ML20206S009

Proposed Tech Specs for Univ of Il Research Reactor

ML20206S009
Person / Time
Site:	University of Illinois
Issue date:	05/11/1999
From:	ILLINOIS, UNIV. OF, URBANA, IL
To:
Shared Package
ML20206S007	List: ML20206S001 ML20206S009
References
NUDOCS 9905210030
Download: ML20206S009 (8)

Text

e Revised Technical Specifications With Revision Marks i

9905210030 990511 PDR P ADOCK 05000151 pop

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6.4 Procedures Written procedures shall be prepared, reviewed and approved prior to initiating any of the activities listed in this section. The procedures shall be reviewed by the Reactor Committee and approved by the Reactor Administrator and such review and approval shall be documented in a timely manna. The procedures shall be adequate to assure the safety of the reactor, but should not preclude the use ofindependent judgment and action should the situation require such.

a. Staitup, operation, and shutdown of the reactor, b.' Installation or removal of fuel elements, control rods, experimmts, and experimental -

facilities.

c. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components,

including responses to alarms, suspected primary coolant leaks, and abnormal reactivity changes.

d. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, reentry-entry, recovery, and medical support.

e. Maintenance procedures which could have an effect on reactor safety.-

f. Periodic surveillance of reactor instrumentation and safety systems, area monitors an'd -

continuous air monitors.

g. Personnel radiation protection, consistent with applicable mgulations or guidelines. The procedures shall include management commitmmt and programs to maintain exposures and releases As Low As is Reasonably Achievable (ALARA).

h. Intp:ementation of physical security plan I t. Those procedures necessary to safely maintain thefadlity during the S4F570R period and decommissioning. This shallinclude a pertoibc physical check ofthe support 9 stems and equipment uithin thefacility to be defined by the weekly and quarterly surveillance checklists. -

Substantive changes to the above procedures shall be made only after documented review by the Reactor Committee and approval by the Reactor Administrator. Minor modifications to the original procedures which do not change their original intent may be made by the Reactor Administrator. Temporary deviations from the procedures may be made by the responsible Senior Reactor Ope ator or higher individual present, in crda to deal with special or unusual circumstances or conditions. Such deviations shall be documented and reported to the Reactor Administrator.

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Written procedures shall be prepared, reviewed and approved prior to initiating any of the activities listed in this section. The procedures shall be reviewed by the Reactor Committee and approved by the Reactor Administrator and such review and approval shall be documented in a timely manner. The procedures shall be adequate to assure the safety of the reactor, but should not preclude the use ofindependent judgment and action should the situation require such.

a. Startup, operation, and shutdown of the reactor.

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b. Installation or removal of fuel elements, control rods, experiments, and experimental facilities.

c. Actions to be taken to wrrect specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary coolant leaks,and abnormal reactivity changes.

d. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, reentry-entry, recovery, and medical support. 1

e. Maintenance procedures which could have an effect on reactor safety. )

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f. Periodic surveillance of reactor instrumentation and safety systems, area monitors and J continuous air monitors.

g. Personnel radiation protection, consistent with applicable regulations or guidelines. The procedures shall include management commitment and progrrms to maintain exposures and releases As Low As is Reasonably Achievable (ALARA).

h. Implementation of physical security plan

i. Those procedures necessary to safely maintain the facility during the SAFSTOR period and decommissioning. This shall include a periodic physical check of the support systems and equipment within the facility to be defined by the weekly and quarterly surveillance checklists.

Substantive changes to the above procedures shall be made only after documented review by the Reactor Committee and approval by the Reactor Administrator. Minor modifications to the original procedures which do not change their oiiginal intent may be made by the Reactor Administrator. Temporary deviations from the procedures may be made by the responsible Senior Reactor Operator or higher individual present, in order to deal with special or unusual circumstances or conditbns. Such deviations shall be documented and reported to the Reactor Administrator.

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. 6.8 ina Reauirements  :

i; in addition to the requiremets of applicable regulations, and in no way substituting therefore, reports shall be made to the USNRC as follows:

. ' a. ihere shall be a report not later than the following working day by telephone and confirmed in writing by.

facsimile or similar conveyance to the Project Manager, USNRC Headquarters to be followd by a l written report that describes the circumstances of the event within 14 days to the Document Control g Desk, USNRC Headquarters of any of the following:

1. Release of radioactivity from the site above allowed limits.

2. Violation of safety limits.

3.' Any significant variation from measured values from a corresponding predicted or previously measured value of safety-connected operating characteristics occurring during operation of tM reactor.

' 4. Incidents or conditions relating to operation of the facility which prevented or could have prevented the performance of engineered safety features as described in these specifications.

5. Any abnormal occurrences as defined in Section 1.14 of these specifications.

b. A report within 30 days (in writing to the Document Control Desk, USNRC Headquarters) of:

l. Any substantial variance from performance specifications contained in these specifications. .

2. Significant changes in the transient or accidert analysis as described in the Safety Analysis Report.

3. Permanent changes in the facility organization involving the Reactor Health Physicist, Reactor Administrator or Department Head,

c. A report within 60 days after criticality of the reactor (in writing to the Document Control Desk, USNRC Headquarters) upon receipt of a new facility license or an amendment to the license authorizing an incr ease in reactor power level or the installation of a new core, describing the measured values of the  ;

operating conditions or characteristics of the reactor under the new conditions, including:

1. Total control rod reactivity worth.  ;

2. Reactivity worth of the single control rod of highest reactivity worth.

3. Total and individual reactivity worths of any experiments inserted ir. the reactor.  ;

4. Minimum shutdown margin both at room and operating temperatures.

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Revised Technical Specifications .

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j 6.8 Reportma Roenirements i

In addition to the requirements of applicable regulations, and in no way substituting therefore, reports shall be made to the USNRC as follows: I

a. _ There shall be a report not later than the following working day by telephone and confirmed in writing by facsimile or similar conveyance to the IMj n ' ^ ' - 2:, USFC, P_:g:- !!! - ' k US!=.C

' ^ , T:; _,- _ 2: :eeneer-ProjectManager, USNRCfleadquarters to be foiIowed by a written ~

report that describes the circumstances of the event within 14 days to the Document Control Desk, l.

USNRC Headquarter::, .d: ::py ic h P:g:r' 'N-5:::, UEh".C, P:j:- !!! of any of the l i-following:

1. Release of radioactivity from the site ebove allowed limits.

2. Violation of safety limits.

3. Any significant variation from measured value. f.m a corresponding predicted or previously .{

measured value of safety-connected operating characteristo curring during operation of the -

reactor. -

4. Incidents or conditions relating to operation of the facility which prevented or could have prevented the performance of engineered safety features as described in these specifications.

5. Any abnormal occurrences as defined in Section 1.14 of these specifications.

b. ' A report within 30 days (in writing to the Dccument Control Desk, USNRC Headquarters) of: ' )

1. Any substantial variance from performance specifications cmtained in these specifications.

2. Significant changes in the transimt c accident analysis as described in the Safety Analysis Report.

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3. Permanent changes in the facility organization involving the Reactor Health Physicist, Reactor Abinistrator or Departmont Head.

c. A report within 60 days aAer criticality of the reactor (in writing to :he Document Control Desk, USNRC  ;

Headquarters) upe receipt of a new facility license or an amendment to the license authorizing an i increase in reactor power level or the installatian of a new core, describing the measured values of the j

p;rathg ccadous or chsracteristics of the reactor under the new conditions, including-

1. Tes! control rod reactivity worth.

2. Reactivity worth ofihe single control rod of highest reactivity worth.

3. Total and individual reactivity worths of any experiments inserted hi the reactor.  ;

4. Minimum shutdown margin both at room and operating tempcratures. l I

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p'.. g Operations Weekly Checklist Licensed Operator g Date Building Walk Through Truck door Closed Emergency Exit Locked Closed Truck Bay Storage Pits locked Storage Cage Locked Fuel Present Physical Plant Check _

Beam Ports: Shut & Locked _,

Primary Aux. Cooling Pump On Primary Tank Heater On Air System: Accumulator Dryer Compressor tank Check Compressor Oil Mechanical Equip. Room Check Radioactive Waste Storage Area Check BST Visual Check / water level Primary Tank Visual Check / water level BST Purification Pump On Primary Tank Fuel Check BST Fuel Checks Run Lazy Susan 3 min.

Conunents -

Purification System [< 16 psid]

Filters: Purification inlet pressure Outlet pressure _

Flowmeter reading .,BST Pump Disch psig BST Filter Out psig BST Fine Filter: Inlet Pressure psig Outlet Pressure psig Conductivity Local Reading Purif. Sys. (< 4 S/cm) Inlet Outlet .

BST Purif. (< 4 S/cm) Inlet Outlet ]

City Wtr. (< 2 S/cm) Outlet

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i Intrusion Alarm Operational check satisfactory Sensor Checked Reviewed by Reactor Administrator Reactor Administrator (or designated alternate) l l

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7 Envirnamental Report on the SAFSTOR Status of the University of Blinois Nuclear Reactor laboratory The University of lilinois Nuclear Reactor Laboratory is located at the North end of the University ofIllinois At Urbana-Champaign unpus. The Nuclear Reactor Laboratory building houses the Advanced TRIGA reactor and offices for reactor personnel only. The .

University of Illinois Advanced TRIGA reactor was a 1.5 Megawatt research reactor utilized '

for research ad instructional purposes between 1960 and 1998. The decision was made in i1998 to permanently shutdown the reactor.

A decommissioning plan was submitted on November 13,1998 to the Nuclear Regulatory

Commission stating that the University ofIllinois would employ the SAFSTOR option due to the inability to ship the TRIGA fuel for the foreseeable future. Decommissioning utilizing the SAFSTOR option will consist of transfering the majority of the fuel to the Bulk Shielding

- Facility to facilitate inspections and monitoring of the facility on a routine basis until such time that the fuel can be shipped.

There have been no major contamination events at the Nuclear Reactor Laboratory. There is no intent to transfer any radioactive material out of the building until such time that the fuel is shipped and a final decommissioning plan is accepted. Any use of the facility other than that necessary for SAFSTOR and maintaining of offices for the Reactor Administrator and Reactor Health Physicist will be evaluated by the Reactor Administrator and/or the Reactor Committee for any effect on the SAFSTOR status of the facility.

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The controls and limits on procedures and equipment to protect occupational and public health and safety that were utilized during reactor operation will continue during the SAFSTOR period. Since the reactor is no longer in operation, and byproduct material no longer being produced or handled, the radiation exposure to the staff and public will be minimized during the SAFSTOR period. Occupational and public dose commitment during the SAFSTOR period should be less than 100 mrem per year. Typical dose commitment, as reported in the annual teport, to the public at the site boundary is less than 2 mrem per year. Occupational dose committment on average is typically less than 50 mrem per year.