ML20209H345
| ML20209H345 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/30/1985 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20209H334 | List: |
| References | |
| PROC-851030, NUDOCS 8511110076 | |
| Download: ML20209H345 (130) | |
Text
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VOLUME 2
- . CHAPTER 2 .;
l '- OPERATIONS TRAINING PROGRAMS ~ i . i
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n. ( DUQUESNE LIGHT COMPANY Vol . 2 Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.1 2.0> OPERATIONS TRAINING PROGRAMS 2.1 LICENSED OPERATOR TRAINING
'2.1.1 Program Objective The objective of the Licensed Operator Training Program is to prepare per- -
sannel with entry-level qualifications to assume the duties, under both nor-
. mal operating and emergency conditions, of the Nuclear Shift Supervisor, I Nuclear. Station' Operating Foreman or Nuclear Control Operator position.
2.1.2 Program Application p Personnel whose duties require them to possess and maintain a Reactor Opera-() tor or Senior Reactor Operator license will complete the Licensed Operator Training Program. When projected to the time of examination, personnel will have met the eligibility requirements for examination by the U.S. Nuclear Regulatory Commission specified in NUREG-1021, Section ES-109. 2.1.3 Scope of Training 4 Successful trainees will apply for either a Reactor Operator's license or a
- Senior Reactor Operator's license, depending upon eligibility and need for
- license type. The program consists of formal instruction or study conducted in six phases, as follows:
- 1. Phase 1 - Academic Training. Classroom training in the funda-mentals of mathematics, nuclear sciences and theoretical aspects of nuclear power _ plant behavior. This phase also includes training in supervisory and leadership skills. A comprehensive examination on theoretic principles will be administered during this phase.
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Vol. 2 [] G DUQUESNE LIGHT COMPANY Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.1
- 2. Phase 2 - Station Systems Training. Classroom training in the
' design, operating characteristics, operating procedures and interrelationships of the Beaver Valley Power Station turbine plant, reactor plant and reactor control systems.
- 3. Phase _3 - Qualifications Standards Checkoffs. A combination of independent sel f-study. and examination on Beaver Valley Power Station systems. Trainees review and study plant systems addressed in Phase 2 and participate. in system-oriented oral and/or written examinations.
- 4. Phase 4 - Simulator Training. A combination of classroom and con-trol room simulator . training culminating in the " hot license" certification of NUREG-0094, Appendix F. Trainees practice reactor
)- startups, reactor shutdown, power maneuvering and responses to equipment / system failures.
- 5. Phase 5 - On-Shift Training. Approximately 9 months of on-the-job training in the plant and Control Room. This includes 3 months of training in the Control Room as extra man on shift to satisfy the requirements of NUREG-1021. Trainees practice control manipula-tions as available under the direct supervision of licensed operat-ing personnel and participate in Control Room routine under the supervision of a staff Instructor or Control Room Supervisor. They also complete in-plant watchstanding qualifications for each of four watchstations outside the Control Room.
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- 6. Phase 6 - Review and Evaluation. Trainees participate in Instructor-led review of technical subjects and are administered O
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/\ DUQUESNE LIGHT COMPANY Vol. 2 (m_sb Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.1 written ~ and oral examinations, including third-party, similar in scope to the U.S. Nuclear Regulatory Commission's licensing examinations.
2.1.4 Training Outline. 2.1.4.1 General.
- 1. New-hire employees are normally -provided with general training ,
prior to . commencement of the Licensed Operator Training Program. This' may include, as schedules permit:
- a. Station Orientation (Volume 2, Section 1.1)
- b. Radiation Worker Training (Volume 2, Section 3.4) t
( c. First Aid Training (Volume 2, Section 10.4)
- d. . Respiratory Protection Training (Volume 2, Section 10.1)
- e. Fire Protection Training (Volume 2, Section 10.2)
- f. Station Layout Qualifications (Volume 2, . Section 2.8)
- 2. Trainees enrolled in the Licensed Operator Training Program may be -
' periodically assigned to in-plant duties as Nuclear Operators-under-instruction. If so assigned, they will not be required to act independently as Nuclear Operators - unless qualified by completing the ' required on-the-job training program, and specifically authorized by the Manager - Nuclear Training.
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- 3. The Licensed Operator-Training Program is normally conducted in the sequence presented in the following outline.
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r'-- , 7 DUQUESNE LIGHT COMPANY Vol . 2 N' Nuclear Group Ch.'2 Training Administrative Manual Sect. 2.1 2.1.4.2 Outline of Instruction
- 1. Academic Training (Phase 1A)
Mathematics Atomic and Nuclear Physics Chemistry Fundamentals
- Fluid Flow and Thermodynamics Mechanical Orientation Electrical Fundamentals Electrical Practical ,
Intrumentation and Control Fundamentals Materials . n v 2. Station Systems Training (Phase 2A) Turbine Plant Systems.
- 3. Systems Qualifications (Phase 3A)
Turbine Plant Systems.
- 4. On-Shift Training (Phase SA)
Turbine Plant Watchstations.
- 5. Academic Training (Phase 1B)
(Sequence optional) Radiation Protection Emergency Plan. Revision 0 Page 2.4
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DUQUESNE LIGHT COMPANY Nuclear Group Ch. 2 Training Administrative Manual , Sect. 2.1
- 6. Station Systems Training (Phase 2B)
Reactor Plant Systems.
- 7. System Qualifications (Phase 38)
Reactor Plant Systems. I 1
- 8. On-Shift Training (Phase SB)
Reactor Plant Watchstations.
- 9. Academic Training (Phase IC)
(Sequence optional) Reactor Theory. Comprehensive Theory Examination. l 10. . Station Systems Training (Phase 2C) Normal Operating Procedures.
- 11. System Qualifications (Phase 3C)
Normal Operating Procedures. 3
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' Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.1 L
- 12. Academic Training (Phase 1D) i y.
Accident and Transient Analysis. Mitigating Core Damage. I
- 13. Station Systems Training (Phase 2D)
Abnormal / Emergency Operating Pracedures.
- 14. System Qualifications (Phase 30)
Abnormal / Emergency Operating Procedures. O V 15. Simulator Training (Phase 4) 1 (Sequence optional. Refer to Section 12.2 of this volume. . Simula- I tor training may be completed at any time between completion of Phase 3D and the start of Phase 6.)
- 16. Academic Training (Phase 1E)
(Sequence optional) Supervisory Training. Trial NRC Examinations. Each trainee will be administered a set of written and oral examinations similar in scope and style to those administered by the Nuclear Regulatory Commission. Results of these examinations will be used to establish the framework for the
~ .- Phase 6 License Review Series. <
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t DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.1
- 17. On-Shift Training (Phase SC)
Control Room training.
- 18. ' Review and Evaluation (Phase 6)-
- a. License Review Series. Specific content and duration of the License Review Series will be determined by the results- of the trial NRC examinations administered during Phase IE. -Instruc-tors will use Licensed Operator Training Program Lessen Plans flexibly to conduct a general review as well as to address -
identified weaknesses with appropriate emphasis.
- b. Trial NRC Examinations.- Each trainee will be administered a set of written and oral examinations similar in scope and style
- to those administered by the Nuclear Regulatory Commission.
The examinations will be administered by a qualified third-party team selected by the Manager - Nuclear Training. Resul ts will be used to assess trainee preparedness for licensing examinations and to provide guidance to trainees for final study and preparation. 2.1.5 Program Administration 2.1.5.1 Responsibility The Manager - Nuclear Training is responsible to the General Manager - Nuclear Services for performance and documentation of the Licensed Operator Training Program. This responsibility includes timely preparation and submittal of license applications. Responsibility for coordination and supervision may be delegated. Revision 0 Page 2.7
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DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual Sect.~2.1 2.1.5.2 Training Program Duration and Content
- 1. With the exception of Phase SC of On-Shift Training, the scope and duration of phases of the Licensed Operator Training Program will be determined by the level of prior training and experience in a group or class of trainees. The Manager - Nuclear Training will approve the scope and duration of each phase via the 10-week Train-ing Program Schedule (refer to Subsection 2.1.6.8).
- 2. With the excehtion of Phase SC of On-Shift Training, the Licensed .
Operator Training Program may be reduced in scope on a case basis for individuals whose qualifications exceed entry-level qualifica-tions established for the group or class. Reductions in scope will be approved via the Waiver of Training Requirements form in accord-(Q' s ance with Volume 1, Chapter 5. The reasons for waivers will be equivalent training and/or experience and satisfactory completion of examinations.
- 3. A composite list of lesson plan numbers and titles used in Phases 1, 2, and 4 of the Licensed Operator Training Program will be main-tained under the cognizance of the Manager - Nuclear Training.
2.1.5.3 Qualifications of Instructors . The following instruction will be conducted by Nucle'ar Operations and Main- l tenance Instructors or personnel with equivalent qualifications (Refer to Volume 1, Chapter 2): ,
)
- 1. Instruction in abnormal, emergency, station startup and station shutdown procedures.
/) Accident and Transient Analysis Training (Phase 10). U/ 2. Revision 0 Page 2.8
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- 3. Mitigating Core Damage Training (Phase 10).
2.1.5.4 Conduct of Qualification Standards Checkoffs (QSCs) The following guidance will be applied to the conduct of QSCs in addition to the general guidance of Volume 1, Chapter 5 for oral examinations:
- 1. The conduct of QSCs will follow the guidance of the System Quali-fication Standards for licensed personnel.
- 2. Trainees will " sign up" for QSCs at a designated location or may be.
scheduled for QSCs. Instructors qualified to conduct QSCs will contact and examine trainees in order.
. n U 3. To the extent practical in terms of accessibility and radiation exposures, QSCs will include a walk-through of the system in the plant and Control Room. Trainees will demonstrate their knowledge of physical system layout and location of principal components.
- 4. If a trainee is terminated twice on the same QSC, the Instructor will notify the Director - Operations Training who will formally counsel the trainee and complete a Report of Counseling (Volume 1, Chapter 5). Responsibility for counseling may be delegated.
- 5. Trainee progress will be checked weekly. The Director - Operations Training or designated alternate will formally counsel employees who fall behind schedules established for checkoff segments.
- 6. The Director - Operations Training should monitor or appoint personnel to monitor a sampling of QSCs to assure that Instructors are maintaining proper scope and following administrative Revision 0 Page 2.9
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. Nuclear Group. Ch. 2 Training Administrative Manual Sect. 2.1 guidelines. This function -should be documented by countersigning the QSC.
2.1.5.5 Applications Applications for operator licenses will be handled in accordance with NUREG-1021, Section ES-109E. Certifications pursuant' to 10CFR55.10(a)(6) and 10CFR55.33(a)(4) and (5) will be signed by the Vice President - Nuclear Group. 2.1.6 Program Documentation
- 1. The results of individual written examint*. ions will be, documented on the Examination Grade Report (Volume 1, Figure 5.10) and filed.
N with program records.
- 2. The results of written examinations will be transcribed onto the Personnel Grade Summary (Volume 1, Figure 5.11). After the comple-tion of training, Personnel Grade Summaries will be maintained with program records.
'3. Formal counseling will be documented on the Report of Counseling (Volume 1, Figure 5.13).
- 4. Satisfactory completion of Qualification Standards Checkoffs will
,,- be documented on the Trainee Checkoff Sheet; System Qualification.
Standard (Figure 2.1.3).
- 5. A record of reactivity manipulations performed by trainees during Phase SC of On-Shift Training will be maintained on the On-the-Job '
Training Record (Volume 2, Figure 2.2.3). Supervising licensed C Revision 0 Page 2.10 i
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" Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.1 personnel will place their initials in appropriate blocks. Com-pleted On-the-Job Training Records will be filed with program records.
- 6. The Training Coordinator - Simulator will provide a statement which describes the Phase 4 training program, the activities completed by trainees and the results of " hot license" certification examina-tions. Simulator training statements will be filed with program records. ,
- 7. A Training Roster (Volume 1, Figure 5.7) will be initiated at the completion of each course in Phases 1, 2, and 3, and at the com-pletion of Phases 4, 5, and 6. Training Rosters will be filed with f program records.
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- 8. Each cou rse in the Licensed Operator Training Program will be scheduled on the 10-week Training Program Schedule (Volume 1, Figure 5.5). Following the completion of training, 10-week Schedules will be filed with program records as permanent documentation of how the program was conducted.
- 9. During Phase SC of On-Shift Training, trainees will complete the On-Shift Training Checklist (Figure 2.1.4) to signify their review of procedures, documents or areas of responsibility. Completed checklists will be filed with program records.
- 10. During Phase SC of On-Shif t Training, an on-duty Instructor or licensed Senior Reactor Operator will sign the On-Shift Training Verification (Figure 2.1.5) to signify completed shifts for indi-vidual trainees. Completed verifications will be filed with pro-gram records.
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DUQUESNE LIGHT COMPANY Nuclear Group Vol . 2 Ch. 2 Training Administrative Manual Sect. 2.1 2.1.7 Program References 2.1.7.1 Requirements / Commitments
- 1. '10CFR50, Definition (t) and Parts 50.54(i), (j) and (1).
- 2. 10CFR55. _
- 3. Regulatory Guide 1.8.
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- 4. ANSI N18.1-1971, Sections 4.3.1, 4.5.1, and 5.2.
- 5. Final Safety Analysis Report (Updated), Section 12.2.2.
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- 6. NUREG-0737, Sections 1.A.2.1, I.A.2.3, and II.B.4.
- 7. NUREG-1021, Section ES-109.
- 8. March 28, 1980 Letter from H. R. Denton--Qualifications of Reactor Operators.-
2.1.7.2 Recommendations / Guidance
- 1. NUREG-0094.
- 2. INP0 82-008; Control Room Operator, Senior Control Room Operator and Shift Supervisor Qualifications.
- 3. INP0 82-026; Technical Instructor Training and Qualifications.
- 4. INP0 STG-01; Nuclear Guidelines for Training to Mitigate the 1
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\~. Consequences of Core Damage.
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- 5. INP0 STG-02; Guidelines for Heat Transfer, Fluid - Flow and Thermodynamics Instruction.
.2.1.8 Summary of Figures
- 1. Trainee Checkoff Sheet; System Qualification Standard - Figure 2.1.3
- 2. On-Shift Training Checklist - Figure 2.1.4
- 3. On-Shift Training Verification - Figure 2.1.5
- 4. 10-week Training Program Schedule - Volume 1, Figure 5.5
- 5. Waiver of Training Requirements - Volume 1 Figure 5.6
- 6. Training Roster - Volume 1, Figure 5.7
- 7. Examination Grade Report - Volume 1, Figure 5.10
- 8. Personnel Grade Summary - Volume 1, Figure 5.11
- 9. Report of Counseling - Volume 1, Figure 5.13
- 10. On-the-Job Training Record - Volume 2, Figure 2.2.3 O
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) DUQUESNE LIGHT COMPANY Vol. 2 Y Nuclear Group Training Administrative Manual Ch.~2 Sect. 2.2 2.2 LICENSED OPERATOR RETRAINING 2.2.1, Program Objective The objective of the Licensed Operator Retraining Program is to assure that
. licensed personnel remain competent to operate the Beaver Valley Power Sta-tion in a safe, reliable 'and efficient manner under . normal, abnormal and emergency operating conditions.
2.2.2lProgramApplicability I Personnel licensed as Reactor Operators or Senior Reactor Operators for the Beaver Valley Power Station (licensees) will complete the Licensed Operator ( Retraining Program. The Licensed Operator Retraining Program will be conducted continuously for 24 months and upon conclusion will be followed by successive 24-month pro-
. grams, each of.which will begin promptly at the conclusion of the preceding program. Each 24-month retraining' program is comprised of two retraining cycles 1 year in length.
2.2.3 Scope of Training The Licensed Operator Retraining Program is conducted in five phases of instruction or evaluation, as follows:
- 1. Phase 1 - Annual Written Examinations. Licensees are administered ,
a comprehensive written examination similar in scope and style to
-USNRC licensing examinations.
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- 2. Phase 2 - Formal Classroom Training. Structured classroom training based in.part on the results- of annual written examinations. , ,
- 3. Phase 3 - Plant- Manipulations Training. Licensees perform or >
supervise ~ the performance of control manipulations in the plant or at the Beaver Valley- control room simulator. +
- 4. Phtse 4 - Individual Study. Review and self-study 'of significant operating experience reports, Incident ' Reports, design changes and procedure changes.'
- 5. Phase 5 ~- Performance Evaluation. Organized evaluations of general p+trformance and competence via the Beaver Valley Power Station performance review program.
2.2.4 Training Outline 2.2.4.1 Annual Written Examinations Once each year, licensees will complete a comprehensive written examination similar in scope and style to licensing examinations administered by the l USNRC. The purposes of these examinations will be to evaluate effectiveness of the prior year's retraining, and to identify areas where training may be required to upgrade knowledge. An overall grade of 80% combined with i a grade of at least 70% in _each category will be considered passing. .
- 1. Licensees who fail the annual written examination will be relieved of Control Room duties requiring a license and will participate in an accelerated retraining program. Refer to Subsection 2.2.5.4.
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-2. - During the subsequent retraining cycle, licensees will be required
- to complete formal classroom training in any category for which a
' score of less than 80% is earned.
- 3. The Manager - Nuclear-Training, the Director - Site Operations and the Plant Manager will review the results of written examinations to determine where emphasis in retraining is needed.
2.2.4.2 ~ Formal Classroom Training I' The -scope,; duration and precise content of formal classroom training will vary according to needs ~ identified ~ for individual cycles of the- Licensed 0perator Retraining Program. Instruction will average at-least 4 hours per
.- month per licensee.- Formal classroom training will be accomplished each cycle in 6 -modules of instruction, repeated 6 times to acconinodate the operating schedule cycle. Instructional. emphasis will be placed where annualJwritten examination results and feedback from*khe- Site Operations-
'Section indicate that weaknesses may be developing. Classroom training will 1be scheduled in the following topics during each retraining program:
1
- 1. Topic I - Theory and Principles of Operation
- 2. Topic II - Thermodynamics, Heat Transfer and Fluid Flow 3.. Topic III - Plant Instrumentation and Controls
- 4. Topic IV - Radiation Control and Safety
, 5. Topic V - Plant Protection / Engineered Safety Systems
- 6. Topic VI,- Administrative Controls
- 7. Topic VII - Abnormal and Emergency Procedures Review
- 8. . Topic VIII - Plant Status Updates Films, videotapes, and other effective training media may be used to supple-ment live instruction. The use of these media will not exceed 50% of the
= total time devoted to formal classroom training.
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._ _ _ y DUQUESNE LIGHT COMPANY Vol . 2 Nuclear Group . Ch. 2 Training Administrative Manual Sect. 2.2 2.2.4.3 Plant Manipulations Training Licensees will participate in control manipulations which demonstrate their skill and/or familiarity with reactivity control systems, and their pro-ficiency with abnormal and emer gency procedures. Senior Reactor Operator licensees are credited with control manipulations if they direct or evaluate the manipulations-as they are performed. To the extent practical, as deter-mined by the availability of station equipment and systems, control manipu-lations should be - practiced on the controls of the Beaver Valley Power Station. The Beaver Valley control room simulator may be used to supplement in-plant. experience.
In the following list, items' designated (*) will be performed at least annually. All other items will be performed at least once every 2 years. A Os - diversity of control manipulations should be achieved for each licensee, and the use 'of boration or dilution as a. training manipulation will be mini-mized. Completion of these control manipulations from NUREG 0737 will satisfy the reactivity control requirements of 10CFR55, Appendix A.
*l. Plant or reactor startup to include a range that reactivity feed-back from nuclear heat addition is noticeable and heatup rate is established.
- 2. Plint Shutdown.
*3 Manual centrol of steam generator and/or feedwater during startup and shutdown.
- 4. Boration and/or dilution during power operation.
- *5. Any significant (>10%) power change in manual rod control.
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*6.. Loss'of' coolant, including:
- a. Significant PWR steam generator tube leaks b.- Inside and outside containment
- c. Large_and small, including leak-rate determination.
- d. Saturated reactor coolant response -
t-
- 7. Loss of instrument air.
- 8. Loss of electrical power.
*9. Loss of core coolant flow / natural circulation.
t 10.- Loss-of condenser vacuum. l 2\ 11. Loss ~of safety-related service water. l 12. Loss of shutdown cooling.
- 13. Loss of component cooling system or cooling to an individual j component.
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- 14. Loss of normal feedwater or normal feedwater system failure.
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- *15 . Loss of all.feedwater (normal and emergency).
i [~ 16. Loss of protective system channel. 17.. Mispositioned control rod or rods (or rod drops).
- 18. Inability to drive control rods.
I: ' O - Q 19. Conditions requiring use of emergency boration. t Revision 0 Page 2.18
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- 20. Fuel cladding failure or high activity in reactor coolant.
- 21. Turbine or generator trip. -
- 22. Malfunction of automatic control system (s) which affect reactivity.
- 23. Malfunction of reactor coolant pressure / volume control system.
- 24. Reactor trip.
- 25. Main steam line break (inside or outside containment).
- 26. Nuclear instrumentation failure (s).
U 2.2.4.4 Individual Study , Licensees will complete monthly reading assignments. The subjects covered in reading assignments may include, but not be limited to:
- 1. Facility design changes
- 2. Facility procedure changes
- 3. Technical Specification changes
- 4. Emergency Preparedness Plan .
- 5. Radiation control procedures
- 6. Temporary station procedures
- 7. Station Industrial Security Procedures
- 8. Abnorma'l and emergency procedures Revision 0 Page 2.19
DUQUESNE LIGHT COMPANY Vol. 2 U )- Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.2 - 2.2.4.5 Performance Evaluation Evaluations of the performance and competency of Nuclear Control Operators, Nuclear Station Operating Foremen and Nuclear Station Shift Supervisors will be performed annually. Deficiencies or trends will be identified to the Manager - Nuclear Training for incorporation into the Licensed Operator Retraining Program. Evaluations should include a critique of the manner in which personnel recognize and respond to abnormal occurrences or off-normal operating conditions. Annual performance evaluations are implemented by I Beaver Valley Powe* Station Administrative Procedure No.15--Evaluation of Job Performance. In addition to the foregoing, systematic evaluations of recognition and (N handling of off-normal, abnormal or emergency conditions may be performed on , k the Beaver Valley control room simulator. 2.2.5 Program Administration 2.2.5.1 Responsibility , The Manager - Nuclear Training is responsible to the General Managcr - Nuclear Services for performance and documentation of the Licensed Operator Requalification Program. This responsibility includes timely preparation and submittal of license renewal applications. Responsibility for coordina-tion and supervision is delegated to the Director - Operations Training. The Director - Site Operations is responsible for the annual performance evaluations of Phase 5 (Subsection 2.2.4.5). i T O l Q Revision 0 Page 2.20 l i
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Vol . 2 - Ch. 2 Training Administrative Manual Sect.'2.2 p 2.2.5.2. Lesson Plans
. Lesson plans'for the Licensed Operator Retraining Program will be developed on an a# needed basis. They will be' identified on appropriate retraining /
L , continuing ' schedules . (Volume '1, Chapter ,5), and maintained 'in the lesson plan file:in accordance with Volume 1. Chapter 6. i '2.2.5.3~ Accelerated Retraining Any licensee who scores less than 80% overall on tbe annu'al written examina- ! tion, or scores' less than 70% in any category, will be relieved of Control Room duties requ' iring a license and will be placed in accelerated retraining under the direction of the Manager - Nuclear. Training. The licensee will be j reinstated to licensed duties after completing the prescribed retraining and ! scoring at least . 80% overall on re-examination and at least 70% 'in each
. category. The' USNRC will be notified of the succefsful- completion of r accelerated retraining prior to the. individual's return to Control Room
- licensed duties.
L, 2.2.5.4 Periodic Examinations Periodic written examinations or quizzes will be administered to assess licensees' xnowledge of topics covered in Phase 2 formal classroom instruc-tion. Remedial' training will be performed.for licensees who score less than 80% on periodic examinations. 2.2.5.5 Inactive Licenses Any licensee assigned to Control Room duties who does not work 'at least one 8-hour shift in the Control Room over any 3-month period will not be O - Revision 0 Page 2.21 L--__-__-___-___________-_-___ _l
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- permitted "to perform duties requiring a license until he has completed an
; individual retraining program which includes:
- 1. Review of design changes and changes to operating procedures,-
. administrative procedures and Technical Specifications issued since his last shift assignment.
'2. Completion of an oral examination ~ administered by an individual licensed or certified by the USNRC at the Senior Reactor Operator level for the Beaver Valley ' Power Station.
' The USNRC will be notified of successful completion of retraining and exami-
, nation prior to reinstatement to Control Room duties requiring a license. '
The -foregoing inactive license provision will not apply to personnel assigned to the Beaver Valley Power Station staff. It will, however, apply-to personnel who experience prolonged absence from the station because of
. illness, accident or other~ reason.
2.2.6 Program Documentation
.Unless .otherwise specified, each of the documents sp'ecified in this subsection will be maintained, with the program records for each 24-month
- Licensed Operator Retraining Program.
- 1. Each. module of the Licensed Operator Retraining. Program will be scheduled via the Retraining / Continuing Training Schedule (Volume ,
1, Figure 5.2).
- 2. A record of each licensee's participation in the Licensed Operator Retraining Program will be maintained on the BVPS Licensed Operator Retraining Summary (Figure 2.2.1).
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- 3. Attendance during Phase 2 formal classroom training will be report-ed on the Retraining Attendance Record (Volume 1, Figure 5.8).
- 4. Phase 5 individual study will be programmed on a monthly basis.
The Director - Operations Training will prepare the Individual' Study Guide (Figure 2.2.2) and distribute a copy to each licensee.
- 5. A record of Phase 3 in-plant control manipulations will be main-tained via the On-the-Job Training Record (Figure 2.2.3). Super-I vising Senior Reactor Operator licensees kill place their initials in . appropriate blocks. In addition, the Coordinator - Simulator Training will forward a completed copy of the Simulator Evolution Summary Sheet (Figure 12.2.7) for each ' student at appropriate p intervals.
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- 6. A copy of each annual examination, periodic examination or quiz, and the answers provided by licensees will be maintained with individual examination files.
- 7. The Summary of Recommendations (Figu. e 2.2.5) will be used 'to docu-ment the recomendations for training emphasis arising from the reviews of annual written examination results.
- 8. At the conclusion of each 1-year retraining program tycle, the Manager - Nuclear Training will address a report to the General
< Manager - Nuclear Services, which evaluates the effectiveness of the program. A copy of this report will be maintained with program records. An acceptable format for this report is provided in Figure 2.2.6, Retraining Program Cycle Report.
- 9. The Oral Examination Report (Figure 2.2.4) may be used to document the oral examinations of Subsection 2.2.5.5--Inactive Licenses, or Revision 0 Page 2.23
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w - ('_ ,)~ DUQUESNE LIGHT. COMPANY Vol. 2 Nuclear Group .Ch. 2 Training Administrative Manual Sect. 2.2 any other oral examinations administered in connection with the Licensed Operator Retraining Program. 2.2.7 Program References
- 2.2.7.1 Requirements /Connitments
- 1. 10CFR50, Definition (t) and Part=50.54 (1-1).
- 2. 10CFR55, Appendix A.
~
- 3. Regulatory Guide 1.8.
("' 4. ANSI N18.1-1971, Section 5.1. L)i~
- 5. Final Safety Analysis Report (Updated), Section 12.2.4.
'6. NUREG-0737, Sections I.A.2.1, I.A.2.3, I.C.5 and 11.8.4.
- 7. March 28, 1980 Letter from H. R. Denton--Qualifications of Reactor Operators.
2.2.7.2 Recommendations / Guidance
- 1. NUREG-1021, Section ES601.
~
- 2. INP0 GPG-02; Requalification Tra1ning and Evaluation.
- 3. INPO 82-026; Technical Instructor Training and Qualifications.
-s 4. INP0 STG-01; Nuclear Guidelines for Training To Recognize and s ,) Mitigate the Consequences of Core Damage.
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DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group _ Ch. 2 Training Administrative Manual . Sect. 2.2
- 5. INP0 STG-02; Guidelines for Heat Transfer, Fluid Flow and Thermodynamics Instruction.
2.2.8 Summary of Figures
- 1. BVPS Licensed Operator Retraining Summary - Figure 2.2.1
- 2. Individual Study Guide - Figure 2.2.2
- 3. On-the-Job Training Record - Figure 2.2.3
- 4. Oral Examination Report - Figure 2.2.4 I
- 5. Summary of Recommendations - Figure 2.2.5
- 6. Retraining Program Cycle Report - Figure 2.2.6
- 7. Retraining / Continuing Training Schedule - Volume 1, Figure 5.2
- 8. Retraining Attendance Record - Volume 1, Figure 5.8
- 9. Simulator Evolution Sumary Sheet - Volume 2, Figure 12.5.7 O
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DUQUEENE LIGHT COMPANY-Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual Sect.'2.3 2.3 LICENSED OPERATOR UPGRADE TRAINING PROGRAM i 2.3.1 Program Objective ; The objective of the Licensed Operator Upgrade Program is to prepare Beaver ) Valley Power Station Licensed Reactor Operators to assume, under normal, s abnormal and emergency conditions, the duties of the on-shift Senior Reactor Operator positions. 2.3.2 ' Program Application Prior to appointment to duties requiring a Senior Reactor Operator's li-cense, personnel will meet the experience requirements of NUREG-1021, Sections ES-109B through D. LJ 2.3.3 Scope of Training l The i.icensed Operator Upgrade Training Program consists of a preliminary l audit examination, experience as Nuclear Shift Operating Foreman under in-struction (on-the-job training), formal instruction, self-study, and final evaluation. ; 6 , i 2.3.4 Training Outline 1 2.3.4.1 Phase 1 - Preliminary Audit Examinations i 2 l Each trainee will be administered written and oral examinations similar in j- scope and style to the U.S. Nuclear Regulatory Commission (USNRC) licensing j examinations for Senior Reactor Operators. The results of Preliminary Audit i Examinations will be analyzed and will be used as the basis for developing l formal instruction requirements for Phase 3 training. j - i \
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I DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.3 2.3.4.2 Phase 2 - On-Snif t Training Each trainee will complete approximately 3 months (60 working days) of on-the-job training. -Trainees will participate in station and Control Room routine under the instruction of the on-duty NSOF. 2.3.4.3 Phase 3 - Review Series Formal classroom training and self-study will be conducted to upgrade the knowledge of trainees in the theoretic 61 espects of Senior Reactor Operator responsibilities. The precise duration and content of the Review Series will be determined by the results of the preliminary audit examinations
- administered in Phase 1. Instructors will use Licensed Operator Training Program Lesson Plans flexibly to address identified weaknesses with appro-s priate emphasis. Periodic examinations will be administered to gauge the effectiveness of training.
2.3.4.4 Phase 4 - Trial NRC Examinations Each trainee will be administered a second set of written and oral examina-tions at the Senior Reactor Operator level. These examinations will be administered by a third-party team selected by the Manager - Nuclear Training. Results will be used t'o assess trainee preparedness for ' licensing examinations and as guidance to trainees for final study and preparation. . 2.3.5 Program Administration 2.3.5.1 Responsibility Responsibility for coordination and supervision of Licented Operator Upgrade Training is delegated to the Director - Operations Training. U l Revision 0 Page 2.27
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-(6'] DUQUESNE LIGHT COMPANY Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.3 2.3.5.2 Qualifications of Instructors Personnel who conduct Licensed Operator Upgrade Training will possess the qualifications required of Instructors who conduct equivalent portions of the Licensed Operator Training Program. Refer to Volume 2, Section 2.1.
2.3.5.3 Applications Applications for Senior Reactor Operator licenses will be handled in ac-cordance with NUREG-1021, Section ES-109E. Certifications pursuant to 10CFR55.10 (a)(6) and 10CFR55.33 (a)(4) and (5) will be signed , by the Vice President - Nuclear Group. f-ss 2.3.6 Program Documentation The following documentation will be maintained with training program records in accordance with Volume 1, Chapter 6:
- 1. Phase 3 classroom training will be scheduled and approved on the 10-Week Training Program Schedule (Volume 1, Figure 5.5).
- 2. The results of written examinati.ons will be documented on the Examination Grade Report (Volume 1, Figure 5.10) and transcribed on to the Personnel Grade Summary (Volume 1, Figure 5.11). Completed written and oral examinations will be retained.
. 3. A Training Roster (Volume 1, Figure 5.7) will be initiated at the completion of the Review Series Phase.
- 4. ~ During Phase 2, On-Shift Training, trainees will complete the On-Shif t Training Checklist (Figure 2.1.4) to signify their review of
(, ) procedures, documents or areas of responsibility. Additionally, an Revision 0 Page 2.28
O~ DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual - Sect. 2.3 on-duty Instructor or licensed Senior Reactor Operator will sign the On-Shift Training Verification (Figure 2.1.5) to signify com-pleted shifts for individual trainees.
- 5. The Summary of Recommendations (Figure 2.2.5) will be used to docu-ment the recommendations for training emphasis, arising from the review of the Preliminary Audit Examination results.
2.3.7 Program References 1 2.3.7.1 Requirements / Commitments
- 1. 10CFR50, Definition (t) and Parts 50.54(i), (j) and (1).
- 2. 10CFR55.
- 3. Regu'atory Guide 1.8.
- 4. ANSI N18.1-1971, Sections 4.3.1, 4.5.1, and 5.2.
- 5. Final Safety Analysis Report (Updated), Section 12.2.2.
- 6. NUREG-0737, Sections I.A.2.1, I.A.2.3, and II.B.4.
-7. NUREG-1021, Section ES-109.
- 8. March 28, 1980 Letter from H. R. Denton; Qualifications of Reactor Operators.
2.3.7.2 Recommendations / Guidance
- 1. NUREG-0094.
i l Revision 0 F4;e 2.29
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CT DUQUESNE LIGHT COMPANY Vol. 2 V Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.3
- 2. INP082-008; Control Room Operator, Senior Control Room Operator and Shift Supervisor Qualifications.
- 3. INP0 82-026; Technical Instructor Training and Qualifications.
i
- 4. INP0 STG-01; Nuclear Guidelines for Training to Mitigate the Consequences of Core Damage.
- 5. INP0 STG-02; Guidelines for Heat Transfer, Fluid Flow and Thermodynamics Instruction.
2.3.8 Summary of-Figures
- 1. 10-Week Training Program Schedule - Volume 1. Figure 5.5
- 2. Training Roster - Volume 1, Figure 5.7
- 3. Examination Grade Report - Volume 1, Figure 5.10
- 4. Personnel Grade Summary - Volume 1 Figure 5.11 1
- 5. On-Shift Training Checklist - Volume 2, Figure 2.1.4
- 6. On-Shift Training Verification - Volume 2, Figure 2.1.5
- 7. Summary of Recommendations .- Volume 2, Figure 2.2.5 Revision 0 Page 2.30
(} (_,/ DUQUESNE LIGHT COMPANY Nuclear Group Vol. 2 Ch. 2 Training Administrative Manual Sect. 2.6 2.6 FUEL HANDLING SR0 TRAINING PROGRAM 2.6.1 Program Objective The objective of the Fuel Handling SR0 Training Program is to prepare per-sonnel- to function as Refueling Shift Supervisors during refueling and core alterations. 2.6.2 Program Application i The Fuel Handling SRO Training Program will be completed by Shift Technical Advisors or engineers assigned to supervise fuel handling or other core al-terations. Entry level personnel will have ' completed the formal classroom training and simulator training phases of the Shift Technical Advisor Train-() ing Program. Refer to Volume 2, Section 5.2. Personnel who complete this program will apply for a USNRC Senior Reactor Operator's license limited to fuel handling. 2.6.3 Scope of Training The Fuel Handling SR0 Training Program consists of on-the-j ob training, academic training, and systems and equipment Qualification Standards . Checkoffs related to the duties of the Refueling Shift Supervisor. I O D Revision 0 Page 2.40
I DUQUESNE LIGHT COMPANY Vol. 2 \ Nuclear Group . Ch. 2 Training Administrative Manual Sect. 2.6 2.6.4 Training Outline 2.6.4.1 Phase 1 - Academic Training
- 1. Theory
- a. Core Design
- b. Subcritical multiplication
- c. Source-to-detector geometry
- d. Source Range instrumentation
- e. Portable n.easuring devices .
- f. Shutdown margin 2.- Administrative Controls
- a. Operating Manual Chapter 48
- b. Relevant portions of the Maintenance Manual, Radiation Control Manual and Chemistry Manual
- c. Refueling Procedures
- d. Technical Specifications
- e. New fuel receipt and inspection
- f. Communications
- 3. Emergency Procedures
- a. Irradiated fuel damage
- b. Emergency Plan Procedures
- c. Evaluation procedure
- d. Sipping cans Revision 0 Page 2.41
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' I DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.6 4 Radiation Control
- a. Time, distance and shielding
- b. Exposure limits
- c. Measuring instruments
- d. Radiation Work Permits
- e. Radiation Clearances
- f. _ Su rveys 9 Types of hazards
- h. New and irradiated fuel
- 5. Hardware Review
- a. Spent fuel pool and crane
- b. Refuel cavity and manipulator crane
.,. c. Tools x) d. Control and interlocks
- e. Reactor internals
- f. Disassembly and assembly
- g. Surveillance Testing 2.6.4.2 Phase 2'- Systems and Equipment Qualification Standards Checkoffs Trainees will complete Qualification Standards Checkoffs in the following systems, operations and procedures. QSCs will be limited to the knowledge required of Fuel Handling SR0s.
- 1. Reactor Coolant Systems
- 2. Low Head Safety Injection
- 3. Residual Heat Removal
- 4. Fuel Pool Cooling and ,Putificatiof
- 5. Reactor Plant River Water' *
- 6. Component Cooling Water .
- 7. Fire Protection System Revision 0 Page 2.42
i DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.6
- 8. Supplementary Leak Collection and Release System
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- 9. Process Cooling Systems
- 10. Containment Ventilation
- 11. Drains and Vents
- 12. Airlock operations
- 13. Radiation Monitoring System 2.6.4.3 Phase 3 - On-the-Job Training
- . Trainees will actively participate in refuel operations, either as fuel handlers or as Refueling Shift Supervisors-under-instruction. A combination of both is recommended. 2.6.5 Program Administration 2.6.5.1 Responsibility Responsibility for supervision and coordination of Fuel Handling SR0 Train-ing is delegated to the Director - Operations Training. 2.6.5.2 Qualification Standards Checkoffs Guidelines for the completion of Phase 2 Qualification Standards Checkoffs will be as given in Volume 1, Section 2.1 for the Licensed Operator Training Program. 2.6.6 Program Documentation The following documentation will be maintained with program records in accordance with Volume 1, Chapter 6. Revision 0 Page 2.43
( DUQUESNE LIGHT COMPANY Vol. 2 b Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.6
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- 1. A Training Roster (Volume 1, Figure 5.7) will be initiated at the completion of each course of Phase 1 training, and at the com-pletion of Phase:: 2 and 3.
- 2. Phase 2, Systems and Equipment Qualification Standards Checkoffs, will- be documented on 'the Trainee Checkoff Sheet; System Qualifica-
. tion Standard (Volrame'2, Figure 2.1.3).
- 3. A record of the results of examinations will be maintained.
- 4. Phase 3 on-the-job training will be documented via page 1 of the On-Shift Training Verification (Volume 2, Figure 2.1.5).
fw 2.6.7 Program References J}, U.S. Nuclear Regulatory Commission Memorandum; Limited License - November 21, 1967. 2.6.8 Summary of Figures
- 1. Training Roster - Volume 1, Figure 5.7.
- 2. Trainee Checkoff Sheet; System Qualification Standard - Volume 2, Figure 2.1.3.
- 3. On-Shift Training Verification (Volume 2, Figure 2.1.5).
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;DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2
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Training Administrative Manual Sect. 2.7 2.7 REFUELING LICENSE RETRAINING PROGRAM 2.7.1 Program Objective The objective of refueling license retraining -is to assure the continued competency of personnel assigned as Refueling Shift Supervisors during refueling and core alterations. - 2.7.2 Program Applications I
}
Personnel who possess a Senior Reactor Operator's license limited to fuel handling will be continuously enrolled in the Refueling License Retraining Program.
~D O
4 The Refueling License Retraining Program will be conducted continuously for 24 months and upon completion will be followed by successive 24-month programs , each of ' which will begin - promptly at the conclusion of the preceding program. .Each 24-month retraining program is comprised of two retraining cycles 1 year in length. 2.7.3 Scope of Training Refueling license retraining is conducted in four phases of instruction or practice, as follows:
- 1. Phase 1 - Annual Written Examinations. Licensees are administered a comprehensive written examination limited in scope to the duties and responsibilities of Fuel Handling SR0s.
- 2. Phase 2 - Formal Classroom Training. Structured classroom training
, based in part on the results of annual written examinations, Revision 0 Page 2.45 i
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m Vol. 2 ( DUQUESNE_ LIGHT COMPANY Nuclear. Group _ Ch. 2 Training Administrative Manual : Sect. 2.7
- 3. Phase 3 ~- Oral Examinations. Walk-through of procedures, controls .
and indications related to Fuel Handling SR0 duties.
- 4. Phase 4 - . Individual - Study. Review and self-study of significant
. operating experience reports, procedure reviews, Incident Reports, design changes-and procedure changes.
I 2.7.4 -Training Outline i 2.7.4.1 -Annual Written Examinations Once each ' year, licensees will complete a cor.prehensive written examination similar in scope and style to -licensing examinations administered for Fuel
. Handling SR0s by the USNRC. The purposes of these examinations will be to O evaluate effectiveness of the prior year's retraining, and _to identify areas.
where training may be required to upgrade knowledge. An overall grade of ^ 80% combined with a grade of at . least 70% in each category will be - . considered passing. 4 1. . Licensees who fail the . annual written examination will be relieved of . duties requiring a license and will participate in an accelerated retraining program. Refer to Subsection 2.7.5.3. I 2. Licensees will be required to complete formal classroom training in [ any category for which a score of'less than 80% is earned.
- 3. The Manager - Nuclear Training, the Director - Site Operations, and the -Plant Manager will review the results of written examinations l _
to ' determine where emphasis in retraining is needed. Where appro- +
.priate, results of this review will be incorporated into Phase 2.
r :n l} f Revision 0 Page 2.46
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/ DUQUESNE LIGHT COMPANY Vol. 2 V Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.7 9 2.7.4.2 Formal Classroom Training The scope, duration and precise content of -formal classroom training will vary according to needs identified for individual cycles of the Refueling License Retraining Program. Instructional emphasis will be placed where annual written examinations- indicate that weaknesses may be developing. Fuel Handling SR0s will attend Modules I through IV of the Licensed Operator Retraining Program each cycle. (Refer to Section 2.2.) Modules V and VI will be developed specifically for Fuel Handling SR0s. Module V will l 1 consist of formal classroom training and the Phas'e 3 oral examinations. Module VI will be dedicated to the annual written examinations of Phase 1. 2.7.4.3 Oral Examinations
) \
,h Proficiency with normal, abnormal and emergency procedures will be maintained by requiring licensees to demonstrate their familiarity with controls, indications, actions to be taken and expected plant responses. As a minimum, this will be achieved by walk-through exercises. 2.1.4.4 Individual Study Licensees will complete periodic reading assignments. The subjects covered in reading assignments may include, but not be limited to the following as they relate to the duties and responsibilities of Fuel Handling SR0s:
- 1. Facility design changes
- 2. Facility prodedure changes
- 3. Technical Specification changes
- 4. Emergency Preparedness Plan
- 5. Radiological control procedures i
- 6. Temporary station procedures O
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'( DUQUESNE LIGHT COMPANY Vol. 2 k'- Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.7
- 7. Station Industrial Security Procedures
- 8. Abnormal and emergency procedures 2.7.5 Program Administration 2.7.5.1 Responsibility Responsibility for coordination. and supervision of the Refueling License Training Program is delegated to the Director - Operations Training.
2.7.5.2 ' Accelerated Retraining . - Any . licensee wt> scores less than 80% overall on the annual written examina-j- . tion, or scores less than 70% _in any category, will be relieved of duties
\s requiring a license and will be placed in accelerated retraining under the direction of the Manager - Nuclear Training, or his alternate. The licensee will be reinstated to licensed duties 'after completing the prescribed retraining and scoring at least 80% overall on re-examination and at _1 ast 70% in.each category.
2.7.5.3 Periodic Examinations "eriodic written examinations or quizzes will be administered to assess licensees' knowledge of topics covered in Phase 2 formal classroom instruc-tion. Remedial training will be performed for licensees who score less than
. 80% on periodic examinations.
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. DUQUESNE LIGHT COMPANY Nuclear Group Vol. 2 Ch. 2 Training Administrative Manual Sect. 2.7 2.7.6 Program Documentation Each of the documents specified in this Subsection will be maintained with the program records for each cycle of the Refueling License Retraining Program.
- 1. A record of each licensee's participation _in the Licensed Operator Retraining Program will be maintained on the Refueling License Retraining Summary (Figure 2.7.1).
\
- 2. Attendance during Phase 2 formal classroom training will be reported ' on the Retraining Attendance Record (Volume 1, Figure 5.8).
(/ 3. Phase 4 individual study will be programmed on a monthly basis. The Director - Operations Training will prepare the Individual Study Guide (Figure 2.2.2) and distribute a copy to each licensee.
- 4. Completion of Phase 3 oral examinations will be. documented on the Fuel Handling SR0 Walk-Through Training Checklist (Figure 2.7.2).
- 5. A copy of each annual examination, periodic examination or quiz, and the answers provided by licensees will be maintained with program records. l
- 6. The Summary of Recommendations (Figure 2.2.5) wiil be used to document the recommendations for training emphasis arising from the reviews of annual written examination results.
b)
-LJ Revision 0 Page 2.49
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F Yol . 2 -
'[' DUQUESNE LIGHT COMPANY Nuclear Group Ch. 2.
Training Administrative Manual Sect. 2.7
'2.7.7 Program References
'U.S. Nuclear Regulatory Commission Memorandum; Limited License -
November 21, 1967. 2.7.8 Summary of Figures
.1. Refueling License Retraining Summary - Figure 2.7.1
- 2. Fuel Handling SR0 Walk-through Training Checklist - Figure' 2.7.2
- 3. Retraining Attendance Record - Volume 1, Figure 5.8 4, Individual Study Guide - Volume 2, Figure 2.2.2
- 5. Summary of Recommendations - Volume 2, Figure 2.2.5 1-O Revision 0 Page 2.50 t
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/ DUQUESNE LIGHT COMPANY Vol. 2 C/ Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.9 2.9 UNIT I/II CROSS-TRAINING PROGRAM DESCRIPTION 2.9.1 Purpose The objective of Unit II Cross-Training is to prepare Beaver Valley Power
- Station Unit I licensees for dual licensing on Beaver Valley Units I/II.
Training goals are to familiarize operating personnel with:
- 1. Unit II systems and components and the differences between Unit I and Unit II systems.
2.' The approved methods for operating Unit II systems and components by use of normal operating procedures.
. (~T V 3. Reactor and plant controls and station parameters to the extent that operating personnel are able to take correct action in the event of an unusual occurrence or emergency.
- 4. Use of Unit II abnormal and emergency procedures.
2.9.2 Personnel to be Trained Unit I/II Cross-Training will be completed by personnel licensed on Unit I and required to hold a Unit I/II dual license. The training program is applicable to Reactor Operator and Senior Operator licensees. < 2.9.3 Scope of Training The Unit II Cross-Training Program is approximately 8 months in length and includes Unit 'II System Difference Training, Procedure Training, Simulator Training and License Review Series. The scope of Unit I/II Cross-Training will be adjusted on the basis of the examination to be administered Revision 0 Page 2.54
l r DUQUESNE. LIGHT COMPANY Vol. 2 s Nuclear Group Ch. 2
. Training Administrative Manual Sect. 2.9 e
by USNRC Region 1. For example, if a waiver is granted for theoretical sections of the -written examination, and for' the. operational examination,
- theory review and simulator training may not be performed.
. 2.9.4- Training and Outline and Schedule
- 2. 9. 4.1' ~ Unit;II System Difference' Phase The 15-week -System Difference Training phase .is based on the differences
. between Unit I and Unit II systems. The student, who is already knowledge--
able :of Unit l' systems. -is taught the differences, such that he/she may qualify on the associated Unit II systems. Approved lesson plans have been
' developed for _this phase to specifically explain these differences. A copy of the Unit I/II Difference Analysis is also provided to each student.
In addition to classroom instruction on each of. the selected systems -the student is provided with ample study time and time to trace out the systems
- in-Unit II. Systems with limited. differences may be covered by stu(y pack-ages provided to the student, and an Instructor will be available for ques-tions and answers.
2.9.4.2 ' Plant Layout Phase The student is given several weeks of in-plant familiarization at Beaver Valley Power Station Unit I.
.Several days are provided at the .beginning of the Unit II System Difference
- Training phase for-initial Unit 11 exposure and familiarization. This por-
- tion of the training consists of guided tours by qualified Instructors, and
- time for students to tour the plant individually, Three weeks are scheduled at the' end of the Unit II System Difference Training phase for in-plant training and familiarization. The student is. given a detailed list of major Revision 0 Page 2.55
s b'l O DUQUESNE LIGHT COMPANY Nuclear Group Vol. 2 Ch. 2 Training Administrative Manual Sect. 2.9 equipment and components which he/she is required to locate and sign off on. This component checklist is part of the system checkout process. Trainees will review and study plant system differences and complete system checkouts by participating in system-oriented oral and/or t:ritten examina-tions along with the component checklist described above. 2.9.4.3 Procedures / Technical Specifications Training Phase This phase will cover normal! operating procedures (startup and shutdown), emergency procedures, and abnormal procedures, with emphasis on the dif-ferences between Unit I and Unit II. Technical Specifications will also be covered during this phase. 2.9.4.4 License Review Series Phase This phase will consist of a review of major safety-related system differ-ences, instrumentation and control functions, administrative procedures (including Technical Specifications), and various areas of related theory. This program will be based on the results of a pre-examination and the type of examination to be administered by USNRC Region 1. 2.9.4.5 Simulator Training Phase , A Simulator Training program consisting of a minimum of 30 Simulator hours has been developed to ensure all candidates . applying for dual license receive simulator training and practice on the categories of control manip-ulations specified in NUREG-0737. The program is intended for personnel currently licensed for Beaver Valley Unit I. (Note: This program will not be completed if USNRC Region I waives the operational examination on the basis of the existing experience of candidates.) Revision 0 Page 2.56 r
O DUQUESNE LIGHT COMPANY Vol. 2-U Nuclear Group Ch. 2 Training Administrative Manual Sect. 2.9 2.9.5 Program Administration Responsibility for administration of the Unit I/II Cross-Training Program is delegated to the Director - Operations Training. 2.9.6. Program Documentation
- 1. The results of individual written examinations will be documented on the Examination Grade Report (Volume 1, Figure 5.10) and filed with program records.
- 2. The results of written examinations will be transcribed onto the Personnel Grade Summary (Volume 1, Figure 5.11). After the completion of training, Personnel Grade Summaries will be v maintained with program records.
- 3. A Training Roster (Volume 1, Figure 5.7) will be initiated as applicable at the completion of phases or courses.
- 4. The Unit I/II Cross-Training Program will be scheduled on the 10-week Trainir.g Program Schedule (Volume 1, Figure 5.5).
Following the completion of training, 10-week Schedules will be
- 1. filed with program records as permanent documentation of how the program was conducted.
2.9.7 Program References 2.9.7.1 Requirements / Commitments
- 1. NUREG - 1021, Section ES - 106; Administration of Examinations at Multi-Unit Facilities.
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Vol. 2
.O DUQUESNE LIGHT COMPANY Nuclear Group Ch. 2 Sect. 2.9
.- Training Administrative Manual 2.9.7.2 Recommendations / Guidance None 2.9.8 Summary of Figures
- 1. 10-Week Training Program Schedule - Volume 1, Figure 5.5
-2. Training Roster - Volume 1, Figure 5.7
- 3. Examin'ation Grade Report - Volume 1, Figure 5.10 4 Personnel Grade Summary - Volume- 1, Figure '5.11 O
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, J (' ' DUQUESNE LIGHT COMPANY Vol. 2 ' ( . Nuclear Group Ch. 2 Training Administrative Manual Fig. 2.1.3 . TRAINEE CHECK 0FF SHEET; SYSTEM QUALIFICATION STANDARD System: Unit: }, Trainee: A. Function 1 B. Flow ~ paths
.C. System components D. ~ System parameters E. Technical Specifications F. ' Principles of operation .
./) G. Plant tour.
QJ H. Control Room tour
'I. Responses during transients
-J. ' Normal, abnormal and emergency procedures K. Incident Reports i
Written examinaton grade: , Instructor Date t a Revision 0 Page 2.61 l
3 .y. .es DUQUESNE LIGHT COMPANY Yol . 2 i ) Nuclear Group Ch. 2
'" Training Administrative Manual Fig. 2.1.4 Page 1 of 2 ON-SHIFT TRAINING CHECKLIST Trainee: Class :
INSTRUCTIONS: Place your initials opposite each activity as it is completed. R0 candidates will perform the duties of the NC0 under instruc-tion. SR0 candidates will . perform the duties of the NSOF or NSS under. instruction. All candidates will. perform on-the-job training manipulations as operational situations arise.
. Time Activity I in Days _ ,
Initials
- 1. (_RO) Familiarization with NC0 duties and'responsi-bilities. Review Operating Manual Chapter 48 Sections 1.48.2,1.48.8,1.48.9(A,B,C,H,I,J,K) and 1.48.3(G,H) (1) e)
( (SR0) Familiarization with NSOF and NSS duties and responsibilities. Review Operating Manual Chapter 48, Sections 1.48.2, 1.48.5, 1.48.8, 1.48.9(A,B,C,H,I,J,K,0) and 1.48.3(G,H) (1)
- 2. Overall Control Room familiarization, Control Room materials and locations (1)
- 3. Review Operating Manual Chapter 54 - NCO, NSOF and NSS logs, shift turnover procedures and checklists (1)
- 4. Control board locations and familiarization (1)
- 5. Surveillance logs (L5) and Technical Specifications cross-reference (2)
- 6. Alarm procedure familiarization. Become familiar with annanciator window reference and use of Alarm Response Manuals (2)
- 7. Nuclear instrumentation racks and radiation monitor familiarization (1)
- 8. Process Control and Shutdown Panel familiarization (1)
O (Q (continued) Revision 0 Page 2.62
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,-s . DUQUESNE LIGHT COMPANY Yol . 2 7 Nuclear Group Ch. 2 \- Training Administrative Manual Fig. 2.1.4 Page 2 of 2 ON-SHIFT TRAINING CHECKLIST (continued)
Time Activity in Days Initials
- 9. Nuclear Instrumentation Operations Surveillance Tests (OSTs).
Review: OST 1.2.1 Power Range Functional Test OST 1.2.2 Intermediate Range Functional Test OST 1.2.3 Source Range Functional Test (1)
- 10. Review Reactor Startup Procedure 1.50.4. Review Estimated Critical Position Calculation and Shutdown Margin Calculation OSTs 1.49.1 and 1.49.2 (2)
- 11. Review Heat Balance Procedure 1.54.4 and RCS Water Inventory OST 1.6.2 (1)
- 12. Review Main Turbine startup and shutdown procedures
- 1. 26.4C, D ,E ,F ,0,Q ,R ,T ,U ,W (2)
- 13. Review Main Generator startup and shutdown procedures
- 1. 35.4 A ,B ,C ,D ,F .G .I ,L (2)
- 14. Review Operating Manual Chapter 50 (2)
- 15. Review Operating Manual Chapter 51 (2)
- 16. Review Operating Manual Chapter 52 (2)
- 17. Review Abnormal Procedures, Operating Manual Chap. b; (2)
- 18. Review Emergency Procedures, Operating Manual Chap. 53 (3)
- 19. Review Liquid Waste Discharge Procedures 1.17.4V,W (1)
- 20. Review Gaseous Waste Discharge Procedure 1.19.4E (1)
- 21. EPP familiarization (2)
- 22. Station tour with plant operator (1)
.\ v Revision 0 Page 2.63 m
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'DUQUESNE LIGHT COMPANY Vol . 2 f' Nuclear Group Ch. 2.
Training Adninistrative Manual Fig. 2.1.5-Page 1 of 3 ON-SHIFT TRAINING VERIFICATION' . t
. Name: Class :
(Total time required is 60 days.) Day Date Shift NSOF/NSS/ Instructor 1-2 3 t 4 !- 5 i f A i 6 V 7_ 8 i -- 9 10 , 4 11 l' 12' F 13 14 _ 15 . 16 e i 17-i 18 L 19
- O .
Revision 0 Page 2.64 , i
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. DUQUESNE LIGHT COMPANY Vol . 2
}.
' Nuclear Group Ch. 2 0 c- s Training Administrative Manual Fig. 2.1.5 Page 2 of 3
~0N-SHIFT TRAINING VERIFICATION (continued)
Name: C1 ass : Day Date Shift NSOF/NSS/ Instructor 21 22 23 24 t
~ ' 25 26 --
27 28 29 30 31 32 s 33 34 35 36-37 38 39-40
~
0 Revision 0 Page 2.65 l
s -DUQUESNE LIGHT COMPANY Vol . 2 Nuclear Group . Ch. 2 Fig. 2.1.5 Training Administrative Manual Page 3 of 3
~
0N-SHIFT TRAINING VERIFICATION (continued) Name: Class: Day Date Shift NSOF/NSS/ Instructor 41 _ 42
- 43. ,
- 44 45
.46 47 48 49 50 51 52 53 -
54-55 56 57 58 59 60 9 0 Revision 0 Page 2.66
- _ = . , . .-. . - - . -.- -. .- - - - _ _ _ _
I DUQUESNE LIGHT COMPANY- Vol . 2 ~. -1(; .:;a.) '- Nuclear Group Ch. 2
'v ' Training Administrative Manual Fig. 2.2.1
- - Pace 1 of 5 ;
LICENSED OPERATOR RETRAINING-CYCLE
SUMMARY
License Date ' Name': ~* Number: Issued: Retraining Cycle: A.- WRITTEN EXAMINATION RESULTS (End of prior cycle) Date: Examination Re-examination Reactor Operator Examination Grade Grade
. 1. - Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow % %
- 2. - Plant Design, Including Safety and Emergency Systems % %
.r y
.y
- 3. ' Instruments and Controls %- %
- 4. Procedures--Normal, Abnormal, Emergency and Radiological Control % %
- g. Average: % %
Senior' Reactor Operator Examination
- 5. Theory of Nuclear Power Plant Operation, Fluids and Thermo-dynamics % %
- 6. Plant Systems Design, Control and Instrumentation _
- 7. Procedures--Normal, Abnormal, Emergency and Radiological Control ,
- 8. Administrative Procedures, Conditions and Limitations % %
Average: % % O Revision 0 Page 2.67
, DUQUESNE LIGHT COMPANY Yo1. 2 Nuclear Group Ch. 2 (d' Training Administrative Manual Fig. 2.2.1 Page 2 of 5 .
LICENSED OPERATOR RETRAIhING CYCLE
SUMMARY
(Continued) Name: Retraining Cycle: Approx. B. LECTURE ATTENDANCE RECORD Hours Topic . Required for Completed I. Theory and Principles of Operation <80% Cat.1 or 5 II. Thermodynamics, Heat Transfer and Fluid Flow <80% Cat.1 or 5 III. Plant Instrumentation and Controls <80% Cat. 3 or 6 IV. Radiation Control and Safety <80% Cat. 4 or 7 (v V. Plant Protection / Engineered Safety Systems <80% Cat. 2 or 6 VI. Administrative Controls All licensees VII. Abnormal and Emergency Procedures j Review All licensees VIII. Plant Status Updates All licensees l C. INDIVIDUAL STUDY GUIDE
SUMMARY
Month Complete (/) Month Complete (/) September March October April November May December June January July l February August Revision 0 Page 2.68 l
DUQUESNE LIGHT COMPANY 3 Vol. 2 ' O Nuclear Group Ch. 2
' Training Administrative Manual -
Fig. 2.2.1. '- Page 3 of 5 LICENSED OPERATOR RETRAINING CYCLE
SUMMARY
(Continued) Name: Retraining Cycle: D. REACTIVITY MANIPULATION SUM ARY , ,
. Number of reactivity manipulations completed during cycle:
E. ANNUAL OBSERVATION Annual observation complete on - 3 y. s Date s
,. i i -
- F. MDDULE-QUIZ GRADES.
s L Module I: II: III: IV: Grade % % % % G. COMMENTS: j m, . Revisicn 0 Page 2.69
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DUQUESNE LIGHT COMPANY Vol. 2 -( Nuclear Group Ch. 2
- V) Training Administrative Manual Fig. 2.2.1 Page 4 of 5 L
LICENSED OPERATOR RETRAINING CYCLE
SUMMARY
(Continued) Name: Rt^ raining Cycle: I. WRITTEN EXAMINATION RESULTS (End of this cycle) Date: Examination Re-examination Reactor Operator Examination Grade Grtde
- l. Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow ,
- 2. Plant Design, Including Safety and Emergency Systems % %
- 3. Instruments and Controls % %
m . 4. Procedures--Normal, Abnormal, Emergency ( and Radiological Control % % Average: % % Senior Reactor Operator Examination
- 5. . Theory of Nuclear Power Plant Operations, Fluids and Thermodynamics % %
- 6. Plant Systems Design, Control and Instrumentation % %
- 7. Procedures--Normal, Abnormal, Emergency and Radiological Control % %
- 8. Administrative Procedures, Conditions and Limitations % %
Average: % % Results' reviewed by: Manager - Nuclear Training Date Director - Site Operations 'Date Plant Manager Date Revision 0 Page 2.70
.2
t ' Vol. 2 DUQUESNE LIGHT COMPANY
~
[ ^ Nuclear Group Ch. 2 n ; .' f Training Administrative Manual Fig. 2.2.1-Page 5 of 5
! LICENSED OPERATOR RETRAINING CYCLE Sul#%RY-.(Continued)-
p Name: Retraining Cycle: J. ACCELERATEDRETRAINING(Lessthan80%overall,lessthan70%anycatego.ry) l. i I- 1. . Lice.nsee removed from licensed duties:
. Date
- 2. Accelerated retraining program assigned:
Date
.--\ - l \
- 3. Accelerated retraining program approved:
l- Director OperatioFs Training Date Manager..- Nuclear Training Date {
- 4. Re-examination passed, licensee returned to licensed duties:
_ Manager --Nuclear Training Date F 1 k 7 4 4 Revision 0 Page 2.71 e L .:, . . - . . - , - . - - . . _ . . . , , , _ _ _ _ _ . _ . . _ . . _ . . - . . . _ _ . . , , . . _ - _ - -- ,._-_.. - .,..- - ____,-..- _, .
O .- DUQUESNE LIGHT COMPANY Vol. 2
- -~ ~ ~ Nuclear Group Ch. 2 Training Administrative Manual
. Fig. 2.2.2 s
INDIVIDUAL STUDY GUIDE Licensee: Date: Retraining Cycle: .
-Instpuctions: The following areas are'to b2 reviewed by individual study.
An oral quiz will be given to determine your knowledge of the subject (s) on or about the end of: Month, Year A. REVIEW: O~ Individual study c.ompleted: - Licensee l B. RESULTS OF ORAL QUIZ: SAT OUNSAT WEAK AREAS: b
. Senior Reactor Operator C. DISPOSITION:
Date Director - Operations Training Revision 0 Page 2.72
,r DUQUESNE LIGHT COMPANY Vol . 2 Nuclear Group- Ch. 2' O Training Adninistrative Manual Fig. 2.2.3 ON-THE-JOB TRAINING RECORD (Exhibit only)
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l DUQUESNE LIGHT COMPANY Vol . 2 Nuclear Group Ch. 2 [f\ s/ Training Administrative. Manual Fig. 2.2.4 Page 1 of 9 [ ORAL EXAMINATION REPORT i Name Class. 'Date i
. Qualification Desired Current Qualification
~Overall Grade:
SAT OUNSAT. Examiner-Examiner. Reviewed by Category Category . . Grade Weak Areas
- 1. Principles of Reactor Theory
- 2. Heat Transfer, Fluid Flow and Thermodynamics
.t p) '
- 3. Plant Design
- 4. Plant Instrumentation and~
Control.
-5. Radiation Protection and Health Physics
- 6. Administration
- 7. Transient, Accident and Instrument Failure Analysis
- 8. Normal, Abnormal ~and Emergency Procedures Student review:
4 O Revision 0 Page 2.74
1 l DUQUESNE LIGHT COMPANY Yol. 2 O s- / Nuclear Group Training Administrative Manual Ch. 2 Fig. 2.2.4 Page 2 of 9 ORAL EXAMINATION REPORT (Continued) l
- 1. Principles of Reactor Theory Grade ~ .
I e l l Overall Grade: Connents (Required for any ~ area not graded satisfactory): 1 I l l 1 '( Revision 0 Page 2.75
.,7 ; _
x 1 L Yo1. 2 O DUQUESNE LIGHT COMPANY Nuclear Group Training Administrative Manual Ch. 2 Fig. 2.2.4 Page 3 of 9
- ORAL EXAMINATION REPORT (Continued)
- 2. Heat Transfer, Fluid Flow and Thermodynamics Grade 1
i O Overall Grade: i Comments (Required for any area not graded satisfactory): t I i
)
Revision 0 Page 2.76 J
J-n DUQUESNE LIGHT COMPANY Yol . 2 ( t
~
Nuclear Group Ch. 2 Training Administrative Manual Fig. 2.2.4
- Page 4 of 9 ORAL' EXAMINATION REPORT (Continued)
- 3. .
Plant Design Grade t 1 } O Overall Grade: I Coments (Required for any area not graded satisfactory): t 3 O + U. Revision 0 Page 2.77
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4 i-DUQUESNE LIGHT COMPANY Yol . 2 Nuclear Group Ch. 2 Training Administrative Manual Fig. 2.2.4 c- Page 5 of.9 ORAL EXAMINATION REPORT (Continued)
- 4. Plant Instrumentation and Control Grade J
j -. Overall Grade: Coments (Required for any area not graded satisfactory): I l
. l
- O .
, Revision 0 Page 2.78
_- s DUQUESNE LIGHT COMPANY Yol. 2 L s Nuclear Group Ch. 2 Training Administrative Manual Fig. 2.2.4 Page 6 of 9 ORAL EXAMINATION REPORT (Continued)
- 5. Radiation Protection and Health Physics Grade i
O Overall Grade:
.Coments (Required for any area not graded satisfactory):
O Revision 0 Page 2.79
I fS DUQUESNE LIGHT COMPANY Yo1. 2
'6 Nuclear Group Ch. 2 Training Administrative Manual Fig. 2.2.4 Page 7 of 9 ORAL EXAMINATION REPORT (Continued)
- 6. . Administration Grade 4
4 i I l t O Overall Grade: I Coments (Required for any area not graded satisfactory):
~
i O Revision 0 Page 2.80 t
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DUQUESNE LIGHT COMPANY Yol . 2 fi J Nuclear Group Training Administrative Manual Ch. 2 Fig. 2.2.4 Page 8 of 9 ORAL EXAMINATION REPORT (Continued)
- 7. Transient, Accident and Instrument Failure Analysis Grade O
Overall Grade: Connents (Required for any area not graded satisfactory): l Revision 0 Page 2.81
I (g g.. DUQUESNE LIGHT COMPANY Nuclear Group . Yol . 2 Ch. 2
, Training Administrative Manual Fig. 2.2.4 Page 9 of 9 ORAL EXAMINATION REPORT (Continued)
- 8. Normal, Abnormal and Emergency Procedures Grade O
Overall Grade: Connents (Required for any area not graded satisfactory): O Revision 0 Page 2.82
DUQUESNE LIGHT COMPANY Vol. 2 Nuclear Group Ch. 2
?O Training Administrative Manual Fig. 2.2.5 SUMARY OF RECOMtENDATIONS
. Examination
Title:
Date(s) Administered: Based on a review of the forgoing examination, emphasis is recommended in tha following areas during the requalification cycle: ' , Exam Question
- Section Number: Topics to be Emphasized 4
i E : 4 i \ 4 (Attach continuation sheets if necessary.) i Manager - Nuclear Training Date Concurrence:
- Director - Si,te Operations Date Concurrence
- Plant Manager Date
- - Revision 0 Page 2.83 2
- - . . , - , . , , _ , _ _ . _ _ , , , . . , _ . _ _ . . . .._, . . - _ . - _... _ _ -,-,. - ._., _ . ,, ._ . _. .,.. .. ,,_,~,_.-._ _.. .. - _..,- -
4 DUQUESNE' LIGHT COMPANY Vol. 2. Nuclear Group .Ch. 2 1 - Training Administrative Manual Fig. 2.2.6-
- RETRAINING PROGRAM CYCLE REPORT To: ; General Managerc. Nuclear Services Requalification year:
Total hours; classroom: Total hours simulator:. All licensees completed all required portions of the requalification program with the. exception of: 0Noexceptions O Attachment- O As follows: Corrective actions and schedule to be applied to the above: Not applicable O Attachment. As follows: Summary of significant problems and recommended corrective actions or actions taken: ONone O Attachment As follows: s With the exceptions noted above,'the requalification program was completed in a satisfactory and effective manner. Director Operations Training Date Revision 0 Page 2.84
l Vol. 2 Ch. 2 Fig. 2.4.4 l/ Page 1 of 46 DUQUESNE LIGHT COMPANY Nuclear Group Non-Licensed . Ooerator On-The-Job Trainina Procram Name Emp. No. Soc. Sec. No. Job Title . Revision 0 O . Page 2.91
.. . . . . . . ~ . . . = - . - . , - . . -. -- -____
Vol. 2 Ch. 2 Fig. 2.4.4 rn l'- Page 2 of 46 D) The following watchstation requirements may be signed by a qualified Startup Operator, Instructor, Nuclear Control Operator, Nuclear Shift j- Supervisor or Nuclear Station Operating Foreman. All personnel who are involved in checking off a particular topic should initial the i topic when. completed. When all the requirements are met for a parti-
- . cular topic, the student may then get that topic signed off com-g plately, and dated. Only the Nuclear Shift Supervisor or Nuclear Shl.t Operating Foreman. pay sign the Master Sign-Off page.' Sections one through six should be completed prior to commencing watchstation
}' qualifications where possible. Attempt to perform as many items as possible, discussing or simulating only those items that are necessary 4- to be done in this manner. I i e i O f 1 . i a Revision 0 4
+
iO i Page 2.92
- . . ~ , . ~ . . _ . _ , . _ _ . _ - . _ , . _ _ . . _ _ , _ . _ , _ _ _ - . _ _ . _ . - _ _ . . , _ . _ , _ . _ . . _ _ _ . _ . . . -
Vol. 2 Ch. 2 Fig. 2.4.4 Page 3 of 46 i
)
DUQUESNE LIGHT COMPANY NUCLEAR GROUP Nuclear Services Unit i NON-LICENSED ON-THE-JOB OUALIFICATION CHECKOFF MASTER SIGN-OFF PAGE NSS/NSOF Sicnature Date I. Valving / II. Monitoring Equipment Performance / III. Use of Special, Equipment and / Tools IV. Administrative, Communications, / Fire Protection System V. Emergency, Casualty Controls, / Fire Fighting
~VI. Plant Tour /
VII. Turbine Plant Operator / VIII. Auxiliary Building Operator / IX. Water Treating Operator /
'X . Outside Operator /
XI. Electrical Switching Program / Revision 0 Page 2.93
Vol. 2 Ch. 2 Fig. 2.4.4 Page 4 of 46
)
. NON-LICENSED ON-THE-JOB OUALIFICATION CHECK-OFF I.. VALVING Terminal Learnina Obiective:
During all' modes of operation, the trainee should be able to: Determine the position of any valve associated with the various plant systems, as per OM 48.9. Properly change a valve line-up. State what to do about valves n21 in their proper position. i State the requirements for venting or draining contaminated systems, as per OM 48.6A, General Description and Precautions. Enablina Obiectives: A. Check valve position, as per OM 48, / Section 9.J Signature / Date
- 1. Discuss, or perform the verification of /
safety or relief valves D21 gagged or Initials / Date
-blocked.
- 2. Discuss or perform a check on the Initials / Date following listed valves, to determine open or closed positions of that valve, as per OM 48.9.J.
Globe Valve / Butterfly Valve / Ball Valve / Gate Valve / Diaphragm Valve / Motor Operated Valve / Air Operated Valve /
- 3. Discuss the precautions you must take when /
shutting a diaphragm valve and explain why.
- 4. Perform or discuss how to take manual con- /
-[~% trol and locally operate a motor driven x valve (MOV). Revision 0 Page 2.94
+
Vol. 2 Ch. 2 Fig. 2.4.4 Page 5 of 46 (f 5.- Discuss the precautions to take, and the / problems that could occur upon taking manual control of a motor operated valve, and closing it hard on-its seat. + :
- 6. Perform or discuss manual operation of air- /
operated valves.
- 7. Perform or discuss how to locally fail air /
to an air-operated valve to place it in its fail-closed position. 1B . Perform'a. verification of the status of at / least three (3) safety related valves, using the padlock log and the proper procedure, as stated in OM 48.9.J.
- 9. Perform or discuss the proper method for /
for filling out an OM Valve List.
- 10. Discuss the requirement for double-O verification of a valve position.
/
B. Change Valve Line-ups as per OM 48. / Signature / Date
- 1. Perform or discuss isolating and un- /
isolating a pump, stating the precau- Initials / Date tions to follow, as per OM 48.6.A.
- 2. Discuss manipulation of a locked valve, /
that will be out'of NSA for an extended . period, or.on clearance, as per OM 48.5.C. Include procedure for clearing and returning to NSA any critical and/or safety related valve.
- 3. Discuss manipulation.of an ESFS valve /
found out of normal position, as per 48.5.E.
- 4. Discuss or perform the updating of valve /
, positions, after they have been changed, Initials / Date as per OM 48.5.E. .
() C. Venting or draining contaminated systems, per OM 48.6.A. and 48.6.B caution Signature /
/
Date Revision 0 Page 2.95
a l Vol. 2 Ch. 2 Fig. 2.4.4 Page 6 of 46 II. MONITORING EOUIPMENT PERFORMANCE Terminal Learnina Obiective During all modes of operation, the trainee should be able to:' Perform equipment checks on any piece of station equipment,
-either shutdown, running, or for a start-up.
Perform the addition of oil to any major piece of station equipment,.using the lube oil log for information as to the proper lubricant for the equipment. Enablina Obiectives: A. Perform or discuss standby equipment / checks Signature / Date
- 1. Discuss verifying equipment clear to /
operate Initials / Date
- 2. Discuss the importance of a proper lube /
oil, cooling water, or seal water line-up. Initials / Date
/ 5. Perform or discuss an operability check /
of a major piece of equipment to be Signature / Date started up.
- 1. Check for noise, vibration, bearing and /
seal temperatures, oil flow and tempera- Initials / Date ture, and a cooling medium. C. Perform or discuss a check on a running / piece of equipment. Signature / Date
- 1. Check for noise, vibration, bearing and /
seal temperatures, oil flow and tempera- Initials / Date ture, and a cooling medium. D.- Perform or discuss the proper method of / filling a pump or motor bearing ollur. Signature /-Date
- 1. Discuss when an oiler should be filled, /
and how to select the proper lubricant. Initials / Date
. 2. State the location of all oil storage /
areas, and the lube oil logbook. Initials / Date Revision 0 O Page 2.9'6
ir,p--.,W- ,te,%--..eir.
-, *%en w e,% e -&'-
a v Vol. 2 Ch. 2 Fig. 2.4.4 Page 7 of 46-(}
- III.USE OF SPECIAL EQUIPMENT AND TOOLS Terminal Obiective:
During all modes'of; operation, the trainee.should be able to: Perform any equipment checks that are necessary, using the proper test equipment. Operate any special equipment, or temporary equipment presently in use at this time. Operate portable radiation monitoring equipment, to provide his/her own radcon coverage whenever necessary. , Enablina Obiectives: A. Perform equipment checks on, equipment, / using: (N/A for equipment not currently used Signature /.Date , or available.)
- 1. Voltage: Glow stick, beeper, Wiggins, /
DMV Initials / Date
- 2. Speed: strobotac / '
- 3. Vibration: IRD, shaft stick, sounding rod /
- 4. Gas: 02 analyzer, explosimeter, /
draeger
- 5. Temp : pyrometer, digistick, mitimite /
- 6. Shaft End micrometer, eccentricity /
Position: dial micrometer
- 7. Leaks: Leaktech, ultrasonic detector /
- 8. Specific Hydrometer / ,
Gravity-
- 9. Wheatstone Bridge /
- 10. Discuss or simulate locating high / ,
pressure and/or high temperature steam - leaks. B. Operate Special or Temporary Equipment / Signature / Date
- 1. Jaeger Fire Pump O
/
Initials / Date
- 2. Diesel Driven Air Comprassor /
Revision 0 ! Page 2.9'7
]
Vol. 2 Ch. 2
,' Fig. 2.4.4 /'
- D}
PLge 8 of 46
- 3. ' Control Room Emergency Air Pressurization /
System Back-up Air Compressor Initials / Date
- 4. Any temporary domineralizers being used /
in the plant at this time.
- 5. Any other temporary equipment presently /
in use. List equipment: C. Operate portable radiation monitoring / equipment Signature / Date Check each detector for: physical condition, up-to-date calibration sticker, and finally, perform battery check.
- 1. Frisker (RM14/HP210) /
Initials / Date
- 2. Ion Chamber Detector (RO-2, RO-2A) /
- 3. Geiger Mueller Detector (E-530/HP270 or /
240) (E-520/HP270 or 240) Revision 0 O Page 2.918
Vol. 2
. Ch. 2 Fig. 2.4.4 Page 9 of 48 J
*V. Administrative. Communications. Fire Protection A. Administrative Terminal Obiectives During a routine shift, in any mode of operation, but preferably Mode 1, the trainee should be able to:
Take and maintain the required set of logs, pertaining to the watch station. Perform a proper shift turnover, using the shift turnover checklist for that particular watch station. Enablina Obiectives Perform or discuss the following associated with / administrative duties of an operator Signature /Date A. Administrative
- 1. Maintain required logs, records, charts, and status boards for all the watchstations.
O)- (m, a. Turbine Plant Operator / Initials / Date
- b. Water Treatment Operator /
- c. Auxiliary Building Operator /
- d. Outside Operator /
NOTE: Logs are to be checked by NSOF.
- 2. Perform shift turnover procedure /
- 3. Fill out and post Caution Tags and /
Caution Tag Log '
- 4. Fill out and post OOS stickers and OOS log /
- 5. Under proper guidance and supervision, /
perform an OST on a piece of station equipment.
- 6. Discuss the significance of red versus /
blue calibration stickers. Revision 0 Page 2.99
, ,. --. .- ~ . . . - . . . . . - .n, -. , .
Vol. 2 Ch. 2 Fig. 2.4.4 Page 10 of 48
) q B. Communications System l
Terminal Obiective '- Upon completion of this section, the operator will be able to operate the different communications systems available to him/her throughout the plant during normal and emergency operations. Enablina Obiectives i Perform or discuss the following asso- / ciated with the Communications Systems: Signature /Date
- 1. ' Operate the intra-plant communications /
. systems (PAX and Gaitronix Page Party) Initials /Date ! 2. Discuss the Stand-by and Evacuati,on Alarms:
la . What each one is used for /
- b. What each one sounds like. /
- c. When are they tested in the plant? /
( d. Where they can be actuated from. /
- e. How many times they should be . /
actuated for each type of emergency.
- 3. Operate the Calibration Communication /
System
- 4. Operate the two-way radio Walkie-Talkies /
- 5. Operate the communications high band and low /
band radios ,
- a. Discuss the purpose of each. /
C. , Fire Protection System Terminal Obiective Upon completion of this section, the operator will be able to operate the different methods of fire protection at BVPS Unit 1 during normal and emergency operations following applicable procedures. Enablina Obiectives Perform or discuss the following asso- / ciated the Fire Protection Systems: Signature /Date Revision 0 Page 2.100 I
-- ., _ . , .. , . _._ 3
. 1
).
" ^
( Vol. 2 t - Ch. 2 Fig. 2.4.4 () l Page 11 of 48 s
- 1. Normal Line-ups of,the' Fire Prot,ec_ tion Subsystems: c&
j
- a. Dry-pipe deluge'. / j Initials / Date b.;-Wet-pipe sprinkler - ./
t .- c ., , C0g / d.',- Foam /
~
e. Halon 1301 / 3 Initials / Date l
- 2. Operate motor driven fire pump, con- / .
tactor and its local controls, and the
; fire pump breaker. ', i l x -
- 3. Operate diesel driven fire puno. an'd all /
its associated auxiliary equipaont.
- 4. Operate fire detection / alarm equipment; /
be able to' reset e^ smoke detector and the associatedalards. Q ,
- 5. 5 ton and/or\10 ton C32 system - show /
where to read pressure and level, locally.
- 6. DiscussunterkngCO/Halen1301 2 pro- /
tected area afte,r system actuations.
- 7. Opbratethefollowing'fireprotection /
, , equipment to control a fire. ~
CO2 System Halon System
. Deluge System ~
Hose Stations
- Portble Fire Extir'guishers m v
- 8. Resetting of a deluge valve /
l A 6 Revision 0 O4 i., , 3' ., a I
'- Page 2.101 b
Vol. 2 l Ch. 2 Fig. 2.4.4 () Page 12 of 48 V. -Emeraency & Casualty control, and Fire Protection Terminal Obiectiveg ,' While completing this section, the student will be able to demonstrate l a knowledge of the fire brigade and the different uses of protective equipment used during abnormal operations. Enablina obiectives Perform or discuss the following con- / carning Emergency & Casualty Control and Signature / Date Fire Fighting A. Discuss the Emergency Squad (Fire Brigade)
- 1. Makeup, hierarchy ! /
Initials / Date l
- 2. Assembly locations /
'B. Discuss MSA 401 unit locations - put on and /
demonstrate proper use of an MSA 401 breathing unit.
- c. Discuss chlorine gas precautions - put on and /
' demonstrate proper use of CHEMOX breathing unit.
D. Locating and resetting tripped fire detectors / __ and smoke dampers. E. Emergency squad room familiarization / ( ) Revision'O
, Page 2.102
.,.,, . . . - _ . _ . . ~ - . _ _ . . . _ _.. - -. . . _ . . _ _ _ _ . _ ,
Vol. 2 Ch. 2 i Fig. 2.4.4 Page 13 of 48 VI. Plant Tour (Can be done while qualifying on watchstation) Terminal Obieqtly,3 Upon completion of this session, the operator will be able to identify abnormalities and normal conditions related to his/her araa and i equipment, during normal and abnormal operation. l Enablincr Obiectives ! ! Parform or discuss the following concerning a plant tour. A. Discuss or perform checks for the / , following iteam during a plant tour. Signature / Date
- l. Fire hazards, explosion hazards and other / 'I t.)
safety hazards. Initials / Data 2 .- Flooding /
- 3. Rain inleakage /
- 4. Fire barrier integrity /
iO 5. w.s Fire-door requirements /
- 6. Emergency lighting /
- 7. Structural failures /
- 8. Equipment degradation /
- 9. Signs of sabotage, forced or illicit /
entry
- 10. Safety systems integrity /
- 11. Discuss precaution and necessary /
operator awareness when radiography is
- being done in the plant.
B. Discuss response to abnormal indica- / tions and annunciator, including Signature / Date
- 1. 1. Investigation /
Initials / Date , l
- 2. Reporting /
l 3. Documentation / i- Revision 0 )
- 1 Page 2.103 I
-...__.n__..__,.-._.._.,_.___,.__ -.
-. .=. - - .
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Vol. 2 Ch. 2 Fig. 2.4.4 () Page 14 of ,48 VII. Turbine Plant ODerator Terminal Obiective Upon completion of Section 7, the operator will be able to operate the system associated with the Turbine Plant, during normal and emergency operations, using approved procedures. Enablinu Obiectives Perform or discuss the following, associated with Turbine Building Watchstanding and Plant Systems. i A. Steam Generator Blowdown System /_, Signature / Date
- 1. Normal lineup of the steam generator /
blowdown system
- Initials / Date
- 2. Startup the blowdown recovery system /
utilizing blowdown Hx
- 3. Operate blowdown domineralizers /
- 4. Bottom blowdown of theS/G's /
- 5. Monitor the S/G blowdown system /
- 6. Shift blowdown between normal and /
startup discharges
- 7. Adjust steam generator blowdown flow /
B. Turbine Plant Sampling System / Signature / Date '
- 1. Assist in lineups on the turbine plant /
sampling system Initials / Date
- 2. Startup the mechanical water chiller /_.
C. Seal Oil System / Signature / Date
- 1. Normal lineup on the seal oil system /
Initials / Date
- 2. Startup the seal oil system /
() 3. Monitor seal oil system operation Revision 0
/
Page 2.104
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Vol. 2 Ch. 2 Fig. 2.4.4 Page 15 of 48
- 4. Shutdown the seal oil system /
- 5. Operate the seal oil filters -(auto-man) /
- 6. Operate the seal oil vapor extractor /
1
- 7. Maintain seal oil temp. manually /
D. Hydrogen Gas Storage. System / Signature / Date .
- 1. Normal lineup of the hydrogen storage /
system- Initials /~Date i
- 2. . Fill the hydrogen storage system / :
- 3. Place in service and remove from service /
hydrogen cylinder tanks
- 4. Monitor hydrogen supply system operation /
E. Main Generator H2 and'CO2 System / ! Signature / Date
- 1. Remove air from the generator w/CO 2 / i' Initials / Date
- 2. Remove carbon. dioxide from generator /
with hydrogen (H 2) l
- 3. Make up H2 to the generator /
- 4. Remove H 2 from generator with CO 2 /
- 5. Remove CO 2 from generator with. air /
- 6. Op6 Tate the hydrcgen gas dryer / _
.7. Monitor generator gas system operation / !
- 8. Operate carbon dioxide compressor and /
vaporizer units (Cardox) !
- 9. Bleed and feed generator for H2 purity /
- 10. Drain generator liquid level indicators /
- 11. Leak check generator hydrogen gas system /
Revision 0 Page 2.105
c-
.l l
Vol. 2 Ch. 2 Fig. 2.4.4 Page 16 of 48 i [~')N
\. '
l F. Generator Bus Duct Cooling System / l Signature / Date i 1. Normal lineup of the bus duct cooling / system Initials / Date
- 2. Start up the bus duct cooling system /
l
- 3. Monitor the bus duct cooling system / i Initials / Date
- 4. Shift to the backup duct cooling unit /
- 5. Shut down the bus duct coolilng system /
G. Sumps and Drain System / Signature / Date
- 1. Operate a building sump pump /
Initials / Date
- 2. Operate floor drain valves to remove /
spilled oil
- 3. Be able to perform the Turbine Plant /
1 Operator's duties in Oil Spill / Prevention Plan, OM Ch. 48, Section 9, Procedure K
- 4. Discuss or perform the appropriate /
steps of the procedures for Acts of Nature - Flood, Tornado H. Instrument Air System / Signature / Date
- 1. Normal lineup of the instrument air /
system Initials / Date
- 2. Startup the instrument air system /
- 3. Monitor instrument air dryer system /
operation .
- 4. Shutdown or bypass the instrument air /
dryer system ,
- 5. Blowdown instrument air drain traps and /~
receiver tanks Revision.0 ( Page 2.106
Vol. 2 Ch. 2 Fig. 2.4.4
.(L Page 17 of 48 I. Station Air System / ,
Signature / Date
- 1. Normal lineup of station air system /
Initials / Date :
- 2. Startup, monitor and shutdown of a /
- station air compressor
- 3. Monitor station air system operation /
4.. Shift station air compressors / 5.- Initiate back-up cooling water to air / compressors
- 6. Blowdown station air drain traps and /
receivers J. River Water System / Signature / Date
- 1. Normal lineup of the river water system /
Initials / Date
- 2. Startup, monitor and shutdown the river /
water system
- 3. Operate river water pumps and heat /
exchangers in various combinations
- 4. Icolate river water from individual /
components
- 5. Cross-connect the diesel driven fire pump /
to reactor plant river water
- 6. Cross-connect turbine plant river water /
and reactor plant river water systems K. Circulating Water System / Signature / Date
- 1. Normal lineup of circ. water system /
Initials / Date
- 2. Startup, monitor and shutdown the circ /
water system
- 3. Fill and drain of the circ water system /
Revision 0 Page 2.107
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e - ... .. . . . - . - . _ _ m,. . - ,. -- .-
Vol. 2 Ch. 2 Fig. 2.4.4 Page 18 of 48
- 4. Operate.the vacuum priming system on the /
circ. water system i- 5. Deicing Subsystem operation, as per OM / 31.4.I
- 6. Clean the trash rack /
- 7. Operate / monitor the screen wash system /
- 8. Isolate a water box, restore flow to a /-
water box L~. CCT System / Signature / Date
- l. Normal lineup of CCT System '
/
I Initials / Date
- 2. .Startup, monitor and shutdown the CCT /
system
- 3. ' Operate CCT heat exchangers and pumps in /
different combinations t
- 4. Control CCT flow to CCT heat exchanger manually Adjust-CCT flow manually through equip-
- 5. /
ment heat exchangers
- 6. Feed and bleed CCT for chemistry control /
- 7. Control makeup manually to CCT surge /
tanks
- 8. Locally operate CCT-13 /
- a. Discuss when valva (CCT-13) is /
to be open or shut and why M. , Condenser Air Removal System / I Signature /Date j
.l. Normal lineup of the condenser air /
l removal system Initials / Date 1
- 2. Fill condenser vacuum breaker seal /
- 3. Operate steam jet air ejectors O
/
(including hoggers) i Revision 0 Page 2.108
Vol. 2 Ch. 2 Fig. 2.4.4 /) Page 19 of 48 Q
- 4. Monitor the condenser air removal system /
operation discuss where air ejector disch. goes and why.
- 5. Find and read local indication of con- /
denser vacuum, and Auxiliary Steam Pressure N. Exhaust Hood Spray System / Signature /Date
- 1. Normal lineup of the exhaust hood spray /
system (auto) Initials / Date
- 2. Manually control exhaust hood spray /
(by pass valve)
- 3. Discuss problems encountered with /
improper operation of this system. O. Feedwater Heater Vent and Drain System / Signature /Date
- 1. Normal lineup of the feedwater heater /
vent and drain system Initials / Date k_sk 2. Isolate and restore a feedwater heater; / heater train
- 3. Monitor operation of the heater drain /
pumps; discuss operation of HDP seal water system.
- 4. Startup, monitor operation of and _/
shutdown the feedwater heater vent and drain system P. Condensate System / Signature /Date
- 1. Normal lineup on the condensate system /
Initials / Date
- 2. Startup, monitor operation and shutdown /
the condensate system
- 3. Vent condensate system prior to startup /
- 4. Fill condenser hotwell /
- 5. Operation of the condensate recire. /
system, in Auto and Manual {; Revision 0 Page 2.109
Vol. 2 Ch. 2 Fig. 2.4.4 l Page 20 of 48
}
s
- 6. Monitor condensate hotwell level locally /
using site glasses. Q. Vain Feedwater System / i Signature /Date
- 1. Normal lineup of the main feedwater / l system Initials / Date l
- 2. Startup of the main feedwater pumps, /
including aux oil pump
- 3. Monitor main FW pump, and system /
operations, including recirc. valves 4.- Rotate main feed pump lube oil cuno / filters ;
- 5. Operate / test the Dedicated Aux Feedwater /
Pump (FW-P-4) R. Main Turbine Lube oil System / Signature /Date b 1. Startup, monitor and shutdown main / turbine lube oil system Initials / Date
- 2. Operate lube oil coolers manually /
Initials / Date
- 3. Transfer lube oil between reservolors/ /
tanks (to fill main lube oil reservoir from clean oil tank) l
- 4. Clean lube oil pump strainers and filters / l
- 5. Operate main oil purifier (centrifuge) /
- 6. Drain dirty lube oil /
- 7. Press oil to main lube oil reservoir /
- 8. Discuss how oil spills are handled and /
, fire protection is provided for the t-Turbine L.O. System S. Main Turbine Electro-Hydraulic _
/
Control System (EHC) Signature /Date
- 1. Fill the hydraulic power unit reservoir /
during normal operations , Initials / Date Revision 0 page 2.110 l 1 I
- - . _ . . . . - . _ . . _ . ~ . . _ _ . . , _ . _ . . . _ _ _ _ , . _ . , _ . . _ _ _ . ,- - - - -
Vol. 2 Ch. 2 Fig. 2.4.4 z () Page 21 of 48
- 2. .Startup and operate EHC hydraulic pumps, /
monitor _the EHC system, shutdown EHC system
- 3. Shift EHC hydraulic coolers /
- 4. Operate polishing filters (Fuller earth /
. filters)
- 5. Discharge hydraulic fluid while shutdown /
"T. Main Turbine /
Signature / Date
- 1. Startup of Main Turbine, from turbine on /
turning gear to full load operation, using OM 52, Procedure "A" Initials / Date a 2._ Monitor the turbine generator during /
-operation, including the turbine bearing lift oil pumps
- 3. Trip the turbine generator locally at /
the turbine pedestal Initials / Date
- 4. Operate the turbine turning gear in /
Manual and Auto
- 5. Cycle turbine bearing lift oil pump /
knife edge (CUNO) filter , 6. Overspeed protection controller / test of the turbine generator
- 7. Perform turbine auto-stop functional /
test (pedestal checks for Protection Trips) i 8. Use of turbine loading curves / U. Main Generator /' Signature / Date
- 1. Start up of main generator, from turbine /
at sunchronous speed, to' unit at full Initials, Date load, using OM 52, Procedure A. - 1 2.- Operation of synchronizing selector / switches and synch meters (normal and emergsncy) -
/) Revision 0 Page 2.111
Vol. 2 Ch. 2 Fig. 2.4.4 Page 22 of 48
- 3. Operation of PCB 331, 341, and exciter /
breaker
- 4. Operation of voltage regulator and base /
adjuster, and how to change power factor
- 5. Use of generator capability curve /-
V. Main Turbine Gland Steam / Signature / Date
- 1. Normal lineup of the gland steam system /
Initials / Date
- 2. Lineup the gland steam system for startup, /
monitor system, shutdown gland steam system 3.- Shift sources of steam supply for the / gland steam system
- 4. Operate gland seal exhaust blowers /
- 5. Adjust main turbine gland steam pressure /
locally W. Auxiliary Steam System / Signature / Date
- 1. Normal lineup of the aux steam supply /
Initials / Date
- 2. Startup, monitor system, shutdown the /
aux steam supply
- 3. Supply aux steam header from main steam / 1 to operate equipment
- 4. Isolate auxiliary steam to the auxiliary / -
building X. Main and Reheat Steam System / Signature / Date
- 1. Warm up and pressurize main steam lines; /
normal and bypass operation of steam Initials / Date traps
- 2. Discuss operation of moisture separator / /
reheater; be able to point out all the p/ s_ g piping entering and leaving the MSR, and explain what each line is for and where they go to/come from. l l Revision 0 Page 2.112
* =
Vol. 2 Ch. 2 Fig. 2.4.4 Page 23 of 48 [V'T
- 3. Start up and shutdown main steam system /
and reheat steam system
- 4. Be able to point out all major isolation /
valves, control valves, and ties to other systems. Y. Steam Dump System / Signature /Date
- 1. . Normal lineup of steam dump system; /
include air supply and I/P's Initials / Date
- 2. Isolate steam dump to the condenser ~ /
- 3. Manual operation of steam dump system /
- 4. Place steam dump system in different /
modes of operation Z. Extraction Steam System / Signature /Date
- 1. Test / verify extraction steam non-return /
J valve operation Initia'.s/ Date
- 2. Monitor the extraction steam system /
operation AA. Chiller Units / Signature /Date
- 1. Startup and shutdown of a chiller unit, /
including support systems necessary for Initials / Date chiller operation
- 2. Monitor chiller unit and support systems /
operation
- 3. Discuss various trips on chillers, pump /
down cycle and problems that usually occur with the chillers
- 4. Perform /dl; cuss pump operat. ion and /
discuss water supply for fill of chilled water system
- 5. Discuss chiller temperature control and /
operation during refueling periods Revision O l l Page 2.113
Vol. 2 Ch. 2 Fig. 2.4.4 Page 24 of 48
)
VIII. Auxiliary Building Operator Terminal Obiective Upon completion of Section 8, the operator will be able to operate the systems associated with the auxiliary building during normal and emergency operations using approved procedures. Enablina Obiectives Perform or discuss the following associated with auxiliary building watchstanding. A. Reactor Coolant Pamps / Signature /Date
- 1. Adjust seal injection flow locally, to /
the RCP Seals (Penetration A) Initials / Date
- 2. Addition of oil to running reactor /
coolant pumps
- 3. Local operation of RCP thrust bearing /
oil lift pump
- 4. Discuss RCP oil collection system, /
installed as part of 10 CFR 50 Appendix R Criteria B. Chemical and Volume Control System) / (CVCS) Signature /Date
- 1. Normal lineup of the CVCS, including /
charging pumps Initials / Date
- 2. Local lineup of the hydrogen and nitrogen /
manifold,outsidetheVCTcubiege, normal and emergency hydrogen H supply including valves. /
- 3. Lineup for a nitrogen purge of the VCT. /
1
- 4. Perform hydrogen-nitrogen purge and /
establish hydrogen overpressure in the VCT
- 5. Line up to place in/ remove from service a /
mixed bed domineralizer
, Revision 0 i
Page 2.114
Vol. 2 Ch. 2 Fig. 2.4.4 [ Page 25 of 48
- 6. Line up to place;in/ remove from service a /
deborating demineralizar T
.7. Line up to place / remove from service the /
cation domineralizer I
- 8. Addition of oil to charging pump; checks /
on pump, motor,. speed increaser operation, and. aux oil pump
- 9. Line up the CVCS to make up to refueling /
water storage tank, as per the Procedure.
- 10. Mix boric acid and water to proper con- /
centration in batch tank, and fill boric acid tanks (CH-TK-1A, IB)
- 11. Line-up to recirculate boric acid tank /
with transfer pump
- 12. Line-up boric acid tank for service, /
through B.A. filter, to the blender , and charging pumps , [' C. Discuss or perform the following opera-tions associated with the RHR System
/ ,
Signature /Date '
- 1. Normal' lineup of the residual heat /
' removal system Initials / Date
- 2. Lineup the residual heat removal system /
for operation with the fuel pool cooling l system l
- 3. Lineup purification of the residual heat /
removal system during plant cooling
- 4. Drain the reactor cavity using the /
residual heat removal system
- 5. Fill.and vent residual heat removal /
system components and RHR pumps
- 6. Operation of RHR system with RCS /
partially drained D. Discuss or perform the following opera- / tions associated with the SI system Signature / Date
- 1. Lineups for filling or draining /
accumulator Initials / Date Revision *0 Page 2.115 l
- ~ . . . . , - - . _ _ . - . . _ _ _ _ , . . . _ . , _ ., _ _ _ . , _ . _ . . . _ - . . _ _ _ _ . _. -- ... - , . , , .
+
Vol. 2 ! Ch. 2 Fig. 2.4.4 l( Page 26 of 48
- 2. Lineup for adjusting accumulator pressure /
- 3. Lineup to sample an accumulator /
- 4. Batch to the boron injection tank /
- 5. Fill the refueling water storage tanks /
- 6. Recirculate and/or purify the refueling /
water storage. tank
*7. Fill the reactor refueling cavity system /
from refueling water storage tank !
- 8. Lineup the safety injection system for /
operation in the recirculation mode, as per Emergency Presedures i
- 9. Preparing the safety injection system for /
!- a normal plant shutdown to Mode 5 ! 10. Drain the safety injection system low / head safety injection pump
*11. Lineup charging pumps after auto change- /
l over from injection to recirculation as per Emergency Procedure
- 12. Lineup outside recirculation pumps to the /
suction of the charging pumps j
- Local manual actions only.
E. Discuss or perform the following opera- / tions associated with the CCR System Signature /Date
- 1. Normal lineup of the Reactor Plant Com- /
ponent Cooling Water System during plant Initials /Date operations.
- 2. Lineup of the CCR system during RHR /
operations
- 3. Place a second CCR heat exchanger into /
service, following the procedure.
- 4. Control Rx plant river water flow through /
CCR heat exchanger manually at HX. Adjust R.W. flow without causing an auto-start of the standby R.W. pump. Revision 0 Page 2.116
'+d m Vol. 2 Ch. 2 Fig. 2.4.4
() *
- 5. Drain CCR. system components in prepara-Page 27 of 48
/
tion for clearance / maintenance work.
- 6. Fill and vent CCR system components to /
return to service after maintenance
- 7. Fill CCR surge tank, from the normal M/U /
source, LCV-CC-100. Also fill surge tank using a randolph pump, pumping the chromated water from the 55 gallon storage tanks. Discuss precautions and hazards associated with this operation. 8.- Cross connect 8" CCR header with the 14" / CCR header, to' supply fuel pool cooling.
- 9. Monitor CCR pump operations. /
Discuss proper suction pressure ' discharge pressure, and how to determine if the pump is cavitating. F. Discuss or perform the following opera- / tions associated with the containment Signature / Date airlocks and the containment itself.
- 1. Operate the personnel air lock for a con- /
tainment entry and and exit using the Initials /Date proper entry procedures.
- 2. Operate the manual personnel airlock /-
(built into the equipment hatch) using the proper procedure
- 3. Operate the emergency escape doors in the /
. personnel air lock
- 4. Monitor for containment integrity. Dis- /
cuss in general what valves would be checked for containment integrity and where they are located.
- 5. Actions to betaken if containment /
integrity is violated.
- 6. Accompany supervisor on Containment /
final close-out for plant startup.
- 7. Breaking containment vacuum, and equal- /
izing containment pressure with atmospheric pressure. . Revision 0 Page 2.117
as. .. ..; .. . Vol. 2 Ch. 2 Fig. 2.4.4
.-(,.~) Page 28 of 48
- 8. Purging the containment via:
- a. Purge to ventilation vent stack /
- b. . Purge to supplementary leak /
collection c) Purge to gaseous waste system / G .' Perform or discuss the following opera- / concerning the Quench Spray System Signature /Date
- 1. Normal lineup of the quench spray system /
including QS-9 and 10, (QS pump recirc Initials / Date valves)
- 2. Fill and recirc the quench spray /
i ~ chemical addition tank
- 3. -Lineup and-operation of the RWST /
(QS-TK-1) cooler and refrigeration units. (~ H. Hydrogen Recombiner and Purge System /
\
Signature / Date
- 1. Lineup of the hydrogen recombiner /
and purge systems Initials / Date
- 2. Startup hydrogen recombiners-and /
purge system
- 3. Shutdown the hydrogen recombiners and /
purge system I. Penetration Cooling System / Signature / Date
- 1. Normal lineup on the penetration /
cooling system (from CCR System) Initials / Date
- 2. Cross Connecting the fire protection /
system (F.P.S.) to penetration cooling coils, as per OM 56C - Subprocedure F-E. (In compliance to 10 CFR 50, App. R Criteria) . Revision 0 Page 2.118
- .; - ; ~a ~
.-i e
Vol. 2 2 Ch. 2 3 () . Fig. 2.4.4 Page 29 of 48 J. Perform or discuss the following opera- / tions concerning spent fuel pool Signature / Date cooling and purification 4
- 1. Normal lineup on spent fuel pool /
. cooling system and F.P. cooling heat exchangers Initials /Date
- 2. Startup the spent fuel pool cooling /
system in different pump / heat exchanger combinations
- 3. Spent fuel pool purification using filter /
- 4. Spent fuel pool purification using /
, domineralizer and filter
- 5. Operate the spent fuel pool skimmer /
! 6. Monitor spent fuel pool cooling system / operation and fuel pool' level Spent: fuel pool leakage test; check of ()
- 7. /
fuel pool tell-tale drain receiver-
- 8. . Decay heat removal using the spent fuel /
cooling system K. Perform, discuss or siralate the follow- / ing operations concerning the Auxiliary Signature / Date Feedwater System.
- 1. Normal lineup of the aux. feedwater system /
Initials / Date
- 2. Monitor the aux. feedwater system when /
operating ,
- 3. ' Reset steam driven aux. feedwater pump _/
gov. stop valve a
- 4. Locally, from aux. feed pump room, /
control aux. feedwater flow to maintain SG level +
- 5. Lineup of alternate water supply to the /
4 aux. feed pumps (river water)
- 6. Check all aux. feed pump discharge piping /
O at any pump not running, by a hands-on inspection to verify the piping is at ambient temperature e Revision 0 Page 2.119 i
. :- -e. - - - -
Vol. 2 Ch. 2
- g Fig. 2.4.4 Page 30 of 48
- 7. Manually control speed of sta drivan /
aux feed pump (FW-P-2) to throttle dis-charge flow of pump, as per OM 56C,Section 4, Procedure C (in compliance with 10 CFR 50 App. R Criteria. L. Perform or discuss the following opera- /
. tions concerning the Emergency Dieselr Signature / Date Generator System
- 1. Lineups of the D/G auxiliary support /
systems.as per the OST's for the #1 and
#2 diesel generators Initials / Date
- 2. Operate the diesel starting air /
compressers
- 3. Blowdown D/G air start strainers and /
receivers - -
'4. Manually crank the diesel over by the /
jacking tool
- a. Open/close cylinder vents looking /
ON for signs of water in cylinders
- 5. Test alarms on the entire control /
cabinet and clear any alarms 6._ Check the governor for proper set- / points on load limiter and speed droop compensator
- 7. Manually start a diesel generator /
locally from the engine control cabinet
- 8. Locally operate the governor control /
to raise or lower speed of engine
- 9. Manually flash the field by depressing /
the field flash contactor in the exciter / regulator cabinet and adjust the voltage with local voltage regulator control ,
- 10. Monitor the diesel generator during /
startup, running and shutdown, recording recording readings necessary.
- 11. Manually shutdown a diesel generator /
locally. Revision 0 Page 2.120
1 Vol. 2 Ch. 2 _ ,_s Fig. 2.4.4 Page 31 of 46
,' 11. Show/ discuss all the various ways /
to shutdown the D/G's
- 12. Transfer. fuel oil from main storage /
tanks to the diesel day tank using the fuel transfer system
- 13. Take a fuel oil sample.for analysis /
~
- 14. Receive fuel oil and unload to the /
storage tanks and holding tank
- 15. Locally monitor level of fuel oil avail- /
able tolboth diesel generators ensuring compliance to tech specs
- 16. Inspect diesel generator room trenches /
for water / oil
- 17. Inspect D/G fuel oil storage / loading /
area for water / oil. M. Perform or dis' cuss the following / operations concerning the Boron Recocvery Signature /_Date
-System
- 1. Transfer operations from a coolant /
recovery tank Initials / Date
- 2. Transfer operations from a boron /
recovery test tank
- 3. Transfer operations from primary drains /
transfer tank #1
- 4. Lineup to operate a boron recovery /
cesium removal ion exchanger
- 5. Lineup to transfer evaporator bottoms /
- 6. Lineup to operate clean up lon /
exchangers -
- 7. Recirculate evaporator distillate /
through the clean-up ion exchanger. N. Perform or discuss the following opera- / tiens concerning the Liquid Waste System Signature /Date
- 1. Transfer operations from various sumps / /
O tanks to the high and/or low level waste tanks Ravision 0 Initials, Date Page 2.121
_ , , . . , . .. _. - .- ~
. , ~ . . - , _ . .. , - . . -
Vol. 2 Ch. 2 Fig. 2.4.4 () 2. Line up the liquid waste ion exchanger Page 32 of 46
/
- 3. Operate and monitor the liquid waste /
evaporator and support equipment (in-plant)
- 4. ' Process the contents of the high and low / l level waste tanks
- 5. Process the contents of the liquid' waste /
test tank
- 6. Transfer operations of liquid waste /
between-the liquid waste system and the boron recovery system
- 7. Locally monitor the liquid waste system /
equipment when in operation
- 8. Flush the liquid waste rad monitor /
- 9. Lineup to transfer wasta evaporator /
bottoms to the solid weste disposal system
~
- 10. Change the liquid waste pre-filter /
O O. Perform or discuss the following opera- / tions concerning the Gaseous Wasta System Signature / Date
- 1. Shift.G.W. process vent filters /
i Initials / Date
- 2. . Fill the G.W. relief loop seal from PG /
water system
- 3. Monitor' waste gas disposal system opera- /
tion and operating parameters / indications
- 4. Purge waste gas surge tank and com- /
. pressors with nitrogen
- 5. Purge wiste gas decay tanks with /
+ nitrogen
- 6. Operate the sweep gas blowers from their /
local control station P. Perform or discuss the following opera- / tions concerning the Area Radiation Signature / Date Monitoring-System ! (~' l. . Locations of-the Area Rad Monitors in / the Aux. Bldg. Initials / Date Revision 0 Page 2.122
Vol. 2 Ch. 2
. Fig. 2.4.4 -( Page 33 of 46
- 2. Actions to be taken if a monitor /
is found in alarm?
-Q. Perform or discuss the following opera- /
concerning the Process Radiation Monitoring Signature / Date , System
- 1. Locations in plant of process monitors /
Initials / Date
- 2. Flush a process radiation monitor /
detector chamber .
- 3. Monitor for proper operation /
R. Perform or discuss the following operations / associated with the Nitrogen System j j Signature / Date
- 1. Purge and fill the nitrogen system; /
place N2 bottles or truck in service Initials / Date on header
- 2. Remove N2 cylinders / tanks from service /
- 3. Monitor N2 system operation /
- 4. State /show the location of header /
isolation valve
.S. Perform or discuss various operations /
associated with the Heat Tracing Signature /Date System
- 1. ' Test the local heat tracing annunciators /
located in the PAB and pipe tunnel Initials /Date
- 2. Test the master heat tracing annunciator /
alarm panel located in the control room
- 3. Shift redundant heat tracing circuits from /
one power source to the other source
~
- 4. Shift power for. local heat tracing annun- /
ciators from one power source to the other source Revision 0 Page 2.123
Vol. 2 l Ch. 2 Fig.~2.4.4 l- (f Page 34 of 46 l 5. Shift power for master heat tracing / j alarm panel from one power source to I. the other source T. Perform or discuss the various opera . / tions. associated with the Building Services Signature /Date j hot water heating and glycol heating systems l l 1. Lineup of the hot water heating system / l Initials / Date l
- 2. -Lineup of the glycol heating system /
- 3. Startup and operate the hot water heat- /
ing system pumps; monitor suction and discharge pressure and flow
- 4. Lineup aux steam supply to hot water heat- /
ing. system heat exchangers, and place HX's in service. Monitor aux steam supply pressure, l HX inlet and outlet temperatures. l 5. Startup and operate the glycol heating / system cire pumps; monitor suction and discharge pressure and flow.
) ! 6.- Lineup hot water supply to the glycol /
heat exchangers and place HX's in service. Monitor HX inlet and outlet temperatures, hot water supply temperature.
- 7. Maintain hot water heating and glycol /
heating expansion tanks' level and pressure.
- a. Adjust N2 pressure /
- b. Operate fill pumps /
U. Primary Makeup Water System and / Deaerator Signature / Date
- 1. Lineups of the makeup water supply /
system and dewater pumps / tanks Initials / Date
- 2. Monitor the makeup water supply /
- 3. Lineup of the deaerator on header /
~
- 4. Startup the deaerator and monitor the /
J deaerator for proper flow, level, pressure
~
Revision 0 Page 2.124
i Vol. 2 Ch. 2 Fig. 2.4.4 Page 35 of 46
- 5. . Startup and operage PG water pumps. /
Monitor recirc and discharge pressure. V. Control Rod Drive System / Signature / Date
- 1. Startup and shutdown of the rod driva /
motor generator' sets
- 2. Take vibration readings on rod drive /
motor generator sets
- 3. Monitor rod drive motor generator sets /
- 4. Locally operate a reactor trip breaker /
and a Rx trip bypass breaker l ; W. Perform or discuss the following opera ; / 1 tions concerning the Instrument Air System Signature / Date 1.- Cross-connect containment instrument / air and station instrument air Initials / Date
- a. State the location of IA-90 /
- b. Precautions / limitations associated /
with opening IA-90 X. Perform or discuss the following opera- / tions associated with the Sumps and Drains System Signature / Date
- 1. Operate a building sump pump /
t Initials / Date
, 2. Be able to perform the Auxiliary /
Building operator's duties in the oil spill / prevention plan, OM 48, Section 9, Procedure K , i Revision 0 , Page 2.125
._ . _ _ _ . _ _ . _ . _ . _ _ . _ . _ _ . . . . _ _ ._ - - - ~ , _ _ . . _ _ , _ . , _ _ _ , . . .
Vol. 2 Ch. 2 Fig. 2.4.4 Page 36 of 46 p IX.. Water Treatment Onerator Terminal Obiective: Upon completion of Section 9, the operator will be able to operate the systems associated with water treating using approved procedures. Enablina Obiectives: A. Perform or discuss the following opera- / tions concerned with the Water Treatment Signature / Date System
- 1. Place the water treatment system in -/
recirculation
- 2. Place the water treatment system in /
operation from the recirculation mode 3.- Monitor the water treatment system /
- 4. Fill the condensate storage tank (s) /
- 5. Backwash charcoal filters /
- 6. Regenerate the cation and anion units /
- 7. Regenerate the mixed bed domineralizar /
- 8. Assist in filling the caustic storage /
tank
- 9. Assist in filling the acid storage tank /
- 10. Place the chem. wasta sump in service /
- 11. Bypass the chem waste sump tank /
- 12. Sample the chem. waste sump '/
- 13. Neutralize the contents of the chem / -
waste sump
- 14. Pump down the chen. waste sump and then /
secure it by shutting discharge valve WT-278
- 15. Transfer caustic to demineralizers /
for regeneration Revision 0 Page 2.126
Vol. 2 Ch. 2
,-s Fig. 2.4.4 Page 37 of 46
-(}
- 16. Clean softener using salt water brine /
- 17. Transfer acid to'demineralizers for /
regeneration
- 18. Isolate water treatment blowdown /
domincralizers B.- Perform'or discuss the following opera- / tions concerned with the chlorination Signature / Date System
- 1. Startup the chlorination system /
Initials / Date
- 2. Monitor the chlorination system includ- /
ing circ. water and river water
-g chlorinator parameters 3.- Shutdown the chlorination system /
- 4. Change the chlorine bottles. State all /
precautions to be followed when changing bottles. C. Perform or discuss.the following opera- / tions concerned with the Domestic Water Signature / Date System
- 1. Startup the domestic water supply system /
and fill.the domestic water tank Initials / Date
- 2. Monitor domestic water supply system /
operation including tank level D. Perform or discuss the following opera- / tions concerned with the Auxiliary Boilers Signature / Date
~
- 1. Operate the aux steam boiler (manual and /
auto) Initials / Date
- 2. Change burner tips in the aux boiler and /
clean dirty tips. Discuss difference between winter and summer' tips.
- 3. Perform bottom blowdown of aux boilers /
- 4. Supply aux steam header from aux boilers /
O , Revision 0
- Page 2.127 8
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Vol. 2 Ch. 2 Fig. 2.4.4 Page 38 of 46 , l
- 5. Cooldown and place aux boilers in wet /
layup ,
- 6. Discuss operation of all aux boiler /
equipment (feed pumps,~ fuel oil pumps,
, condensate pumps, deaerator, fans).
O - 1 O Revision 0 Page 2.128 i . i
- . . _ _ . - . - - _ . _ _ - _ _ _ _ _ _ _ _ ._ _ - _ _ . - - _ . _ _ _ _ _ _ _ - _ - . . . _ _ _ . . _ _ _ _ _ _ _ . _ , . - - _ - - - _ - _ _ _ , ~ , _ _ _ . - _ . , _ - . - -
t
;7 Vol. 2..
s Ch. j 1 Fig. 2.4.4 e Page-39 of 46 X. ' " Outside Onerator Terminal Obiective During all modes of operation the trainee should be able to:
- Determine the operating status of plant equipment, associated with
.the outside operators tour around the plant.
- Perform the necessary equipment checks on'the meteorological equip ment at BVPS. ._,
- Perform the required inspections and operations at the Sewage ,
Treatment Plant.- ^ ' s;i ,
- Complete the L4-19 Outside operator log
- Enablina Obiectives '
7 A. Perform or discuss the following operations /- , concerning the outside operator: Signature /Date '
- 1. . Monitor operation of the condenser circ '
/
water pumps ~ Initials /Date ' O
- 2. Drain the circ water pump cavities __. /
- 3. Assist in fill of the circ water system /
- 4. Assist in draining of the circ water /
system
- 5. Operate circ water pumps seals. water /
flushing and lube water system 6. Blowdown pump house air , compressor / ' receiver . n
- 7. Test wheat trace annunciator ANN-PL U "_
- 8. Monito'r operation of the ERF service ' " '
- /g_/ " s%
~
transformers 3A and 3B s- s 9.. Monitor ERF diesel lube oil and fuel / oil systems t s. . i 10. Monitor operation of the ERF UPS / (Uninterruptible Power Source) I O s ? Revision 0 ! Page 2.129 .
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. '".. . s. Fig. 2.4.4 Page 40 of 46
- 11. Add salt to the ERF softener brine /
tank
- 12. Complete L4-19 outside log /
' 13 . Operate oil separator backwater gate /
valve 1FD-11
- 14. Shut the sewage treatment effluent valve /
(STP-3) and open branch line valve (STP-4)
- 15. Fill the raw sewage holding and /
sludge tanks from a fire hydrant
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, Page 2.130.
s
- u. . m-Vol. 2 Ch. 2 Fig. 2.4.4
.( ) Page 41 of 46 XI. Electrical Switching Program , Terminal obiective: During all modes of operation at BVPS, the trainee should be able to:
- Determine-the position of any breaker associated with the various plant electrical loads; i.e., breaker open or closed, breaker racked on or off its buss.
- Demonstrate the proper procedures for racking a 4KV or 480V breaker on or off its electrical supply buss.
- State the precautions associated with handling energized electrical !
equipment at BVPS. '
- Perform or discuss an electrical clearance on a major piece of station equipment following the proper procedure in OM 48.6 - t
-Clearances.
-~ Demonstrate the proper use of station key interlocks on major electrical equipment and state why the interlocks are on this equipment.
( - Demonstrate the proper use of electrical test equipment and state precautions associated with'its use on electrical equipment of any voltage.
- Perform electrical switching necessary for normal daily operations.
. Perform electrical switching necessary where an emergency exists, such as loss of all off-site electrical power.
Enablina Obiectives A. Perform or discuss the following opera- / tions associated with 120 VAC and 125 VDC Control Power Signature / Date
- 1. Location and replacement of (PT) poten- /
tial transformer secondary side fuses Initials / Date
- 2. Explain the precautions and hazards of /
the primary side potential transformer (PT) fuses on an energized buss
- 3. Explain the hazards of opening the /
secondary side of a current transformer Revision 0 Page 2.131
Vol. 2 Ch. 2 Fig. 2.4.4 Page 42 of 46
)
- 4. Explain what the source of 125 VDC /
-control power.to 480V and 4KV switchgear is,.and why
- 5. -Show or explain the locations of 125 VDC /
control power Heinemann breakers in the 480V and 4KV switchgear
- 6. Monitor the DC Electrical Distribution /
System for grounde, and proper operation
- a. Batteries
- b. Battery Chargers -
- c. Switchgear/ Switchboards
- d. Power Panels j l
- 7. Transfer loads from DC busses 1 or 2, to /
DC Buss 5, via the transfer switches B. . Perform or discuss the following opera- / tions associated with the 480V Motor Control Centers Signature / Date
- 1. Demonstrate how to properly open the /
door of a 480V line-starter Initials / Date
- 2. Explain or demonstrate how to properly /
open the door of a line-starter on a
- 480V MCC, without de-energizing it
- 3. Discuss the hazards associated with /
pulling the pan off the bus, or pushing the pan back onto the bus
- 4. Perform the removal of the Linestarter /
Pan, and return pan to buss, as per proper procedure C. . Perform or discuss the following opera- / associated with the 480V Substations Signature / Date
- 1. Discuss the precautions to adhere to when /
opening and closing an Air Interrupter Initials, Date Load Break Switch
- 2. Discuss the difference between an air /
interrupter load break and a regular disconnect switch Revision 0 Page 2.132
. ., p . -
w Vol. 2 Ch. 2 Fig. 2.4.4
~ /"')
- (_j Page 43 of 46 es
. 3. Discuss or perform the following opera- /
tions associated with a 480V Air Circuit Breaker (AC3)
- a. De-energ.. zing control power /
Initials / Date
- b. Racking the ACB to the TEST position / -
c .' Testing ACB while in TEST position / d.- Releasing the stored energy mechanism /
- e. Racking ACB to the DISCONNECT posi- /
tion
- f. Explain how the key interlocks on /
selected 480V ACB's work, and why they exist
- 4. Perform or discuss how to transfer 480V /
loads from the Control Room to the Emergency Shutdown. Panel, and back to the control board D. -Perform or~ discuss the following opera-(--)- tions associated with 4KV (4160 volt) Signature / Date
/
busses
- 1. Operate 4KV disconnects (480V trans- /
former supply side) Initials / Date
- 2. Discuss the precautions associated with /
racking out/in and energizing a 4KV breaker
- 3. Demonstrate the proper method for racking /
a 4KV breaker on/off the buss,, using the proper-protective equipment
- 4. Discuss or perform the following opera- /
tions associated with a 4KV Air Circuit Breaker (ACB)
- a. De-energizing control power /
- b. Racking brkr to TEST position /
- c. Testing breaker in TEST positon ~ /
Revision 0
, Page 2.133 e
. . .c.
Vol. 2 Ch. 2 Fig. 2.4.4 (} d. Releasing stored energy mechanism Page 44 of 46
/
- e. Racking breaker to the DISCONNECT /
position
- g. Removal of ACB from cell completely. /
and use of proper tool.to rool breaker around lb.- Operation of protective shutters over / energized buss connectors
- 5. Perform or discuss how to transfer 4KV /
loads from-the control room to the Emer. Shutdown Panel, and back to the control board . 6. Operate or discussioperation of Kirk Key / interlock system on AE/DF Busses to de-energize the buss 'for maintenance f E. Perform or discuss the following opera- / ! tions associated with the AC Electrical Distribution System signature / Date I/ 1. Transfer power.to 4KV Unit Station / Service transformers from System Station Initials / Date Service transformers (Live Buss Transfer)'
- 2. AC Breaker line-up verificaclon (OST /
, 1.36.8 and 1.36.9)
- 3. Off-site to on-site power distribution /
, breaker alignment verification (OST 1.36.7)
- 4. Monitor the AC Electrical Distribution /
System for grounds
- 5. Perform or discuss tracing and clearing /
a ground from the AC Electrical Distribution System, using the proper procedure F. LPerform or discuss the following operations / associated with the Switchyard Signature / Date
- 1. Discuss the general layout of the 138KV /
and 345KV equipment in the switchyard Initials / Date associated with BVPS f 4
- 2. Discuss the key interlock system to assure /
load current removed from disconnects before l j Page 2.134 r
l
- Vol. 2 '
Ch. 2 l Fig. 2.4.4 l
~ 'N Page 45 of 46 !
x-l l
- 3. Operate or discuss operation of the Kirk /
Key interlocks on 4KV breakers, to de-energize the-1A and 1B 138KV/4KV System Station Service transformers
- 4. Describe basic construction and operation /
of the 138KV Oil Circuit Breakers-(OCB)
- 5. Describe basic construction and operation /
of the 138KV/345KV auto transformers, and what busses they service
- 6. Describe basic construction and opera- /
tion of the 345KV Power Circuit Breakers (PCB) G.- Discuss or perform the following opera- / tions-associated with metering and pro- Signature / Date taction of electrical distribution
- 1. Discuss the basic construction and-use -
/
of potential transformers at BVPS Initials / Date
- 2. Discuss the basic construction and use /
of current transformers at BVPS
- 3. Discuss the functions of the various /
types of protective relays used at BVPS and be able to point out examples of each
- a. ground fault
- b. overcurrent
- c. undervoltage
- d. underfrequency
- e. differential Include 480V, 4KV, 22KV, 138KV and 345 KV systems
- 4. Discuss the color-coding found on these /
protectiv~e relays, pertaining to the functions they perform
- a. blue
, Revision 0 4 Page 2.135
., . - - 4 . - _ _ , _-. . , - _ . _ . .
h Vol. 2 Ch. 2
- Fig. 2.4.4
!. Page 46 of 46
- b. red
- c. green
, d. yellow i-
- a. black H. Perform or discuss a clearance /-
on a major piece of station equipment, Signature / Date following the proper procedure in OM 48.6. Include in the discussion all the necessary paperwork to complete a clearance, and the ' paperwork flowpath
- l. MWR-Maintenance Work Request /
Initials /-Date ; 4
- 2. Equipment Clearance Permit /
- 3. Siwtching Permit /
- 4. Clearance Tags /
l: 5. Clearance Logbook /
- 6. Radiation Clearance and RWP - Radiation /
Work Permit
- 7. ESF Checklist /
- 8. Conditional Clearance /
l t i c' i B 4 R Revision 0 Page 2.136 i
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1 I l l DUQUESNE LIGHT COMPANY- Vol. 2 d Nuclear Group Training Administrative Manual Ch. 2 Fig. 2.7.1 Pace 1 of 5 REFUELING LICENSE RETRAINING CYCLE
SUMMARY
License Date
>Name:-
Number: Issued:
. Retraining Cycle:
A. WRITTEN EXAMINATION RESULTS (End of-prior cycle) Date: . Examination Re-examination Grade Grade
; M. [ Reactor and Fuel Characteristics % %
N. Equipment, Instrumentation and Design Description % % O. Procedures and Limitations % % P. Emergency Systems and Safety w Devices' % % 1 Q. Health Physics and Radiation Protection % %- I Average: % % i . i
~
'O 4 Revision 0 Page 2.138 _ - . .._._ . ._. .~_.____. _.._.,.._ _._._._._._._. . . . . . . . _ . . _ _ . - _ _ _ _ . . _ .
O DUQUESNE LIGHT COMPANY Vol. 2
-{} Nuclear Group Training Administrative Manual Ch. 2 Fig. 2.7.1 Page 2 of 5 r
REFUELING LICENSE RETRAINING CYCLE
SUMMARY
(Continued) . Name: Retraining Cycle: B.- LECTURE ATTENDANCE RECORD fpprox. Hours
-Topic Required for Completed
.I. Theory and Principles of Operation All licensees
- II . Thermodynamics, Heat Transfer and Fluid Flow All licensees III. Plant Instrumentation and Controls 'All licensees IV. Radiation Control and Safety , All licensees O V. Reactor and Fuel Characteristics <80% Cat. M
-O' VI. Equipment Instrumentation and Design Descriptions ,
<80% Cat. N VII. Procedures and Limitations <80% Cat. 0 VIII. Emergency Systems and Safety Devices <80% Cat. P IX. Health Physics and Radiation Protection <80% Cat. Q C. INDIVIDUAL STUDY GUIDE' SuffiARY Month Compiete (/) Month Compiete (/)
September March October April November May December June January July ks February August Revision 0 Page 2.139 L
. . . , , _.....4 .,
e { :- 1 1 DUQUESNE LIGHT COMPANY ~ Vol . 2 Nuclear Group Ch. 2 Training Administrative Manual Fig. 2.7.1 Page 3 'of 5 REFUELING LICENSE RETRAINING CYCLE
SUMMARY
(Continued) 4 Name: Retraining Cycle:
- D. WALK-THROUGH TRAINING I Walk-through training complete on
. Date 2 E. MODULE QUIZ GRADES
- Module I: II: III: IV:
I Grade % % % % O
~
F. COMENTS: s l d 4 7 LO 1 Revision 0 Page 2.140 l i .. - . . _ . _ , - . . . _ _ _ _ _ . . _ . _ _ _ , _ _ _ _ _ _ _ . _ _ _ . . . _ . _ . . . . _ _ _ _ . . . _ . _ _ , _ _ . _ _ _ . . . _ _ _
- DUQUESNE LIGHT COMPANY Vol . 2 Nuclear Group Ch. 2
' Training Administrative Manual Fig. 2.7.1 Page 4 of 5 REFUELING LICENSE RETRAINING CYCLE
SUMMARY
(Continued)
'Name: . Retraining Cycle:
G. WRITTEN EXAMINATION RESULTS (End of this cycle) Date: Examination Re-examination Grade Grade M. Reactor and Fuel Characteristics % % N. Equipment, Instrumentation and Design Description % i
- 0. Procedures and Limitations % %
P. ' Emergency Systems and Safety Devices % %
/ Q. Health Physics and Radiation
'fy Protection % % Average: % % Results reviewed by: Manager - Nuclear Training Date Director - Site Operations Date Plant Manager Date ks Revision 0 Page 2.141 2
4 DUQUESNE LIGHT COMPANY Vol. 2.
.U
[ - Nuclear Group Ch. 2
. Training Administrative Manual Fig. 2.7.1 Page 5 of 5 R5 FUELING LICENSE RETRAINING CYCLE
SUMMARY
(Continued) Name: Retraining cycle: H. ACCELERATED RETRAINING (Less than 80% oyerall, less than 70% any category)
-1. Licensee removed from licensed' duties.
Date
- 2. Accelerated retraining program assigned:
- 3. Accelerated retraining program approved:
Director - Operations Training Date Manager - Nuclear Training Date
- 4. Re-examination passed. -licensee returned to licensed duties:
Manager - Nuclear Training Date D[ Revision 0 Page 2.142
y ' '
. c .
DUQUESNE LIGHT COMPANY Yol. 2
/'.- Nuclear Group b) -
Training Administrative Manual . Ch. 2 Fig.- 2.7.2 Page 1 of 6 FUEL HANDLING SR0 WALK-THROUGH TRAINING CHECKLIST
- Name Class- Date
= Quali fication _ Desired Current Qualification.
Overall Grade: SAT UNSAT
=. Examiner
. Examiner. Reviewed by Category
' Category Grade . Weak Areas
-1. . Theory and Core Design
- 2. Administrative Controls
- 3. Emergency' Procedures
- 4. Radiation Control d-
- 5. Refueling Hardware and Interlocks Student Review:
Revision 0 Page 2.143
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DUQUESNE LIGHT COMPANY Yol . 2 O Nuclear Group . Training Administrative Manual Ch. 2 Fig. 2.7.2 Page 2 of 6 FUEL HANDLING SRO WALK-THROUGH TRAINING CHECKLIS' '(Continued)
- 1. . Theory and Core Design Grade O
Overall Grade: Comments (Required for any area not graded satisfactory): 1 O Revision 0 Page 2.144 i
P. J DUQUESNE LIGHT COMPANY Vol . 2 O Nuclear Gr up Training Administrative Manual Ch. 2 Fin. 2.7.2 Page 3 of 6 FUEL HANDLING SR0 WALK-THROUGH TRAINING CHECKLIST (Continued)
- 2. Administrative Controls Grade l
O Overall Grade: Coments (Required for any area not graded satisfactory): O Page 2.145
.DUQUESNE LIGHT COMPANY Vol. 2 O Nuclear Group .
Training Administrative Manual Ch. 2 Fig. 2.7.2 Page 4 of 6 FUEL HANDLING SR0 WALK-THROUGH TRAINING CHECKLIST (Continued)
- 3. Emergency Procedures Grade 1
4-i l
- O Overall Grade
Coments (Required for any area not graded satisfactory): i . 1 i f f i 1 O l Revision 0 Page 2.146 l
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DUQUESNE LIGHT COMPANY Yol. 2 t : Nuclear Grouo' Ch. 2 A Training Administrative Manual Fig. 2.7.2 Page 5 of 6 FUEL HANDLING SR0 WALK-THROUGH TRAINING CHECKLIST (Continued)
- 4. Radiation Control Grade 6
I i O Overall Grade: Coments (Required for any area not graded satisfactory): O Revision 0 Page 2.147
. . ,. u , ,- .-- . .
7- , j-DUQUESNE-LIGHT COMPANY Yol . 2
/
Nuclear Group Ch. 2
;- ( Training Administrative Manual Fig. 2.7.2 Page 6 of 6 FUEL-HANDLING SR0 WALK-THROUGH TRAINING CHECKLIST (Continued)
- 5. Refueling Hardware and Interlocks Grade-i a
s'
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Overall Grade: Coments (Required for any area not graded satisfactory): Revision 0 Page 2.148
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