ML20099M101

Rev 1 to Requalification Program for NRC Licensed Personnel

ML20099M101
Person / Time
Site:	Catawba
Issue date:	11/27/1984
From:	DUKE POWER CO.
To:
Shared Package
ML20099M086	List: ML20099M082 ML20099M101
References
NUDOCS 8412030232
Download: ML20099M101 (15)

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DUKE P N ER COMPANY CATAWBA NJCLEAR STATION

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RQUALIFICATION PROGRAM FOR

. NBC LICENSED PERSONNEL August 21, 1984 -

REVISION 1 NOVEMBER 27, 1934 hog 2SDO$ 0 j V

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4 CMM1R NUCLEAR STATION REQUALIFICATION PROGRAM EVR NIC LICENSED PERSOiNEL TABLE & CONTENTS SECTIm Egig 1.0 Introduction 3 2.0 Pre-Planned IAK:ture Series 3 3.0 Skills Training and Evaluation 5 .

4.0 Requalification Schedule 9 Operational Review Program.

.5. 0 - -

10 6.0 Annual Requalification Examination 11 i

7.0 Administration of Requalification 13 a

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DUKE POfER COMPANY CATAWBA NOCLEAR STATION ,.

REQUALIFICATION PROGRAM EOR NBC LICENSED PERSONNEL 1.0 INHGUCTION Appendix A to 10CFR55 requires all licensed operators to participate in an NBC approved requalification program. W e requalification program for -

Catawba Nuclear Station was generated using the INPO Guidelines as a reference. h is requalification program consists of pre-planned lecture series, skills training and evaluation, operational review, and an annual examination and evaluation.

S e operator requalification program shall be conducted on a cyclical basis so that all program requirements are conpleted in a period not to exceed two years. ,

2.0 PRE-PIANNED LEC1ERE SERIES 2.1 h e requalification. program will includS two types of lectuse series . -

. . as follows: ,

A. Fundamental Review Lecture Series B. Operational Proficiency Iacture Series 2.2 Lecture Series 'Iboics 2.2.1 @e Furvhmanh1m Review lecture topics are selected on as-needed basis to reflect the results of the annual exam, as well as past performance of licensed personnel, and will include the following topics:

A. Seory and Principles of Reactor Operation B. Heat Transfer, Fluid Flow and hennodynamics -

C. Features of Facility Design, including Plant Systens D. General and Specific Plant Operating Characteristics  ;

including Expected Response to Equipment Failure E. Plant Instrumentation and Control Systems F. Plant Protection Systems

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G. Radiation Control and Safety l l

H. Engineered Safety Systens Page 3 of 14

I. Applicable Portions of Title 10, Chapter I, Code of Federal Regulations J. Fuel Bandling and Core Parameters K. Plant h iatry 2.2.2 The Goerational Proficiency lecture topics are selected to ensure coverage of essential plant operational  :

guidelines, and to reflect operational changes and l experiences. The following topics are typical of what will be covered during this lecture series:

A. Normal, Abnormal and Bnergency Operating Procedures B. Technical specifications i C. A&ninistrative Procedure, Conditions and Limitations ,

D. Major Operational Evaluations E. Facility Design'and License Changes .-

l F. Procedure Changes ,

I l G. Operating History and Problens 1

H. Related Naclear Industry Operating Experience I. Accident Mitigation of Degraded Core 2.3 REQUALIFICATION TRAINIMI TIME QMTINENTSr l The total annual Pre-planned lecture series training time for each l licensed operator will consist of a minimum of 100 contact hours of j classroom instruction. ,

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3.0 SKIILS TRAINIE AE EVAIEATION .

3.1 Each licensed individual shall demonstrate operational proficiency by participating in the following skill phases of requalification training.

A. Reactivity Manipulations B. Plant Evolutions C. Nuclear Plant Simlator Exercises 3.2 Feactivity renim1ations Cn an annual basis, each licensed operator will participate in evolutions selected from the following list, either on the Catawba Plant or at the McG. lire Simlator or Catawba Simlator (when the , 1 the Catawba Simlator is available). A minimum of any five (5) evolutions per year are required for satisfying this requirement. Items with an asterisk shall be performed on the

. Simlator annually. .- -

• l. Plant or reactor startup, and power escalation to a range where reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.

• 2. Plant shutdown to Source Range.

• 3. Manual control of steam generator water level and/or feedwater flow during plant startup and/or shutdown.

. *4. Boration and/or dilution during power operation.

• 5. Reactor power changes of 10% or greater where rod control is in manual, or where feedwater flow is controlled manually.

6. Reactor power changes of 10% or greater where load change is l performed with the DEH turbine control in manual. I

7. Operation of turbine controls in manual during turbine startup.

8. Decay Heat Removal System (2) Operation.

9. Operation of Manipulator Crane during refueling over the core.

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t 3.3 P1 ant Evolutions (Abnormal / Emergency) .

3.3.1 On an annual basis, each licensed operator will participate in exercises covering the following plant abnormal / emergency conditions either at a Catawba operating unit or on the McAtire Sinulator, or the Catawba Sinulator when it becomes available.

1. Reactor trip

2. Turbine generator trip

3. Loss of reactor coolant flow

4. Load Rejection

5. Ioss of Steam Generator Feedwater (G/CA)

6. Imakage Calculation (IOCA)

7. Plant Operations during natural circulation l

8. Ioss of Natural Circulation l

9. NCS at Saturation l

10. Inadvertent NC system depressurization

11. Actions required for A'IWS event

12. Ioss of control room

13. Significant Steam Generator Tube Isaks

14. Small IOCA (Inside and Outside Containment)

15. Large IOCA Page 6 of 14

'3.3.2 On a two year cyclical basis, each licensed

, operator will participate in exercises covering the following plant abnormal conditions at an operating unit of Catawba or at the McGuire M=ilator, or on the Catawba sinulator when it W= available.

1. Malfunction of Nuclear Instrumentation System j

2. Boron Dilution - Conditions Requiring Emergency Boration

3. Control Failures Affecting Reactivity

4. Inoperable Control Rod (Control Rod Misalignment, Control Rod Drop, Inability to Drive Control Rods)

5. Ioss of Makeup or Letdown

6. High Activity in Reactor Coolant .

7. Ioss of Instrument Air Systen

.- - . 8. Ioss of Electrical Power - * -

.9. Ioss of Condenser Vacuum l 10. Loss of Nuclear Service Water System l

l 11. Ioss of Couponent Cooling Water System

12. Hi Activity in Off Gas

13. Secondary Line Rupture (Inside & Outside Cont.)

14. Ioss of Residual Heat Removal

15. Ioss of Protective System Channel

16. Malfunction of NC Pressure / Volume Control Systems

17. Feedwater System Failures I

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3.4 1*elaar Plant similator Exercises 3.4.1 Licensed operators are required to participate in a structured simlator training program on an annual basis, and the following guidelines apply:

1. The use of Catawba Technical Specifications should be maximized during the simlator contro1~ manipulations.

2. Team c.w % utilized, enphasizing individual roles in reporting, assignment of operational duties, use of plant procedures and use of. technical specifications.

3. No more than four (4) licensed operators will be assigned to participate in a requalification training session which requires direct interaction with the simlator control panel.

3.4.2 Personnel with senior licenses are credited with ,

reactivity control manipulations as though they had performed them if they:

, , t 1. Direct these control manipulatibns w they ar-e . -

. . performed. , ,

2. Evaluate these control manipulations as they are performed (Training Staff Only).

3.4.3 Simlator Training will consist of a minimm of twenty (20) simlator hours per year, which includes all simlator training consisting of reactivity manipulations, plant evolutions, and an annual simlator examination.

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4.0 RErXIALIFICATION SCHEDULE 4.1 'the requalification schedule for Catawba consists of 5 ten week segments. Each shift is scheduled for approximately two-(2) weeks of training during each segment.

4.1.1 The last segment will be utilized for administration of an annual requalification examination on subjects covered throughout the year, as well as general subjects as specified in Section 6.2.

4.1.1 Licensed personnel are required to achieve a grade of 80% of each segment quiz. A grade of less than 80% but greater than or equal to 70% will result in management counseling with the individual concerned. A grade of lecc than 70% will require renedial self study, and a new quiz retake for than segment. ,

4.2 Licensed Training Staff are not requir,ed to attend the segment training but should participate in appropriate sections of requal to

, ,- assure they are cognizant of current operating history problems,- .

. station modifications, etc. _

4.3 Newly licensed personnel shall enter the Requalification Program upon receipt of their license.

4.4 Licensed Reactor Operators.(RO's) who are in training for a Senior license (SRO) will be exenpt from all requalification requirements for the duration of their training. They will continue to be updated on changes to the facility design, procedure changes, and facility license changes in accordance with station administrative procedures.

They will also receive training on emergency and abnormal procedures.

Any R0 who fails the SR0 exam will be evaluated by Operations Department Managers (i.e. Superintendent of Operations, Operating i

Engineers, SR0's, Shif t Supervisors) on their past and present job

- performance. A recommendation will be made based on this evaluation 1

regarding the individual's return to licensed duties.

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5.0 GPERATIONAL REVTW P'0 GRAM

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5.1 'the Operational Review Program provides a systen for rev1ew of selected operationally related events, reportable occurrences, nuclear industry information, and changes to existing operational guidance or equipment to maintain continued update of licensed personnel.

5.1.1 An Update Documentation Form (Typical example in Enclosure 1) is utilized to allow all licensed personnel continued update of the following information.

1. Plant design changes

2. Station nodifications

3. Procedure changes

4. 'Itchnical Specification changes

5. Pertinent IE Bulletin Information 6., . Incident Reports (Station and Industry)

7. Audit, evaluation a'nd inspection reports

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8. Publications covering nuclear industry inforIration

9. NSAC/INPO significant event reports 5.1.2 The annual reading and review of Emergency Procedures, Abnormal Procedures and Controlling Operating Procedures will be documented.

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6.0. AME RENPICATIM N@mTIM <

6.1 An annual requalification written examination and sirulator examination will be administered to all licensed individuals to

' determine their knowledge of topics covered in the segmented requal program.

6.2 The written examinat' ion will be grouped into at least six (6) categories for evaluation purposes, and will contain questions ,

covering topics which were presented during the yearly requal training segments,-as well as from general topics requiring operator knowledge. Some typical exagles are an follcws:

1. Theory and Principles of Reactor Operations 2 Heat Transfer, Fluid Flow and Thermodynamics

3. Features of Facility Design 4 General and Specific Plant Operating Characteristics

5. Plant Instrumentation and Control Systers

6. Plant Protection Systems

7. Engineered Safety Systens 8 Radiation Control and Safety

9. - Applicable Portions of Titi.e 10, Chapter.I, Code of Federal Regulations 10 Fuel Handling and Core Parameters .

11. Normal, Abnormal and Er rgency Operating Procedures 12 Technical Specifications

13. Administrative Procedures, Conditions and Limitations

14. Nuclear Industry Operating Exp rience

15. Accident Mitigation of Degraded Core 16 Electrical Theory 6.3 A licensed operator receiving a grade of less than 70% on any

' examination category, or an overall grade of less than 80% shall be placed in an accelerated requal program consisting of self-study with instructor guidance and support, followed by an exam re-take.

Failure of one category with less than 70% will require a category retake only, provided an 80% overall average is maintained. A licensed operator placed in accelerated requal shall not perform licensed duties until successfully completing the program.

6.4 An annual examination will be conducted on the McGuire Simulator or the Catawba Simulator (when it becomes available) for each licensed operator during the last segment. A licensed operator reveiving a grade of less than 80% on the Simulator exam shall receive accelerated requal training. A licensed operator placed in accelerated requal shall program not perform licensed duties until successbully completing the s

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6.5 Newly licensed individuals successfully completing their NRC licensing examination less than six (6) months ~ prior to an annual requalification written examination, may be excused from taking the current annual requalification examination and the simulator examination.

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7.0 AMTNTWRATION & RmtWMICATION .

7.1 Introduction

'this section will define specific responsibilities and provide guidance in the implenentation of the Catawba Requalification Program.

7.2 Reactivity Manimlations

1. A minicum of five (5) manipulations as defined in Section 3.0 will be accomplished per year with no more than two being of the same type.

2. Documentation of Reactivity Manipulations will be made at the Plant or during sf.mulator training with documentation forms transmitted to the Station Training Unit for formal record keeping of each licensed operator's performance.

7.3 Plant Evolutions

. ..- 1. Training exercises as referred to in Section -3.3 are actual . -

planned plant training drills, actual plant transients or simulated transients.provided during the sinulator'phas.e of the '

requalification program.

2. Documentation of the exercises will be acconplished in the Control Room at the time of the event, or at the Training Center during the simulator phase of requalification training.

7.4 crAssRocM/SIMD50R TPAINIm PWORDS 7.4.1 All classroom and sinulator training will be documented and transmitted to the Station Training Unit reflecting conpletion of each Requalification segment.

7.4.2 All records nust be of adultable quality and shall include the following:

1. '

Written examination results for each individual.

2. Sinulator training participation and team evaluation.

7.4.3 Records of training and qualification for current members of the station staff will be retained for the life of the station in accordance with Technical Specification 6.10.2.g. These records will include copies of written examinations administered, the answers results of evaluations and documentati,on of any additional training administered in areas in which an operator or senior operator has exhibited deficiencies.

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7.5 QPERATIONAL REVIDi PROGRAM (Sec. 5.0) 7.5.1 An Update Documentation Form will be utilized to allow imediate update of all licensed personnel on inportant information that may affect plant safety.

7.5.2 The Operating Engineer Document Develognant will be responsible to disseminate priority information from material described in Section 5.1.1 of the Requal Program, and route to all licensed personnel utilizing an Update Documentation Form.

Various informational areas defined under 5.1.1 which may not be priority information, will be provided to all licensed personnel during the classroom phase of each requal segment.

7.5.3 The Operating Engineer Document Development will be responsible to di====inate the Operator Update for the annual reading and review of Emergency Procedures, Abnormal Procedures and '

controlling Operating Procedures to all licensed personnel. .

7.5.4 Supervisory (SRO) personnel should provide the guidance to On-Shift Operators in interpreting and reviewing related information, and ensure all shift personnel' initial an Update '

4 Documentation Form, acknowledging their understanding of i associated information. .

7.5.5 All coupleted Update Documentation Forns should be returned to the Operating Engineer Document Develognent for review and filing.

7.6 CHAPEES TO REQUAL PROGRAM Any changes to the Requal Program will be nutually agreed on and approved by the Superintendent of Operations and the Senior Instructor.

7.7 ImIFICATIONS TO PIANT MANAGDIENT -

Cbservations made by Training Services Staff of personnel with less than acceptable performance will result in notification of plant managenent.

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_, . . . . . _ _ _ _ _ _ _ - - --- - -- - --- -- ---U

! P;pe a gr I .

Enclosure l' .-

Typical Example ,

Update Documentation Form 10: "A" SHIFT SUPERVISOR ISSUED DATE:

SUSJECT: COMPLET1005 Daft:

RClustelED 10 Jeetes NeeUTI ITEM l'T E M ITEM stAME INIT. 1N17 DMif.

SR18000ER, CHARLES HALLIE SilADSHAW. SCO T IY LYtIII ~

LOGIG. LARRY SEN1081 CRISP, EDWill ANSEL ELL 8 - a. ROOCER WAYISC RAftSEUR. TIMOTHY SCOTT SMSTN. GRA44AM ALLEst YOGI, J00801 LARRY .

ASERIIATHY, 9tARCUS CLE8888 l ALCORII, RElIOGETH B.

i AR elect 001, STEVEll 1000 MAS .

SAASCH, COL 5000 L.

I CALOWELL, IRIS E.

• l CAWLEY, JAMES P. .

HAMILT000, CARY WILLI AM JENRIES. TERRY R. __

J000ES, DWIC41T B.

3 CEEVFA, MARTHA JEAN 80001 NE JR. , C41ARLES WAYNC .

RORINS001, JOHN W.

R000. WILLIAM G. -

SORROW, RICHARD D. _ . .

4 8101ES: .

1) Tills FORM 15 USED TO NOTIFY YOU, ANO DOCUMENT YOUR RECCIPT i 0F PFRTINENT I N T ORMA T IO90.

2) THIS F0flM ftAY BE USED BY S.S. TO DOCUMENT INFORMATION NE DESI,RES.

Fonet GATE: 19 JA88 19AN VAN F8LE: DIR:PROCEDURC:SICse0FF

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