ML20071Q940

From kanterella
Jump to navigation Jump to search
Rev 1 to Training Manual Procedure TRA-204, Licensed Operator Requalification Training Program
ML20071Q940
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 05/13/1983
From: Rosalyn Jones
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20071Q933 List:
References
TRA-204, NUDOCS 8306090315
Download: ML20071Q940 (27)
v • d • e


Text

-- . . -

COMANCHE PEAK STEAM ELECTRIC STATION TRAINING MANUAL b

V N{t V M LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM

! PROCEDURE NO. TRA-204 REVISION NO. 1 SAFETY-RELATED SUEMITTED BY: s C  ! DATE: 3 3 ADMINISTRATIVE SUPERINTENDENT l APPROVED BY: /  % A /d W DATE: [ 69 l MANAGER, PLANT'GPERATIONS

!$0'000$d'o!SooSIs V PDR

CPSES ISSUE DATE PROCEDURE NO.

-n i vuruc viuniv , ~72 :nq LICENSED OPERATOR REQUALIFICATION tunturve concosu ernvernu un , nicy o ny 7, 1.0 Purpose The purpose of the licensed operator requalification program is to ensure a proficient operating staff. This program is established to comply with the requirements of 10 CFR 55. Appendix A, while providing as indfvidualized a retraining program as possible.

2.0 Applicability This procedure applies to all USNRC licensed personnel. This procedure becomes effective upon issuance of USNRC Licenses to station operating personnel.

3.0 Definitions 3.1 Reactor Operator (RO) - any individual who possesses an operator's license pursuant to Title 10, Code of Federal Regulations, Part 55, " Operator's Licenses".

3.2 Senior Reactor Operator (SRO) - any individual who possesses a senior operator's license pursuant to Title 10 Code of Federal Regulations, Part 55, " Operator's License".

4.0 Instructions 4.1 Responsibilities i

4.1.1 The Manager, Plant Operations has the overall responsibility for ensuring that the CPSES staff is l adequately trained and fully qualified to operate equipment / systems at CPSES in accordance with regulatory and station guidelines.

4.1.2 The Director, Nuclear Training provides any requested training services to the Operations Department, and is responsible for documenting all training administered to that group.

4.1.3 The operations Superintendent is responsible to the Manager, Plant Operations for identifying training needs, and developing and implementing a training program for the Operations Department.

t 4.1.4 The Operations Supervisor is responsible to the Operations Superintendent for the following training functions:

j 4.1.4.1 Recommending and supervising the development of course curricula.

i l

? , . _ _ --,. - . - - - - - - -- - - . - -

i CPSES ISSUE DATE PROCEDURE NO.

TRATNTMC MAMTTAT TD* ?OA LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PACF 3 OF 27 4.1.4.2 Reviewing training records, lesson material, and qualifications.

4.1.4.3 Evaluating the Requalification Program effectiveness, and recommending changes as necessary.

4.1.4.4 Scheduling requalification training.

4.1.5 The Shift Supervisor (s) are responsible to the Operations Supervisor for the following:

4.1.5.1 Identifying the training needs of the Reactor Operators.

4.1.5.2 Identifying and recommending any specialty training needed by the Reactor Operators to adequately operate equipment / systems at CPSES.

4.1.5.3 Observing Reactor Operator performance of assigned tasks and determining if specific skills have been obtained and are being maintained.

4.1.5.4 Notifying the Operations Supervisor of inability to complete requalification program activities as scheduled.

4.2 Lectures The Licensed Operator Requalification Program shall include pre-planned training sessions conducted on a regular and continuing basis. The training sessions will include two types l of lecture series as follows:

l 4.2.1 Fundamental Review Lecture Series l The Fundamental Review training sessions cover areas in f which the knowledge required of a licensed individual is relatively constant.

4.2.1.1 Lecra-; Series Topics The Fundamental Review lecture topics are -

selected on an as-needed basis and include the following:

1. Principles and Theory of Nuclear Power Plant operation.

t j ..

CPSES ISSUE DATE PROCEDURE NO.

TRATMTMc MAMTTAT. TDA ?nA

. LICENSED OPERATOR REQUALIFICATION TRATNING PROCRAM REVISION LO. 1 PACF 4 OF 77

2. Fundamentals and Theory of Fluid Flow, Heat Transfer, and Thermodyna._ics.
3. Plant Systems Design. Control and Instrumentation.

t

4. Plant Protection Systems.
5. Engineered Safeguards Systems. ,
6. Fuel Handling and Core Parameters.
7. Mitigating Core Damage.
8. Radiation Protection and Control.
9. General and Specific Plant Cperating Characteristics.

Technical Specifications and Title 10. Code of Federal Regulations shall be included in lectures as applicable.

4.2.1.2 Lecture Series Topic Selection The topics presented in the Fundamental Review i

Jeries should reflect the general results of the annual examinations and performance of the licensed personnel as evaluated by their supervisors.

The scope of the lecture series should be

. , determined by the Director, Nuclear Training.

The depth of coverage in each topic should reflect typical deficiencies identified by the

, annual examinations.

4.2.2 ' Operational Proficiency Lecture Series The Operational Proficiency training sessions cover areas which involve essential plant operational guidelines.

4.2.2.1 Lecture Series Topics The Operational Proficiency lecture topics are selected to ensure coverage of essential plant

operational guidelines and to ensure operational changes and experiences are integrated into licensed individual's training. The lecture topics include the following

CPSES ISSUE DATE PROCEDURE NO.

TR ATMTMC MAMTTAT. TDA ?nA LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PACF 5 OF 97

1. Administrative Procedures, Conditions ar,d Limitations
2. Major Operational Evolutions
3. Facility Design and License Changes
4. Procedures - Normal, Abnormal. Emergency Operating, and Radiological Control
5. Operating History and Problems
6. Related Nuclear Industry Operating Experience
7. Procedure Changes
8. Reportable Occurrences 4.2.2.2 Lecture Series Topic Selection The topics presented in the Operational Proficiency series will include all the topics listed in Section 4.2.2.1, unless the applicable i information is covered in another appropriate manner, such as on-shift discussion sessions, staff meetings, or written communications to each licensed individual, and documented in accordance with procedures NOT-104, " Training Records" or ODA-106, " Review of Documents".

The scope of the lecture series should be determined by the Director, Nuclear Training taking into account the licensed individual's Supervisor's input, the general results of the annual examinations, and the available operational experience inputs.

4.2.3 Pre-Planned Lecture Series Schedule The requalification training program will be conducted on a two year cycle.

Lectures r.hould be evenly spaced throughout the year except during heavy vacation and refueling periods.

Lectures may be deferred due to unanticipated events, but should be conducted as soon as practicable thereafter and within the two-year cycle, l

l

e CPSES ISSUE DATE PROCEDURE NO.

TRAINING MANTTAT. TMA-704 LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PAGE 6 0F 27 4.2.4 Pre-Planned Lecture Series Attendance Licensed individuals shall attend:

1. All pre-planned lectures relating to any annual examination subject in which they received a grade of 80% or less on the previous examination.

Note: Attendance for all cold licensed personnel shall be based upon their scores on the USNRC exam.

2. All Operational Proficiency Lectures regardless of their scores on the previous annual examination or USNRC en mination.
3. Any Fundamental Review Lecture if so directed by their supervisor.

4.2.5 Training Aids Training aids such as films, video tapes, and slides may be used and some self-study may be required in conjunction with the lectures. An instructor will participate in a least fifty percent of the lecture series.

4.a On-The-Job Training 4.3.1 Control Manipulations Reactor operators shall manipulate and senior reactor operators shall manipulate or direct the activities of those manipulating the station controls during the term of their licenses for the following activities. Items 1 thru 5 shall be performed annually, all other items shall be performed on a two-year basis. The control manipulations

- which are not performed at the plant shall be performed on a suitable simulator.

1. Manual control of steam generators and/or feedwater during startup and shutdown.
2. Any significant power changes in manual rod control

(>10%).

3. Loss of coolant including:
a. Significant steam generator leaks,
b. Inside and outside primary containment.

CPSES ISSUE DATE PROCEDURE NO.

TRAINING MANUAL TRA-704 LICENSED OPERATOR REQUALIFICATICN TRAINING PROGRAM REVISION NO. 1 PAGE 7 OF 27

c. Large and small, including leak-rate determination.
d. Saturated reactor coolant response.
4. Loss of core coolant flow / natural circulation.
5. Loss of all feedwater (normal and emergency).
6. Startup to the point of adding heat and heatup rate established.
7. Plant shutdown.
8. Boration and/or dilution during power operation.
9. Loss of electrical power (and/or degraded power sources).
10. Loss of condenser vacuum.
11. Loss of station service water.
12. Loss of component cooling water system or cooling to an individual component.
13. Loss of normal feedwater or normal feedwater system failure.

14 Loss of protective system channel (inverter).

15. Mispositioned control rod (s) (or rod drops).
16. Inability to drive control rods.

l 17. Conditions requiring use of emergency boration.

i

18. Fuel cladding failure or high activity in reactor coolant or offgas.
19. Turbine or generator trip.
20. Malfunction of automatic control system (s) which affect reactivity.
21. Malfunction of reactor coolant pressure / volume control system.
22. Reactor trip.
23. Main steam line break (inside or outside containment).

CPSES ISSUE DATE PROCEDURE NO.

PDATMTMc MAMffAT TDA_9AA LICENSED OPERATOR REQUALIFICATION TRATMTNO PROCRAM RFVTATOM MO- 1 UAcF R nr 97

24. Nuclear instrumentation failure (s).

l 25. Loss of instrument air (when simulated on a plant specific simulator).

In the event that an actual abnormal / emergency condition occurs at the plant and performance of the licensed personnel controlling the condition is satisfactory (as evaluated by their Supervisor), credit for completion of a training exercise may be taken.

A record of control manipulations shall be maintained on Form TRA-204-1, "Requalification Control Manipulations" (Attachment 1). A notebook in the Shift Supervisor's office shall be used to contain all forms in use for the current requalification period (as defined by the Operations Supervisor). All forms shall be reviewed by the Operations Supervisor and then transmitted to the Director, Nuclear Training upon expiration of the scheduled completion date.

If personnel do not complete the required control manipulations within 3 months prior to the scheduled completion date, they may be scheduled at a simulator to obtain the required control manipulations. Observation and evaluation of performance during simulated abnormal and emergency conditions will be conducted by simulator training personnel.

4.3.2 Knowledge of Plant Systems Reactor operators and senior reactor operators shall have an understanding of the operation of controls and equipment and shall be familiar with the operating procedures in each area for which they are licensed.

Frequent manipulation of the controls and use of plant operating procedures is expected to maintain the operator proficient during the normal conduct of his duties.

l 4.3.3 Review of Abnormal and Emergency Procedures Reactor operators and senior reactor operators shall review the contents of Abnormal Conditions Procedures and Emergency Response Guidelines annually, plus or minus three months. Verification of review will be provided by sign-off sheets. (Attachment 2). All completed forms shall be reviewed by the Operations Supervisor and then transmitted to the Director, Nuclear Training upon expiration of the scheduled completion date. A review of l Abnormal Conditions Procedures and Emergency Response

CPSES ISSUE DATE PROCEDURE NO.

TV A TVTVc VA b7?t AT P7A_"AA l

LICENSED OPERATOR REQUALIFICATION  !

TRATNTNC PROCRAM RFVTATOM Mn. 1 Dac7 Q nr 97 i

Guidelines shall also be conducted as part of the regular l scheduled lecture series (Section 4.2.2.1) and the annual  !

examination (Section 4.4.1). ,

l In addition, a review of the Abnormal Conditions j Procedures and Emergency Response Guidelines shall be j performed by performance evaluations (Section 4.4.3), ,

on-shift walkthroughs of the procedures conducted by the l l Shift Supervisor or Assistant Shift Supervisor (and documented per NOT-104, " Training Records"), and actual i r use on a simulator (Section 4.3.1) conducted by training i

! personnel.

4.4 Evaluation i 4.4.1 Annual Examination j In order to determine each licensed individual's knowledge of topics covered in the requalification program and provide a basis for determining areas in which retraining is needed, an annual written requalification examination shall be administered to each licensed rcactor operator ,

and senior reactor operator during each calendar year. I Separate reactor operator and senior reactor operator examinations shall be administered. This annual examination shall cover the following subjects with depth appropriate to the license:

1. Principles and Theory of Nuclear Power Plant Operation.
2. Fundamentals and Theory of Fluid Flow, Heat Transfer, and Thermodynamics.

l 3. Plant Systems Design, Control and Instrumentation. 1

4. Engineered Safeguards Systems.
5. Procedures - Normal, Abnormal. Emergency Operating, and Radiological Control.
6. Radiation Protection and Control.
7. Tech. Specs and Applicable 10CFR Sections.
8. Mitigating Core Damage
9. Administrative Procedures, Conditions, and Limitations.
10. Fuel Handling and Core Parameters.

.--.-y

, . , . - - - me,-

CPSES ISSUE DATE PROCEDURE NO.

TR ATMTMC VAmfAf TDA_9AA LICENSED OPERATOR REQUALIFICATION TRATNING PROCRAM REVT9 TON MO. 1 UAcF 10 OF 77

11. Plant Protection Systens.
12. General and Specific Plant Operating Characteristics.

Licensed personnel scoring less than 80% on any category of the most recent writtan examination will be required to attend the pre-planned lectures applicable to that section. Licensed personnel scoring less than 70% in any category or less than 80% overall on the most recent written examination will be placed in an accelerated requalification training program (Section 4.5.1).

A maximum of three individuals responsible for preparing and administering the examination will be credited with successfully completing the examination.

4.4.2 Periodic Examination After each lecture or group of lectures, trainees may take a written quiz covering the lecture topic (s). These tests are to evaluate training effectiveness, i

A performance standard of 80% will be established for a written quiz. Individuals who receive a grade of less than 80% in a subject may be assigned additional retraining in that subject. The extent of this retraining shall be determined by the Director, Nuclear Training.

4.4.3 Performance Evaluations Annual performance evaluations of reactor operators and senior reactor operators shall be conducted by the immediate supervisors. These evaluations should include the following areas:

(a) Shift Relief.

(b) Log and Record Keeping.

(c) Plant Awareness and Control.

(d) Administrative Procedures.

(e) Technical Specifications.

(f) Normal Procedures.

(g) Emergency Procedures.

(h) Attitude

CPSES ISSUE DATE PROCEDURE NO.

TW ATNTMd MANT? AT PM _9 A A LICENSED OPERATOR REQUALIFICATION TRATMTMC PROCRAM QFUTCTON Mn 1 pace 11 nr 97 Unsatisfactory performance evaluations may result in the licensed individual being placed in the accelerated requalification program (Section 4.5.1).

The Operations Supervisor is responsible for conducting the evaluations of the Shift Supervisors. The Shift Supervisors are responsible for evaluating their subordinate personnel. The appropriate Supervisor shall complete the "Watchstanding Evaluation" form (Attachment

3) and then route it to the Operations Supervisor. The Operations Supervisor and the Operations Superintendent shall then review and sign the form and submit it to the Director. Nuclear Training in accordance with Section 4.7.

Non-shift personnel shall be evaluated during simulator retraining. Documentation shall be obtained that includes evaluated areas described in this section and shall be reviewed by the Operations Superintendent and Director.

Nuclear Training as a minimum.

4.5 Special Retraining Programs 4.5.1 Accelerated Requalification Program The accelerated requalification program is for licensed individuals having identified deficiencies requiring assignment to a special retraining effort. Accelerated Requalification Programs shall be assigned based on:

(a) Unsatisfactory performance ((80% overall) on the annual examination.

(b) Unsatisfactory performance (<70% on any category) on the annual examination.

(c) Review of on-the-job proficiency and performance.

(d) Review of needs for inactive status retraining described in Section 4.5.2.

If an individual is enrolled in the accelerated requalification training program, he shall not perform licensed duties involving the area in which he is i deficient until he has successfully completed the accelerated program.

These programs should be tailored to the needs of the individual. The Director, Nuclear Training will tailor

the scope and duration of the accelerated program to the

! individual's demonstrated deficiencies. The individual's I supervisor should provide any appropriate recommendations l

CPSES ISSUE DATE PROCEDURE NO.

TRATNTMC VAMf7At TWA_?na LICENSED OPERATOR REQUALIFICATION TRAIhING PROGRAM REVISION NO. 1 PAGE 12 OF 77 to the Director, Nuclear Training regarding program content.

The program content should be specifically structured to upgrade knowledge and skills identified as deficient.

Examination categories and areas in which performance standards were not met shall be covered in the program.

Successful completion of the accelerated requalification program shall be determined by administering an examination. The examination shall cover all categories of the requalification written examination in which the individual was originally deficient. Performance standards for the accelerated requalification program shall be: a score of at least 80% ou each written examination category or satisfactory completion of an oral examination.

In the event that these standards are not met, the individual's suitability for resuming licensed duties will be reviewed by the Director, Nuclear Training. The Director, Nuclear Training shall provide a recommendation to the Operations Superintendent regarding the individual's status in relation to licensed duties or additional upgrading efforts to be considered. If appropriate, another accelerated requalification program shall be structured to correct deficiencies.

4.5.2 Inactive Status Retraining If a licensed individual has not actively carried out licensed duties for a period in excess of four months, a special retraining program or evaluation is required prior to resuming licensed duties.

Active status can be maintained by performance of licensed duties and participation in this Licensed Operator Requalification Training Program.

'In the event that a licensed individual does not maintain an active status, he may be required to attend specific pre-planned lecture series or to take a written examination similar in scope and format to the annual written examination (Section 4.4.1) prior to resuming licensed duties. Consideration may be given to assigning the licensed individual to a training status on an operating shift prior to resuming licensed duties.

The performance standards applied to the annual requalification examination shall be used in evaluating

CPSES ISSUE DATE PROCEDURE NO.

TR ATMTMC MAMTTAT. PDA ?nA LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PACF 13 0F 27 the results of this written examination. If the performance standards are not met, the licensed individual shall complete an accelerated requalification program prior to resuming licensed duties.

4.5.3 Newly Licensed Individuals Newly licensed individuals shall enter the requalification program and participate in the annual program cycle upon receipt of their license. Newly licensed individuals successfully completing their NRC licensing examination less than six (6) months prior to an annual requalification examination may be excused from taking the current annual written examination.

4.6 Staff Members Individuals who maintain reactor operator or senior reactor operator licenses for the purpose of providing backup capability

to the operating staff shall participate in the requalification program except to the extent that their normal duties preclude the need for specific retraining in particular areas.

As a minimum these individuals shall:

! (a) Take the annual written examination and participate in the lecture series based on the results thereof. (Sections

( 4.2.1 and 4.4.1)

(b) Manipulate the controls or supervise the manipulation of the controls as specified in Section 4.3.1.

(c) Systematically review design changes, procedure changes and facility license changes. (Section 4.2.2)

(d) Systematically review the content of Abnormal Conditions i Procedures and Emergency Response Guidelines on a regularly scheduled basis. (Section 4.3.3)

I (e) Receive performance evaluations described in Section 4.4.3.

4.7 Records Records of the Licensed Operator Requalification Training Program shall be maintained in an auditable manner. The Director, Nuclear Training is responsible for maintaining the following records:

(c) Copies of the written examinations administered, and the answers given, results of evaluations, and documentation

CPSES ISSUE DATE PROCEDURE NO.

TR ATNTMC MANUAT. TWA 70A LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PACE 14 OF 27 of any training administered pursuant to Section 4.5.1 and 4.4.2.

(b) Annual performance evaluations (c) Additional training administered in areas in which an operator or senior operator has exhibited deficiencies.

l (d) Annual review of abnormal and emergency procedures.

(e) Control manipulation and plant evolution participation records.

l l All training records specified by this procedure shall be j maintained in accordance with procedure NOT-104, " Training l Records".

4.8 References l

l 4.8.1 FSAR, Section 13.2.2.1

! 4.8.2 INPO Guideline GPG 02-40, " Nuclear Power Plant Requalification Program For Licensed Personnel".

4.8.3 10 CFR Part 55, Appendix A - Requalification Programs for Licensed Operators of Production and Utilization Facilities.

4.8.4 ANSI 18.1 - 1971, " Selection and Training of Nuclear Power Plant Personnel".

4.8.5 ANS 3.1 - 1980, " Standard for Selection, Qualification, and Training of Personnel for Nuclear Power Plants".

4.8.6 CPSES Procedure NOT-104, " Training Records".

4.8.7 USNRC Letter Dated March 28, 1980, " Qualifications of l Reactor Operators" (Harold Denton letter).

4.8.8 USNRC Letter dated December 16, 1981, " Qualification of Reactor Operators - License Examinations" (Darrell G.

Eisenhut letter).

5.0 Attachments 5.1 Requalification Control Manipulation, Attachment 1 5.2 Requalification Program Emergency / Abnormal Procedures Checklist, Attachment 2 5.3 Watchstanding Evaluation, Attachment 3

CPSES ISSUE DATE PROCEDURE NO.

TWATMTMC M AMYT A T Tea _9nA LICENSED OPERATOR REQUALIFICATION TRATMTMC PROCRAM RFVTATOM NO. 1 PACF 19*n? 77 ATTACHMENT 1 PAGE 1 0F 3 REQUALIFICATION CONTROL MANI?ULATIONS NAME: LICENSE: RO SRO (Please Print) (Circle One)

SCHEDULED COMPLETION DATE:

Type of Shift: Unit: S.S.

Control Manipulation Night / Day / Evening 1/2 Date Initial A. Manual control of steam generators and/or feed-water during startup and shutdown r

l B. Any significaut power changes in manual rod control () 10%)

C. Loss of coolant:

1. Significant steam generator leak
2. Inside/outside primary containment .
3. Large and small, in-cluding lent-rate determination l

4.

Saturated reactor coolant response D. Loss of core coolant flow / natural circulation

! E. Loss of all feedwater (normal- and emergency)

~

F. Startup to the point of adding heat l G. Plant shutdown TRA-204-1

_ --. __. _A__: 4 2 CPSES ISSUE DATE PROCEDURE NO.

TR ATMTNC MANTf AT. TDA 90A LICENSED OPERATOR REQUALIFICATION TRATNINC PROGRAM REVTRTON NO. 1 PACF 16 OF 77 ATTACHMENT 1 PAGE 2 0F 3 ,

REQUALIFICATION CONTROL MANIPULATIONS NAME: LICENSE: RO SRO (Please Print) (Circle One)

SCHEDULED COMPLETION DATE:

Type of Shift: Unit: S.S.

Control Manipulation Night /Dav/ Evening 1/2 Date Initial H. Boration and/or dilution during power operation I. Loss of electrical power (and/or degraded power sources) __

/

J. Loss of condenser vacuum K. Loss of station service water L. Loss of component cool-ing water system or cool-ing to an individual component M. Loss of normal feedwater l or normal feedwater sys-ten failure N. Loss of protective system channel (inverter)

O. Mispositioned control l

rod (s) (or rod drops) l P. Inability to drive l control rods Q. Conditions requiring use of emergency boration TRA-204-la l

l i

\__.--- , . . - - -. _ _ , ,

l l

CPSES ISSUE DATE PROCEDURE NO.

vn i rutur vimu r en i oni.

  • l LICENSED OPERATOR REQUALIFICATION TRATNTMC DDOCDAM DFVTCTOM Mo 1 DAcF 17 nF 77 ATTACHMENT 1 PAGE 3 0F 3 REQUALIFICATION CONTROL MANIPULATIONS NAME: LICENSE: RO SRO (Please Print) (Circle One)

SCHEDULED COMPLETION DATE:

i Type of Shift: Unit: S.S.

Control Manipulation Night / Day / Evening 1/2 Date Initial R. Fuel cladding failure or high activity in reactor coolant or offgas S. Turbine or generator trip T. Malfunction of automatic control system (s) which affect reactivity U. Malfunction of reactor coolant pressure / volume control system V. Reactor trip W. Main steam line break (inside or outside containment)

X. Nuclear instrumentation failure (s)

Y. Loss of instrument air Operations Supervisor Review: /s/ Date:

TRA-204-lb

CPSES ISSUE DATE PROCEDURE NO.

TRATMTMC MAMTMT. TDA.?O&

LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PAGE 18 0F 27 ATTACHMENT 2 PAGE 1 0F 7 ,

REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST NAME: SCHEDULED COMPLETION DATE:

(Please Print)

Procedure No. Title Signature /Date E0P-0.0 Reactor Trip or Safety Injection EOS-0.0 Reactor Trip Recovery EOS-0.2 Natural Circulation Cooldown EOS-0.3 SI Termination Following Spurious SI l EOS-0.4 Natural Circulation Cooldown with l Steam Void in Vessel Upper Head E0P-1.0 Loss of Reactor Coolant (LOCA)

EOS-1.1 SI Termination Following LOCA EOS-1.2 Post-LOCA Cooldown and Depressurization i

EOS-1.3 Transfer to Cold Leg Recirculation l Following LOCA EOS-1.4 Transfer to Hot Leg Recirculation E0P-2.0 Loss of Secondary Coolant (LOSC)

EOS-2.1 SI Termination Following LOSC EOS-2,2 Transfer to Cold Leg Recirculation Following LOSC E0P-3.0 Steam Generator Tube Rupture (SGTR)

EOS-3.1 SI Termination Following SGTR TRA-204-2

CPSES ISSUE DATE PROCEDURE NO.

TRATNTNC MANTTAT. TRA ?na LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PAGE 19 OF 27 ATTACHMENT 2 PAGE 2 0F 7 REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST NAME:

(Please Print)

Procedure No. Title Signature /Date EOS-3.2 SGTR Altarnat..- Cooldown By Back-filling RCS EOS-3.3 SGTR with Secondary Depressurization

! ECA-1.0 Anticipated Transient Without TRIP (ATWT)

ECA-2.0 Loss of All AC Power l ECA-2.1 Loss of All AC Power Recovery Without l SI Required l

l ECA-2.2 Loss of All AC Power Recovery With SI Required ECA-3.0 SGTR Contingencies .

I ECA-4.0 Response To Multiple Steam Generator Depressurization ECA-5.0 Loss of Emergency Coolant Recirculation l

l ECA-6.0 Secondary High Energy Line Rupture with l Loss of SI Function 1

ECA-7.0 Combined SGTR and LOCA ECA-8.0 Unisolable SGTR l

l TRA-204-2a

.m . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

~ -

.' l CPSES ISSUE DATE PROCEDURE NO.

TRATNTMC MANTTAT- TDA_?oA LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PACE 20 0F 27 ATTACHMENT 2 PAGE 3 0F 7 REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST NAME:

(Please Print)

Procedure No. Title Signature /Date ECA-9.0 SGTR Without Pressurizer Pressure Control FRS-0.1 Response to Nuclear Power Generation FRS-0.2 Response to Loss of Core Shutdown FRC-0.1 Response to Inadequate Core Cooling FRC-0.2 Response to Degraded Core Cooling FRC-0.3 Response to Potential Loss of Core Cooling FRC-0.4 Response to Saturated Core Cooling Conditions FRP-0.1 Response to Imminent Pressurized Thermal Shock Conditions FRP-0.2 Response to Anticipated Pressurized Thermal Shock Conditions FRH-0.1 Response to Loss of Secondary Heat Sink FRH-0.2 Response to Steam Generator Overpressure FRH-0.3 Response to Steam Generator High Level FRH-0.4 Response to Steam Generator Low Level TRA-204-2b

. _= ,- _ , . - - - - - -

l-CPSES ISSUE DATE PROCEDURE NO.

TR ATMTMC MANTTAT TWA ?Oli LICENSED OPERATOR REQUALIFICATION TRATMINC PROCRAM REVISION NO. 1 PACE 21 OF 27 ATTACHMENT 2 PAGE 4 0F 7 REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST NAME:

(Please Print)

Procedure No. Title Signature /Date FRH-0.5 Response to Loss of Steam Generator PORVs and Condenser Dump Valves FRZ-0.1 Response to Containment High Pressure FRZ-0.2 Response to High Containment Sump Level ,

FRZ-0.3 Response to High Containment Radiation Level FRI-0.1 Response to Pressurizer Flooding FRI-0.2 Response to Low System Inventory FRI-0.3 Response to Voids in Reactor Vessel ,

ABN-101 Reactor Coolaat Pump Malfunctions ABN-102 Excessive Reactor Coolant Leakage i

ABN-103 High Reactor Coolant Leakage l ABN-104 Residual Heat Removal System Malfunction l

l ABN-105 Chemical and Volume control System Malfunction ABN-106 Abnormal Containment Conditions ABN-108 Steam Generator Tube Leakage TRA-204-2c

/

4 CPSES ISSUE DATE PROCEDURE NO.

TDATMTMI' MAMffAT TDA_9AA LICENSED OPERATOR REQUALIFICATION TRATNTMC PROCRAM REVT9 TON MO. 1 PACF 79 OF 77 ATTACHMENT 2 PAGE 5 0F 7 REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST NAME:

(Please Print)

Procedure No. Title Signature /Date I ABN-109 Pressurizer Pressure / Level Control Malfunction ABN-201 Recovery From a Spurious Phase B Actuation ABN-202 Recovery From a Spurious Main Steam Isolation i

ABN-301 Steam Dump System Malfunction ABN-302 Feedwater/ Condensate System Malfunction ABN-303 Auxiliary Feedwater System Malfunction ABN-304 Condenser Tube Leakage ABN-305 Circulating Water System Malfunction l ABN-401 Turbine Malfunction ABN-402 Main Generator Malfunction i

1 l ABN-501 Station Service Water System Malfunction ABN-502 Component Cooling Water System Malfunction ABN-503 Spent Fuel Pool Cooling and Cleaning l

System Malfunction l

TRA-204-2d

CPSES ISSUE DATE PROCEDURE NO.

TWATMTMC MANTTAT. TR A 2Ola LICENSED OPERATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PAGE 23 0F 27 ATTACHMENT 2 PAGE 6 0F 7 REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST 4

NAME:

(Please Print)

Procedure No. Title Signature /Date ABN-601 Operations During Abnormal System Transmission Conditions ABN-701A Source Range Instrumentation Malfunction ABN-702A Intermediate Range Instrumentation Malfunction ABN-703 Power Range Instrumentation Malfunction ABN-70 Tc/N-16 Instrumentation Malfunction ABN-705 Pressurizer Pressure Instrumentation Malfunction ABN-706 Pressurizer Level Instrumentation -

Malfunction ABN-707 Steam Flow Instrumentation Malfunction ABN-708 Feedwater Flow Instrumentation Malfunction ABN-709 S/G Pressure, Steam Line Pressure, P imp Instrumentation Malfunction ABN-710 Steam Generator Level Instrumentation Malfunction ABN-711 Inverter Malfunction ABN-901 Fire Protection System Malfunctions ABN-902 Accidental Release of Radioactive Gas TRA-204-2e

CPSES ISSUE DATE PROCEDURE NO.

TDATMTMt* MAMTT A T T13 A _ t ri /.

LICENSED OPERATOR REQUALIFICATION TRATNTMC PROOAM DFVTCTnM MA 1 D / ,gP ?A nr ?'

ATTACHMENT 2 PAGE 7 0F 7 REQUALIFICATION PROGRAM EMERGENCY / ABNORMAL PROCEDURES CHECKLIST NAME:

(Please Print)

Procedure No. Title Signature /Date ABN-903 Accidental Release of Radioactive Liquid ABN-904 Accidental Release of Chlorine Gas ABN-905 Loss of Control Room Habitability ABN-906 Loss of P2500 Computer-ABN-907 Acts of Nature

~

ABN-908 Fuel Handling Accident Operations Supervisor Review: /s/ Date:

TRA-204-2f

(

.-- - , ,, , . - - - - . -y . . . , _ . . . - - - . - - . , . _ _ . . - - . . - - - . - - . ... .-.--..-_ - -

CPSES ISSUE DATE PROCEDURE NO.

TWATNTNC MANITAl' TDA 70A LICENSED OPEFATOR REQUALIFICATION TRAINING PROGRAM REVISION NO. 1 PACE 25 OF 27 ATTACHMENT 3 PAGE 1 0F 3 WATCHSTANDING EVALUATION s

NAME: DATE: ~~

(Please Print)

LICENSE: R0 SRO I

A. SHI'T e RELIEF S M U

1. Makes a good tour of the centrol board before taking the shift.
2. Obtains a good turnover so that he is fully cognizant of plant status and plans for the shift.
3. Conducts a review of the logs either before or after taking the shift.
4. Gives a good turnover on being relieved.
5. Follows procedures for turnover per ODA-302.

B. LOG AND RECORD KEEPING l

1. Maintains an accurate chronological record of shift events including abnormalities and significant events.
2. Follows CPSES practices for log and record keeping per ODA-301 and ODA-104.

C. FLANT AWARENESS AND CONTROL _

1. Is aware of maintenance, operations,

, and surveillance testing being conducted on shift.

2. Is aware of equipment deficiencies (e.g. equipment out of service).
3. Is aware of consequences of equipment deficiencies.
4. Has good knowledge of plant systems.
  • S-SAT
  • M-MARGINAL
  • U-UNSAT TRA-204-3 esy 7.-- - . -

---.-,.--g ,,y,, - - - - . -

CPSES ISSUE DATE PROCEDURE NO.

TDATMTMt' V AMTT A T TO A _ M A LICENSED OPERATOR REQUALIFICATION TWATNTWt: Prot' DAM DFUTSTnM Mn 1 D a t'T 76'nr 97 AITACHMENT 3 PAGE 2 0F 3 WATCHSTANDING EVALUATION D. ADMINISTRATIVE PROCEDURES' S M U 4

1. Is knowledgeable of
a. Applicable Station Administrative Procedures
b. Applicable Operations Department i Administrative Procedures E. TECHNICAL SPECIFICATIONS t
1. Is knowledgeable of' Technical

' Specifications.

2. Is knowledgeable of revisions to

! Technical Specificaticus.

- F. NORMAL PROCEDURES

1. Utilizes normal procedures.
2. Knows and can follow normal procedures.
3. Is knowledgeable of revisions to normal procedures. _

G. EMERGENCY PROCEDURES l

1. Utilizes emergency proceduras when applicable.
2. Knows the symptoms and immediate actions associated with the emergency .

procedures. '

3. Is knowledgeable of revisions to emergency procedures. _ _
4. Can adepely handle himself in ql/

emergency situations.

H. ATTITUDE

1. Has vigilant attitude, keeping aware of plant conditions at all times.

TRA-204-3a m

. ,- -< 'w, v - ' - ' - - - - - ' '

.o C?SES ISSUE DATE PROCEDURE NO.

,.n i vuvur. unmu p _

,nr LICENSED OPERATOR REQUALIFICAIION muiturun nuncniv nevrevnu un 3 nice on ne on ATTACHMENT 3 PAGE 3 0F 3 WATCHSTANDING EVALUATION I. SUPERVISOR REVIEW YES NO r

1. Has this individual caused or been ,.

responsible for a significant operating event or reportable occurrence?

2. Has this individual compromised the safety of the plant or the public during this review period?

If answer to 1 or 2 is yes, explain.(attach addition sheets if necessary) <

3. Is this individual a safe operator?

J. ADDITIONAL COMMENTS Provide additional information for area above indicated as unsat.

I i

l i Supervisor (s) Date Operations Supervisor Review Operations Superintendent Review TRA-204-3b

, . _ _ . . _ - - _ _ _ _ . - - . _ _ _ _ ~ _ . - _ _ _ _ _ . . . _ _ _ . _ . _ - -

Retrieved from "https://kanterella.com/w/index.php?title=ML20071Q940&oldid=2821043"