Text

Forwards Amend 38 to Ford Nuclear Reactor TS Redefining Specification 3.1,under License R-28 for Phoenix Project
	ML20126E657
Person / Time
Site:	University of Michigan
Issue date:	10/29/1992
From:	Fleming R; MICHIGAN, UNIV. OF, ANN ARBOR, MI
To:	Michaels T; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
	NUDOCS 9212290252
	Download: ML20126E657 (54)
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University of Michigan Michigan Memorial-Phoenix Project Office of the Director Ann Arbor, Michigan 48109-2100 October 29, 1992 Docket 50-2 License R-28 United States Nuclear Hegulatory Commission Document Control Desk Attn: Theodore S. Michaels. Project Manager Standardization and Non-Power Henctor Project Directorate Division of Reactor Projects 111, IV, V, and Special Projects office of Nuclear Reactor Regulation Washington, D.C. 20565 Re: Ford Nuc1 car Reactor Technical Specifications, Amendment 38

Dear Mr. Michaels:

The University of Michigan hereby submits Amendment 38 to the Ford Nuclear Henctor Technical Specifications. A revised copy of the

' Technical specifications is enclosed. All changes related to Amendment 38 are denoted in the right margin.

The significant changes are on page 10, specification 3.1. In specification 3.1.1, the statement "except during the process of verifying shutdown margin" has been added. In specification 3.1.3, the statement "except during the process of verifying exporiment reactivity has been added. This will permit measurement of shutdown margin and sample reactivities under carefully controlled conditions prior to reactor operation at i power. If the values are not within Technical Specification limits, adjustments can be made prior to taking the reactor to power.

Specification 3.1.4 has been-changed to read "during fuel movements to and from the reactor core". This makes it clear that the reactor must be suberitical by at least 0.025 delta K/K for any fuel insertion into or removal from the reactor core including during a critical loading experiment. Fuel movement would be permitted within the reactor pool, for example, from-one storage rack to another.

In Table 3.2, the radiation monitor "G. Primary Demineralizer" has been deleted. The intent of the monitor was: (1) to detect fission products from a failed fuel element and (2) to detect radioactive water in the facility's " cold sump" which at one time was pumped directly into the sewer system. The cold sump connection to the sewer has been disconnected, and-the sump pumps directly to the facility retention tanks. From there the .<ater is recycled back to the reactor pool. The demineralizers never showed any increase in radiation levels as the result of the three i failed fuel elements that have occurred at the facility. The mobile air particulate monitors provided-immediate indication and longer term confirmation was obtained by pool water analysis.

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Theodore S. Michcels October 29, 1992 The reactor basement where the detector is located is a locked and monitored high radiation area.

A thorough review of the Technical Specifications has been completed. Changes have been made to correct typographical and spelling errors, to correct section cross reference numbers, to provide consistency between sections, and to clarify the exact meaning. N o rie of the additional changes alter the intent or the meaning of the specifications.

The following is a page-by-page summary of the changes proposed in Anie nd me n t 38 to the Ford Nuclear Reactor Technical Specifications. -_

EDXe SC Ilion ___ Descrintion 2 Definition Heactor Operation The definition has always been interpreted to mean six standard elements plus the four control elements already in the core with the rods. For the original low enrichment critical experiment, five standard elements were arranged in a cross in the center of the core with four control elements in place, one housing each of the reactor's control rods.

4 Definition Shim-Safety Rod Shim-safety hyphenated here and throughout the rest of the Technical Specifications.

5 Definition Time Intervals Biweekly interval has been defined as 14 to 20 days because pool water radioactivity measurements are required biweekly.

10 3.1.1 "except during the process of verifying shutdown margin" added to the end of the shutdown margin requirement. This will permit measurements that may be slightly out of specification to be made prior to power operation of the reactor.

10 3.1.3 The two specifications, 3.1.3 and 3.1.4, have been combined into a single specification, 3.1.3, for clarity.

"axcept during the process of verifying experiment reactivity" has been added to the end of the experiment reactivity requirement. This will permit measurements that ma:. be s1ightly out of specification to be made prior to power operation of the reactor.

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l Theodore S. Michaels October 29, 1992 EftR'l liiLClijn1 De8eription 10 3.1.4 " loading changes" has been changed to " movements to (Formerly and from the reactor core". This makes the 3.1.5) specification clear that minimum suberiticality of 0.025 delta K/K is required for any fuel movement to or from the core.

10 3.1.5 The wording of the specification has been altered to (Formerly be consistent with the wording of specification 3.1.6) 3.1.I and to clarify the intent. The last two words, "for inspection" have been deleted; the _

specification applies to any rod removal.

11 3.1.G The wording of the specification has been altered to (Formerly be consistent with the wording of specification 3.1.7) 3.1.5 and to clarify the intent.

11 3.1 Insertion or removal of m.oveabh experiments will Bases not produce a period less than 30 seconds.

Para 3 11 3.1 .. reactivity worth of secured end to t til experiments Dases to values of reactivity.....

Para 4 11 3.1 The wording of the bases for specifications 3.1.4, Bases 3.1.5, and 3.1.6 has been changed to be consistent Para 5 with the specifications themselves.

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1i Table The wording of the function of the reactor coolant 3.2 inlet temperature instrument has been altered slightly to more clearly state its purpose.

14 Table The Primary Demineralizer Radiation Monitor has been 3.2 deleted because it does not serve its intended function of: (1) detecting failed fuel elements and (2) preventing radioactive water from being dumped from the ec1d sump to the sewer; the cold sump dumps to the facility's retention tanks.

15 c. The wording was revised to mahe the requirement perfectly clear.

16 3.2 A basis for having rod holddown mechanisms has been Bases added.

Para 7 16 3.3 A portion o f the objective from specification 3.~>

Objective was moved to 3.3 because that is where it applied.

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Theodore S. Michaels October 29, 1992 lits11pn Description EMR 10 3.3.1 The specification was more clearly delineated, but unchanged in content.

17 3.3.2.e Revised to clarify that the north door is sealed rather than clamped closed.

17 3.3 The basis for keeping reactor building access doors Bases closed was worded "the integrity of the confinement Para 3 will be maintained at or below the value assumed in the llazards Summary Report." The wording has been chariged to "at or above the leve.1 assumed...".

18 3.4 Resistivity changed to conductivity to be consistent Applic, with the actual measurement at the facility.

18 3.4.2 Conductivity has replaced resistivity in the specification to be consistent with practice at the facility. The facility measures conductivity rather than resistivity. The values in the specification have not been changed.

19 3.4.3 Sample holders have replaced grid plugs as acceptable devices to be inserted in core grid locations. Sample holders will prevent fuel elements from being inadv e rtent ly inserted in an empt y core grid location.

19 3.4.4 The pool gate should be stored at any time the reactor is in operation. -

19 3.5 A portion of the Objective was moved to Objective specification 3.3 where it was applicable.

20 3.5.2 The exact nomenclature used to describe the a and b particulate monitors, the gaseous activity monitors, and the exhaust stacks has been inserted to avoid confusien and to assist reactor operators in understanding the Technical Specifications.

20 3.5 Reference to section 3.G.1 corrected to 3.5.1.

Bases Para 1 20 3.5 Reference to section 3.6.2 corrected to 3.5.2.

Bases Para 2 21 3.G.2 Reference to section 3.7.1 corrected to 3.6.1.

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f Theodore S. Michaels i October 29, 1992 !

Eggg Section Description !

21 3.6 The facility no longer discharges potentially Bases radioactive water to the Ann Arbor city sewer Para 2 system. The wording " Current experience" has been changed to "In the past". The specification should 4 remain in Technical Specifications in the event that- l discharges to the sewer should be-resumed'at some- i time in the future.

22 3.7 References to sections 3.8.1, 3.8.4, 3.8.5, and :

23 Bases 3.8.0 have been corrected to 3.7.1, 3.7.4, 3.7.5, l and 3.7.6.

24 4.1.1.a Not less than once each calendar. year" has been changed to." Annually" to be consistent with the Technical specification definitions of time-intervals. ;

24 -4.1.1.d "an outer face" was changed to_"the outer faces" to ,

make the statement clear that a total of three !

clements on the faces was intended, not three !

elements on each face.

26 4.2.2 at least once each year" has been changed to annually" to be consistent with the Technical Specification definitions of timerintervals. ;

26 4.2.4 The verification requirements for the operation of-the radiation monitoring system have been specifically stated rather than been referenced to another section of the Technical Specifications.

20 4.2.5 "not less than once every six months" has been changed to " semiannually" to be consistent with the-Technical Specification definitions of time

. intervals.

26 4.2.6 a "At least' once each calendar year" has been changed to " annually" to be. consistent with the Technical Specification definitions of time intervals.

27 4.3.1 The-wording of the specification.has been revised to-

- make the requirement clear.

27- 1.3.2 "at intervals not to exceed six months" has been.

changed to " semiannually" to be consistent with the Technical Specification definitions of time intervals.

28 4.4.2 Resistivity has been changed to conductivity. "

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Theodore S. Michaels October 29, 1992 Eggg Section Description 28 4.4.3 The wording of the specification has been revised to make the requirement clear.

29 4.5.1 "not less than once every six months" has been 4.5.2 changed to " semiannually" to be consistent with the 4.5.3 Technical Specification definitions of time intervals.

29 4.6.1 "not less than once every six months" has been changed to " semiannually" to be consistent with the Technical Specification definitions of time intervals.

30 1.7 Reference to section 3.9 corrected to 3.8.

Objective 30 4.7 Reference to section 3.9 corrected to 3.8.

Bases 31 5.1 The street name Glacier has been corrected to Para 2 Glazier.

and 4 35 6.1.8 The wording of the specification has been revised to make the requirement clear.

38 6.3.2 Deleted the word "of" and changed the second "of" to or".

44 6.6.1.h Added "whole body" to radiation exposures. ,

44 6.6.2.a " telegram" has been replaced with " FAX" and slight Para 1 rewording to text.

45 6.6.2.b Title changed from " Unusual Events" to avoid confusion with Emergency Plan definition. Report made to both llendquarters and Region III.

Sincerely,

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Ronald F. Fleming, Directo

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Michigan Memorial-Phoenix Project Enclosures i

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OPERATING LICENSE AND TECl!NICAL SPECIFICATIONS l

Ford Nuclear Rocctor

Docket 50-2, Licenso-R-28 l i

Amendment.38: 100792 P

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APPENDIX A TO FACILITY LICENSE Il-28 [

TECIINICAL SPECIFICATIONS !

1 DOCKET 50-2 t'

L HICli10AN- HEH0llI AL PilOENIX Pit 0 JECT

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TIIE UNIVEllSITY OF HICllIGAN Ann Arbor, Michigan L

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OPERATING LICENSE ~AND.TECIINICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2. Liconee R-28 Amendment 38:100792 CONTENTS 1

1.0 REFINITIONS 6

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETT1NGE 6

2.1 Safety Limits 2.1.1 Safety Limits in the Forced 6 convection Mode 2.1.2 Safety Limits in the Natural 7

Convection Mode 7-2.2 Limiting Safety System Settings (LSSS) .

2 2.1 Limiting Safety Systrm Settings in the 7

Forced Convection Modt 2.2.2 Limiting Safety Sys'9m octtings in the 8

Natural Convect in . 4ow Mode

~ 10 3.0 LIMITING CONDITIONS F'- _W Reactivity Limits 10 3.1 12 3.2 Reactor Safety System FNR Confinement Building 16 3.3 18 3.4 Primary Coolant Conditions 19 3.5 Airborne Effluents 20 3.6 Liquid Effluents 21 3.7 Limitations of Experiments Fission Density Limit 23 3.8 24 4.0 EEEVEILLANCE REQUIREMENTS Reactivity Limits 24 4.1 25 4.2_ Reactor Safety System FNR Confinement Building 27 4 3-28 4.4 Primary Coolant System

-29 4.5 Airborne Effluents 29 4.6 Liquid Effluents Fission Density Limits 30-4 . 7.

31 5.0 DESIGN FEATURES Site Description 31 5.1 32

-5.2 Reactor Fuel 32 5.3 Reactor Building

. Fuel Storage 33-5.4 Contents-1 l

OPERATING LICENSE AND TECilNICAL SPECIFICATIONS i Ford Nuclear Reactor Docket 50-2, Licenso R J Amendment 38:100792' ,

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6.0- ADMINISTRATIVE CONTROLS 34 6.1 Organization :

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6.2 Review and Audit l 6.3 Action to be Taken in the Event of a 38 l Reportable Occurrence 38-6.4 Operating Procedures 39 6.5 Operating Records 40 j 6.6 Reporting Requirements i

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l OPERATING LICENSE AND TECilNICAh SPECIFICATIONS Ford Nuclear Reactor -

Docket 50-2 Licenso R-28 '

P Amendment 38:100792 1.0 DEFINITIONS Channel Calibration - A channel calibration is an adjustment of the channel such that its output corresponds with acceptable t 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.

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.

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

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OPERATING 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 situatioa before a safety liinit -is exceeded (10CFR50.30).

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. Qaantities 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 that combination'of safety channels and associated circuitry which forms the automatic protective system for the: reactor or

-provides information which requires manual protective action to be initiated.

Reactor Scram - Shutoff of electrical current to the rod holding magnets and subsequent insertion of the rods into_the _

core by gravity.

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OPERATING' LICENSE AND TECHNICAL SPECIFICATIONS-Ford Nuclear Roactor

' ' 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 expr iments from the core, or control rod maintenance.

Readily Available on Call - Readily available on call shall l mean a licensed senfor operator shall insure that he can be- .

contacted and is within a reasonable driving time (1/2 hour). 1 from the. reactor building when the reactor is being operated 4 by'a licensed operator. ,

Regulating Rod - The regulating rod is a control rod of low-reactivity worth fabricated from stainlecs-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 Experiment - A removable experiment is any e 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. o Reportable Occurrence - A reportable occurrence is any of the following:

l'. 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; l 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; l

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7 OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2,' License 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; e

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; '

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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.

Hundown - 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. <

r Safety himit (SL) - himits upon important process variables which are found to bv necessary to reasonably protect the !

inte4srity of certain of the physical barriera 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 stationury position ,

relative to the reactor by mechsnical means. The_ restraint . '

shall exert sufficient force on the experiment to overcome the expoeted 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 atainless steel which is used to compensate for fuel burnup, temperature, and poison offects._ 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.

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OPERATING LICENSE AND TECllNICAL 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 chan;4 which is measurable by calibrated control rod comparison methods between two defined terminal positions or cenfigurations 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 Annually - 12 to 15 months.

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Biannually - 24 to 30 months.

Biweekly - 14 to 20 days l38 Daily - 24 to 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months .

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 mr.lfunction, -

or a manual shutdown in cesponse to conditions which could adversely affect safe 'peration, not to include shutdowns which occur during testing cr checkout operations.

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OPERATING 1 LICENSE AND-TECHNICAL SPECIFICATIONS Ford Nuclear Racctor 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 Throug' , Core, m Reactor Coolant Inlet Tempoca. Lute, 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 (TA) at 2 Mw shall not exceed 116 oF.

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

Rasag:

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

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OPERATING LICENSELAND TECHNICAL SPECIFICATIONSi Ford-Nucloar Rocctor Docket _50-2, Licenso R-28f Amendment 38:100792 2.1.2 Safety Limits.in:the Natural" Convection Hodo 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 Po-tr. 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 (TA) shall not exceed 131 0F.

3. The height of pool water above the-core (H) shall not be less thannl8 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 t

Applicability:

This-specification applies to the set points-for the safety channels monitoring reactor thermal power ( P), primary coolant flow (m),

height of water above-the top of the core (H ) .-

and core exit temperature (T.).

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OPERATING LICENSE;AND TECHNICAL ' SPECIFICATIONS _

Ford Nucloer Rocctor Docket.50-2, License R-28.

Amendment 38:100792 Objective:

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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 LjiLSR 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.

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OPERATING LICENSE AND TECHNICAL' SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License 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 LESji P (Max) 100 kw 11 (Min) 19 ft T (Max) 129 F Bases:

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

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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 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 roda 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 Diperimen t Reactivitv Wo. rih 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 0.010 delta K/K before shim-safety rods are remaved from the core, page 10

OPERATIN'O 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 0.010 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 g_ 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 3 cooldown and xenon decay even if the rod of the highest reactivity worth sbould 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.

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

The largest positive reactivity increase that can be l33 produced by replacing light water with heavy water in the heavy water reflector tank is 0.04 delta K/K.

Maintaining the core suberitical by at least 0.010 1 38 delta K/K in Specification 3.1.6 during heavy water transfers provides adequate margin to assure that Page 11

Ford Nuclocr Ror.ctor Docket 50-2, biconce R-28 Amend ent 38:100792 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 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 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 lifting of fuel elements through the movement of control rods.

Bases:

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

I 1

page 12 l

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS- '

Ford Nuclocr- Recctor-

. Docket 50-2,- Licence _R-28 Amendment 38:100792' Table 3.1 REQUIRED SAFETY _ CHANNELS Minimum Number Channel Setpoint Required Function Log Count Rate 2 cps 1 Rod Withdrawai-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 2100 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 Scram 1100 kw Header Up/ 900 gpm 1 Scram No Water Flow Building Exhaust 1 mrem /hr 1 Scram Radiation Level Building _ Alarm 1 Scram Manual Switch Manual Scram Switch 1 Scram Magnet Power Keyswitch 1 Scram Reactor Coolant Exit Temp. 129 o F 1 Auto Rundown Pool Level- 1 foot'below pool 1 Auto Rundown overflow Bridge Not When clamps 1 _ Scram Clamped- released Page 13

~

OPERATING LICENSE AND TECHNICAL' SPECIFICATIONS'

-Fo'rd Nuclear Rocctor Docket 50-2,-License R-28.

Amendment' 38:100792 Table 3.2 REQUIRED SAFETY RELATED INSTRUMENTATION Minimum Number Instrumentation Setpoint' _Recuired ~ 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 Interlock 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 l_34 Floor

4. N Wall, Beamport 5(50) mrem /hr 1 Alarm Floor

5. NE Column, Beamport 5(50) mrem /hr 1 Alarm -l34

-Floor l38 Footnotes:

a. Not1 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,- Licence R 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or is replaced by -i a second locally alarming unit of similar range.

l Page 15 w

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS'

. Ford Nuclear Recctor

-DocketJ50-2, Licence: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 1when'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-indicatingineutron 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 t'emperature and below the safety limit for pool level.

The manual scram button and the magnet power keyswitch provide +wo 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;coreLby 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:

l This specification applies'to the Ford Nuclear Reactor confinement building requirements.

Objective:

L 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.

i.

~

Page 16-

LOPERATING' LICENSE AND: TECHNICAL SPECIFICATIONS

- 4 Ford Nuclocr Reactor:

Docket'50-2i. License 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 1close;

c. The beamport exhaust. damper to Stack 2 shall automatically close; and

d. The room 3103 hood exhaust damper to Stack 12 shall automatically close.

2. During reactor operation, the following conditions will be administrative 1y controlled:

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

b. The main equipment.-access door onto the beamport.

~

floor will be opened only long enough.to' permit

.the: passage of equipment;

c. The personnel door to the cooling tower area will remain clamped except to permit the passage.

of personnel and/or equipment to1the-cooling tower area. The door will remain closed but not clamped until all personnel-have left the cooling tower area;

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

e. The personnel exit door located:in the north wall-of the building-will 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-buildingaaf 10% of the building, volume per-day, and concluded that the accident 1 doses

-would be acceptable. Conformance to Specifications page 17

~

_7 OPERATING LICENSE AND-TECHNICAL SPECIFICATIONS Ford Nuclear Reactor-Docket:50-2, License-R-28

-Amendment 38:100792 E

~

-3.3.1an'd 3.3'.2 will assure that theLbu11 ding leak rate-will not exceed the leak rate used in the ,

evaluation.

The 1.0 mrem /hr setpoint for the facil'ity exhaust 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 they release of radioactive material will be' minimized.

3.4 primary Coolant Conditions Applicability:

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

assure proper conditions of coolant.for normal-and emergency requirements.

-Specification:

L l'. The primary coolant pH shall:be maintained between-4.5 and 7.5.

2. - The primary coolant conductivity-shall_be'. l38-l maintained at a value less-than 5Lmicronno/cm-L except for periods of-time not to' exceed 7_ days when the conductivity may not be-greater than 20-micromho/cm.

l

's Page 18

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Rocctor 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 {38 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 c omponents 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 uncccupied grid plate position.

Specification 3.4.4 that the gate be stored assures that the full volume cf 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 Nuclocr Rocctor:

DocketE50-2, License:R -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. _Iffeither unit is out of service for more than 24= hours,'

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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- Tj 38 incorporate a dilution factor of 400-for effluents released through the exhaust stacks. This dilution j 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- 1 dispersion-factors, this dilution factor wil'l-assure -l that concentrations of radioactive material in-unrestricted areas around the FNR site will txt far below the limits of 10CFR20.

The requirements of'specli'ication 3.5.2 are considered l38 adequate to assure proper airborne effluent monitoring.

3.6 Liquid Effluents l Applicability:

jl This specification supplies to.the monitoring af 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 -1 minimized, page 20

OPERATING hICENSE AND TECHNICAh. SPECIFICATIONS Ford-Nuclear Rocctor-

=* - DocketD50-2, Liconoc_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 Arborfsanitary. sewer-system shall not exceed the concentrations 1specified; in 10CFR20-for releases to sanitary sewer systems.

2. The amount of liquid-dis.~harged shall be limited. ]33 to the~ equivalent of 3,000 gallons of-liquid at the concentration limit specified in 3.6.1 each day. l38

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 inLa 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 3 81 per year have been required. -During 1970,-the1 North Campus water released into the sanitary sewer system-averaged 946,000 gallons per day. This provides a dailp 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 experimenth installed in the FNR.

Objective:

To prevent damage te the reactor or excessive release of radioactive materials in the event of an experiment ,

failure.

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Page 21

.p OPERATING _ LICENSE AND_ TECHNICAL SPECIFICATIONS-Pord Nuclear Racetor-DocketL50-2,_ 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-- 1 pressure twice the calculated maximum pressure.

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

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

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

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 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 andi 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 that1the complete _ release of all gaseous, particulate, or volatile components from the encapsulation could not result in doses in excess of the equivalent-annual doses stated in 10CFR20. This dose limit applies to persons occupying unrestricted areas continuously for two.

hours starting at the time of release and restricted areas during the length of time' required to evacuate the' restricted area.

Bases:

Specifications 3.7.1 through 3.7.4-are intended to ,38 reduce the likelihood of damage to reactor components and radioactivity releases resulting from experiment Page .

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford N'aclear 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 experimentr 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. Tne 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 re: lease of radioactive fission products.

Specification:

1. The FNR fission density limit shall be 1. 5 x1021 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 Sia ) fuel in the FNR up to the [34 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 liigh 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 Racetor.

Dockot 50-2, Licenso R-28 Amendment 38:100792 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactivity Limits Applicability:

This specification applies to the surveillance requirements for reactivity limits.

l 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; l38

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

c. Whenever the replacement-of a fuel element'in an-interior core location results in an element fuel mass change of more than 10% in that location;

d. -Whenever the addition of more than three standard fuel elements to the outer faces of l38 the core is made to achieve the desired excess reactivity for the operation of the reactor. -

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

3. The reactivity worth of those experiments whose 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 wherety 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

. OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nucloor Rosctor Docket-50-2.- License-R 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 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 l33 required for heavy water transfers will assure the-reactor stays suberitical under all possible circumstances during >

heavy water. transfers.

4.2 Reactor Safety System Applicability:

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

Objective:

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

Specification:

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

a. prior to each reactor startup following a period when the reactor was secured;

b. After a channel has been repaired or deenergized.

page 25

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS.

Ford Nuclear Racetor Docket:50-2, Liconeo R-28 Amendment 38:100792

2. A channel calibration of the safety channelsz listed-in Table 3.1, which can be calibrated,.shall-be:

performed annually. l38

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 monitoringEsystem-required in Table 3.2 shall be verified:, -l 38.

a. Prior to each reactor startup following a 38-period when the reactor was secured;

b. After a channel has been deenergized.

l38

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 ccre location is changed;

c. Whenever maintenance is1 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

. T OPERATING LICENSE AND TECHNICAL' SPECIFICATIONS Ford Nuclear Rosctor Docket 150-2, Licenso R-28 Amendment 38:100792.

L The measured.rel! ease-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 1 of these parameters is. considered adequate:to detect any deterioration which could change the release-drop time. Binding or rubbing caused by rod misalignment-could result from maintenance; therefore, release drop times will be-checked after-such maintenance.

4.3 FNR Confinement Building Applicability:

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

Objective:

To assure that the condition of the closure devices for the building openings are in satisfactory condition to assure their ability to provide _ adequate confinement of any airborne radioactivity released into the building.

Specification:

1. Operation of the dampers described in [38 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, i

2. The condition of the following gaskets shall be inspected semiannually, and the gaskets shall be l383 replaced whenever any evidence of deterioration is-found:

a. Building ventilation system intake and-exhaust dampers;

b. personnel access doors;

c. Equipment access doors;

d. Cooling tower access door.

i page 27 .,

- w -

, ~

, - = - -- . - . . .

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Remetor

'- -Docket-50-2,-Licence R-28 <

Amendment l38:100792 Bases:

The'prestart check of the main damper. function provides

~

assurance that the automatic functioniprovided byLthese-dampers will be actuated when confinement isolation is :

required.. The semiannual inspection of gasket materials, since these materialsJare.not in a damaging atmosphere, will provide. assurance thatsthe gaskets will perform their-function of' limiting leakage throughi

-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 coolant-from the facility.

Bases:

Regular surveillance;of pool water quality and-radioactivity provides assurance that-pH and conductivity changes that could accelerate the corrosion of the primary coolant system would be detected before significant' corrosive damage would occur, and that the presence 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 28 n.

~

'l OPERATING LICENSE-AND. TECHNICAL' SPECIFICATIONS" Ford NucloarLRsa6 tor Docket 50-2, License R Amendment 138:100792

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. l38-

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 1.iquid 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

s OPERATING LICENSE AND TECHNICAL SPECIFICATIONS-Ford Nuclocr Raactor. ,

Docket'50-2, License R-28; AmendmentL 38:100792

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

Bases:

Experience with,the counting l equipment used-in-measuring the radioactivity in the waste retention-tanks suggests that the above period it 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. l38 Specification:

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

Bases:

Determination of fission densities on a quarterly '

basis will ensure that the fission density limits of - _

-Specification 3.8 are not exceeded. Fuel elementL -l38 swelling will be kept well-below levels which could result in clad rupture and-release of radioactive fission products.

page 30

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS' Ford Nuclocr. Reactor:

Docket 50-2,_ License R-28 Amendment 38:100792 5.0 ' DESIGN FEATURES 5.1 Site Description The Ford Nuclear Reactor (FNR)_is located on tho 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.

i 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:

i 1. Only laboratory and research buildings.will be-constructed within 500 feet of the reactor. l33-l

! 2. No housing or other buildings containing housing-I facilities will be erected within 1500 feet of the l reactor.

I-L The University of Michigan controls all the land within 1500 feet of the reactor site, with'the exception of a L

small portion of the highway rightiof way along

" Glazier Way on the southeast and the Arborcrest- [38 Cemetery located 800 feet to the east of the site.

L 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.

L The reactor restricted area consists of the reactor l-building and the contiguous Phoenix Memorial

) Laboratory (PML); The reactor building is the operations boundary and the emergency planning zone.

1 Page 31 i

OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2,-License R-28 Amendment 38:100792 5.2' Reactor Fuel The fuel assemblies shall be of the MTR type, consisting of plates containing uranium aluminide-(UAls), uranium oxide ( Ua 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 Pumber Plate Loading Assembly Loading of Plates (g 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 exhnusts 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 Rocctor i Docket 50-2 License R-28 i Amendment- 38:100792 ;

5.4 Fuel Storage j I

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 tLe fuel element or fueled device : terperature ,

i will nci eTeeed 100 oC.

2. All reactor fuel elements and fueled devices shall; ;

be stored in a : geometric array which assures !

suberiticality. The array spacings will be' based -I

~

on the experimental results reported in 7 OhNL-CF-58-9-40 for storage array experiments 'i' performed with oak Ridge-Reactor and Bulk Shielding Facility fuel elements.

Page'33

=:

OPERATING h1 CENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor i Docket 50-2, Liconee R-28 i Amendment 38:100792 '

3.0 ADMINISTRATIVE CONTROLS 0.1 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. j

2. The Nuclear Reactor Laboratory Manager shall bo 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 r facility license, including the technical specificottons and operating procedures. During periods of his obsence, his responsibilities are 3 delegated to thu Assistant Manager for Operations 33 J 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 Lab entory Manager shall' report l33 to and be directly responsible to the Director, Michigan Memorial-phoenix project.

)

4. Qualifications, Nuclear Reactor Laboratory- -l33 Hanager and Assistant-Hanagers: 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 l 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 l30 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 1 group shall be responsible for radiological safety at the_ facility.

G. 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 TECIINICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, Licence R-20' Amendment 38:100792

7. The Nuclear Reactor Laboratory Manager or one of l35 the Assistant Managers shall be readily available on-call 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

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

0.2 Review and Audit :

1. A Safety Review Committee (ERC) 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 administrative 1y report to anyone in :

that line organization below the Vi'ce President fer Research. The-Committee shull be made up of -i University staff and faculty who,shall co11cetively- ,

provide experience in reactor engineering, instrumentation and control systems, radiological :

-safety, and mechanical-and-electrical-systems.

3. The Committee shall meetLat least semiannually.

.l . The quorum shall consist of not less than a majority of the full committee and .shall include the chairman ,

or his designated alternate. H

5. Five votes are required to approveLthose changes, experiments, and tests which require-specific SRC approval. Votes may be cast at SRC meetings or via-individual polling of members. ,

6. Minutus of'ench' 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 4

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t OPERATING LICENSE AND TECllNICAL SPECIFICATIONS.

Ford Nucloor Rocctor '

Dockot 50-2, Liconco R-28 Amendment 38:100792-Figure 6.1 Organization Chart for the Ford Nuclear Reactor ,

Regents University of Michigan ,

President I

Vice President Vice President and Chief Research Financial Officer i I Dir(ctor Director Michigan Memorial-Phoenix Project Financial Operations and i

ML20126E657

Text

Dear Mr. Michaels:

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