ML20199D688

Revised TS Sections 1.0,4.7,5.0,6.1.2 & 6.2.3 to Univ of Il Research Reactor

ML20199D688
Person / Time
Site:	University of Illinois
Issue date:	01/12/1999
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20199D453	List: ML20199D447 ML20199D688
References
NUDOCS 9901200175
Download: ML20199D688 (10)

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l 1.0 DEFINITIONS i

1.1 Reactor Shutdown - The reactor is in a shut down condition when sufficient control rods are inserted so as to assure that it is subcritical by at least $1.00 of reactivity, and a senior reactor operator is in charge of any work in progress. j i- 1.2 Reactor Secured - The reactor is secured whend4hc fc!!cuingenditionseHatisfied  :

[ a. Il contains insuf]Icientfissile material or moderator present in the reactor, adjacent l experiments, or control rods, to attain criticality under optimum available conditions ofmoderation, and reflection. or i

j b. All ofthefollowing conditions are met:

el) Suflicient control rods are inserted so as to assure that it is suberitical by at least $1.00 of reactisity; l'

h:2) Power to the control rod magnets and actuating solenoids is off, and the key removed; and l l eJ) No work is in progress invohing fuel or in-core experiments or maintenance of the core l structure, control rods, or control rod drive mechanisms.

l 1.3 Reactor Operation - The Reactor is in operation when it is not secured or shut down.

l 1.4 Standard Control Rod - A standard control rod is one having rack and pinion, electric motor drive, and

scram capability.

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t 1.5 Transient Control Rod A transient control rod is one that is pneumatically operated and has scram j i- capability.

1.6 Operable - A system or device is operable when it is capable of performing its intended functions in a normal manner.

1.7 Cold Critical - The reactor is in the cold critical condition when it is critical with the fuel and bulk water temperatures the same (~ 40 C).

1.8 Steady-State Mode - The reactor is in the steady-state mode when the reactor mode selection switch is in the steady-state or automatic position. In this mode, reactor power is held constant or is changed on periods t greater than three seconds.

1.9 Sauarc-Wave Mode - Th; reactor is in the square-wave mode when the reactor mode selection switch is in the squarc-wave position. In this mode, the reactor power is increased on periods less than one second, is held at constant power by automatic motion of the control rods, and is then reduced by shutting the reactor down.

1.10 Eulse Mode - The reactor is in the pulse mode when the reactor mode selection switch is in the pulse position.

' I In this mode, reactor power is increased on periods ofless than one second by motion of the transient control l

rod (s).  !

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l.0 DEFINITIONS I

1.1 Reactor Shutdown - The reactor is in a shut down condition when suflicient control rods are inserted so as to '

. assure that it is subcritical by at least $1.00 of reactivity, and a senior reactor operator is in charge of any l I

work in progress.

1.2 Reactor Segrg-The reactor is secured when: l

a. It contains insufHeient fissile material or moderator present in the reactor, adjacent j experiments, or control rods, to attain criticality under optimum available conditions i of moderation, and reflection, or

b. All of the following conditions are met:

1) Suflicient control rods are insened so as to assure that it is suberitical by at least $1.00 of reactivity;

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2) Power to the control rod magnets and actuating solenoids is off, and the key removed, and

3) No work is in progress involving fuel or in-core experiments or maintenance of the core

! structure, control rods, or control rod drive mechanisms.

1.3 R_ eactor Operation - The Reactor is in operation when it is not secured or shut down.

1.4 Standard Control Rod - A standard control rod is one having rack and pinion, electric motor drive, and scram capability. l l

1.5 Transient Control Rod - A transient control rod is one that is pneumatically operated and has scram i 1

capability, i l

1.6 ' Operable - A system or device is operable when it is capable of performing its intended fwctions in a normal  !

manner. I l

1.7 Cold Critical - The reactor is in the cold critical condition when it is critical with the fuel and bulk water temperatures the same (~ 40*C).

1.8 Steady-State Mode - The reactor is in the steady-state mode when the reactor mode selection switch is in the steady-state or automatic position. In this mode, reactor power is held constant or is changed on periods j greater than three seconds.

1 1.9 Souarc-Wave Mode - The reactor is in the square-wave mode when the reactor mode selection switch is in the square-wave position. In this mode, the reactor power is increased on periods less than one second, is held at constant power by automatic motion of the control rods, and is then reduced by shutting the reactor down.

1.10 Pulse Mode - The reactor is in the pulse mode when the rea: tor mode selection switch is in the pulse position.

In this mode, reactor power is increased on periods ofless than one second by motion of the transient control

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l 4.7 Suberitical Experiments and Fisc/ Storace Usina the Bulk Shielding Facility Applicability his specification applies to the surveillance requirements associated with the suberitical assembly and storage offieel elements in the bulk shielding facility, j l

Obiective To ensure safe operation of the subcritical assembly;. to ensure that the radiation momtoring equipment is operating properly, and that the pool level is maintainedfor radiation protection.

Specification a) The reactivity worth of the control rod shall be determined annually (interval not to exceed fifteen months).

He surveillance may be deferred indefinitely when the suberitical assembly is not being utilized, but shall be the first operation performed when the subcritical assembly is to be operated.

b) Control rod drop time shall be determined annually (interval not to exceed fifteen months). He drop time i from the fully withdrawn to 90 percent of full reactivity insertion shall be less than one second. The surveillance may be deferred indefinitely when the suberitical assembly is not being utilized, but shall be performed prior to operation of the assembly.

c) he radiation monitor utilized for a high radiation signal scram shall be calibrated and verified operable annually (interval not to exceed fificen months). The surveillance may be deferred indefinitely when the  ;

suberitical assembly is not being utilized, but shall be performed prior to operation of the assembly.

l d) Approximately 210 % of the fuel elements in the suberitical assembly. or in wet storage racks, shall be visually inspected annually for any indication of deterioration or distortion (interval not to exceed fifteen months) such that all of the elements in the-suberitical-essembly-are inspected over a f veren year period (interval not to exceed fiveten and one half years). If any indication of deterioration or distortion is noted the element shall be removed fronvservice to other storage and all elements in the Bulk Shieldmg Facility shall be inspected.within one week Other storage shall be any other apprm'edfuel storage area at the Nuclear

' Reactor Laboratory.-

e) The manual and high radiation scrams shall be verified operable daily prior to operation of the suberitical assembly. This specification is only applicable on days when the subcritical assembly is to be operated.

f) The Bulk Shielding Rueilitypool level shall be checked on a weekly (not to exceed ten days) basis.

Basis  ;

ne reactivity worth is measured to assure that control of the subcritical assembly can be maintained. The

control rod drop time verifies the scram capability of the control rod. Calibration and verification of the operability of the radiation monitor verifies the scram capability of the monitor. The visual inspection of the

- fuel elements specified had been shown to be adequate based on prior experience with a lack of fuel deterioration over time.

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-26a-4.7 Suberitical Experiments and Fuel Storage Usine the Bulk Shielding Facility Applicability his specification applies to the surveillance requirements associated with the subcritical assembly and storage of fuel el xnents in the bulk shielding facility.

Obiective To ensure safe operation of the suberitical assembly, to ensure that the radiation monitoring equipment is operating properly, and that the pool level is maintained for radiation protection.

Specification a) ne reactivity worth of the control rod shall be determined annually (interval not to exceed fifteen months).

He surveillance may be deferred indefmitely when the suberitical assembly is not being utilized, but shall be the first operation performed when the suberitical assembly is to be operated.

b) Control rod drop time shall be determined annually (interval not to exceed fifteen months). The drop time from the fully withdrawn to 90 percent of full reactivity insertion shall be less than one second. The surveillance may be deferred indefmitely when the subcritical assembly is not being utilized, but shall be performed prior to operation of the assembly.

c) he radiation monitor utilized for a high radiation signal scram shall be calibrated and verified operable

annually (interval not to exceed fifteen months). He surveillance may be deferred indermitely when the suberitical assembly is not being utilized, but shall be performed prior to operation of the assembly.

d) Approximately 10 % of the fuel elements in the suberitical assembly, or in wet storage racks, shall be visually inspected annually for any indication of deterioration or distortion (interval not to exceed fifteen months) such that all of the elements are inspected over a ten year period (interval not to exceed ten and one half years). If any indication of deterioration or distortion is noted the element shall be removed to other storage and all elements in the Bulk Shielding Facility shall be inspected within one week. Other storage shall be any other approved fuel storage area at the Nuclear Reactor Laboratory.

e) He manual and high radiation scrams shall be verified operable daily prior to operation of the suberitical assembly. His specification is only applicable on days when the suberitical assembly is to be operated.

f) The Bulk Shielding Facility pool level shall be checked on a weekly (not to exceed ten days) basis.

Basis The reactivity worth is measured to assure that control of the suberitical assembly can be maintained. He control rod drop time verifies the scram capability of the control rod. Calibration and verification of the L

operability of the radiation monitor verifies the scram capability of the monitor. He visual inspection of the fuel elements specified had been shown to be adequate based on prior experience with a lack of fuel deterioration over time.

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. 27-5.0 DESIGN FEATURES i 5.1 Reactor Fuel

- Appjicability L  ;

l' This specification applies to the fuel elements used in the reactor corefor a critical mass. ,

Obiective j i

The objective is to assure that the fuel elements are of such a design and fabricated in such a manner as to permit their use with a high degree of reliability with respect to their mechanical integrity.

Specifications

- a. Standard Fuel Element: The standard fuel element shall contain uranium-zirconium hydride, clad in 0.020 inch of 304 stainless steel. It shall contain a maximum of 9.0 weight percent uranium which has a maximum enrichment of 20 percent. There shall be 1.55 to 1.80 hydrogen atoms to 1.0 zirconium atom.

b. Low Hydride Fuel Element: This fuel element shall contain uranium-zirconium hydride, clad in 0.030 inch of aluminum or 0.020 inch of 304 stainless steel. It shall contain a maximum of 9 weight percent uranium which has a maximum enrichment of 20 percent. There shall be 0.9 to 1.54 hydrogen atoms to 1.0 zirconium atom.

c. Loading: The elements shall be placed in a closely packed array except for experimental facilities or for single positions occupied by control rods and a neutron start-up source Basis These types of fuel elements have a long history of successful use in TRIGA reactors.

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1 5.0 DESIGN FEATURES 5.1 R_eagtor Fuel Applicability l

This specification applies to the fuel elements used in the reactor core for a critical mass.

Obiective l

L The objective is to assure that the fuel elements are of such a design and fabricated in such a manner as to permit the ir use with a high degree of reliability with respect to their mechanical integrity.

I i . Specifications

a. Standard Fuel Element: The standard fuel element shall contain uranium-zirconium hydride, clad in 0.020 inch of 304 stainless steel. It shall contain a maximum of 9.0 weight percent uranium which l

I has a maximum enrichment of 20 percent. There shall be 1.55 to 1.80 hydrogen atoms to 1.0

! zirconium atom.

l b. Low Hvdride Fuel Eleme_nt: This fuel element shall contain uranium-zirconium hydride, clad in 0.030 inch of aluminum or 0.020 inch of 304 stainless steel. It shall contain a maximum of 9 weight percent uranium which has a maximum enrichment of 20 percent. There shall be 0.9 to 1.54 hydrogen atoms to 1.0 zirconium atom.

c. Loading: The elements shall be placed in a closely packed array except for experimental facilities

or for single positions occupied by control rods and a neutron start-up source.

Basis

- These types of fuel elements have a long history of successful use in TRIGA reactors.

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i 6.1.2 Staffina

a. %e minimum staffing when4he+eactor4seoteutdown<it the Nuclear Reactor Laboratory shall be: l

1. A4ieensed+eactorsperator-shallbein theeontrol+oom Reactor Administrator. This individual shall meet the requirements ofANSVANS-15 41988 "American National Standardfor the Selection and  :

1' raining ofPersonnelfor Research Reactors "for a Level Two individual. l 1

2.-A-second de:ignatedpersoneall be pre: cat inside the+eactor4mildingeble tohe n the reactor 4n an+mergency-Unexpected b ence4br+s4onges4wohours4eeccen=edateepersonalemergency mayhe-acceptabb precid:d-i==cdicto setion4s4aken4e+btain a repbcementReactor Heahh Physicist.

7his individual shall meet the requirements ofANSI'ANS-IS 4-1988 "American National Standard  ;

for the Selection and Training ofPersonnelfor Research Reactors "fbr a Level 1hree individualin addition to traming in health physics.

3--A-Senior-Reactor-Operator-shall befeadily available+n -call +s<lefmed in4he-Nuclear-Reactor Laboratory-Rules +nd4(egulations:

b. A list of reactor facility personnel by name and telephone number shall be readily available in4hewetrol room 4er-use by-the+peratorto the UlUC Division ofPublic Sality dispatcher. One ofthese individuals shall be reachable and able to respond to thefacihty within approximately one hour. The list shall

. include:

1. Op::ctions-SupervisorCampus Radiation Safety Ofliter l l

2. Reactor Administrator

! 3. Head, Department of Nuclear Engineering

4. Reactor Health Physicist

5. Licer. sed operators

c. Events requiring the presence at the facility of a Senior Reactor Operator:

l 1. Initial startup and approach to power.

2. All fuel or control rod relocations.-within4he+eactor-core +egion. l

3. Relocation of any in-core experiment with a reactivity worth greater than one dollar.

4. Recovery from unplanned or unscheduled shutdown or significant power reduction (In these instances, documented verbal concurrence from the Senior Reactor Operator is required).

l 6.1.3 Selection and Trainina of Personnel i

He Reactor Administrator is responsible for the training and requalification of the facility reactor operators and l

senior reactor operators. The selection, training, and requalification of operations personnel shall be consistent with cil current regulations and guidelines.

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- -3 2-6.1.2 Staffing l a. The sninimum staffing at the Nuclear Reactor Laboratory shall be:

l l 1. Reactor Administrator. His individual shall meet the requirements of ANSI /ANS-15.4-1988 l l "American National Standard for the Selection and Training of Personnel for Research Reactors" for a j l Level Two individual. l i

2. Reactor Health Physicist. This individual shall meet the requirements of ANSI /ANS-15.4-1988 ]

"American National Standard for the Selection and Training of Personnel for Research Reactors" for a j Level nree individual in addition to training in health physics. j l- I

b. A list of reactor personnel by name and telephone number shall be readily available to the UlUC Division of Public Safety dispatcher. One of these individuals shall be reachable and able to respond to the facility within approximately one hour. He list shall include:

! 1. Campus Radiation Safety Officer

2. Reactor Administrator l

L 3. Head, Department of Nuclean Engineering i

L 4. Reactor Heahh Physicist .

5. Licensed operators

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c. Events requiring the presence at the facility of a Senior Reactor Operator.

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1. Initial startup and approach to power.

2. All fuel or control rod relocations..

3. Relocation of any in-core experiment with a reactivity worth greater than one dollar.

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4. Recovery from unplanned or unscheduled shutdown or significant power reduction (In these instances,

! ' documented verbal concurrence from the Senior Reactor Operator is required).

6.1.3 Selection and Training of Personnel ne Reactor Administrator is responsible for the training and requalification of the facility reactor operators and senior reactor operators. De selection, training, and requalification of operations personnel shall be consistent with all current regulations and guidelines.

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• ' 34-l 6.2.3 Audit Function j f The audit function of the Reactor Committee shall include selective (but comprehensive) examination of l cgatinvecords, logs, and other documents. Discussions with cognizant personnel and observation of - '

. operauerwevohuions should be used also as appropriate. In no case shall the individual immediately responsible for the area perform an audit in that area. The following items shall be audited:

a.' Facility operations for conformance to the technical specifications and license, at least once per  ;

~ calendar year (interval between audits not to exceed 15 months). i t . . ..

b. The requalification program for the operating staff, at least every other calendar year (interval

. between audi:s not to exceed 30 months).  ;

c. The action taken to correct those deficiencies that may occur in the reactor facility .

equipment, systems, stmetures, or methods of operations that affect reactor safety, at least once per calendar year (interval between audits not to exceed 15 months). l

d. The reactor facility emergency plan, and implementing procedures at least once every other calendar year (interval between audits not to exceed 30 months).

Deficiencies uncovered that affect reactor safety shall immediately be reported to the Head, Department of h Nuclear Engineering. A written report of the 6ndings of the audit shall be submitted to the Reactor

! Committee within three months after the audit is completed and then forwarded to the Head, Department l ofNuclear Engineering.

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-3 4-e 6.2.3 Audit Fun _qtion The audit function of the Reactor Committee shall include selective (but comprehensive) examination of records, logs, and other documents. Discussions with cognizant personnel and observation of evolutions should be used also as appropriate. In no case shall the individual immediately responsible for the area perform an audit in that area. The following items shall be audited:

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a. Facility operations for conformance to the technical specifications and license, at lert once per l l

calendar year (interval between audits not to exceed 15 months).

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b. The requalification program for the operating staff, at least every other calendar year (interval between audits not to exceed 30 months).

c. The action taken to correct those deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operations that affect reactor safety, at least once per calendar year (interval between audits not to exceed 15 months).

d. The reactor facility emergency plan, and implementing procedures at least once every other calendar year (interval between audits not to exceed 30 months).

Deficiencies uncovered that affect reactor safety shall immediately be reported to the Head, Department of Nuclear Engineeriag. A written report of the findings of the audit shall be submitted to the Reactor Committee within three months after the audit is completed and then forwarded to the Head, Department of Nuclear Engineering.