curies by nuclide released, based'on representative isotopic analyses performed.
2.
Percent of MPC.
c.
Particulste 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.
j 2.
Liquid Effluents a.
Total gross beta and gamma radioactivity released in curies excluding tritium and average concentration released to the unrestricted area or sanitary sewer averaged over period of release.
Page 42 l
' OPERATING LICENSE AND. TECHNICAL SPECIFICATIONS Ford Nuclear R ector.
Docket 50-2, Licenno R-28 Amendment 38:100792 b.
The maximum concentration of beta'and gamma radioactivity released to the unrestricted area.
Total alpha radioactivity in curies c.
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.)
d.
Total volume in ml of liquid waste released.
e.
Total volume in ml of water-used to dilute the liquid waste during the' period of release prior to release from the building to the sanitary sewer system.
f.
Total radioactivity in curies, and concentration averaged over the period of' release by nuclide released, based on representative isotopic analyses performed for any release from a waste storage tank whose contents have a concentration in excess of 9x10-4 microcuries/cc.
g.
Percent of technical. specification 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 w'ith the highest average and the location of that point with respect to the site.
Page 43
OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nucloor R9 ctor Docket 50-2,.Liconco R-28 Amendment 38:100792
- 5. The maximum cumulative radiation dose which could have been received by an individual continuously present in an unrestricted area during reactor operation from:
a.
Direct radiation and gaseou,s effluent; b.
Liquid effluent.
6.
If levels of radioactive materials in environmental media, as determined by an environmental monitoring program, indicate 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 exposure to individuals and to population groups and assumptions upon which estimates are based.
7.
If significant variations of off 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 whole body radiation l38 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 a.
Reportable Occurrence Reports In the event of a reportable occurrence 38 as defined in section 1.0, 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 FAX to the Reactor Project 38 Manager. Headquarters, U.S.
Nuclear Regulatory Commission and to the,
/.
Administrator, Region III, followed by a written report within 14 days to the U. S.
Nuclear Regulatory Commission, Attn: Document Control Desk, Washington, D.
C.
20555, and to on the next working dlay FAX 38 the Administrator, Region III.
notification may be sent in the event of a reportable occurrence during a weekend or holiday period. The written report of a reportable occurrence, and, to the extent possible, the preliminary telephone and FAX l38 notification shall:
Page 44
q_3
~
~
OPERATING LICENSE AND' TECHNICAL 1 SPECIFICATIONS Ford Nuclear Rssetor-
' Docket.50-2, Licanto R-28:
"~
L Amendmentf38:100792 1.l Describe, analyze, and' evaluate safety-implications;.
L
- 2. Outline'the measures'takenLto assure that the cause of the condition is determined;,
?. Indicate the corrective. action includingJany
- 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_11ghtLof the cumulative-experience'obtained from thefrecord of.
~
l previous failure and malfunctions'of similar; l
systems'and. components.-
b.
Technical Specification,. Safety Analysis, 38 and System. Deficiencies..
A written report shall-be forwarded w'ithin'_30 days to the U.
S. Nuclear Regulatory Commission,-
Attn -Document Contrel. Desk, Washington D.1C.-
3l
~
j 20555, and to the Administrator,zRegion" 38-III, in the event of-
~
j
.1.
Discovery _of any substantial errors in the I
transient or accident analyses or injthe methods used for such analyses, asTdescribed in.the safety analysis or in the bases:
for the technical specifications;-
l
- 2. Discovery of any substantial' variance?from performance specifications contained in the technical' specifications'and' safety?
analysis.-
- 3. Discovery'of any condition involving,a' single failure which, for a: system c
possible designed against assumed' failures,icould-L result in a-'losscof the capability ofLthe:
system to perform ~its safety function.
i Page 45
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