ML20215D425
| ML20215D425 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, 05000000 |
| Issue date: | 09/03/1986 |
| From: | Black J CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20215D345 | List: |
| References | |
| NTM---3.04, TAC-64620, NUDOCS 8612160359 | |
| Download: ML20215D425 (49) | |
Text
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NUCLEAR TRAINING MANUAL CONNECTICUT YANKEE LICENSED OPERATOR CONTINUING TRAINING PROGRAM IMPLEMENTING PROCEDURE NTM 3.04 w'
V 80 h 2 9b Approved:
Dired C uclear Training W"
Director / Station Superintendent Revision:
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Date:
August 29, 1986 l
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Concurrence:
Manager, Quality Assurance
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Submitted:
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8612160359 861200 PDR ADOCK 05000213 V
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i 1.0 PURPOSE T'N The purpose of this procedure is to implement the k
)2 Connecticut Yankee (CY) Licensed Operator Continuing
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Training Program (LOCT) in accordance with the Nuclear Training Manual (NTM) and as detailed in the Connecticut Yankee LOCT program description.
The CY LOCT program fulfills the Licensed Operator Requalification requirements of 10 CFR 55, Operator Licenses, except for items required by paragraph 3c Appendix A.
Those. requirements are fulfilled per Reference 3.5.
2.0 APPLICABILITY 2.1 This procedure applies to:
2.2.2 CY and Nuclear Training Department personnel involved in the planning, delivery, evaluation, and review of the CY LOCT program.
2.1.2 CY and Nuclear Training Depa'rtment personnel who hold an NRC Reactor Operator (RO) or Senior Reactor Operator (SRO) License or equivalent certification.
3.0 REFERENCES
3.1 Nuclear Training Manual 3
3.2 10 CFR 55, Operator Licenses 3.3 NUREG 0737, Clarification of TMI Action Plan Requirements 3.4 NUREG 1021, Operator Licensing Examiners Standard 3.5 CY ACP 1.0-13, Document Acknowledgment.
4.0 DEFINITIONS 4.1 License Holder l
An individual who currently holds an RO license, SRO i
license, or equivalent certification on the CY Plant l
and is enrolled in the CY LOCT program.
4.2 Segment Examination A Category I examination that comprises one of the four topic areas, that in total, make up the required Annual LOCT Examination.
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4 4.3 LOCT Cycle
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A complete shift rotation period, normally six weeks,
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during which each license holder receives the same scheduled continuing training.
4.4 Annual Evaluation Examination An annual examination used to, determine areas in which retraining is needed to upgrade overall license holder knowledge.
4.5 Instructor Assistant An individual assigned to aid a certified instructor.
4.6 Annual LOCT Examination A required Category I examination administered to determine each license holder's knowledge of subjects covered in the LOCT program and provide a basis for evaluating their knowledge of abnormal and emergency procedures.
4.7 Accelerated Requalification Training Individualized training administered to license holders who do not successfully meet LOCT program criteria.
5.0 RESPONSIBILITIES 5.1 Connecticut Yankee Station Superintendent 5.1.1 Responsible for ensuring CY license holders are enrolled in the LOCT program.
5.1.2 Responsible for providing CY Supervisory /
Management personnel to act as Category V examination evaluators.
52 Connecticut Yankee Operations Supervisor 5.2.1 Responsible for performing Supervisor's Assessments of Training.
5.2.2 Responsible for approving tentative LOCT schedules.
5.2.3 Responsible for assigning CY personnel to provide OJT.
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5.3 Supervisor, Operator Training, Connecticut Yankee
,f'Qs 5.3.1 Responsible for the overall conduct of the LOCT i.
/
program in accordance with the Nuclear Training Manual and the Training. Program Description.
5 3.2 Responsible for ensuring LOCT examinations are administered.
5.3.3 Responsible for approving LOCT examinations.
5.3.4 Responsible for approving tentative LOCT schedules.
5.3.5 Responsible for performing Supervisor's Assessments of Training.
5.3.6 Responsible for approving lesson plans and OJT guides for use.
5.3.7 Responsible for ensuring Nuclear Training Department license holders are enrolled in the LOCT program.
5.3.8 Responsible for advising Supervisory / Management personnel when license holders must be removed from licensed duties.
5.3.9 Responsible for assigning Nuclear Training Department personnel to develop and implement individualized training.
5.4 Assistant Supervisor, Operator Training, Connecticut Yankee.
5.4.1 Responsible for preparing LOCT program schedules.
5.4.2 Responsible for reviewing and approving written and oral examinations.
5.4.3 Responsible for assigning personnel to provide instruction.
5.4.4 Responsible for performing and assigning Nuclear Training Department personnel to perform assessments of training.
5.4.5 Responsible for approving lesson plans and OJT guides.
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5.4.6 Responsible for coordinating the review of emergency and abnormal operating procedures.
(p).I 5.5 Assistant Supervisor, Simulator Training, Connecticut Yankee.
5.5.1 Responsible for reviewing and approving simulator examinations.
t 5.5.2 Responsible for assigning Nuclear Training Department personnel to provide simulator instruction.
5.5.3 Responsible for preparing LOCT program schedules.
5.5.4 Responsible for performing and assigning Nuclear Training Department personnel to perform assessments of training.
5.5.5 Responsible for approving lesson plans.
5.6 Nuclear Training Department Personnel 4
Responsible for conducting training activities, as assigned, in accordance with the Nuclear Training Manual and Training Program Description.
C 5.7 License Holders
[b Responsible for completing assigned CY LOCT activities.
5.8 LOCT Training Program Control Committee Responsible for approving LOCT Cycle Schedules.
6.0 INSTRUCTIONS i
6.1 Program Duties 6.1.1 The Supervisor, Operator Training, Connecticut Yankee shall:
i 6.1.1.1 Supervise the CY LOCT program to ensure compliance with the Nuclear Training Manual and the Training Program Description.
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6.1.1.2 Act as the cognizant supervisor for all requirements specified by Reference 3.1
(_T,d supervisors.
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not specifically assigned to other 6.1.1.3 Serve as the point of contact between the Nuclear Training Department, the TPCC, and CY Operations Supervision.
6.1.1.4 Ensure Nuclear Training Department license holders complete all LOCT requirements as assigned.
6.1.2 The Assistant Supervisors, Operator and Simulator Training, Connecticut Yankee shall:
6.1.2.1 Schedule, coordinate and evaluate the effectiveness of training activities associated with the conduct of the LOCT program.
6.1.2.2 Assign Nuclear Training Department personnel to carry out the training activities of the LOCT program.
6.1.3 The Assistant Supervisor, Operator Training shall coordinate the annual review of emergency c
and abnormal operating procedures. Procedure reviews may occur in the classroom, simulator or on shift environment.
Any one of the following constitute an acceptable review.
6.1.3.1 Discussion of the procedure during a classroom training session.
6.1.3.2 Using the procedure during a simulator session or category V examination.
6.1.3.3 Documented read and sign.
6.1.4 Nuclear Training Department personnel shall conduct training activities, as assigned, to develop, implement and l
administer the LOCT program.
6.1.5 Connecticut Yankee Supervisory / Management personnel shall:
6.1.5.1 Ensure CY license holders participate in the LOCT program.
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6.1.5.2 Approve tentative LOCT program schedules.
f~s, 6.1.5.3 Participate as evaluators for Category V examinations.
6.1.5.4 Evaluate the effectiveness of the LOCT program.
6.1.5.5 Assign CY personnel to conduct LOCT OJT activities.
6.1.5.6 Notify the Supervisor, Operator Training when a license holder requires upgrading to active status.
6.1.6 License holders shall complete all LOCT requirements as assigned.
6.2 Scheduling The Connecticut Yankee LOCT program is a closed enrollment program as described in Reference 3.1.
Each licensed operator will normally attend training sessions for a period of one week out of every six weeks.
Each licensed operator shall participate in a minimum of 12 weeks during each two year continuing training period, with a minimum of five weeks in any
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one calendar year.
6.2.1 The Connecticut Yankee Unit Superintendent and the Supervisor, Operator Training shall ensure that CY and Nuclear Training Department license holders, respectively, are scheduled to attend the LOCT program.
6.2.2 By December 1 of each year, the Assistant Supervisor, Operator Training and Assistant Supervisor, Simulator Training shall jointly prepare a tentative LOCT program schedule for the up coming year using a CY LOCT Tentative Schedule for the Calendar Year form (Figure 7.1). The tentative schedule shall:
6.2.2.1 Include topics covering annual and biennial training requirements listed in References 3.2 and 3.3.
These requirements are stated in Section 5.0 of Attachment 8.1.
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6.2.2.2 Include other training topics selected from Section 4.0 of Attachment 8.1 based on the following considerations.
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Training effectiveness feedback per Reference 3.1.
Direch User Department feedback.-
Annual Evaluation Examination results.
Significant plant / industry operational events.
Plant modifications and backfit items.
Revisions and additions to plant operational documents.
6.2.2.4 List anticipated LOCT Cycle dates.
6.2.2.5 List the training environment (s) and times allotted for each training topic.
6.2.2.6 Allow flexibility such that either content or schedular adjustments can be
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made to reflect additional training requirements or acccmmodate changes to plant operational requirements /
commitments.
6.2.2.7 Be approved by the Operations Supervisor and the Supervisor, Operator Training.
6.2.3 The Assistant Supervisor Operator training and Assistant Supervisor Simulator training shall jointly prepare detailed LOCT Cycle schedules based on the content established in the tentative LOCT schedule. LOCT Cycle schedules shall:
l 6.2.3.1 Be prepared using CY LOCT Cycle Schedule and CY LOCT Cycle Schedule-Continued forms (Figures 7.2 and 7.3, respectively).
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6.2.3.2 Contain the following information.
Training Day k,g, r
M Lesson / Examination Titles Supporting Lesson Plan Code (s)/ Examination Number (s)
Training Environment / Examination Category
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Allotted time 6.2.3.3 Be approved by the LOCT Training Program Control Committee prior to the scheduled start of the LOCT Cycle.
6.2.4 During the course of each LOCT Cycle, the Assistant Supervisor, Operator Training shall prepare, on a weekly basis, a schedule which includes the date, time, location, and assigned instructor for each training lesson.
The Assistant Supervisor, Operator Training shall distribute the weekly schedule to the designated instructors, attendees, the Assistant Supervisor, Simulator training, and the Supervisor, Operator Training.
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6.2.5 Each license holder must attend each scheduled LOCT lesson unless equivalent training is specifically documented and approved in accordance with Reference 3.1.
6.3 Instructor Requirements The Assistant Supervisor, Operator Training and the Assistant Supervisor, Simulator Training, as applicable, shall assign instructors for this program who meet the instructional skills and knowledge requirements detailed in 6.3.1 through 6.3.3.
The Operations Supervisor shall assign Operations l
Department personnel to perform OJT activities who meet requirements detailed in 6.3.3.
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6.3.1 Classroom Training
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6.3.1.1 Currently licensed or certified by the NRC on Connecticut Yankee at the SRO level and certified per NTM-1.10 as a Level II instructor, and is currently enrolled in an NRC approved Licensed Operator Requalification Program.
6.3.1.2 In lieu of 6.3.1.1, an instructor may teach selected topics if certified to teach those areas in accordance with procedure NTM 1.10 of Reference 3.1.
6.3.2 Simulator Training 6.3.2.1 Currently licensed or certified by the NRC on Connecticut Yankee at the SRO level and certified per NTM-1.10 as a Level II instructor, and is currently enrolled in an NRC approved licensed operator requalification program.
6.3.2.2 In lieu of 6.3.2.1, an instructor may teach selected topics if certified to teach those areas in accordance with procedure NTM-1.10 of Reference 3.1.
~s 6.3.2.3 Have satisfactorily completed a simulator instructional skills training program.
Note:
An instructor meeting the requirements of 6.3.1 may provide Simulator Training if teamed with an instructor meeting the requirements of 6.3.2.
6.3.2.4 Certified to operate the Simulator by l
the Assistant Supervisor, Simulator Training.
6.3.3 On-The-Job Training l
l 6.3.3.1 OJT Training Sessions l
l Qualified as an OJT Trainer in accordance with procedure NTM-1.12 of Reference 3.1.
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Satisfactorily completed an OJT instructional skills training
{' /fj program.
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6.3.3.2 OJT Evaluation Sessions Qualified as an OJT Evaluator in accordance with procedure NTM-1.12 of Reference 3.1.
Satisfactorily completed an OJT instructional skills training program.
6.3.4 The Assistant Supervisor, Operator Training or the Assistant Supervisor, Simulator Training may assign Instructor Assistants to aid designated instructors.
Instructor Assistants are not required to meet the above criteria, however, the designated instructor who does shall always be present during training sessions.
6.4 Examinations and Lesson Plans 6.4.1 Supervisors shall approve examinations as specified below:
6.4.1.1 Category I Examinations - Supervisor Operator Training.
a) The Assistant Supervisor, Operator Training or the Assistant Supervisor, Simulator Training shall approve Category I examinations that are administered to the Supervisor, Operator Training.
b) The Supervisor, Operator Training may designate the Assistant Supervisor, Operator Training or the Assistant Supervisor, Simulator Training to approve Category I examinations during his absence.
6.4.1.2 Category III Examinations a) Annual Evaluation Examination -
Supervisor, Operator Training A
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b) Quizzes - Assistant Supervisor, Operator Training or Assistant
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Supervisor, Simulator Training.
v 6.4.1.3 Category IV Examinations - Assistant Supervisor, Operator Training or Assistant Supervisor, Simulator Training.
6.4.1.4 Category V Examinations - Supervisor, Operator Training.
a) The Assistant Supervisor, Operator Training or the Assistant Supervisor, Simulator Training shall approve Category V examinations that are administered to the Supervisor, Operator Training.
b) The Supervisor, Operator Training may designate the Assistant Supervisor, Operator Training or the Assistant Supervisor, Simulator Training to approve Category V examinations during his absence.
6.4.2 Acceptable standards of performance (pass
[~h criteria) shall be established for examinations
(_)
and quizzes as follows:
6.4.2.1 Category I Examinations Annual LOCT Examination: 70% per segment examination with an 80% average over the four segment examinations that comprise the Annual LOCT Examination.
6.4.2.2 Category III Examinations a) Annual Evaluation Examination:
None Established I
b) Quizzes:
None Established 6.4.2.3 Category IV and V Examinations:
Satisfactory.
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i 6.4.3 A Category I Annual LOCT Examination shall be administered to each license holder to determine
('~')N his/her knowledge of subjects covered in the LOCT program and provide a basis for evaluating their knowledge of abnormal and emergency procedures.
No license holder shall be exempted from taking this examination.
6.4.3.1 The Annual LOCT Examination is comprised of four segment examinations.
Segment examinations may be
/
administered separately, or together, during the current LOCT year.
6.4.3.2 The Annual LOCT Examination shall cover the following topic areas.
Each segment examination shall cover one of the areas.
a) Theory of Nuclear Power Plant Operation, Fluids and Thermodynamics.
b) Systems: Design, Control and Instrumentation.
c) Procedures: Normal, Abnormal, f3 Emergency, and Radiological Control.
d) Administrative Procedures, Conditions and Limitations.
6.4.3.3 Annual LOCT Examination questions shall be based on learning objectives covered during the current LOCT year.
6.4.3.4 Each LOCT class shall receive different Segment Examinations to prevent compromise.
No greater than 25% of the questions on a segment examination may come from other segment examinations administered during the same LOCT year.
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6.4.3.5 RO and SRO license holders taking a segment examination normally receive
(~Q the same examination.
However, the 5, jd segment examination covering Administrative Procedures, Conditions and Limitations may differ to allow RO's and SRO's to be examined in their specific j ob areas.
6.4.3.6 Each Segment Examination shall be designed to be approximately two hours in length.
6.4.4 A Category III Annual Evaluation Examination shall be administered to each license holder to determine areas in which retraining is needed to upgrade overall license holder knowledge.
Personnel involved in the preparation and development of the Annual Evaluation Examination may be exempted from taking the examination.
This exemption is limited to no more than three license holders.
6.4.4.1 The Annual Evaluation Examination shall be similar in scope and depth to an NRC licensing examination per Reference 3.4.
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6.4.4.2 Annual Evaluation Examination questions sFall be based on a representative sampling of learning obj ectives contained in the current version of the Licensed Operator Task / Training Matrix.
6.4.4.3 Since this examination is not used to i
evaluate individual license holder knowledge, license holders are not required to complete personal l
information included on the examination l
coversheet, e.g.,
name, etc.
An attendence sheet shall be completed to l
document license holders participation.
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6.4.4.4 RO and SRO license holders taking an Annual Evaluation Examination normally 7
(
y receive the same examination.
- However,
\\ d-that portion of the examination covering administrative requirements may differ to allow RO's and SRO's to be examined in their specific job areas.
6.4.4.5 The Annual Evaluation Examination shall be evaluated to determine areas in which retraining is needed to upgrade i
overall license holder knowledge.
The evaluation shall be done in accordance with procedure NTM-2.05 of Reference 3.1.
The results of the evaluation shall be used as input to develop the up coming tentative LOCT program schedule (See 6.2.2).
6.4.5 An Annual Operational Examination shall be administered to each license holder to systematically observe and evaluate his/her performance and competency during normal, abnormal and emergency operating conditions.
This examination requirement may be met with a Category IV Oral Examination using the CY
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control board or a Category V Simulator
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Operational Examination at the discretion of the Supervisor, Operator Training.
No license holder shall be exempted from this examination requirement.
6.4.5.1 The Annual Operational Examination shall focus on areas important to the safe operation and shutdown of the i
reactor and the prevention of the l
release of fission products to the environment.
6.4.5.2 The Operational Examination for each license holder shall be graded on a Satisfactory / Unsatisfactory basis.
6.4.5.3 Comments on individual / crew strengths and weaknesses shall be documented and discussed with the individual / crew at l
the completion of the examination.
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6.4.5.4 Annual Operational Examinations shall be administered using a sufficient f'S.
number of different event scenarios and
( j, questions to prevent compromise.
t 6.4.5.5 When the Annual Operational Examination is conducted on the simulator, one evaluator should be a CY Management / Supervisory representative.
6.4.6 The Supervisor, Operator Training shall advise the Unit Superintendent, the Operations Supervisor, and the Manager, Operator Training, by memo, that a license holder must be removed from licensed duties to receive accelerated requalification training when the license holder:
6.4.6.1 Receives a score of less than 70% on any one segment examination, or 6.4.6.2 Receives an average score of less than 74% on the first three segment examinations of an Annual LOCT Examination, or 6.4.6.3 Receives an average score of less than 80% on the four segment examinations
[.
that comprise the Annual LOCT Examination, or 6.4.6.4 Receives an unsatisfactory on the Annual Operational Examination, or 6.4.6.5 Fails to attend any LOCT session for which he/she is scheduled. Attendance is not required if a Validation of Equivalent Training is received in accordance with Reference 3.1.
6.4.6.6 Fails to complete the annual review of emergency and abnormal operating procedures.
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6.4.7 The Supervisor, Operator Training shall assign Nuclear Training personnel to develop and
[~'s implement individualized training in accordance
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with procedure NTM-1.14 of Reference 3.1 for each license holder who is removed from licensed duties per 6.4.6 above.
Successful completion criteria for the individualized training shall
~
be an equivalent examination (s) to the one failed or missed.
6.4.8 The Supervisor, Operator Training shall advise the Unit Superintendent, the Operations Supervisor, and the Manager, Operator Training, by memo, when a license holder removed from licensed duties successfully completes Individualized Training and may be returned to licensed duties.
6.4.9 The supervisors indicated shall approve lesson plans as specified below:
6.4.9.1 Classroom Lesson Plans - Assistant Supervisor, Operator Training.
6.4.9.2 Briefing Room Lesson Plans - Assistant Supervisor, Operator Training and Assistant Supervisor, Simulator y
Training.
b 6.4.9.3 Simulator Lesson Plans - Assistant Supervisor, Simulator Training.
6.4.9.4
" Released for Use" for All Lesson Plans - Supervisor, Operator Training.
6.5 Training Program Effectiveness The training assessment forms specified in the Nuclear Training Manual shall be used at the frequency specified below.
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6.5.1 The Assistant Supervisor, Operator Training or the Assistant Supervisor, Simulstor Training, as applicable, shall assign Nuclear Training Department personnel to perform Student and Instructor Assessments at the completion of each l
week of each LOCT Cycle.
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6.5.2 The Assistant Supervisor, Operator Training shall perform one Supervisor's Assessment per f~sg each LOCT Cycle containing classroom
(,y instruction.
6.5.3 The Assistant Supervisor, Simulator Training shall perform one Supervisor's Assessment per
~
each LOCT Cycle containing simulator instruction.
6.5.4 The Supervisor, Operator Training shall perform Supervisor's Assessments of two classroom training sessions and two simulator training sessions during each calendar year.
6.5.5 The Operations Supervisor or his designee shall perform Supervisor's Assessments of one LOCT classroom training session and one LOCT simulator training session during each calendar year.
6.5.6 The Assistant Supervisor, Operator Training shall assign Nuclear Training Department personnel to perform Examination Assessments at the completion of each Category I examination.
6.5.7 The Supervisor, Operator Training shall assign Nuclear Training Department personnel to
(
).
complete one LOCT Training Effectiveness Report per NTM-2.05 at the completion of each calendar year.
6.6 Retraining Requirements 6.6.1 The Unit Superintendent and the Supervisor, Operator Training shall ensure all CY and Nuclear Training Department license holders are continuously enrolled in the LOCT program as long as they are required to maintain their license / certification.
6.6.2 Active licensed operator status is maintained by both the satisfactory performance of licensed duties and participation in the LOCT program.
If an individual has not actively carried out licensed duties for a period in excess of three months, individualized training shall be completed prior to resuming licensed duties.
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6.6.2.1 The Operations Supervisor shall notify the Supervisor, Operator Training if a
(~T license holder with inactive status
(,)
requires upgrading to active status.
6.6.2.2 Upon notification, the Supervisor, Operator Training shall assign Nuclear Training Department personnel to develop and implement Individualized Training in accordance with procedure NTM-1.14 of Reference 3.1.
The content and completion criteria of the individualized training shall meet requirements prescribed in Reference 3.2.
6.6.2.3 The Supervisor, Operator Training shall advise the Operations Supervisor, by memo, when a license holder successfully completes Individualized Training and may be upgraded to active status.
6.7 Records Requirements In addition to the records requirements of procedure NTM-1.16 of Reference 3.1, the following records shall be maintained.
O 6.7.1 A Simulator Reactivity Manipulation Check Off List (Figure 7.4) shall be maintained for each license holder and be used to document the reactivity manipulations he/she performed on the plant or simulator.
6.7.2 License Renewal Applications (NRC Form 398) 7.0 Figures 7.1 CY LOCT Tentative Schedule for the Calendar i
Year i
7.2 CY LOCT Cycle Schedule 7.3 CY LOCT Cycle Schedule-Continued 7.4 Simulator Reactivity Manipulation Check Off List 8.0 Attachments 8.1 Licensed Operator Continuing Training Program Description.
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J FICURE 7.1
)
CY LOCT. TENTATIVE SCHEDULE FOR THE (year) CALENDAR YEAR Prepared by:
(ASOT)
(ASST)
Approved by:
(Ops Sup)
(SOT) i
)
Cycle #1 Dates:
d Topics Environment (s)
Allotted Time i
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2 i
1 1
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CY LOCT TENTATIVE SCHEDULE FOR THE CALENDAR YEAR (CONT.)
f%
V CYCLE #2 Dates:
i T
Topics Environment (s)
Allotted Time 1
i 4
f a
4 1
i f CYCLE #3 Dates:
Topics Environment (s)
Allotted Time l
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CY LOCT TENTATIVE SCHEDULE FOR THE CALENDAR YEAR (CONT.)
CYCLE #4 Dates:
Topics Environment (s)
Allotted Time O
CYCLE
- 5 Dates:
Topics Environment (s)
Allotted Time i
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CY LOCT TENTATIVE SCHEDULE FOR THE CALENDAR YEAT (CONT.)
CYCLE #6 Dates:
i Topics Environment (s)
Allotted Time i
}
}
1 i
CYCLE #7 Dates:
l Topics Environment (s)
Allotted Time t
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FIGURE 7.2 4
CY LOCT CYCLE SCHEDULE Year:
l Cycle haber:
(ASOT) j Prepared by:
(ASST) i.
(TPCC)
Approved by:
i (7PCC) i (TPCC) t,.
1 (TPCC) 1 Lesson Plan Trng. Environment /
Allotted Day Lesson / Examination Title Code (s)/ Exam Number Exam Category Time i
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Rev: 0 Date: 8/29/86 Page: 7.2-1 of 1 i'.,. - - _ -,. - -. _,.
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FIGURE 7.3 b()t CY LOCT CYCLE SCHEDULE - CONTINUED Cycle Number:
Year:
I Lesson Plan Trng. Environment /
Allotted
[
Day Lesson / Examination Title Code (s)/ Exam Number Exam Category Time i
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FIGURE 7.4 m
(j' SIMULATOR REACTIVITY MANIPULATION CHECK OFF LIST Name Year Ending The (1) next to the manipulation designates items
- SIM
- SIM which are completed once per year.
The (2)
INST.
SESSION designates once every (2) yeas;-
INIT.
NO.
1.
Plant or reactor startup to include a range that reactivity feedback from nuclear heat generation is noticeable and a heatup rate is established.
(1) 2.
Orderly plant shutdown.
(1) 3.
Manual control of feedwater systems during startup and shutdown.
(1) 4.
Boration and dilution during power operation.
(1) 5.
10% power change due to manual rod control.
(1) 6.
10% power change due to load change with manual rod control (1) 7.
Loss of instrument air.
(1) 8.
Loss of electrical or degraded power sources.
(1) 9.
Loss of core coolant flow / natural circulation.
(1) 10.
Loss of RCS inventory including:
(1) 10.1 Steam generator tube rupture.
(1) 10.2 Large and small leak including i
leak rate determination.
(1) 10.3 Leak inside and outside containment.
(1) 10.4 Saturated reactor coolant response.
(1) i f) 10.5 Pressurizer Leaks (1) i d
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Figuro 7.4 (cont.)
SIMULATOR REACTIVITY MANIPULATION CHECK OFF LIST-Cont.
/
n 11.
NU u-12.
Loss of service water required for safety system.
(1) 13.
' Loss of shutdown cooling.
(1) 14.
Loss of RPCCW system or to a component.
(2) 15.
Loss of normal feedwater or feedwater system.
(2) 16.
Loss of all feedwater.
(1) 17.
Loss of protective system channel.
(2) 18.
Mispositioned control rods or dropped rods.
(2) 19.
Inability to drive control rods.
(2) 20.
Conditions requiring use of emergency boration.
(2)
(N 21.
Turbine generator trip.
(1) 22.
Malfunction of auto control systems which affect reactivity.
(2) 23.
Malfunction of RCS pressure control /
volume control system.
(2) 24.
Reactor Trip (1) 25.
Main steam line break inside or outside containment.
(2) 26.
Nuclear instrument failures.
(2) 27.
Operation outside control room (1) 28.
Minimum of 10 reactivity manipulations.
(2) 29.
Fuel Clad Failure (2) 30.
Operation of Turbine controls in manual during a Turbine startup.
(1)
O*
If the manipulation is done on shift, substitute the shift supervisor's initials and the date.
NTM 3.04 Rev:
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,f's I
N/
ATTACHMENT 8.1 TRAINING PROGRAM DESCRIPTION COVER SHEET Training Program: Licensed Operator Continuing Training Training Program Number:
none
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Prepared by:
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C-
' Nuclear Tra ng a
1 s
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Students' Prerequisi Verified by:
Al
~
7/
S ati*fdc t Matter Expert i
Reviewed by:
Y 3/s/Ft
'Su pe r v is o r, Op'erator Tra$nifg i
I O
NTM 3.04 Rev:
0 Date: 8/29/86 Page: 8.1-1 of 21
' l.0 TRAINING PROGRAM
SUMMARY
(~N The Licensed Operator Continuing Program is developed to 1
- 'q,)
provide continuing training to licensed operators.
The continuing training is determined by a systematic instructional design process which determines the job tasks that a licensed operator performs.
The continuing training requirements are based on importance to safety, difficulty of the task and frequency of performance.
Feedback and evaluation of the training program insures continued effectiveness of the Continuing Training Program.
Inherent in this process is the ability to change the program to meet training needs identified by evaluation, feedback, NRC requirements, and industrial events.
The training requirements of 10CFR55 and NUREG-0737 are also included.
Each licensed operator shall normally attend training sessions for a period of one week out of every cix weeks.
Each licensed operator shall participate in a minimum of 12 weeks during each 2 year Continuing Training Period, with a minimum of 5 weeks in any one calendar year.
2.0 TRAINING PROGRAM COALS The program goal is to ensure licensed operators remain capable of operating the plant safely and efficiently during normal, abnormal and emergency conditions.
(
f 3.0 STUDENT PREREQUISITES PREREQUISITES:
Reactor Operator or Senior Reactor Operator, License or an Instructor Certification on the Connecticut Yankee Plant.
4.0 PROGRAM OUTLINE A.
Theory and Principles of Reactor Operation.
1.
Reactor Theory e
All Reactor Theory topics supporting terminal objectives listed in section 6.0 of this program description.
2.
Heat Transfer, Fluid Flow and Thermodynamics Review All Heat Transfer, Fluid Flow and Thermodynamics topics supporting terminal objectives listed in section 6.0 of this program description.
.i O
i NTM 3.04 l
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- 3. Transient and Accident Analysis Review
{'j}'
i All Transient and Accident Analysis topics supporting terminal objectives listed in section 6.0 of this q
program description.
- 4. General and Specific Plant Operating Characteristics including Expected Response to Equipment and Instrument Failure Normally, topics in this subj ect are reviewed as part of the continuing training described in section 4C of i
this program description.
However, additional training may be selected from terminal objectives listed in section 6.0 of this program description.
5.
Radiological Protection Review All Radiological Protection topics supporting terminal obj e c t ive s listed in section 6.0 of this program description.
6.
Plant Chemistry Control Review All Plant Chemistry Control topics supporting terminal obj e c t ive s listed in section 6.0 of this program description.
-()
7.
Reactor Core Parameters Normally, topics in this subject are taught as part of plant design change training following refueling.
However additional training in this topic may be selected from terminal objectives listed in section 6.0 of this program description.
B.
Features of Facility Design All Features of Facility Design topics supporting listed i
tasks or items.
1.
Plant Protection Systems a.
- 1) Operate the reactor trip breakers. (open and shut)
- 2) Shift a vital instrument bus power supply.
- 3) Trip the reactor from outside the control room.
l f
O NTM 3.04 Rev:
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~.
^
b.
Safety Inj ection/High Containment Pressure
(~ ~j'-
- 1) Manually initiate engineered safety features.
(_,P
- 2) Reset engineered,afety features.
- 3) Bypass engineered safety features.
- 4) Perform partial loss of AC with safety injection. (refueling interval) 4 c.
Main Steam Isolation Valve Actuation System Perform main steam isolation valve trip test during refueling.
2.
Engineered Safety Systems a.
Residual Heat Removal System
- 1) Start up the residual heat removal (RHR) system.
- 2) Operate a residual heat removal heat exchanger.
- 3) Monitor the residual heat removal system.
- 4) Shutdown the residual heat removal system.
- 5) Fill the refueling cavity / transfer canal using the RHR system.
- 6) Drain the refueling cavity using residual heat removal system.
- 7) Take manual / auto control of the flow control valve.
(FCV602)
- 8) Perform the residual heat removal system g-v.
' ')
operability test during refueling operations.
y
- 9) Perform the residual heat removal system motor operated valve cycling test.
b.
Safety Injection
- 1) Manually initiate safety injection.
- 2) Monitor the safety injection system.
- 3) Secure high pressure safety injection system.
- 4) Conduct high head recirculation.
- 5) Perform swap over from injection to recirculation.
- 6) Operate core cooling block switch.
- 7) Start up of charging pump on emergency diesel generator during safety injection actuation.
- 8) Start safety injection pumps and open valves outside control room.
c.
Containment Air Recirculation System Operate containment air recirculation fans fn emergency conditions with one emergency diesel generator.
O NTH 3.04 Rev:
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3.
Plant Systems
[)'l a.
Control Rod Drive System
- 1) Establish initial conditions at the operator panel for a reactor startup.
~
- 2) Perform shutdown margin calculations.
- 3) Perform a dropped rod recovery.
- 4) Recover from a slave cycler failure.
- 5) Recover from a loss of safety rod out-limit situation. (rod insertion limit violation)
- 6) Perform a shutdown group withdrawal and operate control rod drive system to bring reactor critical.
- 7) Shift control between manual group and manual individual and operate single control rod using rod disconnect panel.
- 8) Operate the control rod drive system to shutdown the reactor.
- 9) Perform the full length control rod assembly drop time test.
- 10) Operate control rods during rod worth measurements.
- 11) Operate control rods during critical boron measurements.
b.
(_j
- 1) Fill the refueling cavity.
- 2) Establish natural circulation.
- 3) Cooldown the reactor coolant system.
4
- 4) Perform reactor coolant system water inventory balance.
c.
Steam Generation System
- 1) Identify a faulted steam generator.
- 2) Isolate a faulted steam generator.
d.
Reactor Coolant Pump
- 1) Start a reactor coolant pump.
- 2) Perform an emergency reactor coolant pump shutdown.
- 3) Restart reactor coolant pump after plant trip.
e.
Chemical and Volume Control System
- 1) Startup the chemical and volume control system.
- 2) Perform boron concentration change calculations.
i O NTH 3.04 Rev:
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- 3) Perform boron concentration dil
!. ion (bleed) of the reactor coolant system.
-y3
- 4) Perform boration (feed) of the reactor coolant
(
y system.
\\/
- 5) Shift to automatic feed and bleed of the reactor coolant system.
- 6) Dilute to a critical condition during reactor startup.
- 7) Shutdown the chemical and volume control system.
- 8) Calculate boration requirements for cold shutdown.
- 9) Degas the reactor coolant system.
- 10) Operate charging to the fill header.
- 11) Emergency borate the reactor coolant system.
- 12) Operate chemical and volume control system during all rods out critical boron test.
f.
Spent Fuel Pool Cooling System Lower refueling pool level. (fuel transfer canal) g.
Fuel Handling System
- 1) Operate the new fuel elevator.
- 2) Operate the new fuel spent fuel building overhead crane.
- 3) Operate refueling machine / main fuel handling bridge.
- 4) Operate reactor control cluster assembly change fixture.
- 5) Operate fuel transfer system carriage and upender.
- 6) Operate the spent fuel handling manipulator bridge and manipulator crane.
- 7) Remove new fuel from shipping containers.
- 8) Conduct spent fuel loading.
- 9) Conduct fuel handling and transfer equipment checkout.
h.
Main Turbine Generator
- 1) Operate system during physics testing.
- 2) Increase load on the turbine generator.
1.
Condensate System Fill the condensate system.
O NTM 3.04 j
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J. Main Feedwater System s
[-,
- 1) Operate the feedwater regulating system in N_
manual and automatic modes.
- 2) Shift feed regulating valve manual / automatic.
- 3) Monitor feedwater system on unit trip.
~ 1 k. Fire Protection System Conduct annual flow test of fire pumps. 1. Alternating Current Electrical Distribution System
- 1) Deenergize an engineering safeguards (4160V vital) bus.
- 2) Restore an engineering safeguards bus (41'60V vital) to service.
- 3) Check alternate off-site power sources prior to removing incoming line from service.
- 4) Perform transfer of power supply to 4kv unit service buses.
4. Instrumentation and Control Systems a. Pressurizer Pressure Control System
- 1) Control pressurizer pressure in master manual 3
mode. (pressure controller in manual) . )
- 2) Transfer from manual to automatic pressure control.
- 3) Use auxiliary spray.
- 4) Operate the low pressure overpressure protection system.
- 5) Operate the pressurizer heaters while on emergency diesel generator.
l b. Nuclear Instrumentation System
- 1) Perform a reactivity balance calculation.
- 2) Perform a quadrant power tilt calculation.
- 3) Perform reactor power range instrument calibration test. (goin adjustment)
- 4) Perform calorimetric / heat balance calculation.
- 5) Perform hot functional and low power physics tests.
c. Main Turbine Control
- 1) Adjust turbine load limits. (load limiter)
- 2) Adjust turbine load using the load limiter.
- 3) Operate turbine trip valves.
O NTH 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-7 of 22
d. Process Monitor ~7 Operate wide range gas monitor. (V} e. Pressurizer, Reactor and Cavity level System
- 1) Operate with various vent header lineups.
- 2) Operate during cavity fill.
- 3) Operate during cavity drain.
- 5. Plant and Industry Experiences Related to Features of Facility Design Items to be selected as required 6.
Plant Design Changes Maintain knowledge of modifications to plant safety related equipment. C. Malfunctions, Transients, Accidents and Related Procedures All topics supporting listed tasks or items.
- 1. Abnormal Operating Procedures a.
Malfunction of rod control system. (f b. Dropped rod at power. c. Stuck rod. d. Uncontrolled rod motion. e. Nr rod motion. f. Control rod out of step. g. Vent non condensable gases from the RCS. h. Reactor coolant pump malfunction.
- i. Loss of residual heat removal.
- j. Loss of residual heat removal - refueling cavity full.
k. Loss of residual heat removal - reactor head secured. reactor head 1. Loss of residual heat removal removed. m. Loss of component cooling n. Loss of component cooling to selected components, o. Rod position indication malfunction. p. Nuclear instrumentation system malfunction. q. Nuclear instrumentation system failure - plant at 100% power. r. Nuclear instrumentation system - reactor shutdown. s. Nuclear instrumentation system - critical in source range. l (~N \\_) L NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-8 of 22 i
t. Nuclear instrumentation system - critical in intermediate range. f f'E?y u. Nuclear instrumentation system - plant refueling. (,/ v. Fuel cladding failure. w. Loss of containment integrity. x. Generator hydrogen temperature deviation. y. Loss of feed flow / feed regulating valve failure. z. Feed regulating valve fails open. sa. Loss of feed water flow. bb. Feed steam generators with' auxiliary feedwater system. ec. Feed steam generators with control room inaccessible. dd. Local manual operation of auxiliary steam generator feed pumps. ee. Loss of vital / semi-vital bus. ff. Loss of vital bus. gg. Loss of semi-vital bus. hh. Low voltage on emergency buses. ii. 480 vac bus ground isolation. jj. DC ground isolation. kk. High process activity level.
- 11. Spent fuel building high exhaust activity.
mm. Loss of closed cooling water. nn. Loss of service water. oo. Natural disasters pp. Hurricane qq. Flooding O' rr. Tornadoen ss. Earthquake tt. Flooding of the Connecticut River. uu. Control room fire. vv. Loss of any portion of fire protection. ww. Loss of water fire suppression system. xx. Loss of CO2 system. yy. Loss of tech spec fire H2O station. zz. Loss of fire detection system. asa. Loss of penetration fire barrier. bbb. Loss of spray / sprinkler system. ccc. Loss of halon system in swgr room, ddd. Fire in HEPA/HECA filter. eee. Plant operation outside the control room. 2. Emergency Operating Procedures a. Loss of load. b. Reactor coolant leak, c. Cavity seal failure. d. Automatic makeup system malfunction. e. Emergency boration. JJ NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-9 of 22
f. Pressurizer relief valve failure. g. Pressurizer spray valve malfunction. / h. Spray valve fails closed. ( )y 1. Spray valve fails open. J. Turbine overspeed. k. Loss of condenser vacuum. 1. Partial loss of condenser vacuum. m. Complete loss of condenser vacuum. n. Partial loss of A.C. o. Diesel starts / bus 1-2 & 1-3 are deenergized. p. Diesel fails to start / bus 1-2 & 1-3 are deenergized. q. Diesel starts / bus 1-2 & 1-3 are reenergized. r. Diesel fails to start. s. Loss of semi-vital power. t. Partial loss of DC. u. Loss of circulating water. v. Loss of control air. w. Loss of condenser vacuum. x. Partial loss of condenser vacuum. y. Complete loss of condenser vacuum. z. Automatic makeup system malfunction. aa. Reactor trip or safety injection. bb. Rediagnosis. ec. Reactor trip response dd. Natural circulation cooldown. ee. Natural circulation cooldown with steam void in vessel. (with reactor vessel level indication [<#) x. system) \\- ff. Natural circulation cooldown with steam void in vessel. (without reactor vessel level indication system) gg. Loss of all AC power. hh. Loss of all AC power recovery without safety injection required. ii. Loss of all AC power recovery with safety injection required. jj. Loss of reactor or secondary coolant. kk. Safety injection termination.
- 11. Post loss of coolant accident cooldown and depressurization.
mm. Transfer to cold leg recirculation. nn. Transfer to hot leg recirculation. oo. Loss of emergency coolant recirculation. pp. Loss of coolant accident outside containment. qq. Faulted steam generator. rr. Uncontrolled depressurization of all steam generators. ss. Steam generator tube rupture. tt. Post-steam generator tube rupture cooldown using backfill. O NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-10 of 22 _~
uu. Post-steam generator tube rupture cooldown using blowdown. /)g vv. Post-steam generator tube rupture cooldown using ( steam dump. ww. Steam generator tube rupture with loss of reactor coolant - subcooled recovery desired. xx. Steam generator tube rupture with loss of resctor saturated recovery desired. coolant yy. Steam generator tube rupture without pressurizer pressure control. zz. Response to nuclear power generation / anticipated transient without scram. aaa. Response to loss or core shutdown. bbb. Subcriticality status tree. cec. Response to inadequate core cooling. ddd. Response to degraded core cooling. eee. Response to saturated core cooling. fff. Core cooling status tree. ggg. Response to loss of secondary heat sink. hhh. Response to steam generator overpressure. iii. Response to steam generator with high level. jjj. Response to loss of normal steam release capabilities. kkk. Response to steam generator low level. 111. Heat sink status tree. mmm. Response to intermittent pressurized thermal shock. nnn. Response to anticipated pressurized thermal shock. oon. Integrity status tree. () ppp. Response to high containment pressure. qqq. Response to containment flooding. rrr. Response to containment high radiation level. sse. Containment status tree. ttt. Response to high pressurizer level. uuu. Response to low pressurizer level. vvv. Response to voids in reactor vessel. www. Inventory status tree. l xxx. Operate with various header lineups. yyy. Operate during cavity fill. zzz. Operate during cavity drain. anaa. Recommend actions to ensure that core cooling and subcooling margin are maintained. bbbb. Analyze indications to determine that an abnormal plant event is in progress. cccc. Analyze indications to determine the cause of the emergency or abnormal event. dddd. Direct corrective actions to mitigate the consequences of the emergency abnormal event. eeee. Perform calculations to determine plant status. (eg, fluid flow / heat balance, quadrant power tilts, etc) l O(~% NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-11 of 22
ffff. Analyze indications to determine that an emergency plan event is in progress. A. gggg. Integrate available information to maintain a broad perspective of the event. hhhh. Determine if indications of core damage are present. 4 3. Maintain knowledge of changes to plant procedures. Topics to be selected as required. 4. Reactivity manipulations. Perform in plant as opportunity permits or as scheduled during simulator training. D. Administrative All administrative topics supporting tasks or items listed in B or C above. 1. Technical Specifications a. Recall safety limits, safety systems settings and limiting conditions for operation addressed by technical specifications. b. Interpret / apply technical specification directions for safety limits, safety system settings and g y-(,/ limiting condition for operation. c. Evaluate system performance and coordinate appropriate actions per technical specifications in event limiting condition for operation is not satisfied. d. Identify limiting conditions for operation for remaining in static post-accident condition during repair efforts. 2. Emergency Plan i a. Initiate emergency plan implementing procedures, l
- b. Provide recommendations on classification of event
[ i in terms of levels of emergency plan. c. Write inputs to required plant condition / incident reports. j d. Classify emergency events requiring emergency plan l implementation. e. Direct emergency response as Director Site Emergency Operations (emergency plant). l f. Determine if indications of fuel element damage are present. j l NTM 3.04 f Rev: 0 Date: 8/29/86 l Page: 8.1-12 of 22 i
g. Cather preliminary radioactivity release data (eg, meteorological data in preparation for release ,s ( h calculation. ws h. Report safety limit violations and reportable occurrences.
- i. Ensure required notifications of on-site and off-site personnel for emergency / abnormal events.
- 3. Fire Protection and Industrial Safety a.
Evaluate potential industrial hazards for operations work ascignments. b. Inspect fire barriers. c. Approve enclosed-volume entry permits. 4. Radiation protection
- a. Approve radioactive waste discharge / release permits.
b. Approve radiation exposure authorization. c. Review radiation work permit. d. Approve radiation work permit.
- 5. Maintenance a.
Review tagging (equipment removal and restoration) requests for plant equipment. b. Prepare maintenance work requests. O-c. Review maintenance work requests. d. Authorize performance of maintenance on shift (including preventative maintenance). e. Monitor the conduct of maintenance on shift. f. Verify post-maintenance operability of safety-related equipment. g. Direct minor repairs by the operating shift. h. Approve jumper and lifted lead removal / placement.
- i. Review audit of j umpers and lifted leads.
- j. Review periodic audit of tagging.
6. Miscellaneous administration l a. Write temporary procedures / changer. b. Approve temporary procedure changes. c. Authorize containment entry and exit. d. Review operating logs for trends and out-of-specification conditions, e. Direct shift personnel actions during major plant evolutions. 4 NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-13 of 22
- 7. Maintain knowledge of changes to plant license, technical specifications and administrative procedures
/, v' \\,/ Items to be scheduled as required. 5.0 _ Training Schedule The content of the Licensed Operator Continuing Training (LOCT) Program shall be based on the, items contained in Section 4.0 of this program description. LOCT schedules shall be developed per Section 6.2 of the CY LOCT Program Implementing Procedure and requirements listed below. 5.1 Regulatory commitments of 10CFR55 and NUREG 0737 shall be met as follows. 5.1.1 Topics from the following subjects shall be taught at least once during every two year period. Reactor Theory Operating Characteristics Instrumentation and Control System Protection and Safety Systems Normal, Abnormal, and Emergency Procedures Radiation Control and Safety Fluid Flow and Pump Theory Thermodynamics 3 Operation with a Damaged Core 4 Technical Specifications 5.1.2 The following reactor control manipulations shall be scheduled and completed during simulator training sessions on an annual or biennial basis es indicated by a (1) or (2) in the margin next to the manipulation. Specific tasks that cause the manipulations to be performed shall be selected from Section 4.0. Plant or reactor startup to include a range that reactivity feedback from nuclear heat generation is noticeable and a heat up rate is established. (1) Orderly Plan Shutdown (1) Manual control of feedwater systems during startup and shutdown. (1) Boration and dilution during power operation. (1) 10% power change due to manual rod control. (1) 10% power change due to load change with' manual rod control. (1) Loss of instrument air. (1) NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-14 of 22
Loss of electrical or degraded power sources. (1) [' u Loss of core coolant flow / natural (? circulation. (1) Loss of RCS inventory including: Steam generator tube rupture. (1) Large and small leak including leak rate determination. (1) Leak inside and outside containment.(1) Saturated reactor coolant response. (1) Pressurizer Leaks. (1) Loss of condenser vacuum. (1) Loss of service water required for safety system. (1) Loss of shutdown cooling. (1) Loss of RPCCW. (2) Loss of normal feedwater or feedwater system. (2) Loss of all feedwater or feedwater system. (1) Loss of protective system channel. (2) Miss positioned control rods or dropped rods. (2) Inability to drive control rods. (2) Conditions requiring use of emergency Boration. (2) Turbine or generator trip. (2) {~')S Malfunction of auto control systems which affect reactivity. (2) q_ Malfunction of RCS pressure control / volume control systems. (2) Reactor Trip (1) Main steam line break inside or outside containment. (2) Nuclear instrument failures. (2) Operation outside control room (1) Minimum of 10 reactivity manipulations. (2) Fuel Clad Failure (2) Operation of Turbine Controls in manual during a Turbine startup. (1) 5.1.3 The following examinations are required on an annual basis. The examinations shall be prepared per requirements of NTM-3.04, Connecticut Yankee Licensed Operator Continuing Training Program Implementing Procedure. l 5.1.3.1 A Category I Annual LOCT Examination based on instructional objectives covered during the current calendar year. 0O NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-15 of 22
5 1.3.2 A Category III Annual Evaluation Examination based on a representative f-v, sampling of instructional obj e ct ive s (j)2 listed in Section 6.0 of this program description. 5.1.3.3 A Category IV or V Annual Operational l Examination emphasizing safe operation and shutdown of the reactor and the prevention of the release of fission products to the environment. 5.1.4 All emergency and abnormal operating procedures are required to be reviewed on an annual basis by each license holder. The review may occur in the classroom, simulator or on shift environment. 5.2 Within the constraints listed in 5.1 above, specific LOCT topics shall be selected considering the following: 5.2.1 Training effectiveness feedback per procedure NTM-2.05 of the Nuclear Training Manual. 5.2.2 User Department feedback and requests. 5.2.3 Annual Evaluation Examination Results. ~, 5.2.4 Significant plant / industry events. 5.2.5 Plant modifications and backfit items. 5.2.6 Revisions and additions to plant operational documents. 6.0 Terminal Objectives CY-OP-LO-RXTH -L35000 CY-OP-LO-RXTH -L35001 CY-OP-LO-RXTH -L35002 CY-OP-LO-RXTH -L35003 CY-OP-LO-RXTH -L35004 CY-OP-LO-RXTH -L35006 CY-OP-LO-RXTH -L35007 CY-OP-LO-RXTH -L35008 CY-OP-LO-RXTH -L35009 CY-OP-LO-RXTH -L35010 CY-OP-LO-RXTH -L35011 CY-OP-LO-HTFF -L65000 O NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-16 of 22
^ CY-OP-LO-HTFF -L65001 CY-OP-LO-HTFF -L65002 CY-OP-LO-HTFF -L65003 p/ CY-OP-LO-HTFF -L65004 ( CY-OP-LO-HTFF -L65005 CY-OP-LO-HTFF -L65006 CY-OP-LO-HTFF -L65007 CY-OP-LO-HTFF -L65008 CY-OP-LO-HTFF -L65009 CY-OP-LO-HTFF -L65010 CY-OP-LO-HTFF -L65011 CY-OP-LO-HTFF -L65012 CY-OP-LO-HTFF -L65013 CY-OP-LO-HTFF -L65014 CY-OP-LO-HTFF -L65014 CY-OP-LO-HTFF -L65015 CY-OP-LO-HTFF -L65016 CY-OP-LO-HTFF -L65017 CY-OP-LO-TA -L70000 CY-OP-LO-TA -L70001 CY-OP-LO-TA -L70002 CY-0P-LO-MITCOR-L75000 CY-0P-LO-MITCOR-L75001 CY-OP-LO-MITCOR-L75002 CY-0P-LO-MITCOR-L75003 CY-OP-LO-MITCOR-L75004 CY-0P-LO-MITCOR-L75005 CY-0P-LO-MITCOR-L75006 CY-0P-LO-MITCOR-L75007 4 CY-OP-LO-FUNHP-L25000 CY-OP-LO-FUNHP-L25001 CY-OP-LO-FUNHP-L25002 CY-OP-LO-FUNHP-L25003 CY-OP-LO-FUNHP-L25004 CY-OP-LO-FUNHP-L25005 CY-OP-LO-FUNHP-L25006 CY-OP-LO-FUNHP-L25007 CY-0P-LO-FUNHP-L25008 CY-OP-LO-FUNHP-L25009 i CY-OP-LO-FUNHP-L25010 CY-OP-LO-FUNHP-L25011 CY-OP-LO-FUNCHM-L22000 CY-OP-LO-FUNCHM-L22001 CY-0P-LO-FUNCHM-L22002 CY-OP-LO-FUNCHM-L22003 CY-OP-LO-FUNCHM-L22004 CY-0P-LO-FUNCHM-L22005 CY-OP-LO-FUNCHM-L22006 CY-OP-LO-PRISYS-L00210 CY-0P-LO-PRISYS-L00220 O NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-17 of 22
CY-OP-LO-PRISYS-LOO 240 CY-OP-LO-PRISYS-LOO 250 (,,)i (' CY-OP-LO-PRISYS-LOO 400 CY-OP-LO-PRISYS-LOO 500 CY-OP-LO-PRISYS-LOO 600 CY-OP-LO-PRISYS-LOO 610 C,-OP-LO-PRISYS-LOO 700 Y CY-OP-LO-PRISYS-LOO 900 CY-OP-LO-PRISYS-LO4300 CY-OP-LO-PRISYS-LO4400 CY-0P-LO-PRISYS-LO4500 CY-OP-LO-PRISYS-LO5600 CY-OP-LO-SECSYS-L01600 CY-0P-LO-SECSYS-L01800 CY-OP-LO-SECSYS-LO2100 CY-OP-LO-SECSYS-LO3500 CY-OP-LO-SECSYS-LO3901 CY-0P-LO-SECSYS-LO3902 CY-0P-LO-SECSYS-LO3903 CY-OP-LO-SECSYS-LO3904 CY-OP-LO-SECSYS-LO3905 CY-0P-LO-SECSYS-LO3906 CY-OP-LO-SECSYS-LO3907 CY-0P-LO-SECSYS-LO3908 CY-OP-LO-SECSYS-LO3909 CY-OP-LO-SECSYS-LO4100 CY-0P-LO-SECSYS-LO4600 CY-OP-LO-ELECT -LO6400 f-(x) CY-OP-LO-ELECT -LO6800 CY-OP-LO-ELECT -LO6900 CY-OP-LO-ELECT -LO7200 CY-OP-LO-ELECT -LO7300 CY-OP-LO-ICSYS -LO7500 CY-0P-LO-ICSYS -LO7600 CY-OP-LO-ICSYS -LO7800 CY-0P-LO-ICSYS -LO7900 CY-OP-LO-ICSYS -LO8000 CY-OP-LO-ICSYS -LO8200 CY-OP-LO-AOP -Lil CY-OP-LO-AOP -L12 CY-OP-LO-AOP -L12000 CY-OP-LO-AOP -L13 CY-OP-LO-AOP -L1401 CY-OP-LO-AOP -L1402 CY-OP-LO-AOP -L150! CY-OP-LO-AOP -L1502 CY-OP-LO-AOP -Ll6 CY-OP-LO-AOP -Ll7 CY-OP-LO-AOP -L1901 CY-OP-LO-AOP -L1902 O NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-18 of 22
CY-OP-LO-AOP -L2001 CY-OP-LO-AOP -L2002 3 ai CY-OP-LO-AOP -L2101 CY-OP-LO-AOP -L2102 CY-OP-LO-AOP -L2201 CY-OP-LO-AOP -L2202 C.Y-OP-LO-AOP -L2301 CY-OP-LO-AOP -L2302 CY-OP-LO-EOP -L30 CY-OP-LO-EOP -L31 CY-OP-LO-EOP -L3201 CY-OP-LO-EOP -L3202 CY-OP-LO-EOP -L33 CY-OP-LO-EOP -L34 CY-OP-LO-EOP -L35 CY-OP-LO-EOP -L36 CY-OP-LO-EOP -L37 CY-OP-LO-EOP -L38 CY-OP-LO-EOP -L39 CY-OP-LO-EOP -L40 CY-OP-LO-EOP -L41 CY-OP-LO-EOP -L42 CY-OP-LO-EOP -L43 CY-OP-LO-EOP -L10001 CY-OP-LO-EOP -L10002 CY-OP-LO-EOP -L10101 CY-OP-LO-EOP -L10102 O CY-OP-LO-EOP -L10103 CY-OP-LO-ADMIN -L81000 CY-OP-LO-ADMIN -L82000 CY-OP-LO-ADMIN -L83000 CY-OP-LO-ADMIN -L83001 CY-OP-LO-ADMIN -L83002 CY-OP-LO-ADMIN -L84000 CY-OP-LO-ADMIN -L85000 CY-OP-LO-ADMIN -L87000 CY-OP-LO-ADMIN -L88000 CY-OP-LO-ADMIN -L88001 CY-OP-LO-ADMIN -L89990 TPG - ADM -1.1-5/ALL TPG - ADM -1.1-34/ALL TPG - ADM -1.1-44/AL TPG - EPIP -1.5-1/ALL l j TPG - EPIP -1.5-2/ALL TPG - EPIP -1.5-3/ALL TPG - EPIP -1.5-4/ALL TPG - EPIP -1.5-5/ALL l TPG - NOP -2.1-2/ALL l TPG - NOP -2.1-3/ALL l TPG - NOP -2.1-6/ALL l l ' O NTM 3.04 Rev: 0 Date: 8/29/86 8.1-19 of 22 Page:_
TPG - NOP -2.2-1/ALL TPG - NOP -2.2-3/ GEN [ 2/'h TPG - NOP -2.2-3/6.3 \\_ TPG - NOP -2.2-4/ALL TPG - NOP -2.3-1/ALL TPG - NOP -2.3-2/ALL TPG - NOP -2.3-3/ALL TPG - NOP -2.4-3/ALL TPG - NOP -2.4-7/ALL TPG - NOP -2.6-2/ GEN TPG - NOP -2.6-2/6.3.1 TPC - NOP -2.6-3/ GEN TPG - NOP -2.6-3/6.1 TPG - NOP -2.6-3/6.2,6.3 TDG - NOP -2.6-3/6.6 TPG - NOP -2.16-2/CEN TPG - NOP -2.16-2/6.1.6.7 TPG - NOP -2.16-2/6.8-7.0 TPG - NOP -2.20-5/ALL TPG - NOP -2.22-1/ALL TPG - NOP -2.22-2/ALL TPG - EOP -3.1-6/ALL TPG - EOP -3.1-8/ GEN TPG - E0P -3.1-8/2.0-5.0 TPG - E0P -3.1-12/ALL TPG - E0P -3.1-15/ALL TPG - E0P -3.1-21/ GEN ("% TPG - E0P -3.1-21/3.0 (,,)c TPG - E0P -3.1-34/ALL TPG - AOP -3.2-5/ GEN TPG - AOP -3.2-5/2.0 TPG - AOP -3.2-ll/ALL TPG - AOP -3.2-14/ GEN TPG - AOP -3.2-14/2.0 TPG - AOP -3.2-14/4.0 TPG - AOP -3.2-15/ GEN TPG - AOP -3.2-15/2.0 TPG - AOP -3.2-17/ALL TPG - AOP -3.2-18/ GEN TPG - AOP -3.2-18/3.0 TPC - AOP -3.2-19/ALL TPG - AOP -3.2-23/ GEN TPG - AOP -3.2-23/2.0 TPC - AOP -3.2-23/4.0 TPG - AOP -3.2-23/5.0 TPG - AOP -3.2-26/ALL TPG - AOP -5.3-19/ALL TPG - AOP -5.3-20/ALL TPG - ERG -E-0 TPG - ERG -ES-0.0 O NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-20 of 22
4 TPC - ERG -ES-0.1 TPG - ERG -ES-0.2 )' TPG - ERG -ES-0.4 TPG - ERG -ECA-0.0 TPG - ERG -ECA-0.1 TPG - ERG -ECA-0.2 TPG - ERG -E-1 TPG - ERG -ES-1.1 TPG - ERG -ES-1.2 TPC - ERG -ES-1.3 TPG - ERG -ES-1.4 TPG - ERG -ECA-1.1 TPG - ERG -ECA-1.2 TPG - ERG -E-2 TPG - ERG -ECA-2.1 TPG - ERG -E-3 TPG - ERG -ES-3.1 TPG - ERG -ES-3.2 TPG - ERG -ES-3.3 TPG - ERG -ECA-3.1 TPG - ERG -ECA-3.2 TPG - ERG -ECA-3.3 TPG - ERG -FR-S.1 TPG - ERG -FR-S.2 TPG - ERG -F-0.1 TPG - ERG -FR-C.1 TPG - ERG -FR-C.2 ( TPC - ERG -FR-C.3 \\ TPG - ERG -F-0.2 TPG - ERG -FR-H.1 TPG - ERG -FR-H.2 TPG - ERG -FR-H.3 TPG - ERG -FR-H.4 ERG -FR-H.5 TPG TPG - ERG -F-0.3 TPC - ERG -FR-P.1 TPC - ERG -FR-P.1 TPG - ERG -FR-0.4 TPG - ERG -FR-Z.1 TPG - ERG -FR-Z.2 TPG - ERG -FR-Z.3 TPG - ERG -F-0.5 TPG - ERG -FR-I.1 TPG - ERG -FR-I.2 TPG - ERG -FR-I.3 TPG - ERG -F-0.6 /~ NTM 3.04 Rev: 0 Date: 8/29/86 Page: 8.1-21 of 22
s r* e 7.0 Training Program Notes The Assistant Supervisor, Operator Training may make changes to the order of instruction set forth in an LOCT Cycle Schedule if the reordering does not adversely impact on the progression of instructional objectives. 1 l l i i r ..)o i i l i l i I NTM 3.04 Rev: 0 i Date: 8/29/86 l l Page: 8.1-22 of 22 ( _}}