ML19331D695
| ML19331D695 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/31/1980 |
| From: | Metropolitan Edison Co |
| To: | |
| Shared Package | |
| ML19331D694 | List: |
| References | |
| NUDOCS 8009030469 | |
| Download: ML19331D695 (42) | |
Text
_
1006 Revision 3 Erclosure di 07/31/80 MRC 80 4 THREE MILE ISLAND NUCLEAR STATION O
UNIT I ADMINISTRATIVE PROCEDURE 1006 OPERATOR REQUALIFICATION PROGRAM Table of Effective Pages Pace Date Revision Pace Date Revision Pace Date R evisier 1.0 07/31/80 3
26.0 51.0 2.0 07/31/80 3
27.0 52.0 3.0 07/31/80 3
28.0 53.0 4.0 07/31/80 3
29.0 54.0 5.0 07/31/80 3
30.0 55.0 6.0 07/31/80 3
31.0 56.0 7.0 07/31/80 3
32.0 57.0 8.0 07/31/80 3
33.0 58.0 9.0 07/31/80 3
34.0 59.0 10.0 07/31/80 3
35.0 60.0 11.0 07/31/80 3
36.0 61.0 12.0 07/31/80 3
37.0 62.0 13.0 07/31/80 3
38.0 63.0 14.0 07/31/80 3
39,0 64.0 15.0 07/31/80 3
40.0 65.0 16.0 07/31/80 3
41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Reco ds Approval Unit 2 Staff Reco
..ec s pproval
~
~
l Acproval
/\\/
Date Approval Date Cogn/zant Dept. Heno Cogni: ant Dept. Head Unit 1 PORC Recom ends Approval Unit 2 PORC R mm d pproval nYo JPW Date 7 0
/l Date Chairmen of PCRC Chairman of POR'C 4
Unit 1 S erintendent Approval v
Unit 2 Superinter ent reval Date7-2L~ O
/l Date V
MGQA Approval NRC Approval
~
^
k-Oh W-___ - D a te N
Date y
TMI.121 8-79 80090301{66
1006 Revision 3 07/31/80 THREE MILE ISLAND NUCLEAR STATION UNIT I ADMINISTP.ATIVE PROCEDURE 1006 METROPOLITAN EDISON THREE MILE ISLAND UNIT ONE OPERATOR REQUALIFICATION PROGRAM Table of Contents PAGE 1.0 GENERAL 2.0 1.1 Purpose 2.0 1.2 Scope 2.0
/
1.3 Program Schedule 3.0 2.0 REQUIREMENTS 4.0 2.1 Requalification Lecture Series 4.0 2.2 On-The-Job-Training 6.0 2.3 Annual Evaluation Examination 9.0 2.4 Records 12.0 2.5 Accelerated Requ'alification Program 12.0 2.6 Four Month Absence Program
~~
13.0 2.7 Newly Licensed Operator 13.0 l
3.0 RESPONSIBILITIES 14.0 3.1 Supervisor - Operator Td.; W yd His Staff 14.0 3.2 Supervisor - Administrative Support Section and His Staff 14.0 3.3 Operations Supervisor, Supervisor of Training, or Other Suitable Qualified Person Designated by the Manager of Training 14.0 l
4.0 Attachments l
4.1 Attachment I - Off Shift Licensed Operator Watch I
l Standing Documentation i
1.0 i
~
1006 Revision 3 07/31/80 THREE MILE ISLAND NUCLEAR STATION UNIT I ADMINISTRATIVE PROCEDURE 1006 METROPOLITAN EDISON THREE MILE ISLAND UNIT ONE OPERATOR REQUALIFICATION PROGRAM 1.0 GENERAL 1.1 Purpose The Metropolitan Edison Requalification Program, as set forth in this document, applies to Unit One of the Three Mile Island Nuclear Generating Station. All licensed personnel will participate in the requalification program. The basis of the requalification program is to maintain operator competence and proficiency for continued safe operation. The guidelines fer the requalification program are found in 10CFR55 Appendix A.
In addition, the implementation of this program conforms to 10CFR50.
1.2 Sccpe The following sections of the requalification program cover:
I.
Program Schedule II.
Pre-planned Lectures III On-the-job-training IV.
Annual Evaluation Examination V.
Records VI.
Accelerated Requalification Program VII.
Four Month Absence Program VIII.
Newly Licensed Operators IX.
Requalification Program Administration 2.0
1C05 Revisien 3 07/31/20 1.3 Program Schedule The requalificatien program described herein will be implemented upon final approval of this document. March 1, and subsequent anniversaries of this date, will be considered to be the starting I
date of each annua 1 cycle of requalification program operation.
The Metrcpolitan Edison Three Mile Island Unit One Requalificatien Program consists of three interrelated segments, two of which run concurrently. These segments are:
1)
Requalification Lectures Series - The requalification lecture
/
series censists of classrocm instruction designed to maintain operator competence and proficiency and is scheduled for a minimum of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year. Each license holder will ccmplete the requalification lecture series requirements en an annual cycle.
2)
On-the-job-training - On-the-job-training is designea to insure that all licensed personnel operate reactor centrols and participate in major plant evolutions. Recofds of all en shift performance are maintained and periodically reviewed by superviscry persennel. The on-the-jeb-training is conducted throughout the two year term of the individual's license, including specific annual requirements. All recuired on-the-job-training will be ccmpleted prier to license renewal.
1 Annual, as referred to in the cperator requalification program, is twelve months, not to exceed fifteen months, in order to acccmedate plant operations. A statecent of Requalification program participatian, signed by the Director of Three Mile Island Unit One, will be submitted with each license renewal application.
3.0
1006 Revision 3 07/31/80 3)
Annual Evaluation Examination - The annual evaluation examinations simulate the written and oral examinations administered by the Nuclear Regulatory Ccmmission (NRC). Performance on these annual evaluation examinations determines the extent of the mandatory up-grading program during the following twelve month requalification period.
The requalification program is designed with fixed perforr;.ance standards and specifiad remedial actions. The program results and records are fully auditable.
2.0 REQUIREMENTS 2.1 Requalification Lectures Series During each year, licensed personnel shall attend the Requalification Lecture Series as either students or instructors.
The following topic; shall be covered as a minimum during the Requalification Lecture Series each year:
(a) Principles of Reactor Operations (including Principles of Heat Transfer and Fluid Mechanics).
(b) Features of Facility Design and Unit ?!cdifications.
(c) General Operating Characteristics.
(d)
Instrumentation and Control.
(e) Safety and Emergency Systems including Unit / Station Protection Systens.
(f) Norr.al, Abnormal, and Emergency Operating Procedures Review.
(g) Radiation Control and Safety (h) Technical Specifications and Safety Analysis.
(i) Major Operational Evolutions (such as refueling).
(j) Applicable portions of Title 10, Chapter 1, Ccde of Federal Regulations.
4.0
1006 Revision 3 07/31/80 (k) Mitigation of accidents involving a degraded core.
(1)
Industrial Experience Reviews.
For Senior Operators the Requalification Lecture Series will also include:
(m) Reactor Theory and Theory of Fluids and Thermodynamics.
(n) Radioactive Material Handling, Disposal, and Hazards.
(o) Specific Operating Characteristics.
(p) Fuel Handling and Core Parameters.
(q) Administrative Procedures, Conditions, and Limitations Lectures shall be held on a continuing basis with a weekly
?
schedule of lectures designed to be repeated for each shift when that shift is designated for its training week. The program and schedule will be detemined by unit operations or projected operations and must take into account planned and unplanned outages and available simulator time. Records of the topics covered in each session will be maintained by the Training Department. Attendance of all licensed personnel will be recorded. Absences will be made up by reviewing lecture materiels and/or discussions with on-shift supervisory personnel or the technical staff. Periodic evaluation quizzes covering the content of the requalification lecture series will be administered. The quizzes may be administered in either the closed book or open book fanat, as class rocm, or on-shift quizzes.
If an unsatisfactory grade (less than 80%)
is received, makeup sessions with assigned instructors will be 5.0
~
1005 Revisi n 3 07/31/20 conducted. The makeup session will conclude when an cral or written evaluatien is satisfactorily co:pleted. The content of the qui: will be different for R0 and SR0 license holders and will aflect the topic areas and degrees of responsibility needed by the license holder. These personnel whose annual written examinatien secres indicate that a =andatory upgrading of
- heir kncwledge level is requirec, as delineated in secticn 2.3, attend the applicable requalification lecture (s) and cust certify their kncwledge by satisfactorily cc=pleting a written examination with a grade of at least 20%.
If a grade belcw 20% is achieved en this certification examination by a licensed holder, a deficiency is assigned
/
and the license holder will be assigned an accelerated requalificaticn program as per section 2.5.
These examinatiens will be specifically directed toward R0 cr SRO kr.cwledge requi enents and =ay be administered in either closed book or cpen bock for=at, in the classreca er on-shift.
2.2 On-the-jcb-training During the two-year ters of his license, each licensed operator shall participate in on-the-jcb-trair.ing which has the follcwinc scals:
(a) Each licensed reactor cperator and senior operator shall perform er participate in a cecbination of reactivity cent ~ci manipulaticns, as defined in this section of the requalificatien program, based en the availability of plant equip =ent and system.
6.0
1C06
~
Revision 3 07/31/3C (b) Each licensed reactor operator or senior operator shall partici; ate as appropriate, in applicable surveillance testing, system checkout and equipment operation based on license level and relevance to the area of license respons.oility.
1 Normal shift rotation and watch station rotattun within the shift organization assures diversity of experience in the on-the-job training program.
(c) Each licensed reactor operator or senior operator shall review procedure changes, unit modifications, technical specificaticn changes, reportable occurrences and incidents either on-the-job or during sessions of the Requalification Lecture Series.
The following control manipulaticns and plant evolutions are acceptable for meeting the reactivity control manipulaticns required by Appendix A, Paragraph 3.a of 10CFR Part 55. The starred (*) items shall be performed on an annual basis; all other items shall be performed en a two-year cycle. Those control manipulations which are not performed at the plant may be performed on a simulator. Each licensed operator will normally spend cne training week per year at a simulator.
Control manipulations during abnormal cr emergency operat br.s will be performed on the simulator or walked through with, ar.d evaluated by, a member of the training staff at a minimun.
Personnel with senior licenses are credited with these activi-ies if they direct or evaluate control manipulations as they are perfomed.
7.0
1006 Rsvision 3 07'31/80
- (l) Plant or reactor startups to include such a range that reactivity feedback frem nuclear heat addition is noticeable and heatup rate is established.
(2) Plant shutdown.
- (3) Manual control of steam generators and/or feedwater during startup and shutdown.
(4) Boration and/or dilution during power operation.
- (5) Any significant (> 10%) power changes in manual rod control.
(6) Any reactor power change cf 10% or greater where load change is performed with load limit control en manual.
- (7) Loss of coolant including:
1.
Significant PWR steam generator leaks.
2.
Inside and outside primary containment.
3.
Large and small, including leak-rate determination.
4.
Saturated Reactor Coolant response (8) Loss of instrument air (if simulated plant specific).
(9) Loss of electrical power (and/or degraded pcwer scurces).
- (10) Loss of core coolant ficw/ natural circulation.
(11) Loss of condenser vacuum (12) Loss of service water if required for safety.
(13) Loss of shutdewn cooling.
(14) Loss of ccmpenent ccoling system er cooling to an individual component.
(15) Loss of nomal feedwater or normal feedwater system failure.
- (16) Loss of all feedwater (nomal and emergency).
(17) Loss of protective system channel.
8.0
1006 R:visien 3 07/31/20 (18) Mispositioned control red or rods (or rod drops).
(19) Inability to drive control rods.
(20) Conditions requiring use of ~ emergency boration or standby liquid control system.
(21) Fuel cladding frilure or high activity in reactor coolant or off gas.
(22) Turbine or generator trip.
(23) Malfunction of autcmatic control system (s) which affect reactivity.
(24) Malfunction of reactor coolant pressure / volume control system.
(25) Reactor trip.
(26) Main steam line break (inside or outside containment).
(27) Nuclear instrumentation failure (s).
Licensed personnel, whose job assignments are not directly related to unit operations will actively participate in control room operation a minimum of one shift per quarter. During this period these licensed personnel must assume (under instruction) and perform the l
duties of the on shift licensed operator as indicated by completing and forwarding to the Training Department.
2.3 Annual Evaluation Examinaticn Evaluations will be conducted on an annual basis as follows:
(a) An annual written evaluation examination will be given to all licensed operators and, senior operators prior to the completien of each annual cycle.
(b) An annual oral evaluation will be administered to all licensed operators and senior operators prior to completion of each annual cycle.
9.0
4 j
1006 Revision 3 l
07/31/80 The annual written evaluation examination will be administered to all licensed personnel as set forth in the following guidelines:
1.
The examination will simulate the examinatic normally administered by the Nuclear Regulatory Commission.
2.
Reactor Operators will take Sections A through G of the examination while the Senior Reactor Operators will take Section H through L and answer selected questions in Sections A through G.
3.
The examination, examination answers and a grading key will be prepared in advance.
4.
The examination results of each individual will be used te identify specific areas in which retraining is necessary to upgrade that individual's knowledge.
5.
The examination will be administered and graded by a member of the station technical staff, station management staff, training department personnel, consultant, or the NRC.
6.
The persons responsible for the preparation of the examinations and answers will be given credit for passing the examination.
The annual cral evaluation examination, using a checklist, will be administered to all licensed personnel. The oral examination will cover topics from the following areas:
(a) Action in event of abnormal conditions.
(b) Action in event of emergency conditions.
(c) Response to unit transients.
(d)
Instrumentation signal interpretation.
(e) Procedure modificatien.
(f) Unit modifications.
10.0
~.
1006 Revisten 3 07/31/20 (g) Technical specifications.
(h) Emergency plans.
The following standards apply to the~ annual evaluatien examinatiens:
1.
If a license holder scores less than 80% cn any section of the annual written examinatien, the license holder, while attending the applicable requalificatien lecture, will be administered a qui: on that section. A grade of 80% will be recuired as a pa, sing score.
2.
An unsatisfactory evaluatien on the annual oral examination will require that discussiens of deficiencies take place
?
betneen the license holder and either the Manager - Training Unit I, Supervisor -Operator Training, or other suitable qualified person designated by the Director - Training and Operational Safety Support. A second oral evaluation examinatien will be administered. If performance is again unsatisfactory, the license holder will be relieved of responsibilities and placed into an accelerated requalification pregram.
3.
If an individual receives a grade of less than 80% overall er less than 70% cn any single section on the annual examinatien it will be mandatcry that (1) he be relieved of his licensed duties and (2) enter an accelerated requalification program.
Upon (1) successfully passing a second written and cral exa=inatien and (2) certification of satisfactory rating by the Director of Three Mile Island Unit I, the individual will be returned to his licensed duties.
11.0 w
y r-w w---
w
1006 R: vision 3 07/31/80 2.4 Records Records of licensed personnel performance on all written evaluation examinations and quizzes shall be available for NRC examination for the two annual requalification cycles prior to license renewal application.
These records shall include:
1.
Examination and quiz questions.
2.
Answer sheets and grade keys.
3.
Examination papers and work sheets.
Records of participation i,n the Requalificaticn Lecture Program will be available for NRC review for the two annual requalification cycles prior to license renewal applicatien.
These records shall include:
1.
Attendance Records.
2.
Requalification Lecture Content.
3.
Quizzes and exams.
4.
Absences and Makeup Sessions.
Records of annual oral evaluation examinations shall be made available for NRC review for the two annual requalification cycles prior to license renewal application.
?.5 Accelerated Requalification Program An operator who does not clear deficiencies assigned due to performance below standards on either the annual written or oral evaluations will be relieved of responsibilities and enter a full time accelerated requalification program.
t J
12.0
1006 Revision 3 07/31/80 The program duration and content will be dictated by the nature of the deficiency. Program duration will be determined by individual performance. When the license holder is (1) able to satisfactorily pass an equivalent written or oral examination and (2) certification of his satisfactcry rating is completed by the Director of Three Mile Island Unit One, he shall resume his on shift responsibilities.
During the period of accelerated requalification, attendance at the
~
Requalification Lecture Series is required.
2.6 Four Month Absence Program If a licensed person has not actively carried out the functions of his license for a period in excess of four months he shall:
(a) Review all material presented or scheduled to have been presented in the hequalification Lecture Series for the period of inactivity.
(b) Be given an oral examination on the applicable Section of the Requalification Lecture Series and current unit status.
If performance on the oral evaluation is unsatisfactory, the individual will be placed in an Accelerated Requalification Program in accor/ance with Section 2.5.
l Upon receipt of a satisfactory rating the licensed person shall be I
recomended for certification by the Manager - Training Unit I,
(
l Supervisor - Operator Training or other suitably qualified person i
designated by the Director - Training and Operational Safety Support, and approved by the Director of Three Mile Island Unit One.
i 2.7 Newly Licensed Operators Newly licensed operators, upon receipt of their license, shall i
l l
enter the program and participate in the annual program cycle. New l
l operators receiving their NRC license less than six months pricr to 13.0
1006 Revision 3 07/31/80 the annual evaluation examination will be required to attend the Requalification Lecture Programs but will be excused from taking the current annual evaluation examination. Mcwever, they will be responsible for taking all other annual evaluation examinaticns.
3.0 RESPONSIBILITIES - RECUALIFICATION PRCGM'4 ACMINISTRATION 3.1 The Supervisor - Operator Training and his staff are responsible for:
1.
Assigning instructors for the Requalification lecture series.
2.
Determining mandatory upgrading assigrments for individual operators.
~
3.
Assigning deficier$cies, deterr.ining appropriate action to clear deficiencies and clearing deficiencies upon satisfactory ccmpletion of assigned action.
4.
Arranging accelerated requalification progra=s as may be necessary.
5.
Defining oral evaluation procedures.
3.2 The Supervisor - Administrative Support Ser. tion and his staff are responsible for:
1.
Maintaining a:1 records.
2.
Scheduling necessary simulater time.
3.3 The Superviser of Operaticns, Supervisor - Operator Training, or other suitable qualified person designated by the Manager of Training is responsible for:
1.
Evaluation of on-the-job performance of all license holders.
2.
Meeting with license holders who receive unsatisfactory annual evaluatic~. examinatien grades.
14.0
i 1006 Revision 3
'07/31/80 i
3.
Certifying operator qualification when returning from a fcur month absence from operation.
4.
Constructing annual written evaluation examination, answers and grade key in lieu of performance by the NRC.
5.
Grading of the annual written examination in lieu of perfor: ance by the NRC.
?
I 15.0
1006 Revision 3 07/31/80 ATTACHMENT I 0FF SHIFT LICENSED OPERATOR WATCH STANDING 00CUMENTATI'ON I certify that has satisfactorily Off Snift Licensed Operator assumed and performed the SS/SF/CR0 duties under instruction for the (circle one) 11-7/7-3/3-11 shift on (circleone)
Date
?
Shift Supenisor 16.0
. 2 NRC80-69 July 31, 1980 UNIT 2 OPERATOR REQUALIFICATION FROGRAM STATUS All licensed operator requalification training currently being conducted in Unit 2 under the guidelines of the existing Operator Requalification Instruction is being geared to cold shutdown plant operations.
g The existing instruction is undergoing complete revision to increase the scope and focus on training for cleanup and recovery systems and operations of Unit 2
/
Continuing negotiations with the Pennsylvania State University are aimed at establishing training sessions (which include both classroom work and operation of their research reactor) that could serve in lieu of simulator operation, as part of the Requalification Program for Unit 2 operators.
It is felt that the program proposed by Metropolitan Edison Company and currently being scoped by Penn State will more adequately meet the needs of the operators with regards to subject areas such as subcritical multiplication, core voiding, differing fuel geometries, nuclear instrumentation and failure modes, and effects of long term corrosion and high radiation on instrumentation and components, than would the standard simulator programs currently.being conducted to meet the control manipulation and plant evolutions required by the Nuclear Regulatory Commission for on-the-job training. Penn State's Proposal for this type of program is expected in early August.
$U TRAltlIllG DEPARTMENT ADMIflISTRATIVE MEMORAllDUit #5 - CHAHGE #2 3
Mly,31,1980 METROPOLITAN EDISON COMP A N Y se.e c.,,
i w uma c.,,u.,
@)
i Subject CATEGORY IV CR0 TRAltnnG PROGRAM Location TMI Nuclear Station Middletown, Pa.
Date October 8,1975 To J.G. HERBEIfl J.J. COLITZ G.P. 11 ILLER DEPT. HEADS l
Enclosures:
(1) Category IV CR0 Study Assignment Sheet (2) Practical Evolutions Sheet (3) 90 Day CR0 Probationary Period 1.
ilhen an Auxiliary Operator is advanced to Category IV CRO,he will imediately be placed into a Control Room Operator training program. This training program will consist of: (1) Specific study assignments, (2) oral checkouts performs or simulates performing certain in which the individual actually(4) oral examinations and (5) classroom sessions, evolutions, (3) written tests, as et forth in the following:
2.
Upon being advanced to Category IV CRO, the individual will fall icmediately into the Shift organization as it exists at the time.
Two (2) hours, as a-minimum, of each day on shift will be specifically devoted to training. The individual will be provided with a desk or other suitable place to study in the Control Room area. -The two (2) ~hcur period vill occur at a definite time of each day on shift insofar as practical.
3.
At the Mqinning of each shift cycle, 5 or (6 shift), the individual will' be provided with an assignment sheet (see Enclosure 1) which will detail study assignments for the two (2) hour periods for the first 11 (14 ~ working days of his shift cycle. On the 12th (15th) working day, the individual will take a written test covering these assignments, On the 13th (16th) working day, the individual will receive assignments as above to cover the 13th (16th) through 23rd (28th) working days of a shift cycle. On the 24th (29th) working day, the individual will again take a written test. On the 25th (30th) working the individual will take an oral examination covering day,'of a shift cycle,f study.during the shift cycle.specifically a'nd comprehensive the assigned areas o j
of the material covered.;to that date.
4.
The written tests will be corrected and returned. Errors and weak areas will be covered.with the individual,, and reassigned.'
Weak areas on written and oral examinations will be. covered with the individual and his bargaining unit representative, if requested.
Complete failure of a written exam or oral exam will be discussed with the individual and a bargaining unit representative prior to a retest on the material.
Failure of the retest will require a subsequent discussion with the individual and a bargaining unit representative.
s 5.
Add'itionally the Category IV CR0 will be required to complete a Practical Evolutions Sheet (see Enclosure 2). This sheet will be ccmpleted either during the individuals' daily training period,or during other times while on shift as INTER-OFFICE MEMORANDUM
situations dictate. Most of the items on Enclosure 2 involve performing evolutions, simulabing performing evolutions, and understanding and being able to explain while simulating or performing. The individuals' Shift Supervise;, Shift Foreman, an SR0 Licensed individual, or (in specifically designated cases) the licensed Training Coordinator may sign the practical evolution sheet.
6.
Assignments detailed in paragraph 3 above, on which written and oral tests will De given, will come largely from iteas in Enclosure 2 with some assignments specifically intended to obtain signatures on Enclosure 2.
7.
Checkouts for items on Enclosure 2 which must be simulated will be conducted in front of the Control Rocm Consoles and Panels, with the individual being required to point to specific items and controls. The checkout must be satisfactory prior to a signature for the evolution.
The evolutions are assigned a point value to track the progress of an individual through the nine (9) month program.
The required rate of progress is approximately,6 points every 4 working days.
8.
To aid him in preparation for the simulator startup certification and licensing examination, the Category,IV CR0 shall come off shift to attend lectures on specific topics, listed below, as arranged by the Supervisor of Training and the Supervisor of Operations.
TOPIC APPROXIMATE DURATION (HRS) a.
Reactor Theory 40 b.
Heat Transfer, Fluid Flow 32 and Thermodynamics c.
Integrated Control System 16 d.
Recognizing and Mitigating the Consequences of Severe Core Damage 26 e.
Emergency Procedures - Emphasis on Transient Analysis and Safety Analysis 32 f.
Health Physics Review 8
g.
Nuclear Instrumentation 4
h.
Non-Nuclear Inrtrumentation 4
l i.
Control Rod Drive System 9
l
- j. Technical Specifications 8
k.
Reactor Coolant Pumps 4
l 1.
m.
Interlocks 2
n.
Simulator Training (including startup certification) 1 20 I...
9.
The first 90 days of the Category IV CR0 Training Program is designated as a Probationary Period. The individual will be evaluated using Enclosure 3.
At the end of this 90 day period, the Shift Supervisor, Supervisor of Operations and the Supervisor of Training will recommend whether or not the individual should continue in the program.
- 10. Prior to the completion of the 9 months time period foi the program, the Category IV CR0 will be given a comprehensive written examination approved by the Supervisor of Operations and the Supervisor of Training.
The results will be available for review by the Category IV CR0 and a Union designated R. O. Licensed individual. Add-itionally, within the Training Program time period the Category IV CR0 will be given a comprehensive oral examination, by an SR0 licensed individual designated by the Supervisor of Operations. The Category IV CR0 will have the option of having a Union designated, R.0. Licensed individual present duHng the oral examination. Any examination failed, written or oral, will be reviewed with the Category IV CR0 and a bargaining unit representative.
If the Category IV CR0 has successfully completed the above outlined training program, within 9 months, including the comprehensive written and oral examination, the individual may be advanced to Category II CRO.
If the Category i
IV CR0 has not successfully completed the training program, within 9 months, and successfully passes the written and oral examinations, the individual may or may not be advanced to Category II CRO.
If the Category IV CR0 has not successfully completed the program, within 9 months, and fails either the written and/or the oral examination, the individual will be returned to the position held prior to being advanced to Category IV CRO.
If the individual successfully completes i
the training program, within 9 months, and fails either the written or oral examination, a re-exam will be considered based l
upon an evaluation by the Supervisor of Operations and the Supervisor of Training.
A t
S.
L. Newton Group Supervisor Nuclear Tech. Training d4.B4 l
R. W. Zechman Supervisor of Training
. A. Knief Manager - Training l
3LN/RWZ/RAK/ mss l
ENCLOSU:tE 1 CATEGORY IV CR0 STUDY ASSIGi.ENT SHEET NAME:
START DATE:
COMPLETION DATE:
ASSIG!!E!!TS CYCLE HALF i
TOTAL FOI?iTS TO DATE FROM ENCLOSURE 2 i
WRITTE?i TEST DATE RESULTS
~
ORAL TEST DATE RESULTS ANSWEES MISSED. HANDED IN CORRECTED DATE:
51GriATURE OF LICENSED TRAINING COGED.
f
.e-
ENCLOSURE I CATEGORY IV ASSIGilMElli SHEET 1.
The enclosed study assignment sheets indicate those items which are to be completed during each two week period (h cycle).
2.
On the reverse side of each a:signment sheet,there is a list of reference material which may be needed to complete some of these assignments.
3.
For information on specific equipment (pumps, valves, motors, etc.) the technical manual (vendor manual) will be needed. The technical manuals are kept in the TMI Technical Library. Contact the TMI Office Supervisor for information on the use of the library.
O..
v I
EllCLOSURE 2
()
PRACTICAL EVOLUTI0ft SHEET The evolution sheet is an outline of specific items which are reqvired to become a proficient Control Room Operator. The evolutions as to actions reauired for satisfactory completion are coded P, S.,D or (X). '
P - Perform: The evolution has to be carried out by the individual to the satisfaction of the Shift Supervisor, Shift Foreman or the Licensed Training Coordinator as denoted by an asterick.
S - Simulate: The evolution has to be demonstrated, without actually performing it, by the individual to the satisfaction of the Shift Supervisor, Shift Foreman, or Licensed Training Coordinator as denoted by an asterick.
D - Discuss: The individual must show orally that the evolution is understood to the satisfaction of the Shift Supervisor, Shift Foreman, or the Licensed Training Coordinator as denoted by an asterick.
(X) - Performed or Simulates:at Simulator The evolutions are additionally assigned a point value. The Category IV CR0 must receive approximately 6 points every 4 working days to satisfactorily complete the program in the nine month period.
Q The evolutions are preceded by capital letters A,B,C,0,E,F or G to indicate which b
category of an flRC exam they fall. Additionally, the capital letter N is used to denote which proced:;res are sent to the f4RC.
Two Plant Startups, to the poht of adding heat are required prior to application for a license, as well as two shutdowns, (to Hot shutdown).
l l
l l
O 1
O O
O
^
EllCLOSURE'i EVOLUTIONS
' ACTIOrt ' CODE '
, SIGNATURE POINTS ADft1tilSTRATIVE PROCEDURES Docunent Control (1001)
D 1 pt F
Tagging (1002)
P or S A D 2 pts il Radiation Protection Hanval (1003)
SAD 2 nts F/fl Radiation Emergency Plan (1004) (2 volumes)
D 2 pts
- 1 pt
- F Station Organization and Chain of Consnand (1009)
D F
Technical Specification Surveillance Program (1010)
D 1 pt F
Shift Relief and Log Entires (1012)
D, 1 pt F
Dypass and Safety Functions and Jumper Control (1013)
D 1 pt F
Call of Standby Personnel to Plant (1014)
D 1 pth D
1 pt F
Operator at the. Controls (1028)
D 1 pt F
Control of Access to Primary System Openings (1030)
Ef1ERGEllCY A!!D ABil0RMAL PROCEDllRES F/fl LoadRejection(1203-1)(2203-2,1)
P or S & D 2 pts F
'lligh Cation-Cond. In Condensate (1203-5)___ _
D 1 pt F
lland Calc. for ()uad. Power Tilt & Core Power Im-balance (1203-7)(2103-1.11)
P or S A D -
2 pts Industrial Waste Treatment (1104-50A) 9
~
O O
O l
EllCLOSURE 2 EVOLUTIONS
~ ACTI0tl' CODE '
SIGNATURE' POINTS gponse to Penetration of Protected Area D
1 pt F/fl Unanticipated Criticality (1203-10)
(2202-1.2)
S&D 2 pts F/N Loss of Reactor Coolant liakeup (1203-15) (2203-1.5.)
S&D 2 pts F/fl R.C. Punp and Motor Emerge.ncies ('1203-16) (2203-1.4)
S&D 2 pts F/fl RiverllaterFailure(1203-19)(1202-38)(2203-1.7)
S&D 2 pts
- i F/fl
!! SCC System Failure (1203-20 (2203-1.6)
S&D 2 pts
- F/fl SSCC System Failure (1203-21) (2203 'i,,',
S&D 2 pts
- F/P Steam Supply System Rupture (1203-24) (2203-2.3)
S&D 2 pts #
E/fl Post Accident 112 (Purge 1203-28)(Control 22'03-2.6)
D 1 pt I
Class 1E Electrical (2107-1.2)
F Control Room IIVAC (1203-34) (2203-2.5)
D 1 pt F
Vibration and Loose parts (1203-40)(2203-1.8)
D 1 pt Substation (500kv)(2107-1.3)
F/fl Blackout (1202-2/2A) (2202-2.1/2.5)
S&D 3 pts F/fl TurbineTrip(1202-3)(2203-2.2)
P or'S & D 2 pts F/fl
. Reactor Trip (1202-4) (2202-1.1)
P or S & D 2 pts F/il DTSGTubeRupture(1202-5)(2202-2.6)
D 1p F/fl Loss of RC/RC Press. (1202-6) (2202-1.3)
P or S & D 2 pts F/fl Loss of RC Flow /RCP Trip (1202-14) (2202-1.4)
P or S & D 2 pts i
i
l 0
0, 0
EllCLOSURE 2' EVOLUTIONS ~
' ACTI0ll'C0DE '
SIGNATURE POINTS i
F/t!
CRD Equipment Failures (1202-8) (2203-1.'2)
P or S & D 3 pts F/N.
CRD !!alfunction Action (2203-1.3)
P or S & D 2 pts F/N Loss of Baron (2203-1.1).
P or S & D 2 pts l
S&D 2 pts" j
F/fl 111 Activity in Reactor Coolant (1202-11)(2202-l'.6)
F/N ExcessiveRadiationLevels(1202-12)(2202-1.7)
S&D 2 pts" l
F/N Loss of Intermediate Cooling (1202-17) (2202-1.9)
.S & D 2 pts
- F/fl loss of Feed to OTSG (1202-26A/B) (2202-2.2).
3 pts S&D F/N PressurizerFailure(1202-29)(2202-1.5)
S AsD 2 pts F/fl Loss of Decay Heat Removal (1202-35) (2202-1.8)
S&D 2 pts #
l F/N Loss of Instrument Air (1202-36) (2202-2.3)
S&D 2 pts F/H Cooldown Outside Control Room (1202-37) (2202-1.10)
S&D 1r 3 pts
- i
'F/N F1-(1202-31) (2202-3.1)
S&D 3 pts
- i l
F/N Flood (1202-32) (2202-3.2)
D 1 pt F/N
~ Earthquake (1202-30)-(2202-3.3)
- D 1 pt*
4 2
F Alarm Responses S&D 5 pts i
}
0PERATING PROCEDURES N
PlantLimitsandPrecautions(1101-1)(2101~1.1)
D 2 pts N
Plant Setpoints (1101-2)(2101-2.1)
D 2 pts
~
o o
o ENCLOSilRE 2 I
EN0LUTIONS
' ACTI0ti ' CODE '
SIGNATURE POINTS i
C/F/N Plant.lleatup to 5.25 F (1102-1) (2102-1.1)
P,5 (X) 2 pts C/F/fl Plant Startup (1st) (1102-2) (2102-1.3)
P.
(X) 2 pts C/F/fl Plant Startup (2nd)'(1102-2) (2102-1.3)
P,-(X) 2 pts l
C/F/fl Power Operation (1102 T) (2102-2.1)
P 2 pts 1
C/F/fl Plant Shutdown (1st) (1102-10) (2102-3.1)
.P.
(X) 2 pts C/F/N Plant Shutdown (2nd) (1102-10) (2102-3.1)
P, -(X) 2 pts C/F/N Plant Cooldown (1102-11) (2102-3.2).
P,S 2 pts i
C/F/fl PressurizerOperat?on(1103-5)(2103-1.3)
P, 1 pt C/F/fl ReactorCoolantPumpOperation(1103-6)(2103-1.4)
P,S f. D 1 pt l
C/F/tl Approach To Criticality (1103-8) (2102-1.2)
P (X) 2 pts' 4
C/fl lleat Balance Calculation (Comouter)(1103-16)(2103-1.1 3)
- C/N lleat Balance Calculation (lland) (1103-16)(2103-1.10)~
- C/fl Reactivity Balance (ECP)(1103-15)(2103-1.9)
- C/fl Reactivity Galance (Pwr Change)(1103-15)(2103-1.9)
C/N
' Reactivity Balance _(Boron Change)(1103-15)(2103-1.9)
- i C/F Reactivity Balance (SDM) (1103-15) (2103-1.9)
- i i
E/il
. Core Flood System (1104-1) (2104-1.1)
P:or S or D 1 pt *
~
E/N tiakeup and Pur'ification (1104-2) (2104-1.2)
P&D 2 pts 4
O O
O
~
l El! CLOSURE 2 1
EV0LUTI0tlS
' ACTI0rl' CODE '
ifGNATURE POINTS 2 pts l
E/fl Decay lleat Removal (1104-4) (2104-1.3)
P&D B/F/N Decay lleat Closed (1104-13) (2104-3.3)
P&D 2 pts" 4
4 8/F/il Decay lleat River (1104-32)
P&D 2 pts E/fl Reactor Building Spray (1104-5) (2104-1.4)
P&D 2 pts B/F/N Spent Fuel Cooling (1104-6) (2104-1.5)
P&D 2 pts
- l B/F/fl Intemediate Cooling (1104-8) (2104-1.6)
P&D 2 pts
- B/F/fl Circulating Water (1104-9) (2104-3.6)
P&D 2 pts D/F/N fluclear Services Closed (1104-11) (2104-3.2)
S a'D 2 pts
- i fluclear Services River (1104-30) (2104-3.1)
P&D 2 pts
- B/F/fl B/F/fl Secondary Services Closed (1104-12) (2104-3.5)
P&D 2 pts
- B/F/fl SecondaryServicesRiver(1104-31)(2104-3.4)
P&D 2 pts
- 1 B/F/N Instrument Air (1104-25) (2104-2.3)
P&D 2 pts B/F/N StationServiceAir(1104-42)(2104-2.10)
P&D 2 pts i
B/F/fl Reactor Bldg. Emerg. Cooling River Water (1104-38)
P&D 2 pts *
)
B Reactor Bldg Ventilation (1104-14A-F) (2104-5.1)
S&D 2 pts
- l B/F/ft fluclear Plant Sampling (1104-43) (2104-1.11)
D 1 pt B/F/fl SecondaryPlantSampling(1104-44)(2104-2.8)
D 1 pt C/fl Bleed and Feed Process (1104-29E)
P or S & D 2 pts i
O O
O
~
ENCLOSllRE 2 EVOLUTIONS
~ ACTI0tt ' CODE '
SIGNATURE POINTS E/N Fire.frotection (1104-45) (2104-6.'l)
S&D 3 pts 1
B/F/G/N Radwaste (1104-27,28,29 A/B/C/D/E/I/P/S)
(UnitI)
D 6 pts 8/F/G/N Radwaste(2104-4.1/2/3/4/5/6)
(UnitII)
,D 6 pts D/N Nuclear Instrumentation (1105-1) (2105-1.1)
S&D 2 pts" D/N flon-iluclear Instrumentation (1105-6 (2105-1.6)
S&D 2 pts" D/N RPS (1105-2)(2105-1.2)
S&D 2 pts E/N Safeguards Actuation (1105-3) (2105-1,3)
S&D 2 pts D/N Incore Honitoring (1105-5) (2105-1.5)
S&D 2 pts G/N Radiation Monitoring (1105-8) (2105-1.8)
S&D 2 pts' D/N ICS (1105-4) (2105-1.4)
P&D 3 pts D/N Control Rod Drive (1105-9) (2105-1.9)
P&D 3 pts D/fl Computer;-(1105-10) (2105-1.10)
D 1 pt j
R/f/N Turbine Generator (1106-1) (2106-3.1)
P&D 3 pts B/F llydrogenSealOil(1106-8)(2106-3.3)
D 1 pt" B/F
' Turbine Lube Oil (1106-9) (2106-3.2)
D I pti B/F Stator Cooling (1106-7)
D I pt" B/F EllC(1106-17)(2106-3.4)
D 1 pt HOP El'ctrical (2107-1.1)
D I pt i
e
O O
O DICLOSURE f EVOLUTI0tlS
' ACTION ~ CODE' '
SIGNATURE POIllTS B/F Isolated Phase Bus Duct Cooling (1106-11)(2106-3.6)
D 1 pt B/F Condensate (1106-2) (2106-2.1)
P&D 3 pts B/F Cond. Polishing (Powdex) (1106-13) (2106-2.2)
D' 1 pt B/F Condenser Air Removal (1106-15)(2106-2.3)
D 1 pt*
B/F Feeduater (1106-3) (2106-2.4)
P&D 3 pts 1
B/F OTSG Fill, Drain, Layup (1106-16)(2106-2.5)
D 1 pt B/F
?'xiliarySteam(1106-4)(2106-1.3)
D 1 pti B/F Gland Steam (1106-10) (2106-1.4)
D 1 pt B/F Extraction Steam, lleater. Vents & Drains.(1105-12).
D 1 pt (2106-1.2)
B/F fiain Steam (Reheat) (1106-14) (2106-1.1)
D 1 pt B/F TurbineBypass(1106-5)(2106-1.5)
S&D 2 pts E
Emergency Feed (1106-6) (2104-6.3)
S&D 2 pts B
!!onnal Electrical System (1107-1)
D 1 pti B
. Component Electrical (Panel) (1107-4/5)
D 1 pt l
B Emergency Electrical (1107-2)
D 1 pt B/E
_ Diesel Generator (1107-3) (2104-6.2)
P or S & D
~
3 pts B
Vibration Loose Parts (1105-14) (2105-1.13)
D 1 pt Soluable Poison Control'(1103-4) (2103-1.2)
P&D 3 pts
O O
O EllCLOSURE 2 EVOLUTI0liS
'ACTI0ff CODE' SIGNATURE P0ltJTS Unit Ventilation (Misc. Procedures) 0 1 pt Chlorination (Chem Treatment)
RiverWater(1104-36)(2104-3.9)
D 1 pt Circulating Water (1104-35) (2104-3.10)
D 1 pt Water Chemistry Control (2103-1.7)
D 1 pt Environmental Barrier System (2104-1.8)
D 1 pt I
CO2 Fire System (1104-66)
D 1 pt R.B. Atmosphere Cleanup (1104-55)
D, I pt l
Control Tower Vent (1104-19) (2104-5.4)
D 1 pt Fluid Block (1104-20)
D 1 pt PenetrationPressurization(1104-21)
D 1 pt P or S & D 2 pts Reactor Building Purge (1102-14) (2102-4.1) 112AdditionandDegas(1102-12)(2103-1.5)
P or S & D 2 pts Decay Heat Removal by OTSG (1102-13) (2102-3.3)
S.D 2 pts
.)lEALTil P!!YSICS G/N
. Radiation Dose Survey (1602)
D 1 pt G/N Neutron Survey (1603)
D I pt G/N Alpha Survey (1604)
D 1 pt
==
.=.
~
i O
O O
i EllCLOSURE 2
/:
,i EVOLUT10 tis ACTION' CODE' SIGNATHRE POINTS N
i G/N Surface Contamination (1609)
D 1 pt -
G/N Est. and Posting Areas (1610)
D 1 pt G/N Radiation Work Permit (1613)
P&D 2 pts D
1 pt f
G/N Use of Respiratory Protection Devices (1616)
G/N RadiationEmergencyProcedure(EmergencyPlan)
D 1 pt (1670.1)(1670.2)(1670.3 1 pt Control of Contaminated)Spil's (1681) j D
G/N 4
G/N UseofProtectiveClothing(1686)
D 1 pt Industrial Waste Treatment (1104-50A)
. s Release of Radioactive Liquid (1621)(1621.1) j Release of !!adioactive Gas (1622)(1622.2)
~
i OTHER B/F Technical Specification Test P
19 pts
- A Reactor Theory Test P
10 pts *
- l G
Radiation Control Test P
10 pts
- i 10 pts
- F
. Refueling Test P
)
l Startup Certification P(X) 10 pts
- i 1
l
.i O
so oey CR0 Probationary Period h
O 9
9 O
a e
O
j i
Use of 90 Day probationary Rating Sheet To be used as a guide for the Cat. IV CRO's, Shift Supervisor and Supervisor of Operations to detemine:
1.
Progress of the Individual (Cat. IV CRO) that is documented, and 2.
Identify the weak areas of the individual (Cat. IV CRO), and 3.
Assess the compatibility of the individual (Cat. IV CRO) with the job,and 4.) Supply more specific infomation to the Supervisor completing the 30, 60, and 90 day evaluations.
All of the areas of evhluation are job related and performance related for a Cat IV CRO. The month blocks (first, second, third) for the areas of evaluation are completed with an evaluation mark and the initials of the shift supervisor, shiftforeman or training co-ordinator (denoted by*). The marks for evaluation are:1.) N/A - does not apply 2.) SAT - Satisfactory - this denotes that the Cat. IV CR0 is progressing nomally, understands the area of evaluation, can discuss the area of evaluation, and can physically perform evaluations under supervision.
3.) UNSAT-Unsatisfactory - this denotes that the Cat. IV CR0 is not progressing, does not understand area of evaluation, cannot discuss area of evaluation and has difficulty with physically performing evolutions under supervision.
4.) !MRG - Marginal - this denotes that the Cat. IV CR0 is progressing but
{-
slowly, is weak in understanding of area of evaluation, has scme difficulty in discussing area of evaluation and has some difficulty with physically perfoming evolutions under supervision.
NOTE: All narks of UNSAT. and !%RG. will require remarks on additional paper and attached to probationary rating sheet. This is to specifically identify the problems in the area of evaluation.
l The block labeled "overall" is to be used by the Supervisor of Operations, Shift Supervisor and the Training Dept. Head of components on areas of evaluation 1
1
1 Cat. IV 90 Day Probationary 1(ating bnecc l
Hame:
Area of Evaluation First!!onth Second Month Third Month OVERALL
- 1. Console Operations' C0ijMEt!TS:
- a. Manual Dexterity
- b. Control Location
- c. Instrument Interpretation
- d. Alarm Response
- e. Basic Operation ICS
- f. Basic Operation Diamond
- 9. Dasic Operation PI Panel II. Leadership COMMENTS:
- a. Directing Aux. Operators
- b. Planning Work
- c. Interface with SF & SS
- d. Decision Making COMMENTS:
III. Ilealth Physics
- a. Basic IIP Concepts
- b. Basic !!P Inst. Concepts
- c. Basic RMS Knowledge t
O e
O e
9 1
Cat. IV CR0 90 Day Prebationary Rating Sheet Area of Evaluation.*
First Month Second Month Third 11onth OVERALL
~
IV. Operating Awareness C0lWErlTS:
- a. Standing Orders
- b. Operations Memos
- c. Revision Review Book
- d. Evolutions Book (0JT)
- e. Tech Specs. Sect. III
- f. Tech Specs. Sect. IV
- g. Tech Specs. " Appendix B" V. Cat. IV CR0 Training C0tmEtiTS:
- a.1st cycle.lst half s
- b.1st cycle 2nd half
's
- c. 2nd cycle 1st half
- d. 2no cycle 2nd half
- e. Cat. IV CR0 Program Encl. 2 VI. Surveillance C0rHEllTS:
i
- a. Tech Spec.
- b. Other 8
O O
s i
~
- o
~
I V
V A
~
I I
r
.X e
I.
I a
I
.b.a O
C o
t d
.c
.b
.a aI.
o f
h
.b
. n m
EF e
l l r
t C G
F D p E
eo L
(Ee a
r u
i u v
mw o
Pfg l
o n
s t
a e
c rfr c u
c p
e l
nP a
ie a u p
t l
r u
t r t
mc t l
s i a a
ai i
at e a o
y O t
rn o
rs d t n
s p i
yt n
y i
s e
o s
oP o r
n E
o
- nl n a
l f
a s it e
SPn c
E el t P
o t
q ca e
h r
u onO r i
i ntp f
c p
d e o a
m a
r r l
e r
a m
~
n y
t e
sa t
)
i d
o
,s n
n F
u ir su s
t w
M a
o u
n t
v h
o y
e u
o u
u
.u v.
S e
c o
n d
~
M o
n t
a h
T h
ird M
on t
h O
C C
C V
O O
O E
M M
M P
M M
M A
E E
E L
N N
N L
o T
T T
S S
S lil
,!j; L
,!i i[!!!!
li!
l
'![
! !i[t l[
t!i
(
~
l'
s
,90 Day Probation Recomendation Sheet
, ; P.
i I
do do not recomend individual'to continue with Cat IV CR0 l_
Training Shift Supervisor Coments:
I do do not approve recomendation of Shif t Supervisor.
i
,u l
Supervisor of Operations Coments:
I
~
9 O
Cat. IV 90 Day Probationary Rating Sheet " Area of Evaluation" Requirement O
Guidelines.
I.
Console Operations a) Manual Dexterity
-Capable of Operation of various systen controls:
(1. Pistol grip control for pump breakers, feeder breakers, etc.,
2.
Push button controls for valves and tests, 3.
Dial controls for voltage.and setpoint adjustment, 4.
Toggle switch for ICS cnntrol)
-Capable of changing paper on recorders.
b) Control Location
-Knows location of valve pump controls in control room (responsible for controls for systems on which he is checked out)
-Has knowledge of controls in the plant (especially those with redundant controls in control room) c) Instrument Interpretation
-Capable of reading instruments accurately
-Capable of judging trends as normal or abnomal
- (special attention should be paid to CRO's ability to interpret source,
{
intemediate, power range, and P'tS Indications).
d) Alarm Response'
-For common alarms knows the required actions (e.g. Neutralizing tank pH Hi/Lo is a conmon alarm)
-Also knows required actions for such things as turb. trip, RX trip
-For uncommon alarms knows where to find required actions (e.g.Generatorgroundisnotacommonalarm)
(i.e. How to use alarm responses) e) Basic Operation of ICS
-Knows whether or not plant will increase or decrease output with-manual adjustment of specific Baily Controls.
-Know what tracking is and what it does.
f) Basic Operation of Diamond Panel
~
-Understands panel operation such that CR0 is capable of,
-Imbalance correction, single rod or group movement
-Can perfom startup under supervision
-Can talk through lights on diamond panel g) Basic Operation of PI Panel
-Knows difference between the two indications available
-Knows how to reset RPI
{
-Knows what red, white, green and amber lights imply c,.... - _ _
-..m
...c
II.
Leadership d
a)
Directing Aux. Operators:
-Can comand needed respect frem AO's
-Can get AO's to accomplish necessary jobs
-Uses tact in dealing with AO's b) Planning work:
Is capable of scheduling work to accomplish it in the alotted time c) Interface ith SF & SS:
-Compatibility with supervisors
-Able to receive and transmit supervisors orders d) Decision Making:
-!!akes decisions that ar'e fair and displays confidence in sticking to the,
decisions
-Is able to react to adverse conditions with. rationality III.
Health Physics a)
Basic HP Concepts:
-Knowledge of radiation
-Radiation areas
-Requirement for RWP's
-Use of protective clothing,) effects of radiation { particulate & gu)
Beta, Ga. a, Alpha, fleutron m
O -" --
b)
Basic HP Instrument Concepts:
-Knows how the different portable detection instruments function and when to use them
-Knows function of TLD, Film Badge, Dosimeter and how they work c)
Basic RMS Knowledge:
-Knows locations of Radiation Monitors and types (liquid, area, gama)
-Knows how Pfl5 detectors and what respective trends indicate
-Has basic idea of trips that can be received frem the Plis and how to bypass the trips.
IV.
Operating Awareness a)
Standing Orders:
-Is signed off and up to date
~
-Understands the standing orders b)
Operations memos:
-Is signed off and up to date
-Understands the meaning of applicable operating memos c)
Revision Review Book:
-Is signed off and up to date
-Is aware of the changes and their effect on the CP,0 operating the plant Oc d)
Evolution Book (0JT)
-Has evolutions such as reactively manipulations, turbine startup, etc.
recorded and signed off
Q e.
e)
Tech Specs Sect. III
-Knows what areas these Tech Specs cover and effects on Plant Operation f)
Tech Specs Sect. IV Knows the areas covered in this section Note: The same depth of Tech. Spec. knowledge is not required at the end of 3 months as would be required at the end of the training program.
V.
Cat. IV CR0 Training a) ist Cycle 1st Half
-Completes required asr.igned material and ccepletes test b) ist Cycle 2nd Half
=
-Ccmpletes required assigned material and test c) 2nd Cycle 1st Half
-Completes required assigned material and test d) 2nd Cycle 2nd. Half Completes required assigned material and tests e)
Cat IV CR0 Program Enclosure 2
-Obtains signatures for procedures / systems on which the SF/SS/ training c - rdinat r feel his knowlege is acceptable.
t9*
(The signature is obtained after oral examination on procedure / system with SF/SS/TC. Rate of progress on practical evolutions should approximate that specified on the Cat. IV CR0 Training Program).
VI.
Surveillance a)
Tech Spec
-Awareness of the surveillance requirements and their effects on the plant
-Participates in surveillance as applicable VII.
Computer Operation a) Displays
-Can display points and groups b)
Functions
-Knows what the various functions will give him (eg single point log, add point to group, etc.)
-Knows how to add and delete points to scan c)
Groups:
-Knows how to use groups and what they tell CR0 d)
Calucations Performed
-Capable of using computer for calculations of leak rate, heat balance, Reactivity Balance, etc.
l
.y
-.r---
,-