ML20096D739

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Rev 3 to Procedure Sp 12.014.07, Licensed Operator Requalification Program
ML20096D739
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 08/10/1984
From: Rose J, Rotthamp K
LONG ISLAND LIGHTING CO.
To:
Shared Package
ML20096D735 List:
References
SP-12.014.07, NUDOCS 8409060269
Download: ML20096D739 (19)
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TPC TPC TPC p- LICENSED OPERATOR REQUALIFICATION PROGRAM 1.0 PURPOSE To establish a method of implementation for the licensed operator requalification program.

2.0 RESPONSIBILITY-The Nuclear Plant Training Supervisor shall be responsible for ensuring proper implementation of the requirements set forth by this procedure.

SR2-1021.199-6.421 L

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3.0' DISCUSSION 3.1 Periodic requalification for all operators and senior operators is

,necessary for'the personnel to maintain competence, particularly to 1 r espond to abnormal and emergency situations.

3.2- This proccJure describes the method to periodically relicense NRC licensed ~

Reactor Operators (RO's) and Senior Reactor Operators (SRO's), and to meet the requirements of References 11.1~ 11.2, and 11.3. ,

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.3.3- ' Licensed RO's and SRO's_who have been actively and extensively engaged as

-RO's or SRO's shall participate in the requalification program.

Individuals who maintain R0/SRO licenses for the purpose of providing backup capability 'to the operating staff shall also participate in the requalification program.

3.4 Definitions related to the SNPS Licensed Operator Requalification Program are contained in Appendix 12.1.

3.5 The following topics are contained in this procedure:

P_ age 8.1 Schedule 3

< .8.2 Lectures 3 8.3 On-the-job Training 4

- 8.4 - Evaluations- 7 8.5 Administration of Requalification Examination 8

8.6 Records 8 4

Appendix 12.1 -- SNPS Requalification Program Definitions Appendix 12.2 '- SNPS Requalification Control Manipulations Appendix 12.3 -. Drill Scenario Form Appendix 12.4 - Administration of Requalification Exams f][

~ Appendix 12.5 --Time on Shift Record for Backup License Holders

. 4.0 ' - PREREQU ISITES N/A 5.0 PRECAUTIONS N/A' 6.0 LIMITATIONS-AND ACTIONS N/A 7.0 MATERIALS AND/OR TEST EQUIPMENT N/A  :.

SP 12.014.07 Rev. 3 Page 2 l

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1 "8.0 PROCEDURE i.

8.1 -Schedule 8.1.1 The SNPS Licensed Operator Requalification Program shall be 4 repetitive and completed on a one year basis, resulting in license l renewal every two years. The program shall consist of preplanned j

' classroom lectures, on-the-job training, simulator training, plant '

  • drills and examinations as necessary to document operator -j proficiency and annual evaluations.

8.1.2 A minimum of 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> of reasonably spread, preplanned lectures shall be scheduled each year.

8.1.3 The lectures will be scheduled throughout the year. Each license holder should participate in the training schedule one week out of every six.

< '2 8.1.4 Individuals who maintain licenses for the purpose of providing backup capability to the operating staff shall participate in the requalification program to the extent that their normal duties preclude the need for specific retraining in particular. areas.

Waivers will only be granted for areas in which an individual received a grade of greater or equal to 80% on his/her annual exam.

8.1.5 -Personnel assigned to license requalification training shall be assigned no concurrent duties during the periods that they are actually engaged in training activities.

8.2 Lectures-

- 8.2.1 Preplanned classroom lectures shall be scheduled and should provide, as a minimum, training in the following subjects:

.1 Theory and Principles of Operation

.2 ' General and Specific Plant Operating Characteristics

.3 , Plant Instrumentation and Control Systems 4 Plant Protection Systems

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.5 Engineered Safety Systems-

.6 Normal, Abnormal, and Emergency Operating Procedures

.7 Radiation Control and Safety

.8 Technical Specifications SP 12.014.07 Rev. 3 Page 3

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.9 ApplicEbis Porticns of Title 10, Chsptar I, Ccdn of Fsdaral 43

.*P, Regulations

.10 Mitigation of Core Damage

.11 Fundamentals of Thermodynamics, Heat Transfer and Fluid Flow 8.2.2

  • Each' license holder shall' review the abnormal and emergency operating procedures on a regularly scheduled basis.

Compliance with this requirement may be met by:

8.2.2.1 Actual performance under abnormal or emergency operating conditions.

8.2.2.2 Walkthrough of the procedural steps necessary to cope with the situation.

8.2.2.3 Drills utilizing a training simulator or on-site preplanned drill scenario.

8.2.2.4 Preplanned lectures.

8.2.2.5 Supervised self study. All self study will be under supervision of the training section and documentation will include examinations to verify effectiveness of the self study.

8.2.2.6 Procedure review and/or rewrite as part of normal job function.

8.2.3 ENo more than 50% of the lecture series outlined in this section may be presented by videotape or film presentation. All lectures should be a balanced presentation of live instruction with related training aids.

8.2.4 'A written examination shall be administered at-the completion of each week of on-site requalification training and each individual should also participate in plant drill scenarios each training

. week.

'8.3 On The Job Training G

8.3.1 . Control Manipulations (Reference -- Appendix 12.2) 8.3.1 Ten reactivity control manipulations are required to be performed annually by each licensed operator and senior operator. Reactivity control manipulations performed at SNPS or at the Limerick simulator can be used to fulfill this requirement.

SP 12.014.07 Rev. 3 Page 4

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8.3.2 Until.tha SNPS-spicific simulctor bscomas cvailabis,-ths

-P. -SNPS requalification training program will utilize the l Limerick plant simulator for retraining licensed 43 7

operators. Use of the Limerick Simulator will include the following:

a) SNPS normal, abnormal, and, emergency operating-

'., ~

procedures as well as the appropriate SNPS alarm e

response ' procedures will be used by SNPS operators.

P, during simulator requalification training at the Limerick' Simulator.

Simulator requalification training will be b) .

conducted using a crew concept; the students will be required to-duplicate to.the extent practical the functions and responsibilities of the normal e

SNPS control' room staff.

4 c) Each SNPS licensed RO and~SRO will undergo at least 4 - five days of training at the simulator every six months. During these five days of simulator

- training, each student will-spend at least three days operating the simulator controls as part of the training crew.1 d) Individual performance. on the simulator will be

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evaluated by use of a drill scenario form. Drill (3-

' scenario forms .will .be completed for each licensed operator during each week of simulator training and

+ evaluated.

P 8.3.2 Pkthods-of Training: ,,3 8.3.2.1 All licensed personnel shall be kept cognizant of SNPS

+

design, procedural and facility license changes using one or more' of the following methods:

.1 Brief lectures conducted by section supervision or 4 other appropriate personnel.

.2' LStaff meetings (also-includes Review of Operations .

Committee meetings).

4

- Written communications to each licensed individual.

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.3

.4 Pre-planned lecture series.

.5 Required reading list.

8.3.2.2 Other on-the-job training such as cross job training and on-shift discussion may be used to increase the

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individuals proficiency.

" SP 12.014.07 Rev. 3 I Page 5 i

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J 8.3.223 On an annual basis, ~esch licsnze holdsr chsll

".F. participate.in plant drills and control manipulations covering:the evolutions listed in Appendix 12.2.

- Participation in a plant drill involves responding to 3

drill conditions or being an evaluator who observes and

< _ evaluates drill response.- l

' <b 1 All;SNPS licensed evaluators'aust also participate as  !

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responders and be evaluated during the course of the requalification program.

Plant drills.will be conducted on a- crew basis and will involve reviewing plant procedures steps, action identification, equipment control location, expected instrumentation response, plant communications and

. Technical Specification action identification.

7 Each .dr'ill will be planned in a drill scenario as indicated in Appendix 12.3 and will include tha following:

.1 Plant Condition

.2 Initiating Indication

.3- Expected Response

.4 Individual Evaluation

.5 ' References

.6 Objectives (F The Training Supervisor or designee will review drill critiques.that'are evaluated as unsatisfactory and l initiate corrective remedial action if necessary.

8;3.2.4 Backup licensed. reactor operators and senior reactor-operators not permanently assigned to an operating shift shall stand one 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> watch per-quarter.

8.3.2.5 1 Persons holding a currently valid NRC license, but not in an active' status.for a period of four months or more, shall.be refamiliarized and examined prior to resuming licensed activities. This refamiliarization shall consist of changes or incidents that occurred during the inactive period and shall include:

- .1 - Procedural changes

- .2 ' License changes SF 12.014.07 Rev. 3 Page.6

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. .4 Plant incidents The completion of the refamiliarization program shall (3

- ' include written and/or oral examinations, 1

as directed by .

the Operations Manager to document that the license holder is currently familiar with the plant. The

. Training Supervisor shall' document the_ satisfactory

' completion of the refamiliarization program, and the NRC

b. shall be notified in accordance with Reference 11.2. A (3-result of less than 80% on the irritten exam and/or a .

' failure on an oral exam shall require;the individual to receive additional training in those designated areas 4

and. to observe station operations for. a minimum of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. prior to re-examination.

- 8.4L Evaluation 4g ,

8.4.1 Actual perfgraance is evaluated on an ar.nual . basis, as a minimum, for all on shift licensed personnel. . These performance

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evaluations are reviewed by the Operations Section and training needs are identified. In general these needs will be used to identify topics to be presented in the requalification program.

However, accelerated retraining-for an individual license holder can also be identified. Back-up licensed holders will be

-evaluated during their reactivity manipulations by a member of the '

training section.

Jul annual written examination comparable in scope and degree of

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8.4.2 difficulty to an NRC examination. consistent with the level of 4'

license held, will be given to. each license holder. Exam topics will be selected from material covered as part of the requalification program. Oral one-on-one walkthrough examinations will also be used to supplement this examination. <3 8.4.3 A ' licensed individual who' receives an overall grade of less than ~

80% or receives a grade of less than 70% in any .one category. of the annual written exam administered by.the SNPS Training Section shall be relieved of his license duties and placed in an accelerated Requalification Program prior to;recesting.-

43 8.4.3.1 Training provided to personnel participating in an r

accelerated requalification program may include preplanned lectures, self study, on the job instruction,

' or other training as required and will be evaluated via written and/or oral examination. (o, A grade of less than 70% on any lecture series examination shall

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8.4.4

. require that = individual to be rescheduled for re-examination and i< upgrading in that area.

SP 12.014.07 Rev. 3

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' 8. 4. 5 ' A licensed individu 1 who r:csivas a failing greda on tha snnusi (J

/, oral exam shall be'placed in an accelerated requalification i l l program.

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8.4.6 Licensed individuals who are directly involved with the (j preparation and grading of examinations are required to take one

' full written and one full oral examination in a 2 year period.

This may be accomplished by a waiver of a. full exam for one year or by partial waivers in each year for identified sections.

Waivers should not be allowed for any one' exam section in consecutive years.

8.5 Administration of Requalification Examination 8.5.1 Administration of Requalification examinations shall be in accordance with Appendix 12.4.

-8.6 Records (J 8.6.1: Records for each individual shall be maintained for a minimum of two years by the Training Division and should include the following:

8.6.1.1 Copies of written examinations administered and answer keys that contain point values for each correct answer.

8.6.1.2 Answers given by the licensee to written examinations.

8.6.1.3 Results of performance evaluations (drill scenarios).

8.6.1.4 Documentation of additional training administered to licensed individuals in areas where deficiencies have been demonstrated.

8.6.1.5 Records of attendance at preplanned lectures.

8.6.1.6 Documentation of licensed personnel cognizance of changes made to station design, appropriate procedures, and the station license.

8.6.1.7 Documentation of the annual review of abnormal and emergency procedures.

8.6.1.8 Documentation of participation in reactivity control manipulations (including use of simulator training if applicable).

9.0 ACCEPTANCE CRITERIA N/A SP 12.014.07 Rev. 3 Page 8

,[ 10.0 FINAL CONDITIONS

.N/A

11.0 REFERENCES

11.1 SP 1'2.014'.01, Personnel Training Requirements 11'.2 ' Code o'f Federal Regulations, Title 10, Part 55 11.-3 FSAR, Section'13.2.2.

.11.4 'FSAR, Table 13.5.1-1, Sections B.1, B.2, B.3 and B.4 11.5 INPO Guidelines for Requalification Training and Evaluation,- GPG 02-10-80

'11.6 ' ANSI /ANS 3.1 - 1978 11.7 ;NUREG - 0660,.Vol. I,.1980 11.8 NUREG'- 0737, 1980 11.9 NRC Generic Letter 83-17 11.10 TITLE 10 CFR Part 50 - Section 50.54, Conditions of License 11.1 hppendix A of 10 CFR Part 55 11.12 NUREG-1021, Operator Licensing Examiner Standards

11.13 Regulatory Guide 1.8 - Personnel Selection and Training 11.14 Regulatory Guide 1.149 - Nuclear Power Plant Simulators for usa in Operator Training 12.0 APPENDICES.

12.1 SNPS Requalification Program Definitions 12.2' SNPS Requalification Control Manipulations 12.3 -SPF 12.014.07-1, Drill Scenario Form 12.4 -Administration of Requalification Exams.

r 12.5. SPF 12.014.07-2, Time On Shift Record for Backup License Holders O

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'SP 12.014.07 Rev. 3

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  • APPENDIX 12.1
  • Page 1 of 1 SNPS REQUALIFICATION PROGRAM DEFINITIONS

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l '. - JOB' CROSS-TRAINING Job cross-training for shif t personnel shall- consist of assuming the duties and

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performing the functions of other shift classifications.

2. ~ON-SHIFT DISCUSSIONS

'On-shift discussions'may include review of procedures, discussions of plant

operations and/or other specific material assigned by the Training Supervisor or Ops. Supervision.- These discussions should include review of Reactor Operating Experiences.
3. ACTIVE STATUS Licensed individuals whose normal duties are at the station on a day-to-day

. basis and who are involved in the daily activities at the station shall be considered on " active status".

4.. BACK-UP PERSONNEL These are personnel holding an-NRC Reactor Operator or Senior Reactor Operator Llicense but not permanently assigned to an operating shift. The Operations Engineer and Assistant Operations Engineer are not considered backup personnel.

I 5. LICENSED OPERATOR (RO)

Any individual who possesses an operator's license pursuant t'o Title 10, CFR, Part 55, " Operators' Licenses".

'6.. LICENSED. SENIOR OPERATOR (SRO)

Any individual who possesses a senior operator's license pursuant to Title 10,

.CFR, Part 55, " Operators' Licenses".

- 7.; ~ NORMAL OPERATING PROCEDURES

  • Normal- Operating Procedures are those procedures which cover those operating activities defined in Appendix 12.1.1.

=8. ABNORMAL OPERATING PROCEDURES Abnormal Operating Procedures are those procedural actions included in the

' appropriate system operating procedures for the activities listed in Ap'pendix 12.1 '.1.

9.; ' EMERGENCY OPERATING PROCEDURES

. Emergency Operating Procedures are those procedural actions provided for combating the potential emergency conditions listed in Appendix 12.1.2.

SP 12.014.07 Rev. 3 Page 10

. 3. . Core. Spray System.

- 4. - Diesel-Generator 5.1 4,160 V System

- 6. 480 V System.

7 .' 120 V_AC Instrument Bus _

4

8. 120 V AC Reactor Protection System Bus

-9. 120 V AC Uninterruptable Power Supply

. l10. 125 V DC System

11. Fuel Pool Cooling

-12.' HPCI

13. LPCI (Mode of RHR)

~ 14.- Offgas'(Incl. SJAE, HOGGER) 4 15.- Primary Containment Inerting

16. HVAC-Drywell Cooling 117. Reactor Bldg Closed Loop Cool. System
18. ' Reactor. Bldg Normal Ventilation System (RBNVS)
19. RCIC
20. RHR System
21.-- Rea'ctor Recirculation System
22. Service Water
23. ' Reactor Bldg Standby Ventilation System (RBSVS)

SP 12.014.07 Rev. 3 Page 11

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~ ' APPENDIX 12.1.1 Page 2 of 2

=,24. Standby Liquid control System

25. ' Condensate System 26., Feedwater System
27. HVAC - Control Room
28. HVAC - Turbine Building
29. Ceneratar Seal Oil System
30. Main Steam System
31. Reactor Water. Cleanup System
32. . Station Air System 33.- Turbine Bldg, Closed Loop Cooling System

'34. Turbine Generator.

35. Turb'ine EHC
36. Turbine Lube Oil System
37. ~ Containment Area Leakage Detection System
38. RBSVS & CRAC Chilled Water SP 12.014.07 Rev. 3 Page 12

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" APPENDIX 12.1.2 Page 1 of 2 EMERGENCY PROCEDURES

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1. Acts of Nature
2. Abnormal Radiation Release - Off Gas 3.. Abnormal Radiation Release - Liquid }
4. Abnormal Radiation Release - Station Ventilation f
5. Control-Rod Drop i
6. Emergency Use of S.L.C. ,
7. Loss of SRM and IRM Systems 8.- Fuel Cladding Failure
9. Fuel Handling Accident
10. Emergency Shutdown
11. Hotwell Salt. Water Intrusion
12. Loss of Condenser Vacuum

'13. . Loss of Primary Containment Integrity

14. -Loss of Secondary Containment Integrity
15. . Loss of Offsite Power
16. - Loss of all AC Power

'17. -Loss of Instrument Air

18. Loss of Reactor Building Closed Loop Cooling Water
19. Loss of Service Water
20. Loss of Shutdown Cooling
21. Loss of Turbine Building closed Loop Cooling Water
22. Shutdown from Outside Control Room
23. Level Control SP 12.014.07 Rev. 3 Page 13

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. APPENDIX 12.1.2 b[;9[. ,

Page 2 of 2

, [24.- Cooldown-d
y. . . 25..- Containment Control- /'

e 4: 26. , Level. Restor'ation-fn 4 '

N'(( l27;-' Rapid RPV Depressurization 3

28. RPV Flooding

- 29.. Transient with Failure to Scram.

30.. Intrusion of Resin into the Reactor Coolant System 4

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APPENDIX 12.2 3

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< SNPS REQUALIFICATION-CONTROL MANIPULATIONS y.

!The following control manipulations and plant evolutions are acceptable for meeting s

cha. reactivity control manipulations required by Appendix A,' paragraph 3.a of 10 CFR P,2rt 55. J The starred . items shall be. performed on an annual basis; all' other items

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'ch:11 be' performed on a:two-year cycle. However, each individual should participate

-in as many reactivity' changes as plant conditions permit. . Those control manipulations which.are not performed at the plant may be performed on a simulator or gGS part-of.the~ plant; drill'. program. Personnel with SRO licensees are credited with th2 aci;iviti' es :if they' direct.or evaluate control manipulations as they are

- parformed, ,.

. #A. . AppNach'~tocriticalfromsuberiticalonthesourcerangeinstrumentationtothe-point of adding nuclear heat verified by establishing a predetermined heatup n..

-rate.-s -g,

BP Plant shutdown.

a<

cC. Manual' control of feedwater during plant startup and shutdown.

. tb.

tD. :Any power change of 10% or greater using control rods or manual recirculation flow control.

!*E.:[ Loss :t^

of coolant including, leak rate determination.

Mb .1.. Inside-and outside primary' containment.

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2. ' Large and small.

F. ~ Losshf instrument air (must be performed via drill at SNPS).

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  • lG. sLoss'of electrical power (and/or' degraded power sources).

e.

.CH.  : Loss,of recirculation flow.

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h y - 1.1 LLossgf'cndenservacuum.

LJ. 'Lossiof' Reactor Building service water.

s. .

K.'NI,oss RBCLCW to individual-components.

CL.-' Loss of-feed; ster /feedwater system. failure.

MJ Loss of a protective system channel.

g NR ?Mispositioned or dropped control rod or rods.

0.h Inability.to move control rods.

SP 12.014.07 Rev. 3

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- APPENDIX 12.2 41 Page 2.of 2 J P. ~ Conditions requiring-use of the s.andby liquid control system.

Q L Fuel cladding failure or high activity in reactor coolant or offgas.

.R.-. Turbine or generator trip.

S. Malfunction of automatic control system (s) which affect reactivity.

. l

. T. -Malfunction of reactor pressure. control system.

U. Reactor Trip.

V. Main steam line break (inside or outside containment).

W. - ' Nuclear-instrumentation failure (s).

Xi . Operation of the fuel handling bridges during refueling or core loading or-unloading (licenses fuel handling personnel only).

Y. . Moving control rods in response to a xenon transient.

Z. Manual rod control prior to and.during generator synchronization.

AA. Turbin'e'- Generator startup.

BB. Recirculation Flow control malfunction.

CC. Abnormal reactor water level.

- DD. Loss'of shutdown cooling.

    • EE SDV Rupture.' .

FF: ' Station Blackout.

0CGG SRV Open. (3.

odHH ECCS Initiation at Power.

CAII-Loss of Feedwater Heating C* ~ Not. required by.1'O CFR 55 or NUREG 0737, but desirable for operator experience.

SP 12.014.07 Rev. 3 Page 16

l {1 APPENDIX 12.3 ~

'~, Page 1 of 1 SAMPLE

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DRILL SCENARIO l 7

PLANT CONDITIONS: l t

-ACTUAL PROBLEM:  !

' INITIAL-INDICATIONS:  !

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OBJECTIVES:

- t CREW - WEEK DATE

' EVALUATION: SAT UNSAT Witch Engineer Watch Supervisor

'NucleariStation Operator Nuclear Assistant Station Operator ,,

Nuclear Assistant Station-Operator'

. Equipment Operator

Othar.- Title

..Plsase-write comments on revers .

EVALUATOR SIGNATURE: REVIEWED BY:

Oper. Trng Specialist or Designee

REFERENCE:

SP r. Drill Title.and Number:-

ARP' "

'T.S. Suffolk; County

Reference:

l.

SPF 12.014.07-1 Rev. 3 SP 12.014.07 Rev. 3 Page 17 Y- ro, - -- , - -, -, w.e.,,--e**--,--+==-c--w+ ew-, - e w e's

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  • APPENDIX 12.4
  • Page 1 of 1

-ADMINISTRATION OF REQUALIFICATION EXAMS

1. As' a' minimum, students will be separated by as least the width of a chair during all' exams. When class size and room size is such that the students can be seated at separate tables they shall be.

z.- All materials not required for exam purposes shall be removed from the students

. table or desk.

. 3. Materials required for exam purposes shall be handed out by the training section

-(i.e., Tech.. Specs, Steam Tables,: Procedures).

'4. ; Js ' exam proctor shall be in the room during all times that exams are in the possession'of.the students. The exam proctor shall have no concurrent duties that would ~ detract from his proctor responsibilities.

15... f 0nly. one person at a time will be permitted to leave the exam classroom.-

t 61 If students'are' suspected, by the proctor of receiving or giving help on the exam the following action shall be taken:

Student giving and/or receiving help shall have exams marked void by the instructor after.the exams have:been turned in.

7.- - All voided exams will be hand-carried to the Training Supervisor or his

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' alternate.

IB . - As a minimum any student that has an exam voided shall' be scheduled for re-examination (different exan) in that area.

In order;that all students are aware of these guidelines the following statement "chruld be included on the cover sheet of all. exams:

All work'done on this exam is my_own, I have neither given nor received aid.

i' (Signature)-

'In~ addition'the students shall be informed that if they do not comply with the above

- ctstement they are subject to disp 11 nary action.

i SP 12.014.07 Rev. 3 Page 18

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APPENDIX 12.5 Page 1 of 1 f($

SNPS

. 3' LICENSED OPERATOR' REQUALIFICATION PROGRAM TIME ON SHIFT RECORD FOR BACKUP LICENSE HOLDERS

)

Nrm:

'0000 --0800 cg 1600 - 2400 p

~ Data and-Tire of Shift 0800'- 1600 c3 Date

Plant Operational Condition

'Significant Evolutions / Events:

'Surveillances: .(Indicate.all surveillances performed or observed during shift)

{

f i  ;

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7 I Backup' License Signature Date L Natch Engineer  ;

-Date ,

f t

Returr Completed Form to' Training Section .

-SPF 12.014.07-2. Rev. 3 SP 12.014.07 Rev. 3 Page 19 i

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