ML19345A696
| ML19345A696 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/05/1976 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19345A694 | List: |
| References | |
| AP-0500, AP-500, NUDOCS 8011240573 | |
| Download: ML19345A696 (20) | |
Text
,
n; Dept. Supv.
g. / Proc. No.
AP-0500 V
//.M Rev. No.
3 Plant Supt. /- //fy>
Issue Ihte Mgr. of Ops'. W/
Review Date v
.u YANKEE ROXE OPERATOR TRAINING PROGRMI PUPECSE To establish a program through which holders and prospective holders of Nuclear Regulatory Co = ission Reactor Operator and Senior Operator licenses will be trained for initial and renewal licensing.
REFERE' ICES 1.
ANSI N18.1 - 1971, Selection and Training of Nuclear Power Plant Personnel.
2.
Title 10, Code of Federal Regulations Part 55 and Part 55 Appendix A.
DISCUSSION The training progran is divided into two separate phases. Tne first of these is the initial operator licensing program.
This phase will be designed to give milicensed personnel the knowledge and experience necessary to nect the, requircaents of the Federal Regulations for license application.
The second phase of the training program will be licensed operator and senior operator retraining. Tne progr= will be conducted to maintain licensed operators and senior operaters at their highest level of competence and proficiency.
The progran is designated to meet or exceed the requirements set forth by the Nuclear Regulator /'
Conission in the Cede of Federal Re;ulation, pertaini:.; to ;grator retrainin; and license renewal.
The prc;ran will censist of a ccdin *ien of the following:
1.
Evaluatica Exans.
2.
On site lecture series supplemented at times by videotapes and other effective training aids.
3.
Innleacntation and documentation of a review program in which all licensed personnel are kept aware f:
Operating and emergency procedures.
a.
b.
Applicable administrative procedures.
c.
Plant design changes.
d.
Abnor=11 plant events, their cause and correction.
Encl..
AP-0500 - Pgs. 1 Rev. 3 Att. A - Rev. 3 APF-0500.1,.2,
.3,.4,
.5,.6,.7,
.8,.9 6.10 - Rev. 3 8011240gp 9
lManas a e b@k@2@d b@adMby
AP-0500
~~..
._~
j Rev. 3 Pg. 2 4.
Actual control manipulation, or direct supervision thereof, for at 1 cast 10 reactor startups, shutdowns, or significant t
reactivity changes which demonstrate familiarity with.the reactor i
control systems.
The following subject areas will be covered during the evaluation and lecture series of both phases of the program:
1.
Reactor Theory and Principles of Operation.
2.
General and Specific Plant Operating Characteristics.
3 3.
Plant Instrumentation and Control System.
I 4.
- Plant Protection Systems.
- )
5.
Engineered Safety Systems.
6.
Radiation Control and Safety.
7.
Technical Specifications.
8.
Standard and Emergency Operating Procedures.
{
9.
Applicable portions of Title 10, Code of Federal Regulations.
Documentation of the initial training and retraining programs will be acccmplished through the use cf the Lecture Attendance Sheet-(APF-0500.1) and transfer of that infomation to the _ individual's 4
training records.
(ADF-0500. 2) i Tne training coordinator has the responsibility of implementing all training. He will also be responsible for maintaining adequate records' of the training effort.
PROCEDURE l
I.
Initial-License Program.
A.
As the need arises for additional X.R.C. licenses at' Yankee Rowe, a training program will be instituted to ensure:cach
[
candidate will receive sufficient training and experience for i
license application submittal.
Tnis program will consist ~
of the following:
i.
1.
Classroom lectures-in the.following_ subject material:
a.
Reactor Theory 3
b.
System and Components Instrtr.entation and Control's c.
j d.
Transient Analysis c.
D: sign Features-S e
es-m a
+ or,
.~g-4--
4 AP-0500
!=
pey, 3
=
Pg. 3 f.
Health Physics g.
Technical Specifications
.h.
Operating and Emergency Procedures 2.
Classroom Iccture attendance and evaluation examination results will be maintained by the training coordinator.
These records will be maintained only for the purpose of~1icense application. The application will become a part of the individual's training file.
3.
Actual manipulation of the reactor controls by the 4
individual to demonstrate his ability to' operate the plant in a safe and competent manner.
4.
Upon completion of the above, each applicant will be required to pass a company examination similar in i
scope and depth to En N.R.C. examination.
B.
When an individual receives'an N.R.C. license, a copy of
~
the license will be filed in the training record.< 'Ihe licensee will then be enrolled in the retraining program.
II.
Licensed Operator Retraining i
A.
Evaluation Examination 1.
Examinations will be administered to each licensed operator and senior operator at least annually.
I 2.
Reactor operator examination categories will consist of the following topics:
a.
Principles of Reactor Operation b.
Features of Facility Dasign l
c.
General Operatir.g Characteristics f-d.
Instrumentation and Control Systems t
l e.
Safety and Emergency Systems f.
Standard and Emergency Operating Procedures g.
Radiation Control and Safety L
3.
Senior operator _ examination categories will consist of the following topics:
l L_
AP-0500 Rev. 3 Pg. 4 a.
Reactor E cory b.
Radioactive Material 11andling, Disposal and liazards c.
Specific Operating Characteristics t
d.
ruel llandling and Core Parameters c.
Administrative Procedures, Conditions and Limitations 3
4.
If a licensed operator or senior operator fails to achieve an overall examination grade of 700, he.will be required to participate in any accelerated requalifica-l tion program prior to resuming any licensed activities.
- A judgement will be nade by the training coordinator at the time of the failure as to how the accelerated program may best be administered.-
\\
5.
The following infomation pertaining to evaluation examinations will become a part of the license holders j
training file:
a.
A copy of the licensees' answers.
b.
The grade the licensee achieved for each section and his overall percentage grade.
(APF-0500.3 or
/JF-0500.4) c.
Recor.endations for retraining in sections'in
~
which the licensee; failed to achieve a satisfactory grade of 80%
(APF-0500.5) 4 t
l' 6.
A copy of all examination questions'will be maintained'
[
by the training coordinator.
7.
The requalification: records shall be maintained for a-period of two years per Reference 2.
3.
On-Site' Lecture Series The on-site lecture series will consist of preplanned lectures.
1 to be given on a regular and continuing basis which will be interrupted by heavy plant workloads or outages and the traditional vacation periods of June,' July and August.
Khere applicable, up to 50% of the lecture series may be
~
i supplemented-by the use of films, video tapes,.and/or individual study.
1.
- The;fo11ewinggeneralsections'willcomprisethelecture.
~
series:
a.
Theory and Principles?of Operation
. b.
General and Specific Plant' Operating ~ Characteristics c.
-Plant Instrumentation and Controls ~-
d.
Plant Protection Systems c.-
Engineered Safety Systems 1
>-, AP-0500 Rev. 3 Pg. 5 f..
Noma 1, Abnomal and Emergency Operating Procedures g.
Radiation Control and Safety-h.
Technical Specifications
(
i.
Applicable portions of Title 10, Chapter I, Code of Federal Regulations
/
2.
Each licensee who fails to achieve a grade of S0% in a-grade section or sections shall be required to attend lectures given pertaining to the subject material in which he has shom the deficiency.
3.
The nomal lecture series will be scheduled so that each licensee will have the opportunity to attend each lecture in the nomal course of his work schedule.
4.
An examination will be administered at.the completion of the lecture period. Any individual failing to achieve a grade of-80% will be given individual instruction on the material to be able to achieve a satisfactory grade.
5.
The training coordinator shall maintain the following records for the lecture series:
a.
Attendance Record (APF-0500.1) b.
Results of Examinatiens' Administered =(APF-0500.3 or -
l APF-0300.4) c.
Schedule and Curriculum Record-C.
Operator. Review Program 1.
-All-licensed operators and senior operators will review applicable administrative, cperating and c=crgency procedures.
2.
The training coordinator vill issue to all licensed; operators and senior operators periodically:a listing of procedures which should be reivewed.
in:.s will be documented by.
APF-0500.6.
l 3.
' The completed foms will be returned to the training coordinator-'
for file in the' individual's file.
-4.
The performance of licensed individuals will be_ frequently-evaluated during actual or sinulated abndmal and emergency, plant conditions._ This will-be done to meet the' requirement-for systematic observation and evaluatica which appears in Paragraph 4c of. Appendix A of-10,CFR Part 55.;
b m.
J
AP-0500 Rev. 3 Pg. 6 5.
The evaluation will be documented on the Operator Evaluation Fom (APF-0500.7) which will be placed in the individual's file.
D.
Reactivity Control Manipulations 1.
Each licensed operator and senior operator is required to perfom a direct at least ten significant reactivity changes, which demonstrate familiarity with the control systems, during the two year duration of his license.
Refer to Appendix A of this procedure for a listing of reactivity changes for which Yankee Rowe will take credit.
2.
Reactivity manipulations will be documented by the training coordinator.
This infomation will be incogorated into the individual's training records on APD-0500.8.
3.
Each operator should make an effort to perfom a variety of reactivity changes in lieu of the same reactivity change ten times.
E.
Operating Experience 1.
10 CFR 55.31 requires satisfactory demonstration of knowledge and understanding of plant operation for any persons who have not actively perfomed operator or senior operator duties for a period of four months or longer.
2.
Any individual absent from operating duties for a period of four months or longer will be given a written and/or an oral examination to detemine any areas in which the individual needs accelerated training before resuming his nomal duties.
3.
The training coordinator shall ensure the individual who has been absent for four months or longer is made aware of procedure, design and license changes which have taken place in his absence.
F.
Simulator Training 1.
In the future, if plant operating history indicates a need for training under emergency or abnormal conditions a reactor simulator similar in layout to Yankee Rowe may be utili cd.
2.
This training, if used, will be used at 1 cast bi-annually for all licensed operators when the need for such training is indicated.
1 AP-0500 Rev. 3 Pg. 7 The trabiing coordinator will be responsible for documentation 3.
of any individual's participation in simulator training.
(APF-0500. 9)
G.
Special Training Assignments I
The training coordinato1 shall document special training l
1.
assignments executed by licensed operators or senior operators,
[I (APF-0500.10), such as:
In-plant assignment to another department.
a.
b.
Off-site seminars or classes.
AP-0500 Rev. 3 Pg. 7 3.
The training coordinator will be responsibic for documentation of any individual's participation in simulator training.
(APF-0500. 9)
G.
Special Training Assignments 1.
The training coordinator shall document special training assignments executed by licensed operators or senior operators, (APF-0500.10), such as:
a.
In-plant assignment to another department.
b.
Off-site seminars or classes.
4
=_
L
~
AP-0500 Rev. 3 App. "A" YANKEE RONE OPER\\10R TRAINING PROGRC1 APPENDIX "A" SIGNIFICLT REACTIVITY OIANGES 1.
Controlled reactor startups or shutdowns.
2.
Control manipulations which result in a reactor thermal power change of 10% or greater such as:
a.
Monthly turbine throttle valve exercise.
b.
Reductions for plant equipment maintenance.
L 3.
Control manipulations required to mintain the desired reactor power level such as:
a.
Main Coolant System borations b.
Main Coclant System dilutions c.
Control Rod motion to adjust power level d.
Xenon buildin or burnout follow e.
Main Coolant System a=noniation f.
Temperature changes during Main Coolant System heatup and cocidown g.
Operation of the feedwater system during reactor power changes h.
Operation of the turbine governor control during reactor
. power changes 4.
Reactor Physics Testing.
5.
Plant Emergency Shutdowns from Power such as Reactor Trips ~.
6.
In order to be credited as a significant reactivity change, a reactor startup will be to the point of adding heat and a reactor shutdo.a will be part of a plant shutdown.
~
k L
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Yn.dE E0'/.T OPERYTP TP.\\!NING PP.0GIU2i LECIURE ATTEND.\\NCE S!!EET Date:
Subj ect A.
Theory 6 Principles of Operations B.
General 6 Specific Plant Operating Characteristics C.
Plant Instrir.entation and Controls D.
Plant Protectica Systems E.
Engineered Safety Systems F.
Normal, Abnomal 6 Emergency Operating Procedures G.
Radiation Control 6 Safety H.
Technical Specifications I.
Applicable Portions of Title 10 Chapter 1 Code of Federal Regulations Presented by:
Material Covered:
I t
APF-0500.1 Rev. 3
Date Licensee License No.
LECTURE PROGP21 Subj ect Hours A.
Theory 5 Principles of Operation ----------------------------------
B.
General 6 Specific Plant Operating Characteristics ----------------
C.
Plant Instrumentation 6 Controls -------------------------- -------
D.
Plant Protection Systems ------------------------------------------
E.
Eng in e e red Sa fe ty Sys tems -- - - - - - -- -- --- -- --- - - - --- - -- - --- -- -- - - - - -
F.
Normal, Abnormal and Emergency Operating Procedure.s ---------------
G.
Radiation Control 6 Safety ----------------------------------------
H.
Technical Spec ifica tions -- -- - -- - -- ----- -- -- --- --- - -- --- -- - --- - - -- -
I.
Applicable Portions of Title 10 Chapter I Code of Federal Regulations -----------------------------------------------
Tot 1 ----------------
Training Coordinator APF-0500.2 Rev. 3
I R.O. ITALUNTION ELUlIL\\ TION IESULTS Licensee License No'.
Date Examination Taken _
=
Point Points Categorv Value of Total Earned Grade A.
Principles of 11eactor Operation B.
F;. n...
.acility Design s.
ang Characteristics C.
G;ac...:
s, s...
D.
Instnr.entatica and Control Systems E.
Safety cnl Emergency Systems F.
Standard and Emergency Operating Procedures G.
Radiatica Control and Safety Overall Grade (%)
Graded 3y APF-0500.3 Rev. 3 a
S.i.. J. EV.\\lH\\ TION EX.V!!NATICN RESUE.s Licensee License No.
Date Examination Taken Point Points Category Value of Total Earned Grade H.
Reactor "Iheory I.
Radioactive Material Handling, Disposal and Ha:ards J.
Specific Operating Characteristics K.
Fuel Handling Procedures, Conditions and Linitations Overall Grade (%)
Graded By l
APF-0500.4 Rev. 3
i OPER\\ TOR RETRAINING RECO.4DNDATIONS LICE _N'SEE LICENSE NO.
IRTE A review of the results of the evaluation examination given on
, indicate your need for additional training in the following areas:
The folicwing requirements shall be implemented to improve your knowledge in the above areas.
Training Coordinator APF- 0500,5 Rev. 3
I PROCED'RE R!IIDl LICENSEE LICENSE NO.
Picase review the listed mterial and return this form to the training coordinator, ll\\TE PROCEDURE REVIEED LICENSEE l
APF- 0500. 6 Rev. 3
u OPERUOR EVAll1HION Licensee has perfomed the actual or simulated Emergency Procedure No.
on (Date)
Following are my co=ents on the performance of the licensee during the emergency situation.
1.
Knowledge of Procedure 2.
Perfomance During Fr.ergency Situation (s) 3.
Deficiencies Noted Shift Supervisor Licensee (Reviet) i i
Training Coordinator APF-0500.7 Rev. 3
(-.. -.
Licensee License No.
INDIVID(RL RECORD OF
, PLANT LO.\\D GL\\NCES 6 RFACIDR STAR'IUPS s
Plant Load Change Reactor Startup Cause of Change in Plant Date Frca - To Fro:n - To Power Level t
i l
l l
APF- 0500. 8 Rev. 3
4 SDUL\\ TOR TRAINING DATE LICENSEE LICENSE NO.
LOCATION 110URS REMARKS:
ADDITIO.'RL TRAINING:
O
- APF-0500.9 Rev. 3
l-Licensee License No.
SPECLtL TRAINING ASSIGraT Time Date Assignment (liours)
Re:aarks f
i i
1 b
APF-0500.10 Rev. 3 L
NRC FoRu 195
(
U.s. NUCLE An ncoutATony C7 isSioN DoCr.ET NUMIE R 2.m 59 79 y
NRC DISTRIBUTION Fon PART 50 DOCKET MATERI AL TO:
FROM:
DATE oF DOCUMENT Yankee Atomic Electric Company 10/5/76 Mr. Roger S. Boyd L'es tborough, Mass.
DATE RECEIVED J. L. French 10/12/76 2b.ETTER ONoToRIZED PROP (NPUT FORM NUMBER oF COPIES RECEsVED RoRiciN AL JifUNC L AsSIFIE o Three Signed OCopy 37 copies enc 1 reevd.
DESCHtPTioN ENCLOSURE Ltr. trans the following:
Furnishing Revision 3 to Procedure AP-
,0500, Yankee Rowe Operator Training Program.
T{x OETEDGS (1-P)
(19-P) -
T PLANT NAFE:
DO NOT REMOVE Yankee Roue SAFETY FOR ACTION /lNFORMATION ENVTRO 10/12/76 RJL I ASSIC'T.D _ AD:
I AS4TC'!En AD!
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s
%gPROJECTMANAGER:
BRANCH CHIEF:
Schwcncer (E) ngANcn enTEp.
Burger PROJECT 1%NAGIR!
X LIC. k ;T.:
Sacppard LIC. ASST.!
INTERNAL DISTRIBUTION
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SYSTEMS SAFETY PT.MiI_SYSIEys SITE SAFETY &
_ __,hiiC PDR HEINEMAN TrnESCO ENVIRO ANALYSIS h(I&E
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SCHROEDER BENAROYA DJNTON & MUTT _FR dOELD
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LAINAS X COSSICK & STAFF ENGINEERING IPPOLJTO ENVIRO TECH _
MIPC MACCARRY KI_ Rig 100D ERNST CASE KNIGHT BALLARD IMNAUER i SIlia'EIL OPERATING REACTORS SPANCT_ER llARLESS
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