ML19331B520
| ML19331B520 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/30/1980 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML19331B519 | List: |
| References | |
| TASK-1.A.2.1, TASK-2.B.4, TASK-TM TAC-44188, TAC-44189, TAC-44538, TAC-44539, NUDOCS 8008120383 | |
| Download: ML19331B520 (9) | |
Text
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8 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT AMENDED LICENSED OPERATOR REQUALIFICATION PROGRAM O
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. Revision 1 07-30-80 POINT BEACH NUCLEAR PLANT AMENDED LICENSED OPERATOR REQUALIFICATION PROGRAM
1.0 INTRODUCTION
All lic*nsed operators, both Reactor Operators and Senior Reactor Operators, must maintain their level of competence at or above a sufficient level to ensure the safe and efficient operation of the facility. This document sets farth the requirements necessary to ensure continued proficiency for these licensees following completion of initial qualification by plant management and licensing by the USNRC. The complexity of design and operating mode of production facilities require that ongoing cotcprehensive requalification programs be conducted,,' as a matter of sound principle and practice. '
2.0 APPLICABILITY 2.1 All holders of valid USNRC Operator Licenses at Point Beach Nuclear Plant Unit 1 and 2 pursuant to 10 CFR Part 55. .
2.2 All holders of valid USNRC Senior Operator Licenses at Point Beach Nuclear Plant pursuant to 10 CFR Part 55.
3.0 OBJECTIVES 3.1 Maintain the knowledge level of each operator consistent with that
. reached during initial qualification in the following areas:
3.1.1 Nuclear reactor theory 3.1.2 Principles of reactor operation 3.1.3 Fundamentals of heat transfer, fluid flow and thermodynamics 3.1.4 Design features of Point Beach Nuclear Plant 3.1.5 Systems design and operation 3.1.6 Operating characteristics of Point Beach Nuclear Plant 3.1.7 Point Beach Nuclear Plant chemistry characteristics and control 3.1.8 Radiation control and safety 3.1.9 overall plant transient response 3.1.10 Normal operating and emergency operating procedures
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3.1.11 Accident analysis, control and aitigation 3.1.12 Technical Specifications 3.2 Ensure dexterity and competence during plant normal, off-normal and emergency operations 3.3 Maintain up-to-date knowledge of changes in the following areas:
3.3.1 Facility design 3.3.2 Operating procedures 3.3.3 Administrative procedures 3.3.4 Technical Specifications 3.3.5 operating experience from similar plants 3.4 Establish a formal method of evaluating and documenting licensed personnel proficiency and competency.
4.0 CERTIFICATION 4.1 Final certification of satisfactory completion of the requalification program set forth in this document shall'be by the Manager - Nuclear '
operations section. This certification shall be completed for each license renewal application.
. 4.2 The requalification program is a continual process. Satisfactory completion of this program means satisfactory participation in the requalification program during the period for which a license is valid; normally two years from date of license issue.
4.3 Lectures covering plant systems, integrated responses and transients shall be conducted by a holder of a valid Senior Reactor Operator license or under the direct supervision of the Training Supervisor who holds such a license.
4.4 Instructors who teach plant systems, integrated responses and plant transients shall participate ih applicable portions of the requalification program to assure cognizance of current operating history, problems and changes to procedures and administrative limitations.
4.5 The Training Supervisor shall designate those nonlicensed persons who must be enrolled in the requalification program in accordance with Section 4.4.
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i 5 IMPLEMENTATION ,OF REQUALIFICATION PROGRAM.
The requalification program consists of lectures, control manipulations, on-the-job training and review sessions, and written examinations. .
5.1 Schedule 5.1.1 A preplanned lecture series is scheduled for a period of approximately two years. Upon completion of this series, the program is repeated.
5.1.2 Annual written comprehensive examinations shall be adminis-tered at ten to fourteen-month intervals, depending upon plant scheduling, to determine deficient areas of operator competence and to determine the effec'tiveness of the
, requalification program.
5.1.3 Additional lectures will be added if the need is indicated by the written annual examinations.
5.1.4 On-shift discussions and reviews shall be repeated on a two-year interval.
5.1.5 Control manipulations shall be performed as plant conditions permit and shall be repeated on a biennial basis per Section 5.4.2 below. Control manipulations as specified in Section 5.4.1 below will be repeated on an annual basis.
5.2 Lecture Series The lecture series is designed to reinforce and to increase the operator's overall knowledge of the plant's control and protection systems, and to improve the operator's ability to safely operate the plant.
5.2.1 Subjects included in this series shall be:
- a. Theory and principles of operation
- b. General and specific operating characteristics
- c. Instrumentation and control
, e. Engineered safeguards systems
- f. Radiation control and safety
- g. Normal, off-normal and emergency operating procedures 1
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- h. Technical Specifications
- i. Applicable Title 10, Code of Federal Regulations requirements
- j. Fundamentals of thermodynamics, heat transfer and fluid flow
- k. Hitigation of accidents involving a degraded core, and plant transients.
5.2.2 The lectures shall be live presentations or proctored video-tape presentations by vendor or utility personnel, supple-mented by handouts and discussion periods. .
5.2.3 The proctor for videotape presentations will be the Training Supervisor or his designated alternate. The proctor shall provide review of all applicable design changes, facility licens.e changes, and operating experience associated with the videotape presentation 5.2.4 The lecture series will be periodically updated as required to reflect facility design, procedure and operating license changes.
5.2.5 Attendance to ^a given lecture shall be mandatory for all f
licensed-personnel receiving less than 80% on the applicable section of the most recent requalification examination.
Attendance is suggested for those operators receiving 80% or greater overall and on the applicable section; however, their attendance is not required.
- a. All licensed personnel shall attend at least six of the lectures planned annually.
- b. Any individual whose attendance at a lecture, or series of lectures on a particular subject is mandatory shall be administered a quiz after completion of the lecture (s) on that subject and shall be required to i
obtain a grade of 80% or greater to complete retraining in that area.
5.3 on-the-Job Training Plant operational experience is necessary to maintain operating dexterity at the control boards. The following requirements and self-study program will ensure proficiency at the control boards and knowledge of plant procedures, Technical Specifications and modifi-cations which affect plant operation.
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. Page 5 5.3.1 On-shift review of normal and emergency procedures 5.3.2 on-shift review of Technical Specifications 5.3.3- On-shift review of the Emergency Plan 5.3.4 on-shift review of Technical Specification bases (SRO.only) 5.3.5 On-shift review of Operating Point Beach Nuclear Plant Administrative Control Policies and Procedures Manual (QA Volume 1) (SRO only) 5.3.6 A minimum of ten (10) significant reactivity changes per license period are required.
5.3.7 Copies of completed modification requests which affect plant operation, procedure changes, Technical Specification changes, and applicable drawing change notices will be routed to the control room for review by all licensed operators.
5.4 control Manipulations Each licensed individual shall perform or participate in a combin-ation of reactivity control manipulations based upon plant equipment and system availability. Personnel possessing Senior Operator Licenses will be credited with an activity if they direct or evaluate the control manipulation as it is performed. Control manipulations which are not performed at the plant may be performed on a simulator.
. Normal control manipulations such as plant or reactor startups must be performed either at the plant or at a simulator. Control manip-ulations during abnormal or emergency conditions, if not performed, must be walked through with and evaluated by a member of the Point Beach Nuclear Plant Training Group, as a minimum.
5.4.1 The following control manipulations shall be performed on an annual basis:
- a. Plant or reactor startup to a range that reactivity I feedback from nuclear heat addition is noticeable and a heatup rate is established.
l l b. Manual control of steam generator water level control system during startup or shutdown.
( . c. Any significant (>10%) power changes in manur,1 rod control.
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- d. Loss of coolant including:
(1) Significant steam generator leaks (2) Inside and outside containment ,
(3) Large and small LOCA, including leak rate deter-mination (4) Saturated reactor coolant response
- e. Loss of core coolant flow / natural circulation
- f. Loss of all feedwater (normal and emergency) 5.4.2 The following control manipulations shall be performed during each biennial requalification period:
- a. Plant shutdown
- b. Boration and/or dilution during power operation
- c. Any reactor power change of 10% or greate' r where load change is performed with turbine EH control
- d. Loss of instrument air (Point Beach Nuclear Plant-specific)
- e. Loss of AC
- f. Loss of condenser vacuum l g. Loss of service water _
- h. Loss of residual heat removal
- i. Loss of component cooling water system or cooling to an individual component
- j. Loss of normal feedwater or normal feedwater system failure l k. Loss of protective system channel
- 1. Hispositioned control rod (s) or rod drops
- m. Inability to drive rods
- n. conditions requiring use of emergency boration
- o. Fuel cladding failure or high activity in reactor coolant l .
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- p. Turbine or generator trip
- q. Malfunction of automatic control systems which affect reactivity
- r. Malfunction of reactor coolant pressure / volume control system
- s. Reactor trip
- t. Main steam break (inside or outside containment)
- u. Nuclear instrumentation system failure (s) 5.5 Evaluation In order to obtain the maximum benefit from the requalification program, an evaluation system consisting of written examintions, oral examinations and evaluations, and lecture quizzes will be used to reflect any areas which require attention, changes or additions.
5.5.1 In order to evaluate the annual written examinations and to obcain a' realistic comparison of an individual to average grade, the examinatiens used are the same for both Operators and Senior Operators. The passing grade is 80% or greater overall and 70% or greater for any one section. '
Differential grading will be used to compensate for the lesser degree of knowledge required of an operator.
5.5.2 If an individual receives an overall average grade of less than 80%, he will be administered an oral examination within two weeks. If the results of the oral examination confirm the results of the written examination, the inoivid% 1 shall not perform his licensed duties until such time as he has satisfactorily completed accelerated requalification. If, based on the results of the oral examination, the individual is permitted to continue to perform licensed duties, he will complete accelerated requalification within fifteen (15) weeks. If this individual does not satisfactorily complete accelerated requalification within this time, he shall not perform his licensed duties until such time as additional training and examination indicate that he has successfully completed accelerated requalification.
5.5.3 Any individual who receives a non-passing grade on any
. section of the annual requalification examination shall be placed on an accelerated requalification program; the content of which shall be determined by the Training Supervisor or his designated alternate. In order to successfully complete accelerated requalification, the individual shall be reexamined in all iailed areas cf the annual requalification exam and obtain a minimum grade of 80% in each area.
. Page 8 5.5.4 A member of the Training Group will periodically observe and evaluate Operator and Senior Operator performance throughout the retraining program during normal and actual or simulated emergency conditions. During simulator training sessions, the simulator instructor will be considered a member of the Training Group for purposes of observation and evaluation.
5.5.5 other written examinations shall be administered during the course of the lecture series. An individual must earn a grade of 80% or better to preclude additional retraining in -
tnat area.
5.5.6 Training Group personnel who are licensed are exerrpt from the provisions of Section 5 of this document for which they have primary administration responsibility.' For example, an individual who prepares, administers and grades a written examination need not take the examination.
6.0 DOCUMENTATION .
6.1 The Training Supervisor is responsible for maintaining the following records:
6.1.1 Copies of written examinations administered 6.1.2 Copies of completed examinations 6.1.3 Results of written examinations and eisluations 6.1.4 Records of lecture attendance 6.1.5 Documentation of any required additional training 6.1.6 Review of records maintained in the control room retraining book 6.1.7 Copies of reviewed modification requests, procedure changes, Technical Specification changes and drawing change notices 6.1.8 Control manipulations performed, simulated or walked through 6.2 Each Shift Supervisor is responsible for maintaining the following records in the retraining book which is located in the control room:
6.2.1 On-shift reviews (see Items 5.3.1'through 5.3.4) 6.2.2 Record of significant reactivity changes performed 6.3 Each non-shift licensed operator is responsible for maintaining his assigned section of the retraining book which is located in the control room.
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