ML20058L076
| ML20058L076 | |
| Person / Time | |
|---|---|
| Site: | 05000356, University of Illinois |
| Issue date: | 07/26/1990 |
| From: | ILLINOIS, UNIV. OF, URBANA, IL |
| To: | |
| Shared Package | |
| ML20058L075 | List: |
| References | |
| NUDOCS 9008060180 | |
| Download: ML20058L076 (9) | |
Text
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College of Enginwring
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214 Nuclear Engineering 217 333 2295 Laboratory -
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Urbana, IL 618012964 I
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.t OPERATOR REQUALIFICATION PROGRAM
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t OPERAIQRlEQUAL1FlCATION_PitQGRAM The following is a general outline designed to meet the requalification requirements of 10CFR56 dated 1-1-89.
The term " operator" is generally meant to include both senior operators and operators.
Ganaral Provisigns A. Imnlamentation:
A program of continuous training of personnel who have a current Senior Operator or Operator license will be followed.
B Administration:
- 1. The Reactor Supervisor, or a designated alternate, is in charge of supervising the program and specif ying scheduled times for meetings and tests, t
- 2. Records on attendance to lecture or discussionperiods are recorded for each meeting.
Evaluations of individual performance will be included in an individual summary.
- 3. The individual in charge of the evaluatic,n is exempt f rom taking tests for the purpose of the individual evaluation.
Raoualification pronran r
A. Oneration N) i:ach licensee shall actively perform the functirris of en operator or senior operator for a minimum of four hours por calendar quarter.
These functions shall include, but not be limited to:
completion of the daily checklist, startup from l
shutdown to 15 watts, changes in power level above 10 kilowatts in both natural and forced convectivo cooling, operation of either square wave or pulsed transients, a*)d the shutdown of the reactor with the completion of the shutdown checklist.
(2) If paragraph (1) of this section is not met then the Reactor Supervisor, or his designated alternate, shall verify that the operator's license is current and valid.
The operator shall also complete a minimum of six hours of operations under the supervision of an operator or senior operator as appropriate.
During this period the operator shall perform all requirements of paragraph (1).
(3) An annual operating test shall be administered by the Reactor Supervisor, or his designated alternate, on each operator such L
that the requirements of 10CFR55.45(a)2 thru 13 are met (see attachment A).
A written evaluation shall be documenteo.
If the examiner deems it necessary an upgrading program shall be developed to correct any deficiencies.
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i B. Lecture and Diteuttion Periodt (1) An annual review of the emergency procedures, abnormal occurrences, energency plans and the building security plan shall be made.
1 (2) As changes occur each licensed operator shall be made cognizant of facility des 1gn changes, facility procedure changes, approved experiments, and facility license changes.
(3) Each licensed operator shall demonstrate satisfactory understanding of the operation of the apparatus and mechanisms associated with the control manipulations required during the annual operating test and knows the operating procedures in each area.
(4) Lectures shall be given in those areas where examinations and operator experience have indicated that emphasis in scope and depth of coverage is needed for all operators.
The Reactor Supervisor is responsible for identifying such areas.
D. Evaluation (1) A comprehensive requalification exam similar in scope to the NRC licensing exam shall be given such that the requirements of Title 10 Code of Federal Regulations Part 55.59.a.2.1 are met (see Attachment C).
Evaluation of examination results shall be as follows:
t (1) Less than 70% on the overall examination will result in a termination of any licensed duties until the ability of the individual is shown to be adequate from further examinations after the completion of an upgrading crogram.
l (ii) tess than 804 in any area on the exam will requtre that the operator participate in an upgracing program.
l F, On-The-Job Trainina Each licensed operator or senior operator of the facility shall manipulate the plant controls during the term of the operator's license.
These manipulations shall consist of the con' trol I
manipulations and plant evolutions required by 100FR$5.59(a)(3)
E as they are applicable to plant design.
Items (A) through (L) are required on an annual basis, all other items must be performed on a two year cycle (see Attachment B).
E. Vooradina In the event that an upgrading program is necessary for an operator due to results of the annual operating exam or the biennial written exam then a written acceleratea tra1ning program shall be developed.
This training program shall address the
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deficiencies that were noted and shall specify requirements for completion of the upgrading program.
F. Escords (1) The following records shall be kept for the period of each individual operators 11 cense.
(1) Copies of written exams administered and answers given.
(ii) Annual evaluations / operating tests.
(iii) Upgrading programs issued to a specific operator to ccrrect deficiencies.
(iv) Lecture and discussion periods including attendance and subject material covered.
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I Attachment A The following is a list of those items required to be covered on the annual operating test by 100FR$$.45(s)2 thru 13 dated 1-1-89.
(2) Manipulate the console controls as required to operate the facility l
between shutdown and designated power levels.
(3) Identify the annunciators and condition-indicating signals and perform appropriate remedial actions where appropriate.
I (4) Identify the instrumentation systems and the significance of facility instrument readings.
($) Observe and safely control the operating behavior characteristics of 1
the facility.
(6) Perform control manipulations required to obtain desired operating results during normal, abnormal, aad emergency conditions.
(7) Safely operate the facility's head removal systems, including primary coolant, emergency coolant, and decay heat removal systems, and identify the relations of the proper operation of these systems to the operation of the facility.
(6) Safely operate the facility's auxiliary and emergency systems, including operation of those controls associeted with plant equipment that covid affect reactivity or the release of radioactive rc.cterials to the environment.
(9) Domonstrate or describe the use and function of the f acility's radiation moritoring systems, including fixed radiation monitors and j
alarms, port 6ble survey instruments, and personnel monitoring equipment, i
(10) Demonstrate knowledge of significant radiation hezards, including permissible levels in excess of those authorized, and soility to perform other procedures to reduce excessive levels of radiation and to guard against personnel exposure.
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(11) Demonstrate knowledge of the emergency plan for the facility, i
including as appropriate, the operator's or senior operator's I
responsibility to decide whether the plan should be executed and the j
duties under the plan assigned.
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(12) Demonstrate the knowledge and ability as appropriate to the assigned position to assume tne responsib111 ties associated with the L
safe operation of the facility, i
(13) Demonstrate the applicant's ability to function within the control room team as appropriate to the assigned position in such a way that the facility licensee's procedures are adhered to ano that the limitations in its license and amendments are not violated.
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Attachment B The following is a list of those items required to be covered by 100FR55.59(a)(3), dated 1-1-89, during the requalification period.
Items (A) through (L) must be performed on an annual basis, all other
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ltems must be performed on a two-year cycle.
Items with an asterisk are not applicable to the TRIGA/LOPRA facility.
(A) Plant or reactor startups to include a range that reactivity l
feedback from nuclear heat addition is noticeable and a heatup rate is established.
(B) Plant shutdown.
- (C) Manual control of steam generators or feedwater or both during startup and shutdown.
- (D) Boration or dilution during power operation.
(E) Significant ( >10% ) power changes in manual rod control or recirculation flow.
- (F) Reactor power change of 10 percent or greater where load change is performed with load limit control or where flux, temperature, or speed control is on manual (for HTGR).
(0) Loss of coolant, including --
(1) Significant PWR steom generetor leaks.
(2) Inside and outsius primary containment.
(3) Large and small, includin.g leak-rate datermination.
(4) Saturated reactor coolant response (PWR).
(H) Loss of instruinent air.
(1) Loss of electrical power (or degraded power sources).
(J) Loss of core coolant flow / natural circulation.
- (K) Loss of feedwater (normal and emergency).
(L) Loss of service water if required for 9A f.
- (M) Loss of shutdown cooling.
- (N) Loss of component cooling system or cooling to an individual component.
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Attachment B (cont)
(Q) Loss of protective system c.hannel.
(R) Mispositioned control rod or rods (or rod drops).
(S) Inability to drive control rods.
(T) Conditions requiring use of emergency boration or standby liquid control system.
(U) Fuel cladding failure or high activity in reactor coolant or offgas.
- (V) Turbine or generator trip.
(W) Malfunction of an automatic control system that affects reactivity.
(x) Malfunction of reactor coolant pressure / volume control system.
(Y) Reactor trip.
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- (2) Main steam line break (inside or outside containment),
j (AA) A nucioar instrJmentation failure, l:
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ATTACHMENT C The following is a list of those items required by 10CFR55.59.4.2.1 for annual written examinations. These items are those in 10CFR55.41 and 10CFR$5.43 that are applicable to the University of Illinois TRIGA.
The written exam for an operator shall include a representative sample from among the following 14 items:
(1) Fundamentals of reactor theory, including fission process, neutron multiplication, source effects, control rod effects, criticality indications, reactivity coefficients, and poison effects.
(2) General design features of the core, including core structure, fuel elements, control rods, core instrumentation, and coolant flow.
(3) Mechanical components and design features of the reactor primary system.
(4) Secondary coolant and auxilary systems that affect the facility.
(5) Facility operating characteristics during steady state and transient conditions, including coolant chemistry, causes and effects of temperature. pressure and reactivity changes, effects of load changes and operating limitations and reasons for these operating l
characteristics.
(6) Design, components, and functions of reactivity cor,t.rol mochani ms and instrumentation.
(7) Design, components, and functions of control and safety systems, including instrumentation, signals, interlocks, f ailure modes, and automatic and manual features.
j (8) Components, capacity, and functions of energency systems.
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(9) Shielding, isolation, and containment design features, incluaing access limitations.
(10) Administrative, normal, abnormal, and emergency operating procedures for the f acility.
(11) Purpose and operation of radiation monitoring systems, including alarms and survey equipment.
(12) Radiological safety principles and procedures.
(13) Procedures and equipment available for handling and disposal of radioactive materials and effluents.
(14) Principles of heat transfer thermodynamics and fluid mechanics.
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ATTACHMENT C (coni, The written examination for a senior operator will contain a representative select 1D of questions from among the following seven items and from the 14 items previously listed for operators:
(1) Conditions and limitations in the facility license.
(2) Facility operating limitations in the technical specifications and their bases.
(3) Facility licensee procedures required to obtain authority for design and operating changes in the facility.
(4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.
(6) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.
(6) Procedures and limitations involved in alterations in core configuration, and determination of variouc internal and external effects on core reactivity.
(7) Fuel handling facilities and procedures.
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July 11, 1990 l
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