ML20215D367
| ML20215D367 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 05/09/1986 |
| From: | Black J NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20215D345 | List: |
| References | |
| NTM---3.04, TAC-64137, TAC-64620, NUDOCS 8612160341 | |
| Download: ML20215D367 (37) | |
Text
b' TRAINING PROGRAM IMPLEMENTING PROCEDURE COVER SHEET NUCLEAR TRAINING MANUAL MILLSTONE UNIT 1 LICENSED OPERATOR REQUALIFICATION IMPLEMENTING PROCEDURE NTM - 3.04 O
Approved:
'91-ractoJf, Nuclear Training
[
Director /Statio Jperintendent Revision:
0 Date:
May 9, 1986 Concurrence:
Mana r, Quality Assura,nce Submitted: __
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Training Program Control Committee 8612160341 861209 PDR ADOCK 05000213 PDR V
1.0 PURPOSE
. O The purpose of this procedure is to implement the Millstone Unit 1 Licensed Operator Requalification (LOR) Program in accordance with the Nuclear Training Manual and as detailed i
in the Millstone Unit 1. LOR Program Description.
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2.0 APPLICABILITY s
c) 2.1 This procedure applies to:
2.1.1 Those Unit I and Nucl. ear Training Department personnel involved in the planning, delivery, evaluation and review of the Unit 1 LOR Program.
2.1.2 Those Unit I and Nuclear Training Department personnel who currently hold NRC Licenses or certifications on Millstone Unit 1.
3.0 REFERENCES
3.1 INPO GPG 02-10-80, Nuclear Power Plant Requalification Program for Licensed Personnel.
3.2 10 CFR 55, Operators Licenses 3.3 ANSI /ANS-3.1, American National Standard for selection, qualification and training of personnel for Nuclear Power Plants.
3.4 Nuclear Training Manual
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As 4.0 DEFINITIONS 4.1 License Holders An individual who currenty holds an NRC Operators License or Instructor Certification on Millstone Unit 1 and is enrolled in the MPl LOR Program.
4.2 Integrated Simulator Training Session A training session conducted at the Unit 1 Simulator which involves the coordination of multiple plant systems and procedures.
4.3 Cycle The length of time required to instruct all license holders on the scheduled weekly topics, normally a 6 week period based on Operations Department shift schedule.
Od NTM - 3.04 Rev: 0 Date: 5/9/86 Page 3 of 10
5.0 RESPONSIBILITIES
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5.1 Supervisor, Operator Training, Millstone Unit 1 s.
4 5.1.1 Responsible for the overall conduct of the LOR Program in accordance with the Nuclear Training Manual and the Training Program Description.
5.1.2 Responsible for scheduling annual requalification examinations.
5.1.3 Responsible for approving examinations.
5.1.4 Responsible for approving changes to the Training Schedule.
5.1.5 Responsible for performing Supervisor's assessment of training.
5.1.6 Responsible for authorizing lesson plans for use.
5.1.7 Responsible for ensuring Nuclear Training Department personnel who hold licenses or certification on Millstone One are enrolled in this program.
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5.2 Assistant Supervisor, Operator Training, Millstone Unit 1 5.2.1 Responsible for preparing day-by-day program schedules.
5.2.2 Responsible for approving written and oral examinations.
5.2.3 Responsible for assigning personnel to provide instruction.
5.2.4 Responsible for performing and assigning Nuclear Training Department personnel to perform assessments of training.
5.2.5 Responsible for approving lesson plans.
V)
I NTM - 3.04 Rev: 0 Date: 5/9/86 Page 4 of 10
5.3 Assistant Supervisor, Simulator Training,
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Millstone Unit 1 5.3.1 Responsible for approving simulator examinations.
5.3.2 Responsible for assigning Nuclear Training Department personnel to provide instruction.
5.3.3 Responsible for performing and assigning Nuclear Training Department personnel to perform assess-ments of training.
5.3.4 Responsible for approving lesson plans.
5.4 Nuclear Training Department Personnel Responsible for conducting training activities, as assigned, in accordance with the Nuclear Training Manual and Training Program Description.
5.5 Millstone Unit 1 Superintendent Responsible for ensuring license holders are enrolled in this program.
5.6 Millstone Unit 1 Operations Supervisor
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Responsible for performing Supervisor's Assessments of Training.
6.0 INSTRUCTIONS 6.1 Program Duties 6.1.1 The Supervisor, Operator Training, Millstone Unit 1 is responsible for the Licensed Operator Requalification Program and shall:
6.1. l '.1 Supervise the Millstone Unit 1 LOR Program to ensure compliance with the Nuclear Training Manual and the Training Program Description.
6.1.1.2 Serve as the point of contact between the Nuclear Training Department and Millstone Unit 1 Operations supervision.
NTM - 3.04 Rev: 0 Date: 5/9/86 Page 5 of 10 y
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6.1.2 The Assistant Supervisors, Operator and Simu-( J-lator Training, Millstone Unit 1, shall 7,
6.1.2.1 Schedule, coordinate and evaluate the effectiveness of training activ-ities associated with the conduct of this program.
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6.1.2.2 Assign Nuclear Training Department personnel to carry out the training activities of this program.
6.1.3 Nuclear Training Department Personnel shall conduct training activities, as assigned, during the course of this program.
6.1.4 Millstone Unit 1 Supervisory / Management personnel shall evaluate the effectiveness of this program.
6.2 Scheduling 6.2.1 The Millstone Unit 1 LOR Program is a closed enrollment program as described in the Nuclear Training Manual.
(N 6.2.2 Supervisor, Operator Training shall ensure that
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all license holders are assigned to scheduled sessions of the LOR Program.
6.2.3 The Assistant Supervisor, Operator Training and Assistant Supervisor, Simulator Training shall prepare a detailed program schedule.
6.2.4 The Supervisor, Operator Training, shall notify the Millstone Unit Superintendent, by memo, of the program start date and the annual requalification examination dates.
6.2.5 The Assistant Supervisor, Operator Training shall provide each license holder with a copy of the classroom program schedule prior to the scheduled program start date. This program schedule shall also include simulator training dates / weeks.
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NTM - 3.04 Rev: 0 Date: 5/9/86 Page 6 of 10
~
r 6.2.6 During the course of the program, the Assistant
(^i Supervisor, Operator Training shall prepare, for K/
each cycle a weekly schedule which includes the date and time that each training session is to be delivered and the location of the_ training session.
6.2.7 The Assistant Supervisor, Operator Training-shall distribute the schedule to the designated instructors, license holders, the Assistant Supervisor, Simulator Training, and the Supervisor, Operator Training.
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 6.3.5.
6.3.1 Classroom Training Sessions 6.3.1.1 Currently licensed or certified by the NRC on Millstone Unit 1 at the SRO level or previously licensed or certified by the NRC at the SRO level
(,)
and currently enrolled in an NRC approved LOR Program.
6.3.1.2 Certified as a Level 1 instructor in accordance with the Nuclear Training Manual.
6.3.1.3 In lieu of 6.3.1.1 an instructor may teach selected topics if certified to teach those areas in accordance with sections 1.10 of reference 3.4.
6.3.2 Integrated Simulator Training 6.3.3.1 Currently licensed or certified by the NRC on Millstone Unit 1 at the SRO level or previously licensed or cer-tified by the NRC at the SRO level and currently enrolled in an NRC approved LOR Program.
NTM - 3.04 Rev: 0 Date: 5/9/86 Page 7 of 10
k 6.3.3.2 Certified as a Level 1 instructor in T
accordance with the Nuclear Training
['J Manual.
6.3.3.3 Have satisfactorily completed a simulator instructional skills training program.
6.4 Examinations and Lesson Plans 6.4.1 Examinations shall be approved as specified below:
Category I exams - Supervisor, Operator Training, or either Assistant Supervisor.
Category II exams - Supervisor Operator Training or either Assistant Supervisor.
Category III exams - Assistant Supervisor, Operator Training or Assistant Supervisor, Simulator Training Category IV exams - Assistant Supervisor, Operator Training or Assistant Supervisor, Simulator Training
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%J Category V exams - Assistant Supervisor, Simulator Training Category V final examination - Supervisor, Operator Training or either Assistant Supervisor NOTE No Supervisor shall approve two (2) consecutive category I or V final exams if he is required to participate in the LOR Program.
No Supervisor shall approve over 50% of the category II exams given during any Requal year if he is required to participate in the LOR Program.
6.4.2 Acceptable standards of performance (pass criteria) shall be established for examinations ac follows:
O NTM - 3.04 Rev: 0 Date: 5/9/86 Page 8 of 10
w categroy I and II examinations:
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70% per section, 80% overall category III examinations: none established category IV and V examinations: Satisfactory 6.4.3 The supervisors indicated shall approve lesson plans as specified below:
6.4.3.1 Classroom Lesson Plans - Assistant Supervisor, Operator Training 6.4.3.2 Briefing Room Lesson Plans - Assistant Supervisor, Simulator Training 6.4.3.3 Simulator Lesson Plans - Assistant Supervisor, Simulator Training 6.4.3.4
" Approval for Use" - 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 spec-(^}
ified:
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6.5.1 The Assistant Supervisor, Operator Training shall assign Nuclear Training Department personnel to perform Examination Assessments at the completion of each written examination.
6.5.2 The appropriate assistant supervisor shall assign Nuclear Training Department personnel to perform instructor assessments and ensure student assessments are completed, at the completion of every cycle of the LOR Program.
6.5.3 The Assistant Supervisor, Operator Training shall perform two Supervisor's Assessments during the annual classroom phase of the LOR Program.
6.5.4 The Assistant Supervisor, Simulator Training shall perform one Supervisor's Assessment annually for integrated simulator training.
O NTM - 3.04 Rev: 0 Date: 5/9/86 Page 9 of 10
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6.5.5 The Supervisor, Operator Training shall perform 7-(_3)
Supervisor's Assessments of two integrated simulator training sessions, and two classroom training sessions during the duration of the annual LOR Program.
6.5.6 The Operations Supervisor or his designee shall perform Supervisors Assessments of one classroom training session, and one integrated simulator training session during the duration of the annual LOR Program.
6.5.7 The Assistant Supervisor, Operator Training shall assign Nuclear Training Department Per-sonnel to complete the Training Effectiveness Report at the completion of the annual LOR Program.
6.6 Retraining Requirements None 6.7 Training Program Records All training records associated with the LOR Program shall be retained in accordance with reference 3.4.
7.0 Figures None 8.0 Attachments 8.1 MP1 Licensed Operator Requalification Program Description.
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NTM - 3.04 Rev: 0 Date: 5/9/86 Page 10 of 10
O TRAINING PROGRAM DESCRIPTION COVER SHEET Training Program: MP1 Licensed Operator Requalification Program Training Program Number: MP1 - LOR-86/87 Prepared by:
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~ 'Nu ar TrailiTng Personnel Students Pre quisites Verified by:
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Subject Matter Expert Reviewed by:
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.M r airdng Supervisor O
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MP1 LICENSED OPERATOR REQUALIFICATION PROGRAM
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1.0 TRAINING PROGRAM
SUMMARY
The MP1 Licensed Operator Requalification ( LOR )~ Program provides the MP1 RO and SRO Licensed Personnel with a review of control room response to power plant off normal transients and emergency maneuvers, operation, theory and principles of operation, and plant systems including engineered safety systems and plant instrumentation and control systems.
This program the requirements of 10 CPR 55 Appendix A complies with "Requalification Program for Licensed Operators" as well as requirements set forth in ANS 3.1, the H.R.
Denton letter dated March 28, 1980 and INPO document GPG-02-10-80.
This program will be conducted in a two-year training period.
Each Licensed Operator shall participate in a minimum of twelve weeks of Licensed Operator Training during that period, with a minimum of five weeks in any one calendar year.
Normally, six weeks of Licensed Opertor Training will be conducted annually.
2.0 TRAINING PROGRAM GOALS The Licensed Operator Requalification Program is p\\d designed to provide License Holders with training to:
individual and group abilities in Improve 2.1
- startups, performing integrated plant evolutions, shutdowns, and certain maintenance procedures.
Improve the ability of licensed personnel to 2.2 in an operating shift.
perform as team members Familiarize the licensed personnel with plant and 2.3 procedural modifications.
Improve the supervisory abilities of the Senior 2.4 Licensed Operators.
Familiarize the licensed personnel with the 2.5 operational events that have occurred in the industry and at MPl.
2.0 Review with the licensed personnel the principles of plant operation.
2.7 Review with the licensed personnel required pl. ant systems knowledge.
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3.0 STUDENT PREREQUISITES 3.1 MP1 Reactor Operator License or 3.2 MP1 Senior Reactor Operator License or 3.3 MPl Instructor Certification 4.0 TOPICAL OUTLINE I.
Lecture Topics A.
Academics 1.
Reactor Physics 2.
Thermodynamics 3.
Mitigating Core Damage B.
Electrical Distribution 1.
4160V Distribution 2.
480V Distribution 3.
Vital and Instrument AC 4.
125V DC Distribution 5.
Gas Turbine Generator C.
Major Nuclear Plant Operating Systems
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V 1.
Recirculation System 2.
Feed, Condensate and Steam 1.
Condensate System 2.
Feed System 3.
Main Steam E.
Cooling Water Auxiliary System 1.
Nuclear Instrumentation System 1.
Source Range Instrumentation 2.
Intermediate Range Instrumentation G.
Emergency Core Cooling System 1.
Feedwater Coolant Injection System 2.
Auto Pressure Relief System 3.
Core Spray System 4.
Low Pressure Coolant Injection
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5.
Emergency Service Water L.
Standby Systems
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1.
Standby Liquid Control System 2.
Isolation Condenser System II.
Simulator Topics A.
Approach to criticality with several malfunctions 1.
Rod fails to move 302/8.0 2.
SRM Hi or Inoperative 401A/8.0 B.
Plant heatup with malfunctions 1.
Rod Drop 302/8.0 2.
Operation of 10% feed valve 316/7.5 3.
IRM HI-HI or inoperative 402A/8.0 C.
1.
Plant startup 203/5.0 D.
Power operation with malfunctions and surveillances 1.
Daily shift surveillances 10.10/ALL 2.
Rod drift 302/8.0
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3.
Secure amplidyne 340/7.5
's 4.
NUSOER 2-82 switching operation 5.
NUSOER l-81 electrical switching 6.
LPRM inoperative E.
Rupture of CRD System 516/1.0 F.
Recirculation System failures G.
Reactor Scram H.
Power operation, malfunctions, surveillances and rupture in the CU System 1.
Nitrogen pressure low 311C/8.0 2.
Flow bias off normal 404A/8.0 3.
CU System rupture 516/l.0 4.
NUSOER 3-83 N2 pressure control I.
Locs of 345KV 503A/1.0 J.
Loss of instrument air 512/1.0 K.
Loss of all AC 1.
Control room operations 6.01/6.2
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2.
MS low' pressure 317/8.0
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3.
Mussel cooling 323/7.10 4.
Secure heat treatment 323/7.11 5.
RBM inoperative 410A/8.0 6.
Loss of all AC 503C/1.0 7.
NUSOER 6-83 operational control L.
Reactor level control to spray cooling 1.
EOP precautions 569/3.0 2.
RPV level control actions 570/3.0 3.
RPV spray cooling 573/3.0 4.
Level restoration actions 576/3.0 M.
Reactor steam cooling 1.
Steam cooling actions 574/3.0 N.
Reactor shutdown to hot standby 1.
Reactor shutdown to hot standby 205/7.0 2.
TBCCW pressure low 309A/8.0 3.
Operation of 10% feed valve 316/7.5 O.
Reactor shutdown to cold conditions 1.
Cooldown to cold shutdown 206/5.0
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2.
NUSOER 2-83, 2A-83 Minimum Natural Circulation level P.
Power operation with fuel clad failure 1.
Recirc System Hi temperature 301/8.0 2.
Main Steam Tunnel Hi temperature 3.
Fuel clad failure 508/1.0 4.
NUSOER l-84 Recirc System O.
Rupture of scram discharge volume 516/1.0 R.
High radioactivity release 509/1.0 S.
Power operation, TBSCCW failures 1.
RBCCW low pressure 309B/8.0 2.
APRM Inoperative 404A/8.0 T.
RBCCW Failures 1.
RBCCW low pressure 309C/8.0 2.
Cor.fensate pump cooling failure 315/8.0 0 i 1
U.
Loss of condenser vacuum 507/1.0 esU V.
Rupture of Isolation Condenser 516/1.0 W.
ATWS trip with EOP power control 1.
RPV Power Conrol EOP Actions 572/3.0 X.
Loss of station AC 1.
Turbine trip, low oil pressure 314/8.0 2.
Loss of station AC 503B/1.0 Y.
Approach to critical from scram recovery 1.
Scram recovery procedure 207/5.0 2.
Loss of 125vdc AA.
Service water failures 1.
SW low pressure alarm condition 321/8.0 BB.
ESW failures 1.
ESW strainer.high DP alarm condition 322/8.0
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CC.
Containment control thru flooding of reactor 1.
RPV flooding EOP actions 578/3.0 2.
Containment EOP actions 580/3.0 DD.
EOP pressure control, level, power thru to alternate shutdown cooling 1.
RPV pressure control 571/3.0 2.
RPV depressurization 577/3.0 3.
Level and power control 4.
Alternate S/D cooling actions 579/3.0 5.
MSIV testing SP611.1
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5.0 PROGRAM SCHEDULE g3
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5.1 Cycle One Lesson Plan /
Lesson Plan Code /
.Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allotted 8.0 1
Refresher Fire Brigade 2.0 2
Quarterly Fire Brigade Trn.
Outage Mod.
out mods-86 Classroom 2.0 Reactor Theory 1115 Classroom 2.0 3
Reactor Theory 1115 Classroom 6.0 4
Reactor Theory 1115 Classroom 6.0 Classroom 2.0 5
Self Study Examination Cycle-1 Ex-Cyc-1 II 4.0
()
5.2 Cycle Two 1
Thermodynamics 1116 Classroom 6.0 2
Thermodynamics 1116 Classroom 6.0 3
Thermodynamics 1116 Classroom 6.0 4
Thermodynamics 1116 Classroom 6.0 Classroom 2.0 5
Self Study l
Examination Cycle-2 Ex-Cyc-2 II 4.0 5.3 Cycle Three 2.0 1
Fire Training Meeting / Drills Extraction Steam 1346 Classroom 1.5 Feedwater Heaters & Drains 1348 Classroom 1.5 O.-.
)
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allottec
,x n
2 Cire Water 1323 Classroom 3.0 Emergency Service Water 1322 Classroom 3.0 3'
Source Range Monitors 1401 Classroom 4.0 Intermediate Range Monitors 1402 Classroom 2.0 4
Emergency Plan Training 14000 Classroom 4.0 Kaman Monitor Operations Classroom 1.0 5
Severe Line Outage Detection Classroom 1.0 Exam Cycle-3 Ex-cyc-3.1 II 4.0 Ex-cyc-3.2 5.4 Cycle Four 1
Condensate 1315 Classroom 4.0 Feedwater 1316 Classroom 2.0 2
Feedwater 1316 Classroom 2.0 Feedwater Coolant Injection 1334 Classroom 2.0 3
Auto Pressure Relief 1337 Classroom 1.5 Core Spray 1336 Classroom 2.0 4
Low Pressure Coolant Inj 1335 Classroom 3.0 Self Study 5
Standby Liquid Control 1304 Classroom 2.0 Exam Cycle-4 Ex-cyc-4.1 II 4.0 Ex-cyc-4.2 5.5 Cycle Five 1
Approach to Criticality RQl-86-1-4-1(S) Simulator 5.0 with Several Malfunctions i
v -
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allotted O
1 Plant heatup w/Several R01-86-4-2(S)
Simulator 2.0 Malfunctions 2
Completion of Plant R01-85-4-3(S)
Simulator 7.0 Heatup and Startup to Power 3
Power Operation with R01-85-4-4(S)
Simulator 2.0 Minor Malfunctions and Surveillances 3
Rupture in the CRD Rol-85-4-5(S)
Simulator 1.0 System 3
Recirculation System RO1-85-4-6(S)
Simulator 2.0 Control Failures Os 3
Reactor Scram Actions Rol-85-4-7(S)
Simulator 2.0 Performed 4
Continued Power Operation RO!-85-4-8(S)
Simulator 3.5 w/ Minor Malfunctions, Surveillances and a Rupture in the Reactor Water Cleanup System 1
4 Loss of All 345 KVA RO1-85-4-9(S)
Simulator 2.0 4
Loss of the Instrument RQl-85-4-10(S)
Simulator 1.5 Air System 5
Loss of All AC ROl-85-4-ll(S)
Simulator 1.5 i
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1
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Time Day Exam Title Exam Number.
Exam Cat.
Allottec
~
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5 Reactor Level Control
'RQl-85-4-12(S0 Simulator 4.0 To EOP Reactor Spray Cooling 5
Reactor EOP Steam RQ1-85-4-13(S)
Simulator 1.5 Cooling 5.6 Cycle Six 1
Reactor Shutdown to Hot RQl-85-5-14(S)
Simulator 2.5 Standby Conditions 1
Reactor Cooldown to RQl-85-5-15(S)
Simulator 4.5 Cold Shutdown 2
Continued Power Operation ROl-85-5-16(S)
Simulator 3.5 w/ Malfunctions and Surveillances and a Failure of the Fuel Cladding 2
Rupture of the Scram ROl-85-5-17(S)
Simulator 2.0 Discharge Volume 2
High Radioactivity RQl-85-5-18(S)
Simulator 1.5 Release 3
Continued Power Operation RQl-85-5-19(S)
Simulator 2.0 w/ Minor Malfunctions and Surveillances and a TBSCCW System Failure 3
RBCCW System Failure R01-85-5-20(S)
Simulator 1.0 0. -
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Timo Day Exam Title Exam Number Exam Cat.
Allotted
(~'s
~J 3
Loss of Main Condenser R01-85-5-21(S0 Simulator 1.0 Vacuum 3
Rupture in the Isolation R01-85-5-22(S)
Simulator 1.0 Condenser 3
ATWS Trip w/EOP Reactor R01-85-5-23(S)
Simulator 2.0 Power Control 4
Loss of Station AC R01 -24 Simulator 0.5 4
Preparation for Approach RQ1-85-5-25(S)
Simulator 1.0 to Criticality from Scram Recovery Conditions 4
Loss of the 125 VDC System R01-85-5-26(S)
Simulator 1.0 4
Service Water Failure R01-85-5-27(S)
Simulator 0.5 4
ESW System Failure R01-85-5-28(S)
Simulator 2.0 i
4 Containment Control EOP R01-85-5-29(S)
Simulator 2.0 Thru Flooding of the Rx
't 5
EOP Reactor Pressure R01-85-5-30(S)
Simulator 7.0 Control to Level and Power Control Thru to Alternate Shutdown Cooling O 1
y.
'4 L
y Lesson Plan /
Lesson Plan Code /
/Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allotted b'i 5.7 Cycle Seven 1
Willimantic Fire Training 8.0 2
Willimantic Fire Training 8.0 Classroom 6.0 3
Review Classroom 6.0 4
Review Classroom 6.0 5
Review 5.8 Annual Requalification Exam I
4.0 5.9 Cycle Eight 1
Quarterly Fire Brigade Trn.
1 1
~2.0 Isolation Condenser 1307 Classroom
~
Main Steam 1317 Classroom 1.5 (s T/
2 Reactor Recirc 1301 Classroom 4.0 '
124V DC Distribution 1344 Classroom 1.5 3
Reactor Water Cleanup 1304 Classroom 3.0 Vitl and Instrument AC 1343 Classroom 2.0 4
4160V Distribution 1341 Classroom 4.0 480V Distribution 1342 Classroom 2.0 5.
Self Study Examination Cycle 8 Ex-Cyc-8 II 4.0 DO -
i Lesson Plan /
Lesson Plan Code /
Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allottec r'b)-
5.10 Cycle Nine 1
Refresher Fire Training 8.0 2
Medic First Aid 8.0 3
Quarterly Fire Brigade Trn.
2.0 Mitigating Core Damage 1800 Classroom 4.0 4
Mitigating Core Damage 1800 Classroom 6.0 5
Self Study Classroom 2.0 Examination Cycle-9 Ex-Cyc-9 II 4.0 i
5.11 Cycle Ten 1
Approach to Criticality ROl-86-1-4-1(S) Simulator 5.0 with Several Malfunctions 1
Plant heatup w/Several RQ1-86-4-2(S)
Simulator 2.0 Malfunctions 2
Completion of Plant RQ1-85-4-3(S)
Simulator 7.0 Heatup and Startup to Power 3
Power Operation with hG.-85-4-4(S)
Simulator 2.0 Minor Malfunctions and Surveillances 3
Rupture in the CRD RO1-85-4-5(S)
Simulator 1.0 Sy s te.a O _
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allotted O
3 Recirculation System ROl-85-4-6(S)
Simulator 2.0 Control Failures 3
Reactor Scran Actions Rol-85-4-7(S)
Simulator 2.0 Performed 4
Continued Power Operation RQl-85-4-8(S)
Simulator 3.5 w/ Minor Malfunctions, Surveillances and a Rupture in the Reactor Water Cleanup System 4
Loss of All 345 KVA R01-85-4-9(S)
Simulator 2.0 4
Loss of the Instrument R01-85-4-10(S)
Simulator 1.5 Air System 5
Loss of All AC ROl-85-4-ll(S)
Simulator 1.5 5
Reactor Level Control RQl-85-4-12(S0 Simulator 4.0 To EOP Reactor Spray Cooling 5
Reactor EOP Steam RQl-85-4-13(S)
Simulator 1.5 Cooling 5.12 Cycle Eleven 1
Reactor Shutdown to Hot RQ1-85-5-14(S)
Simulator 2.5 Standby Conditions 1
Reactor Cooldown to RQ1-85-5-15(S)
Simul'ator 4.5 Cold Shutdown. -
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Time Day Exam Title Exam Number Exam Cat.
Allotted OG 2
Continued Power Operation ROl-85-5-16(S)
Simulator 3.5 w/ Malfunctions and Surveillances and a Failure of the Fuel Cladding 2
Rupture of the Scram R01-85-5-17(S)
Simulator 2.0 Discharge Volume 2
High Radioactivity RQl-85-5-18(S)
Simulator 1.5 Release 3
Continued Power Operation RQl-85-5-19(S)
Simulator 2.0 w/ Minor Malfunctions and Surveillances and a TBSCCW (d'
System Failure 3
RBCCW System Failure ROl-85-5-20(S)
Simulator 1.0 3
Loss of Main Condenser RQ1-85-5-21(S0 Simulator 1.0 Vacuum 3
Rupture in the Isolation RQl-85-5-22(S)
Simulator 1.0 Condenser 3
ATWS Trip w/EOP Reactor RQl-85-5-23(S0 Simulator 2.0 Power Control j
4 Loss of Station AC RQl -24 Simulator 0.5 4
Preparation for Approach RO1-85-5-25(S)
Simulator 1.0 to Criticality from Scram
()
Recovery Conditions -. _
Lesson Plan /
Lesson Plan Code /
Trn. Env.
Timo Day Exam Title Exam Number Exam Cat.
Allotted 4
Loss of the 125 VDC System R01-85-5-26(S)
Simulator 1.0 4
Service Water Failure RQl-85-5-27(S) -Simulator 0.5 4
ESW System Failure R01-85-5-28(S)
Simulator 2.0 4
Containment Control EOP R01-85-5-29(S)
Simulator 2.0 Thru Flooding of the Rx 5
EOP Reactor Pressure R01-85-5-30(S)
Simulator 7.0 Control to Level and Power Control Thru to Alternate Shutdown Cooling 5.13 Cycle Twelve 1
Thermodynamics 1116 Classroom 6.0 2
Thermodynamics 1116 Classroom 6.0 3
Thermodynamics 1116 Classroom 2.0 Examination Cycle Twelve Ex-cyc-12 II 4.0 8.0 4
Willimantic Fire Training 8.0 5
Willimantic Fire Training 5.14 Cycle Thirteen 1
Reactor Theory 1115 Classroom 6.0 1
2.0 2
Quarterly Fire Brigade Trn.
Reactor Theory 1115 Classroom 4.0
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Lesson Plan Cods /
Trn. Env.
Time Lesson Plan /
Exam Number..
Exam Cat.
Allotted Day-Exam Title O
Classroom 6.0 3
Review Classroom 6.0 4-Review Classroom 6.0 5
Review I
4.0 5.15 Annual Requalification Exam Reviews for annual requalification exams will be developed for each individual shift.
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6.0 TERMINAL OBJECTIVES The MPl LOR Program addresses all the tasks listed on Attachment A. The Terminal objectives associated with each task may be found on the appropriate Training Performance Guide (TPG).
7.0 TRAINING PROGRAM NOTES 7.1 A training day consists of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
The time remaining in all scheduled days of training that consists of less than 8 contact hours is to be used as self study.
7.2 Daily critiques will accompany each simulator session.
7.3 The Supervisor, Operator Training may approve changes to the order of instruction set forth in section 5.0 of this program description if the reordering does not adversly impact on the progression of instructional objectives.
7.4 The number of students participating in an integrated simulator training session shall be limited to four.
7.5 The review sessions in the cycle prior to the annual requalification exams will be developed for each individual shift.
7.6 The self study time on the day of the exam for the cycle will be used to review industry events.
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O ATTACHMENT A The attached task listing is for the Licensed Operator Requalification Program.
O O
l ATTACHMENT A.
TRAINING PROGRAM TASK LISTING Program
Title:
Licensed Requalification Program Number: R01-85-1 TASK [
TASK NAME TYPE STATUS COMMENTS 6.01/6.2 CONTROL ROOM CONDUCT RQ ll(S) 10.10/ALL
_ COMPLETE THE SHIFT SURV.
RO 4(S)
LOG 201/5.0 PERFORM AN APPROACH TO RQ 1(S)
CRITICALITY 202/5.0 PERFORM A PLANT HEATUP RO 2(S) 203/5.0 PERFORM A PLANT STARTUP RO 3(S)
TO RATED POWER 204/5.0 PERFORM POWER OPERATIONS RO 4(S) 205/7.0 PERFORM A PLANNED SHUTDOWN RQ 14(S)
('N TO HOT STANDBY OR HOT
\\/
SHUTDOWN
-206/5.0 PERFORM PLANT COOLDOWN TO RO 15(S)
COLD SHUTDOWN 207/5.0 PERFORM A SCRAM RECOVERY R0 25(S) 301/7.2 START RECIRC PUMP WITH RX RQ (L)
SUBCRITICAL 301/7.7 REMOVE ONE RECIRC PUMP FROM RO (L)
SERVICE 301/7.8 RESTORE IDLE RECIRC PUMP TO RO (L)
SERVICE 3.01/7.10 TRANS RECIRC MG SET FROM RO (L)
LOCAL MAN TO IND MAN 301/8.0 PERFORM ALARM RESPONSE RO 16(S) 302/7.1 PLACE CRD SYS IN SERVICE RQ (L) 302/7.5 WITHDRAW CONTROL RODS R0 (L)
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302/7.7 INSERT CONTROL RODS RO (L)
TASK #
TASK NAME TYPE STATUS COMMENTS
_ 302/8.0 PERFORM ALARM RESPONSE RQ 16(S)
~'303/7.1 PLACE RWCU SYS'IN SERVICE RQ (L)
DURING PLANT STARTUP 303/7.4 REMOVE RWCU FROM SERVICE RQ (L)
W/Rx AT RATED PRESSURE 303/7.5 RETURN RWCU TO SERVICE AT RQ (L)
PRESSURE 303/7.6 REJECT REACTOR WATER TO MAIN RQ (L)
CONDENSER 304/7.2 PLACE SBLC SYS IN STBY RQ (L) 304/7.3 INJECT BORON SOLUTION INTO RQ (L)
REACTOR USING SBLC 305/7.2 OPERATE SDC SYS FOR COOLDOWN RQ (L) 306/7.1 OPERATE HEAD COOLING SYS RQ (L)
RQ (L) 306/8.0 PERFORM ALARM RESPONSE RQ (L) 307/7.1 FILL ISO COND SHELL SIDE PLACE ISO COND IN STBY AT RQ (L)
)307/7.2 0 Rx PRESSURE 307/7.3 PLACE ISO COND IN STBY FROM RQ (L)
COLD COND W/Rx AT OPER PRESS 307/7.4 PLACE ISO COND IN SERVICE FROM RQ (L)
STBY 309A/7.1 PLACE TBCCW SYS IN SERVICE RQ (L)
RO 14(L) 309A/8.0 PERFORM ALARM RESPONSE 309B/7.1 PLACE TBSCCW SYS IN SERVICE RQ (L)
RO 19(S) 309B/8.0 PERFORM ALARM RESPONSE 309C/7.1 PLACE RBCCW SYS IN SERVICE RQ (L)
RO 20(S) 309C/8.0 PERFORM ALARM RESPONSE RQ (L) 311/7.1 INERT THE CONTAINMENT RQ (L) 311/7.3 VENT THE CONTAINMENT RQ (L)
()311/7.5 MAINTAIN DRYWELL/ TORUS D/P
t TASK #
TASK NAME TYPE STATUS COMMENTS 311/7.6 CONTROL H
& 0 FOLLOWING RQ (L) 2 2
(~')
FOLLOWING LOCA v
311/7.7 VENT CONT >2PSIG IN DRYWELL RQ (L) 311/8.0 PERFORM ALARM RESPONSE RQ (L) 311C/7.1 PLACE DRYWELL COMP SYSTEM RQ (L)
IN OPERATION 314/7.1 PERFORM TURB GEN WARMUP RQ (L) 314/7.2 PERFORM TURB GEN SHUTDOWN RQ (L) 314/7.3 OPERATE THE TURB TURN GEAR RQ (L) 314/7.4 TEST TURB STOP & BYPASS VLVS RQ (L) 314/7.6 OPERATE GEN STATOR COOLING SYS RQ (L) 4 314/7.8 OPERATE STM PRESS REGULATOR RQ (L) 314/7.9 TEST TURB EMERG GOVERNOR RQ (L) 314/8.0 PERFORM ALARM RESPONSE RO 24(S) 315/7.1 PLACE COND SYS IN SERVICE RQ (L)
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315/8.0 PERFORM ALARM RESPONSE RO 20(S) 316/7.1 START REACTOR FEED PUMP RQ (L) 316/7.3 OPERATE FEEDWATER MAN / AUTO RQ (L)
TRANSFER STATION 316/7.5 OPERATE LOW FLOW CONTROLLER RQ (L) 316/7.7 RESET FEEDWATER CONT FOLLOWING RQ (L)
FRV LOCKUP COND 316/8.0 PERFORM ALARM RESPONSE RQ (L) 317/7.1 MN STM SYSTEM STARTUP RQ (L) 317/8.0 PERFORM ALARM RESPONSE RQ (L) 321/8.0 PERFORM ALARM RESPONSE RO 27(S) 322/7.1 PLACE ESW SYS IN STBY RQ (L) 322/7.2 PLACE ESW SYS IN OPERATION RQ (L)
()322/8.0 PERFORM ALARM RESPONSE RO 28(S)
TASK #
TASK NAME TYPE STATUS COMMENTS 323/7.7 PLACE CW PUMPS IN SERVICE RQ (L) 323/7.10 PERFORM HEAT TREATMENT OF RQ ll(S)
CIRC WATER SYSTEM 324A/7.18 DEAERATE MN STM LINES & Rx RQ (L) 324C/7.'l PLACE AUX OFF GAS SYS IN RQ (L)
SERVICE 329/7.1 PLACE SBGT SYS IN STBY RQ (L) 329/7.2 VERIFY INITIATION OF.SBGT SYS RQ (L) 333/7.2 PLACE INST AIR SYS IN SERVICE RQ (L) 333/8.0 PERFORM ALARM RESPONSE RQ (L) 334/7.2 VERIFY AUTO FWCI OPER DURING RQ (L)
LOCA W/ NORMAL POWER AVAILABLE 334/7.3 VERIFY AUTO FWCI OPER DURING RQ (L)
LOCA W/LNP 334/7.4 RESTORE FWCI TO STBY AFTER RQ (L)
AUTO INITIATION 334/8.0 PERFORM ALARM RESPONSE RQ (L)
'335/7.1 PLACE LPCI SYS IN STBY RQ (L) 335/7.2 OPERATE LPCI IN AUTO DURING RQ (L)
LOCA W/ NORMAL PWR AVAILABLE 335/7.4 OPERATE LPCI DURING.LOCA RQ (L)
WITH A LNP 336/7.1 PLACE CORE SPRAY SYS IN STBY RQ (L) 336/7.3 OPERATE CS SYS IN AUTO DURING RQ (L)
LOCA W/ NORMAL PWR AVAILABLE 337/7.1 PLACE AUTO PRESS RELIEF SYS IN RQ (L)
STBY RQ (L) 337/8.0 PERFORM ALARM RESPONSE 338/7.1 ALIGN D/G FOR AUTO OPERATION RQ (L) 338/7.2 PERFORM MAN SART OF D/G RQ (L)
RQ (L) 338/8.0 PERFORM. ALARM RESPONSE 1
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TASK $
TASK NAME TYPE STATUS COMMENTS 339/7.4 OBSERVE INDICATIONS OF GAS RQ (L)
'~N TURB GEN EMERGENCY START L) 339/7.5 PERFORM GTG TESTING RQ (L) 339/7.6 PERFORM NORMAL SHUTDOWN OF GAS TURBINE GEN RQ (L) 339/7.8 PERFORM EMERG SHUTDOWN OF GAS RQ (L)
TURB GEN 339/8.0 PERFORM ALARM RESPONSE RQ (L) 340/7.1 PLACE SHAFT DRIVEN EXCITER RQ (L)
IN SERVICE 340/7.2 SYNC MAIN GEN TO 345KV RQ (L)
W/AMPLIDYNE IN SERVICE 340/7.5 SECURE AMPLIDYNE W/ GEN RO 4(S)
IN SERVICE 340/8.0 PERFORM ALARM RESPONSE RQ (L) 341/7.7 RESET GENERATOR LOCKOUT RQ (L)
RELAYS
()341/8.0 PERFORM ALARM RESPONSE RQ (L) 342/7.1 ENERGIZE 480V BUSES FROM RQ (L)
NORMAL SUPPLIES 343/8.0 PERFORM ALARM RESPONSE RQ (L) 346/7.1 PLACE EXTRACTION STEAM RQ (L)
SYSTEM IN SERVICE 346/7.4 REMOVE EXTRACTION STEAM RQ (L)
FROM HP FW HEATERS 348/8.0 PERFORM ALARM RESPONSE RQ (L) 350/7.4 PURGE THE STACK GAS RQ (L)
MONITORING SYSTEM 350/8.0 PERFORM ALARM RESPONSE RQ (L) 351/7.1 PLACE POST ACCIDENT RQ (L)
SAMPLING SYS IN OPERATION 401A/7.2 OPERATE SRM's DURING Rx RQ (L)
STARTUP 7()
TASK $
TASK NAME TYPE STATUS COMMENTS 401A/7.3 OPERATE SRMS DURING AND RQ (L) g3 AFTER REACTOR STARTUP V
401A/8.0 PERFORM ALARM RESPONSE RQ 1(S) 402A/7.2 OPERATE IRM'S RQ (L) 402A/7.3 OPERATE IRM's DURING AND RQ (L)
AFTER REACTOR STARTUP 402A/8.0 PERFORM ALARM RESPONSE RQ 2(S) 403A/7.3 BYPASS LPRM CARD RQ (L) 403A/8.0 PERFORM ALARM RESPONSE RQ (L) 404A/7.2 OPERATE APRM SYSTEM RQ (L)
DURING STARTUP 404A/8.0 PERFORM ALARM RESPONSE RQ 8(S) 405A/7.1 406A/7.1 PLACE PROCESS RAD MONITOR RQ (L)
SYSTEM IN SERVICE 406A/8.0 PERFORM ALARM RESPONSE RQ (L) 408A/8.0 PERFORM ALARM RESPONSE RQ (L) 409A/8.0 PERFORM ALARM RESPONSE RO 23(S) 410A/7.2 OPERATE THE RBM SYSTEM RQ (L) 410A/7.3 BYPASS RBM CHANNEL RQ (L) 401A/8.0 PERFORM ALARM RESPONSE RO ll(S) 502/1.0 EMERGENCY PLANT S/D RO 7(S) 503A/1.0 LOSS OF 345KV TRANSMISSION RQ 9(S) 503B/1.0 LOSS OF ALL STATION AC RO 24(S) 503C/1.0 LOSS OF OFF-SITE AND ON RQ 11(S)
SITE AC POWER 504/1.0 RECIRC SYSTEM FAILURES RO 6(S) 507/1.0 LOSS OF VACUUM RO 21(S) 508/1.0 FUEL CLAD FAILURE RQ 16(S)
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TASK-#
TASK NAME TYPE STATUS COMMENTS 509/1.0 EXCESSIVE RADIOACTIVITY RO 18(S)
LEVELS g3(
512/1.0 RAPID AND TOTAL LOSS OF RQ 10(S)
OF INSTRUMENT AIR 515A/1s0 HIGH CONDUCTIVITY PRIOR RQ 12(S)
TO CONDENSATE DEMINERALIZERS 516C/1.0 HI ENERGY PIPE RUPTURE RO 5(S)
RO 22(S)
RO 8(S)
RO 17(S) 523/1.0 LOSS OF FW HEATING RQ (L) 569/3.0 OBSERVE OPERATOR RO 12(S)
PRECAUTIONS FOR EOP's 570/3.0 PERFORM OPERATOR ACTIONS RO 12(S)
FOR RPV LEVEL CONTROL 571/3.0 PERFORM OPERATOR ACTIONS RO 30(S)
FOR RPV PRESSURE CONTROL 572/3.0 PERFORM OPERATOR ACTIONS RO 23(S)
FOR Rx POWER CONTROL 573/3.0 PERFORM OPERATOR ACTIONS FOR R0 12(S)
RPV SPRAY COOLING 574/3.0 PERFORM OPERATOR ACTIONS FOR RQ 13(S)
RPV STEAM COOLING 575/3.0 PERFORM OPERATOR ACTIONS FOR RO 30(S)
RPV LEVEL /Rx POWER CONTROL 576/3.0 PERFORM OPERATOR ACTIONS FOR RQ 12(S)
RPV LEVEL RESTORATION 577/3.0 PERFORM OPERATOR ACTIONS FOR R0 30(S)
EMERGENCY RPV DEPRESSURIZATION 578/3.0 PERFORM OPERATOR ACTIONS FOR RO 29(S)
RPV FLOODING 579/3.0 PERFORM OPERATOR ACTIONS FOR R0 30(S)
ALTERNATE S/D COOLING 580/3.0 PERFORM OPERATOR ACTIONS FOR RQ 29(S)
CONTAINMENT CONTROL O
TASK #
TASK NAME TYPE STATUS COMMENTS 611.1/7.0 PERFORM A MSIV CLOSURE RO 30(S)
FUNCTIONAL TEST' 4
611.1/8.0 RESTORE FROM MSIV RQ 30(S)
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