ML20097B333

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Duke Power Co,Catawba Nuclear Station Requalification Program for NRC Licensed Personnel
ML20097B333
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 08/21/1984
From:
DUKE POWER CO.
To:
Shared Package
ML20097B332 List:
References
NUDOCS 8409140002
Download: ML20097B333 (15)
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IXRE POWER COMPANY CATPWBA NUCLEAR STATION REQUALIFICATION PROGRAM FOR August 21, 1984 -

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CATAWBA N(X1 EAR STATION REQUALIFICATION PROGRAM FOR NIC LICENSED PERS0 teel TABLE T CONIENTS SECTICE jigig 1.0 Introduction 3 2.0 Pre-Planned Iacture Series 3 3.0 Skills Training and Evaluation 5 ,

4.0 aequalification Schedule 9

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5.0 -

Operational Review Program. -

10 6.0 Annual Requalification Examination 11 7.0 A&ninistration of Requalification 13 Page 2 of 14

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DEE POfER C3EPANY CA'DNBA IWCLEAR STATIW

REQUALIFICATION PIOGRAM POR NRC LICENSED PERS0ttiEL l 4

1.0 IEENGxrTIcal Appendix A to 10CFR55 requires all licensed operators to participate in an NRC approved requalification program. % e requalification program for Cam leaclear Station was generated using the INPO Guidelines as a

~ reference. his requalification program consists of pr g lanned lecture

. series, skills training and evaluation, operational review, and an annual i examination and evaluation.

n e operator requalification program shall be conducted on a cyclical

. basis so that all program requirements are coupleted in a period not to exceed two years. ,

2.0 PRE-PIMEIED LECTURE SERIES

,; 2.1 h e requalification. program will include two types of lecture series . -

.. as follows: , ,

A. Fundamental Review Iacture Series B. Operational Proficiency Iacture Series

- 2.2 rachire norf.a 'Iwnica 2.2.1 he Fundamentals Baview 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. %eory and Principles of Beactor Operation B. Heat Transfer, Fluid Flow and %ernodynamics C.- Features of Facility Design, including Plant Systens D. General and Specific Plant Operating Characteristics including Expected Response to Rplipment Failure E. Plant Instrumentation and Control Systems F. Plant Protection Systens G. Radiation Control and Safety H. Engineered Safety Systems Page 3 of 14

l I. Applicable Portions of Title 10, Chapter I, Code of Federal Regulations J. Fuel Handling and Core Parameters l

K. Plant h iatry l 2.2.2 The NeraHonal ProficionW 1ecture topics are selected to ensure coverage of essential plant operational guidelines, and to reflect operational changes and experiences. The following topics are typical of what will be covered during this lecture series:

A. Normal, Abnormal and Emergency Operating Procedures B. Technical Specifications C. A&ninistrative Procedure, Conditions and Limitations ,

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

F. Procedure Changes G. Operating History and Problems H. Related Itaclear Industry Operating Experience I. Accident Mitigation of Degraded Core 2.3 REQUALIFICATION TRAINIE TIME CGeirMEES:

The total annual Pre-planned lecture series training time for each licensed operator will consist of a minimum of 100 contact hours of classroom instruction.

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3.0 SKILLS 'IB&INIE AE EVAURTION 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 Daactivity Manien1ations On an annual basis, each licensed operator will participate in evolutions selected from the following list, either on the Catawba Plant or at the McGuire Simlator or Catawba Sinulator (when the ,

the Catawba Simlator is available). A mininum 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.
  • 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 performed with the DEH turbine control in manual.
7. Operation of turbine controls in manual during turbine startup.
8. Decay Heat Renoval System (10) Operation.
9. Operation of Manipulator Crane during refueling over the core.

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3.3 Plant Evolutions (Abnormal /Dnergency) 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 McGuire Sinulator, or the Catawba Simulator when it becomes available.

1. Reactor trip
2. Turbine generator trip
3. Ioss of reactor coolant flow
4. Ioad Rejection
5. Loss of Steam Generator Feedwater (T/CA)
6. Imakage Calculation (IOCA)
7. Plant Operations during natural circulation

. 8. Ioss of Natural Circulation

9. NCS at Saturation
10. Inadvertent NC systen depressurization
11. Actions required for A1WS event
12. Ioss of control room 13.- Significant Steam Generator Tube IAaks
14. Small IDCA (Inside and Outside Containment)
15. Large IOCA Page 6 of 14

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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 Sinulator, or on the Catawba sinulator when it becomes available.

1. Malfunction of Nuclear Instrumentation Syst e
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 (bntrol Rods)
5. Ioss of Makeup or Letdown
6. High Activity in Reactor Coolant .
7. Ioss of Instrument Air System Ioss of Electrical Power

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9. Loss of Condenser Vacuum
10. Ioss of Nuclear Service Water System
11. Ioss of Cmponent 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 Page 7 of 14

3.4 Melaar Plant Mnnlator 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 control manipulations.
2. Team concept 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 sinulator control panel.

3.4.2 Personnel with senior licenses are credited with .

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

.I 1. Direct these control manipulatibns M they are . -

. . performed. , ,

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

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

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4.0 REQUALIFICATION SCE!DULE 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 stbjects 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 less than 70% will require remedial self study, and a new quiz retake for than segment. ,

4.2 Licensed Training Staff are not required to attend the segment training but should participate in appropriate sections of requal to '

  • assure they are cognizant of current operating history problere,-

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 (Sao) will be exenpt from all requalification requirements for the duration of their training.

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I-5.0 CPERATIONAL RNIN PROGRAM 5.1 The Operational Review Program provides a systen for review of selected operationally related events, reportable occurrences,  ;

nuclear industry information, and changes to existing {

operational guidance or equipment to maintain continued update J of licensed personnel.

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

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1. Plant design changes l l
2. Station modifications
3. Procedure changes
4. Technical Specification changes
5. Pertinent IE Bulletin Information

- - i 6,, Incident Reports (stiation and Industry)

7. Audit, evaluation a'nd inspection reports
8. Publications covering nuclear industry information
9. NSAC/INPO significant event reports 5.1.2 An Update Documentation form will be used to document the annual reading and review of Emergency Procedures, Abnormal Procedures and Controlling Operating Procedures.

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6.0 AIRERL REQUALIFICATION EKAMIMTIGi 6.1 An annual requalification written examination and sinulator examination will be administered to all licensed individuals to determine their kncwledge of topics covered in the segmented requal program.

6.2 'Ihe written examination 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 exanples are as follows:

1. 'Iheory and Principles of Reactor Operations
2. Heat Transfer, Fluid Flow and 'Ihermodynamics
3. Features of Facility Design
4. General and Specific Plant Operating Characteristics
5. Plant Instrumentation and Control Systems ,
6. Plant Protection Systems
7. Engineered Safety Systems
8. Radiation Control and Safety

. . 9.- Applicable Portions of Tit 1.e 10, Chapter.I, Code of .- .- -

. Federal Regulations

10. Fuel Handling and Core Parameters
11. Normal, Abnormal and Emergency Operating Procedures
12. Technical Specifications
13. Administrative Procedures, Conditions and Limitations
14. Nuclear Industry Operating Experience
15. Accident Mitigation of Degraded Core 16 Electrical 'Ibeory 6.3 A licensed operator receiving a grade of less than 70% in nore than one 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.

6.4 An annual examination will be conducted on the McG11re Sinule. tor or the Catawba sinulator (when it becomes available) for each licensed operator during the last segment. A licensed operator receiving a grade of less than 80% on the Sinulator exam shall receive additional training handouts with instructor guidance and support, followed by an exam retake using a different scenario.

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[ 1 6.5 Any licensed person who fails to meet the mininum grades stated in 6.3 and 6.4 will be evaluated by Operations Department Managers (i.e. Stiperintendent of Operations, Operating Engineers, S10's, Shift Supervisors) on their past and present job performance. A recoumendation will be made based on this evaluation regarding the individual's removal from licensed duties.

6.6 Newly licensed individuals successfully coupleting their NIC licensing examination less than six (6) months prior to an annual requalification written examination, may be excused from taking the current annual requalificatica examination and the sila11ator examination.

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E 7.0 ADMINI!m WTIN & REQUALIFICATIM -

7.1 Introduction --

E '1his section will define specific responsibilities and provide T. 4 guidance in the inplementation of the Catawba Roqualification

- Program.

7.2 Partivity Maniculations

- 1. A minimum of five (5) manipulations as defined in Section 3.0 '

will be acconplished 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 sinulator training with docunientation forms f transmitted to the Station Training Unit for formal record g J keeping of each licensed oprator's performance. ,

7.3 Plant Evolutions b , ,,- 1. Training exercises as referred to 2.a Section %3 are actual . -

, , planned plant training drills, actual plant transients or sinulated transients provided during the sinulator' phase of the '

> requalification program.

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2. Documentation of the exercises will be acconplished in the e control Room at the time of the event, or at the Training ~

L Center during the sinulator phase of requalification trcining.

$ 7.4 CIAMSIMA'IDR TRAINTIC RECORDS ..

7.4.1 All classroom and sinulator training will be documented and .

a transmitted to the Station Training Unit reflecting conpletion  !

P of each Requalification Segment.

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

r E 1. Written examination results for each individual.

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i 2. Sinulator training participation and team evaluation. ~

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

7.5.2 ibe Operating Engineer Document Developnent 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 Develognent will be responsible to dia -ninate 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 *he guidance to On-stift operators in interpreting and reviewing related '

. .' information, and ensure all shift personnel' initial an Update Documentation Form, acknowledging their understanding of associated information.

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

7.6 CHANGES 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 M7fIFICATICES TO PIANT MANiGEMENE (beervations made by Training Services Staff of personnel with less than W ahle performance will result in notification of plant management.

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mua_ y Pepe i er 9 Enclosure l' ,

Typical Example Update Documentation Form 10: "A" SN I F T SUPERV s SOR ISSUED DATE:

SusJECV: COMPLETiose DATE:

RETUlt00ED TO JOHN RIOUTI ITEM ITEM ITEM IIAME 1

INIT. INIT. INii.

SKtteeIER, CIIARLES HALLIE BRADSHAW. SCO T I Y 8.VII81 LOfeC. LARRY DENIOff CRISP, EOWIN ANSEL ELLiIOCWOOD, ItOOCER WAYNC RAMSEUII, TIIt0TilY SCOT 1 l SMI TN, GRAIGAM ALLEN f Yoel, J00006. LARRY .

ASERIIATHY, 94AftCUS CLEGIII ALCOstel, NENIGETH I.

ARiteCTOII, STEVEN THOMAS SftASCH, COLSOII L.

CAWLEY. JAMES P.

HAMI L T005, CARY WILLIAM

. JENRINS, TERRY R.

! J000ES, OWIC31T B.

1 REEVFA. MARTHA JEAN i IgOOINE JR., CIIARLES WAYNE .

RORINS001, JOHN W.

RUOO, WILLIAM C. '

i SOftROW, RICHARD 0 __

i i IsoIES:

1) Tills FORM IS USED TO IIOilFY YOU, ANO DOCUMENT YOUR RECEIPT l

0F PFRTINENT INF0ftMATIOel.

2) TNIS FORM MAY BE USED BY S.S. TO 00CUMENT INFORMAT1001 NE DESIEES, i

FORM OAi[3 19 J A" 19888 i VAX FILE: DIR: PROCEDUltEI SIC 000F F i

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