ML19330B732

Topical Rept T2-80, Operator Training Program for NRC Licensed Operator Retraining Program

ML19330B732
Person / Time
Site:	Rancho Seco
Issue date:	07/24/1980
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML19330B720	List: ML19330B719 ML19330B723 ML19330B732
References
T2-80, NUDOCS 8008050429
Download: ML19330B732 (11)

Text

{{#Wiki_filter:-. (~ L) TOPICAL REPORT T2-80 SACRAMENTC MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION OPERATOR TRAINING PROGR.VI FOR NRC LICENSED OPERATOR REIRAINING PROGRAM 8 C08050 NY t

1.0 ' PURPOSE-LTha -purpose of this procedure' is to formally establish the programs, responsibilities and. requirements for the requalifications of NRC . Licensed Senior Operators and Reactor Operators at the Rancho Seco Nucicar Generating Station, Unit 1. The programs and, contents. established by this plan shall be enforced and adhered to for the life of the plant. This program is established ~to meet.the requirements of Appendix A of 10 CFR $5 necessary for renewal of licenses in accordance with Section 55.33 of 10 CFR 55. This requalification program is subject to approval by the Nuclear Regulatory Commission. In accordance with 10 CFR 50.54 (i-1), no changes shall'be made in this program to reduce che scope or time allotted without prior approval by the NRC. 2.0

REFERENCES

.1 ANSI /ANS 3.1 - 1978, Selection and Training of Nuclear Power Plant Personnel .2 10 CFR 50, Licensing of Production and Utilization Facilities .3 10 CFR 55, Operators' Licenses 3.0 DEFINITIONS .-The following definitions are extracted from 10 CFR 55.4. (" Simulator" and " Simulate" are derived from 10 CFR 55, Appendix A, Section 4.d.) .1 " Facility" means any production facility or utilization facility .as defined per 10 CFR 50.2; namely, " Utilization Facility" which means any: nuclear reactor other than one designed or used primarily for the formation of_ plutonium U-223. .2 " Operator" is an individual'who nanipulates controls of a facility. Anf ndividual is deemed to manipulate a centrol if he i directs another to manipulate a control. .3 " Senior Operator" is an' individual desicnated by a facility ' licensee under 10 CFR 50, to direct the licensed activities of ' licensed operators. ~, .4 " Controls" when used with resnect-to a nuclear reactor, means apparatus _and mechanisms, the canipulation of which directly. affect l the reactivity or power level of the reactor. ~

1 3.0 DEFINITIONS (Continued) .5 "Siculator," a working model of the control room sinilar to the plant for which an individual is licensed or is a candidate for license, nay be considered a "si=ulator" provided it reproduces the general operating characteristics of the plant with similar arrange en's of instrumentation and controls. t .6 "Si=ulate," when an individual performs a valk-through of actions to be taken, using the control panel involved, discussing each step without actually operating any centrols, he has "si=ulated" the operation. This method is used as a means of teaching or reviewing actions required by an emergency or abnormal condition. 4.0 PROGR.Ut REQUIRDIEES .1 Schedule The requalification progra shall be conducted for a continuous period not to exceed two years. Successive requalification programs using generally the same for=at and schedule shall follow the first in a continuous cycle of two-year programs. .2 lectures The requalification progran shall include preplanne.d lectures to be given throughout the two-year period. Lectures will nor= ally be scheduled to average sixty hours per man to accommodate all licensed operating personnel during the requalification program cycle; however, the schedule may take into consideration heavy i vacation periods and infrequent operations such as refueling periods and forced outages. Lectures may be deferred due to unsaticipated shutdowns, but shall, be conducted as soon as practicable ~ thereaf ter. Lectures may consist of preplanned supervised classroom discussions'or seminars. Films, video tapes, prograt=ed instruction and other effective training aids =ay be used to supplement lectures; however, an instructor shall participate in at least thirty hours of the lecture-series. Lecture content shall take into consideration the following: .1 Theory and Principles of Operation .2 General and Specific Plant Operating Characteristics ,3 Plant Instrur.entation and Contral Syste=s .4 Plant Protection Systems . S' Engineered safety Systems-. a-

~ -4.0-PROGR.V!- EEQUIRCtESTS. (Continued) - ;2 .6 Normal, Casualty and Emergency Operating Procedures .7 Radiation Control and Safety .8' ' Technical Specifications .9' . Applicable portions of Title'10, Chapter 1 Code of Federal Regulations e .10 Principles of[ Feat Transfer, Fluid Flow and Thermodynamics .11 . Operating Experiences from Similar Plant such as TMI-2 and Lessons. Learned .12 Mitigation of Accidents Involving a Degraded Core .13-Results of Annual Examinations .3 On-the-Job.Traininc The requalification program shall include on-the-job training consisting of: .1 Control Manipulations Each Licensed Senior 0perator and Operator shall participate as much as possible'in plant control manipulations involving reactivity changes to demonstrate his/her skilland/or familiarity with reactivity control systems. ' delineates the control manipula-tions required by. Appendix A, Paragraph.-34 of 10 CFR 55. ~ .2 Simulator Training Each licensed Senior Operator and Operator shall participate ,in simulator training during the term of his/her license. ,A simulator shall be used in meeting the requirements of Section 4.3.1 above for evolutions not performed at the plant. .3 Procedure Revicu Training .1 - Each. operator shall' review the contents of' all emergency, casualty and applicable security' procedures at least once per retraining cycle. .2 Applicable -training methods are described. in Section 4.4. Training in this. area shall be included in the pre-planned schedule of the retrainiag. cycle.. 4V 7 .A

~ 4.0 - PROGRAM REQUIRC!E::TS (Continued) .3- .4 Other Areas-of Training .1 Training of topics that cannot usually be pre-planned as part of the retraining cycle will be conducted as necessary to ensure each Licensed Senior Operator or ~ Operator is cognizant of: .1 Facility Design Changes .2 Procedure Changes .3 Facility License Changes .4 ~ Applicable Operating Experiences. .2 Acceptable training methods are described in Section 4.4. .4 Miscellaneous Trainine "ethods .1-Training in addition to the pre-planned lectures per 4.2 may be conducted.to supplement the scheduled lectures or to conduct training on other areas outlined in Section

4. 3. 3 cnd 4. 3.4.

.2' Acceptable methods used for this training may include, but are not limited to: .1 Brief lectures conducted by the Shift Supervisor or other appropriate personnel. .2 Staff Meeting .3 Written communications'to each licensed individual from facility management. .4 Explanation of major changes as part of the pre-planned . lecture series. '. 5 Supervised discussion. .5' Evaluation and observation The requalification program shall11nclude an evaluation and observation system to obtain the maximum benefits from the retraining program and as a method to' determine areas in which retraining is needed. The evaluations and observations will be conducted by the Training Supervisor or his. designated repre-sentative. ,r e a

. 4'. 0 L PROGR.e! REQUIRD:E:"IS (Continued) - .5 -(Continued) Licensed senior Ocerators or Operators may be assigned to one or _more examination; groups and the annual examinations for their groups are conducted on different datos. Individuals may be shifted'between groups and individuals receiving an initial license may be placed in any group as long as the period between ' annual examinations or between the license effective date and the first annual examination does not exceed thirteen (13) months. It is.not; required'that the individual (s) preparing or reviewing the examination (up to a maximum of 3) also take the examination. The examination and observation process shall include: .1 Annual 1.'ritten Exams .1 Written examinations shall be administered,at 11 to 13-month intervals, depending on plant scheduling. The examination shall folicw the guidelines of 10 CFR'55 Appendix A and vill be used as a system to determine licensed operator and senior operator knowledg3 of subjoets covered in the requalification program; normal, abnormal and emergency procedures; and as a method to determine areas in which retraining .is needed to upgrade licensed operator and senior operator knowledge. .2 An operator scoring above S0% in all sections of the annual requalification examination shall not be required to attend further requalification lectures until the next annual requalification examination. Other operators may be excused from lectures in subjects for which they scored above 80% but shall be required to attend lectures on all other topics. -If'in.the opinion of the Plant Superintendent, an -individual has justifiable cause, such as sickness or emergency shift coverage, the individual may be excused from the required assigned lectures up to a -maximum of 20% of the allotted total lecture time. The individual shall be assigned reading material on a scif-studying basis to fulfill missed lecture time. f -S-O'

L L - 4.0

PROGRA:f REQUIRE"E:TS. (Continued)'

.5 1

.3 If an individual receives a less-than-passing grade

~ (less than 80% overall or less than.70% in any category), the individual will be administered an oral examination within two -(2) wecks. If the results of the. oral' examination confir= the results.of the I written examination, the individual shall not' perform his licensed duties until such time as additional training.is administered through an accelerated-training program and an examination is. administered .to indicate that he is capable of such performance in a safe'and efficient manner. If an individpal is unsuccessful-on.the annual written examination, but is allowed to continue operation' based on the results of the oral examination, within six (6) weeks of the original examination,a written re-examination shall be successfully completed or the individual shall be removed from licensed duties until such time as additional training through an accelerate'd training program and examination indicate that he is capable of such performance in a safe and efficient manner. The scope, duration and type of accelerated program and examination shall be determined on a case-by-case basis as the need arises. .4 A second annual written examination shall be l-a'dministered to all Licensed Senior Operators and. L Operaters and shall be similar in content to the l first annual' written examination. The results of the L written examinations shall be used by the Training l Supervisor or his ' designated representative in l. designing the next two-year cycle requalification program. .2 Quizzes i j' .From time to time, written qui::es will be administered [ to. determine the Licensed Operator and Senior Operator's knowledge of particular subjects covered in lectures or . specific reading assignments. Any individual scoring less than 80% on a' quit shall roccive additional training in. l the weak areas until sufficient knowledge is obtained as evidenced by a requi: or an oral evaluation. l .3 ' Observations . Systematic observation and evaluation of the performance-L 'and competency of Licensed Senior Operators and Operators will be made by the Training Supervisor or his designated representative. ~ -{- 4 6 u_

j ve 4.0 PROGRA!! REQUIRE *!E TS (Continued) .5. .3 (Continued) Such observations should also include evaluations including actions taken during actual or simulated abnormal and emergency conditions. .1 Each' Licensed Senior Operator or Operator shall participate in an annual oral examination with the Training Supervisor or his designated representative. The examination and evaluation shall consist of: 1 A discussion of required actions during abnor=al and emergency conditions. .2 A simulation of abnormal and emergency conditions while in the Control Room showing ca.h_ action and controlling device to be operated. .2 Should the performance of the Licensed Senior Operator or Operator be deemed unsatisfactory, the Senior Operator or Operator will participate in an accelerated review program tailored to place emphasis where there is a clear indication of need. .3 Upon completion of the accelerated review program, the indi,vidual shall be subject to re-examination. .6 Records and Documentation. .l. Training files shall be maintained in format that is auditable to verify that retraining is conducted in accordance with this ~ requalification program and shall meer the requirements of Appendix A, Paragraph 5 of 10 CFR 55. -.2 Records and documentation shall be in accordance with Administrative Procedures. .7 Inactive License .1 Pursuant to 10 CFR 55.31(c), any licensed Senior Operator or Operator who has not been actively performing the functions of an Operator er Senior Operator for a period of four (4) months or longer shall, prior. to resuming licensed activities, complete the following requirements to demonstrate satisfactory knowledge and understanding of ~ facility. operations and administration by: ~. l 7-O e g y e

N. . *~ d 4.0 PROGRMI REQUIRDIEh"IS '(Continued) .7- .1- .1 Complete all individual study assignments made during -the period of his absence. .2 ~ Review all significant changes to operating procedures, license changes, plant design changes and special orders for the period of. his absence. .3 Meet with the Training Supervisor or his designated representative to cover the material in all requalification lectures for which attendance was ' required but missed. .4 Successfully complete an oral examination and evaluation approved by the Plant Superintendent to demonstrate that his knowledge and understanding of the facility is satisfactory. .5 The. Plant Supedntendent must certify to the NRC that the Senior Operator or Operator is requalified. Approval must be received from the NRC that the Senior Operator or Operator's requalificatica is satisfactory . before resuming activities for which he is licen. sed. .8 Instructors Instructors who provide instruction in systems, integrated response and transients related to the safety system shall be Licensed Senior. Operators. For instruction where the instructors who have expertise in the above are not licensed, a Licensed Senior Operator s, hall be present to audit and approve the training-for consistency and accuracy. 5.0 ' ENCLOSURE .1 CONTROL MANIPULATIONS e e _ a_, 9 4

ENCLOSL'RE 5.1 CONTROL MANIPL'LATIONS ' The following control canipulations and plant evolutions where applicable to ' plant design are acecptabic-for =ee' ting the reactivity control manipulations ~ required by Appendix-A, Paragraph ~ 3.a of 10 CFR Part 55. The starred items shall be perforted on an annual basis: all other itens shall be performed on - a two-year cycle. Each. individual shall perform or participate in a combination of.reacti'tity control =anipulations based _on the availability of plant equipment zad systees. Those control nanipulations which are not performed at the plant may be'perferred on a simulator..The use of the Technical Specifications should be en '-fred:during the siculator control manipulations. Personnel with senior licenses are credited with these activities if they direct or evaluate' control manipulations as they are perforced.

• l.

Plant er. reactor startups to include a range that reactivity feed,ack from ncelear heat addition is noticeable and hestup rate is established. 2. Plant shutdown. 3. Manual control of steam generators andor feedwater during startup and shutdcun. 4. Ecratien and/or dilutien during power operation.

• 5.

Any significant (>10%) power change in manual rod control. 6. Any reactor power change of 10% or greater where load chenge is performed with load limit control on manual.

• 7.

Loss of coolant including:

1) Significant steam generator leaks.

l ~2) Inside and outside primary containment.

3) Large and. small, including leak-rate determination.

1

4) -Saturated' Reactor Coolant response.

. 8. . Loss,of electrical power (and/or. degraded power sources).

• 9.. Loss of. core. coolant flow / natural circulation.

10. Loss of: condenser vacuum. 11. Loss of shutdown cooling.

• s.

- ENCLOSURE 5.1.(Continued) * . 12. Loss of -compone'nt cooling system or. cooling -to an individual component.

13.. Loss of normal: feedwater or normal 'feedwater system failure.

• 14;- Loss of all feedwater (normal 'and emergency).

15; L oss of protective system channel. L

16..Mispositione'd-control; rod or rods (or rod drops).

- 17. ;Insbility to drive control rods.

18. l Conditions. requiring use of emergency boration.

5 10 --Fuel'eladding' fail're or high activity in reactor coolant. u

20. Turbine' or generator trip.

21, 2hifunction of automatic control system (s) which af fect reactivity.

22.. Malfunction of reactor coolant pressure / volume control system.

23.. Reactor trip.

24. Main steam line break -(inside or outside containment).

25.

uclear instrumentation failure (s).

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