ML20149G836
| ML20149G836 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 11/08/1993 |
| From: | MARYLAND, UNIV. OF, COLLEGE PARK, MD |
| To: | |
| Shared Package | |
| ML20149G799 | List: |
| References | |
| PROC-931108, NUDOCS 9411080094 | |
| Download: ML20149G836 (10) | |
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Reactor Operator Requalification Program for MARYLAND UNIVERSITY TRAINING REACTOR November 8,1993 1
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L PURPOSE This document sets forth the requirements for the Reactor Operator (RO) and Senior Reactor Operator (SRO) requalification program for the Maryland University Training Reactor (MUTR), in accordance with the Code of Federal Regulations, Title 10, Part 50.54, Condition of Licenses.
II. SCHEDULE The operator Requalification Program cycle will last a period of two years, beginning on the first quarter of the biennial year. The licensed operator will enter the requalification program on the date the USNRC issues a license and will continue in the program until either the expiration date of the current license or the date the current license is terminated. If the operator should receive his/her operating license no greater than six months prior to the completion of the two year cycle, the operator will be exempt from completing the requirements of the current program, but will be required to enter the following requalification program cycle.
If the operator should receive his/her operating license greater than six months prior to the completion of the cycle, the operator will not be required to complete those program requirements required prior to the issuance of the license.
III. REACTOR OPERATION The operator will be required to perform, as either a Reactor Operator or Senior Reacter Operator, a minimum of ten reactor startups during the two-year requalification cycle. The operator must also perform a minimum of four hours per calendar quarter in his/her capacity as a licensed RO or SRO whichever is applicable.
For an SRO, the time devoted to the facility as an "On call" SRO can not be utilized to fulfill the four-hour mandate. These four hours must be recorded while performing direct supervision of the facility.
In the event that an operator does not meet the four hour minimum per calendar quarter the license shall be considered inactive under the terms set forth in 10CFR55.53(e).
In order for the license to be returned to active status, the licensee shall perform six hours of operation supervised by the Reactor Director or his/her designee under the terms prescribed under 10CFR55.53(f).
IV. REQUALIFICATION PROGRAM As part of the requalification program, licensed personnel will participate (as determined by the Reactor Director) as either a student or an instructor. The program will be on a continuing basis throughout the requalification cycle in those areas where annual operator and senior operator written examinations indicate that emphasis in scope and depth of coverage is needed in the following subjects:
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A) Theory and principle of operation B) General and specific plant operating characteristics C) Reactor instrument and control systems D) Reactor protection systems E) Engineered safety systems F) Normal, abnormal, and emergency operating procedures G) Radiation safety and control H) Technical Specifications I) Applicable portions of Code of Federal Regulations Title 10, Chapters 0, 19,20,21,26,51,54,55,71 H) Applicable portions of the Atomic Energy Act (1974-08)
Additionally, a series of lectures / seminars will be conducted throughout the requalification cycle, the frequency of which to be determined by the Reactor Director or his designee. The purpose of these lectures / seminars is to serve as refresher courses for currently licensed RO and SRO's as well as training and instruction for RO and SRO traince's. These lectures will be on a single topic (or related topics)in the areas outlined above, and will be of an average length of 30 to 35 minutes. It will be the responsibility of each licensee and trainee to review the material presented in every topic. This should be accomplished by attending the formal lectures, or, failing that, reviewing the subject matter on an individual basis. Portions of these requirements may be satisfied (as determined by the Reactor Director) by the licensed operator's participation in either ENNU 320, Nuclear Reactor Operations, as a student or instructor, or in the instruction and/or training of students for the NRC license, or both. See Appendix I V. EVALUATION The evaluation of the licensee's knowledge and performance of the requirements set forth in the requalification program will be accomplished by a written and oral examination, including a demonstration at the reactor console.
These will be administered annually to each licensed operator. The written examination for the reactor operator will be prepared in accordance with the modified requirements of USNRC Examiner Standard ES-606, dated 09/01/91, Administration of NRC Requalification Examinations at Non-Power Reactors (NPRs), which is included in this standard as Appendix II.
The oral examination and console performance evaluation will be administered by the Reactor Director, or his designee.
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If a license holder scores less than 70% on any section of the annual written examination, the licensee will attend a makeup session on that section topic and will be administered as a quiz. An overall grade of 80% will be required as a passing score.
If an individual receives a grade ofless than 80% overall, it will be mandatory that he be relieved of his licensed duties and enter an accelerated requalification program.
Upon successfully passing a second written examination and certification of satisfactory rating by the Reactor Director, the individual may return to his licensed duties.
An unsatisfactory evaluation on the annual oral examination will require that discussions of deficiencies take place between the licensee and the Reactor Director or other suitable qualified person designated by the Director. A second oral evaluation will be administered. If performance is again unsatisfactory, the licensee will be relieved of responsibilities and placed into an accelerated requalification program.
VI. ACCELERATED REQUALIFICATION PROGRAM The additional training that a licensee may require (as indicated by his examination) will consist of additional written exams, console performance, or oral facility examination. The additional training and the examination that the licensee receives will depend upon the weaknesses exhibited on previous examinations. The number oflectures and examinations that a licensee will receive will be determined by either the Reactor Director or his designee, the licensee must obtain a rating of at least 80% on the re-evaluation in order to be reassigned to his licensed duties.
VIL DOCUMENT REVIEW The licensee will review during each requalification cycle the following documents and instructions that are pertinent to the operations of the reactor facility:
- 1. Reactor License (R-70)
- 2. Technical Specifications
- 3. MUTR Operating and Emergency Procedures
- 4. Code of Federal Regulations, Title 10, Cbapters: 19, 20, 50.54, 50.59, 55 VIIL RECORDS The following records will be maintained for each licensed operator and retained for the period until the license of the individual has expired or been terminated:
- Current copy of either the licensee's Reactor Operator or Senior Reactor
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i Operator license.
- Copies of the graded requalification examinations administered.
- The operator's Requalification Program checklist.
- The summary of training received by the licensee in the accelerated Requalification Program documented in a memorandum for record and any additional documentation that is pertinent to additional training received by the licensee.
IX. ADMINISTRATION The Reactor Director or his designee is responsible for the development, administration, and execution of the Reactor Operator Requalification Program. In order to adhere to the standards prescribed in 10CFR55.53(h), it is necessary to include all licensed operators in the requalification testing program. To facilitate this procedure there will be two requalification exams prepared and administered, the first set will be prepared by the Reactor Director and will be administered to approximately 50% of the licensed operators, that set will include the most senior SRO on staff. The second set of questions will be prepared by the aforementioned SRO and shall be administered to the Facility Director and the remainder of the operators on that requalification cycle.
In the event that facility would find itself without a licensed Senior Reactor Operator suitable to prepare and administer the exam, the Reactor Safety Committee shall appoint a taskforce to prepare and administer the examination.
The examination shall not include more than 70% questions that have appeared on test administered by the NRC during the past five years, although these examinations may be used as models for the requalification test.
All requalification testing will adhere as closely as possible to USNRC examiner standard ES-606 or equivalent.
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w I< PURPOSE This document sets forth the requirements for the Reactor Operator (RO) and Senior Reactor Operator (SRO) requalification program for the Maryland University Training Reactor (MUTR), in accordance with the Code of Federal Regulations, Title 10, Part 50.54, Condition of Licenses.
II. SCHEDULE The operator Requalification Program cycle will last a period of two years, beginning on the first quarter of the biennial year. The licensed operator will enter the requalification program on the date the USNRC issues a license and will continue in the program until either the expiration date of the current license or the date the current license is terminated. If the operator should receive his/her operating license no greater than six months prior to the completion of the two year cycle, the operator will be exempt from completing the requirements of the current program, but will be required to enter the following requalification program cycle.
If the operator should receive his/her operating license greater than six months prior to the completion of the cycle, the operator will not be required to complete those program requirements required prior to the issuance of the license.
III. REACTOR OPERATION The operator will be required to perform, as either a Reactor Operator or Senior Reactor Operator, a minimum of ten reactor startups during the two-year requalification cycle. The operator must also perform a minimum of four hours per calendar quarter in his/her capacity as a licensed RO or SRO whichever is applicable.
For an SRO, the time devoted to the facility as an "On call" SRO can not be utilized to fulfill the four-hour mandate. These four hours must be recorded while performing direct supervision of the facility.
In the event that an operator does not meet the four hour minimum per calendar quarter the license shall be considered inactive under the terms set forth in 10CFR55.53(e).
In order for the license to be returned to active status, the licensee shall perform six hours of operation supervised by the Reacter Director or '.is/her designee under the terms prescribed under 10CFR55.53(f).
IV. REQUALIFICATION PROGRAM As part of the requalification program, licensed personnel will participate (as determined by the Reactor Director) as either a student or an instructor. The program will be on a continuing basis throughout the requalification cycle in those areas where annual operator and senior operater written examinations indicate that emphasis in scope and depth of coverage is needed in the following subjects:
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w A) Theory and principle of operation B) General and specific plant operating characteristics C) Reactor instrument and control systems D) Reactor protection systems E) Engineered safety systems F) Normal, abnormal, and emergency operating procedures G) Radiation safety and control i
H) Technical Specifications I) Applicable portions of Code of Federal Regulations Title 10, Chapters 0, 19,20,21,26,51,54,55,71 H) Applicable portions of the Atomic Energy Act (1974-08)
Additionally, a series of lectures / seminars will be conducted throughout the requalification cycle, the frequency of which to be determined by the Reactor Director or his designee. The purpose of these lectures / seminars is to serve as refresher courses for currently licensed RO and SRO's as well as training and instruction for RO and SRO trainee's. These lectures will be on a single topic (or related topics)in the areas outlined above, and will be of an average length of 30 to 35 minutes. It will be the responsibility of each licensee and trainee to review the material presented in every topic. This should be accomplished by attending the formal lectures, or, failing that, reviewing the subject matter on an individual basis. Portions of these requirements may be satisfied (as determined by the Reactor Director) by the licensed operator's participation in either ENNU 320, Nuclear Reactor Operations, as a student or instructor, or in the instruction i
and/or training of students for the NRC license, or both. See Appendix I i
V. EVALUATION The evaluation of the licensee's knowledge and performance of the requirements set forth in the requalification program will be accomplished by a written and oral examination, including a demonstration at the reactor console.
These will be administered annually to each licensed operator. The written examination for the reactor operator will be prepared in accordance with the modified requirements of USNRC Examiner Standard ES-606, dated 09/01/91, Administration of NRC Requalification Examinations at Non-Power Reactors (NPRs), which is included in this standard as Appendix II.
The oral examination and console performance evaluation will be administered by the Reactor Director, or his designee.
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If a license holder scores less than 70% on any section of the annual written examination, the licensee will attend a makeup session on that section topic and will be administered as a quiz. An overall grade of 80% will be required as a passing score.
If an individual receives a grade ofless than 80% overall, it will be mandatory that he be relieved of his licensed duties and enter an accelerated requalification program.
Upon successfully passing a second written examination and certification of satisfactory rating by the Reactor Director, the individual may return to his licensed duties.
An unsatisfactory evaluation on the annual oral examination will require that discussions of deficiencies take place between the licensee end the Reactor Director or other suitable qualified person designated by the Director. A second oral evaluation will be administered. If performance is again unsatisfactory, the licensee will be relieved of responsibilities and placed into an accelerated requalification program.
VL ACCELERATED REQUALIFICATION PROGRAM The additional training that a licensee may require (as indicated by his examination) will consist of additional written exams, console performance, or oral facility examination. The additional training and the examination that the licensee receives will depend upon the weaknesses exhibited on previous examinations. The number oflectures and examinations that a licensee will receive will be determined by either the Reactor Director or his designee. the licensee must obtain a rating of at least 80% on the re-evaluation in order to be reassigned to his licensed duties.
VIL DOCUMENT REVIEW The licensee will review during each requalification cycle the following documents and instructions that are pertinent to the operations of the reactor facility:
- 1. Reactor License (R-70)
- 2. Technical Specifications
- 3. MUTR Operating and Emergency Procedures
- 4. Code of Federal Regulations, Title 10, Chapters: 19, 20, 50.54,50.59, 55 VIIL RECORDS The following records will be maintained for each licensed operator and retained for the period until the license of the individual has expired or been terminated:
- Current copy of either the licensee's Reactor Operator or Senior Reactor i
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w Operator license.
- Copies of the graded requalification examinations administered.
- The operator's Requalification Program checklist.
- The summary of training received by the licensee in the accelerated Requalification Program documented in a memorandum for record and any additional documentation that is pertinent to additional training received by the licensee.
IX. ADMINISTRATION The Reactor Director or his designee is responsible for the development, administration, and execution of the Reactor Operator Requalification Program. In ortler to adhere to the standards prescribed in 10CFR55.53(h), it is necessary to include all licensed operators in the requalification testing program. To facilitate this procedure there will be two requalification exams prepared and administered, the first set will be prepared by the Reactor Director and will be administered to approximately 50% of the licensed operators, that set will include the most senior SRO on staff. The second set of questions will be prepared by the aforementioned SRO and shall be administered to the Facility Director and the remainder of the operators on that requalification cycle.
In the event that facility would find itself without a licensed Senior Reactor Operator suitable to prepare and administer the exam, the Reactor Safety Committee shall appoint a taskforce to prepare and administer the examination.
The examination shall not include more than 70% questions that have appeared on test administered by the NRC during the past five years, although these examinations may be used as models for the requalification test.
All requalification testing will adhere as closely as possible to USNRC examiner standard ES-606 or equivalent.
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