ML20065N197
| ML20065N197 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 11/30/1990 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20065N202 | List: |
| References | |
| NUDOCS 9012120017 | |
| Download: ML20065N197 (7) | |
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UT TRIGA-Requalification: Plan ~
. Docket 50 602 r
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.i Revision 1 November 1990-3 r
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' Nuclear Engineering Teaching Laboratory 1.:
- Balcones 'Research: Center The University of Texas at Austin a
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!9012120017 901119 p
L'hDR-ADOCK 05000602 PDC i
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UT TRIGA Reactor Operator Requalification Plan
'1.0 Introduction Reactor operator requalification applies to all the controls and some features of the TRIGA reactor at The University of Texas at Austin (UT),
Balcones Research Center (BRC).
The purpose of this plan is to provide.
training of each individual that is to qualify for a license to operate or direct the operation of the TRIGA reactor.
There are two license classes, one is an. operator and the other is-a senior operator.
License qualification by written and operating test,' and 14. cense issuance or vemoval, are the responsibility of the U.S. Nuclear Regulatory Commiss.lon.
No rights of the license may be assigned or otherwise transferred and ;he licensee is subject to and shall observe.all rules, regulations and orders r,f the Commission.
Requalification training maintains the skills-and knowledge of operators and
' senior operators during the period of the license. Training also provides for the initial license qualification.
1.1 Operator License Status Active status of any licensee shall-require the -performance of' the functions'of an operator or senior operator for a minimum of four hours each calender quarter.
If the. condition of-an active license status is not met, the
. Director of the facility shall certify, (1)-that the qualifications and status of the licensee are current and valid,.and (2) that for.recertification a.
minimum of six hours of license functions have been done.
The license functions shall be done with supervision of tho' appropriate operator or senior operator. Otherwise the license status shall be. inactive and no functions of the license shall be done.
1.2
.Requalification Program Bases-Regulatory requirements and standards provide guidance for.
requalification training.'.SpecificLregulatory requirements are.found in 10CFR55 for the Llicensing of operators and senior. operators with regulations for=requalification set forth in section i3.59.
Standar'ds for the selection L
and training of facility personnel and: reactor operators are available in ANS' 15 4.
Specific regulations in the: form of two sets of license conditions al 2
-apply to the facility personnel and reactor operators.
One set _ of condition,.
for the facility license, 10CFR 50.54, applies to facility personnel. ~The otherfset of conditions.for' individual licenses,.10CFR 55.53 applies to
. operators and senior operators. The following plan 1 documents the requalification of operators and senior operators for the UT BRC TRICA reactor Jfacility.
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2.0 Requalification Program The requalification program consists of training personnel by lectures, instruction, discussion and self study.
At times the number of operators with licenses may be as few.as 1 or 2.
In these circumstances the application of
' discussion and self study methods are necessary to accomplish the training process.
2.1 Schedule Lectures.from the requalification program topics and on the job training will be done on a two year cycle for the completion of all requirements. The part of the program done each year will consist of six lectures, two on the job training activities, and the performance of sixteen hours 'of license functions.
Lectures or instruction on the topics of the requalification program consist of eight topics shown in section 2.2.
Three lectures will be given each six months so that during the year there is an average of one topic presentation every two months.
Each of the eight topics will occur during the two-year cycle with four topics each year. The other two lectures each year are available for special_ subjects, _ repeat subjects or review.
.On the job training relies on two specific reactor control manipulations to be_done each year.
These control _ manipulations will consist of startup, shutdown, operation, coolant loss, loss of control _ rod pneumatic air or electrical power events, and_ other system malfunctions.
The two control manipulations will require a change in system reactivity and will use events from each of the_two lists in section 2.3.
One event from the list of section 2,3.1 must be done each year and one event from the list of section 2.3.2 must be done each two years.
A program of less than two years duration may
- accelerate the training of persons for new operator certification.
2.2 List of Subjects 2.2.1l(A) Theory and principles of operation,
- 2.2,2 (B) General and specific plant operating characteristics, 2.~2.3-(C) Plant instrumentation and control systems, 2.2.'4- (D) Plant protection systems.and Engineered safety systems.
2.2.5 (E) Normal, abnormal, and emergency. operating procedures.
2,2.6 (F) Radiation control'and safety.
2.2.7.(G) Technical. specifications.
2.2.8 (H)_ Applicable' portions of Title 10, Chapter I.. Code of Federal Regulations.
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2.3 On the job training:
2.3.'1 List of annual training tasks; (one must be done each year):
2.3.1.1 Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable and.heatup rate-is established.-
2.3.1.2 Plant shutdown.
2.3.1.3 Significant (>10 percent) power changes in manual rod control.
2.3.1.4 Loss of coolant inside or outside primary confinement.
2.3.1.5 Loss of. coolant, large or small,-including leakrate estimate.
2.3.1.6 Loss of control air (or inadequate pressure).
2.3.1.7 Loss of electrical power (or degraded power sources).
2.3.1,8 Loss of core coolant flow / natural circulation.
2.3.2 List of training tasks; system malfunctions (one must be.done each two years):
2.3.2.1 Reactor trip.
2.3.2.2 A nuclear instrumentation failure.
2.3.2.3 Loss of protective. system channel.
2.3.2.4 Control rod or drive failure such as rod position error, rod drop
-or stuck drive, mispositioned control rod or rods (or rod drops),
Inability to drive control rods.
2.3.2.5 Puel cladding failure or high activity in reactor coolant or:
offgas.
2.3.2.6 Malfunction of an automatic control system that affects reactivity.
2.5.3 On-the job-training ~ will perform the following periodic training checks or-functions.
2.3.3.1 Observation at least once each year of a satisfactory understanding of the reactivity control system and knowledge of operating procedures.
2.3.3,2 Each operator or senior operator will review facility design changes, procedure changes and license changes as they occur or l
once each 6 to 8 months.
l 2.3.3.3 A review of the contents of abnormal and emergency procedures
-will be done by each operator.or senior operator at 6 to 6 month intervals so that at least 3 reviews occur during the two year training cycle.
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l 2.4 Evaluation Evaluation of license personnel depends on annual examination and periodic observation. The evaluation by annual written examination determines the knowledge level and requirements for retraining by a percentage test score.
Other evaluations by visual observation assess the performance and competency with routine procedures and the skill at manipulating the controls of the reactor.
The written annual examination will assess operator or senior operator knowledge of current training subjects end review requirements. A five part test with objective questions will assess the knowledge of four of the eight program subjects, and the areas of section 2.3.3.2 and 2.3.3.3.
These two sections pertain to changes in facilit;r design, normal procedures, reactor license, and abnormal and emergency precedures.
Each of the five parts of the exam will have a 100 point basis with an average of 80% as the acceptance udieria.
An overall score of less than 65%
shall require an immediatr, evaluasten of license duties. Proficiency by retraining shall demonstrate acceptance within 4 months or license duties shall suspend until proficiency is acceptable. A person that scores between 65%-80%
shall retrain as necessary in those areas that written or oral exams indicate a deficiency.
A systematic observation of license activities, by a supervisory senior operator or a level of the facil'.ty management to which a supervisory operator is responsible will evaluate cperator and senior operator performance.
Visual observation of the performance in response to the conditions of sections 2.3.1 and 2.3.2 will provide the basis for judgement of the operator's skill.
In the case of a senior operator the performance may be either direct actions or the direction of a response by another operator. Judgements of a person's skill or competency is subjective and may include general observations of performance at any time the person is responsible for license functions.
2.5 Records Records for each operator or senior operator will consist of the documentation for the requalification activities within the two year training cycle.
The records will be kept until the completion of the next training cycle.
A record for each operator includes at least the following information:
- Attendance at training lecture or acceptable review of the material, including topic and date
- Completion, satisfactorily, of two on the-job training events with performance evaluation; recording date and performance as exec 11ent, average or poor.
- Total # of reactor control system hours and energy production in each calender quarter.
- Scores of the written examination and copics of the exam questions, answers, and responses by personnel.
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~2.6" Tra'.ning Coordinator
' Exemption status for supervisory senior operator.
The person who writes, grades, and administers. the exam and on the-job training events is a reactor supervisor or a supervisory senior operator, The reactor supervisor or supervisory senior operator as the person that coordinates training and examination will not take the annual exam.
Several factors will allow for the exemption of that person from the regular evaluation and~ exam' process.
These factors are the educational experience of a graduate degree in the field of nuclear engineering, daily involvement in performance or review of activities of reactor operation, participation in the training program, preparation of examination material, and evaluation of exam questions.
Evaluation of the reactor supervisor or a supervisory senior operator will, however, be done as part of the routine management responsibilities of the facility director.
This will iriclude certification that the person is performing an active role in training, operation and teaching at the UT BRC TRICA facility.
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Exampla Record Sheet Requalification Record UT BRC TRICA Name:
Year _
Topic:
Date ********
1 A B C D E F G 11 2
A B C D E F GJ 3
A B C D E F G 11 4
A B C D E F G H 5
A B C D E F G 11 6
A B C D E F G ll Events' Performance:
Excellent Acceptable Poor Date 1
E A
P 2
E A
P Examination:
Total Part 1 Part 2 Part3 Part 4 Part 5 Q1 Q2 Q1 9/1 Total Hours:
MW-hours License status:
Comments: (corrective training) inactive;
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retrain complete Evaluation Acceptance:
initial date 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> supervision Supervisory Senior Operator initial date active:
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Date
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