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{{#Wiki_filter:Enclosure II15 NINE MILE POINT NUCLEAR STATION NUCLEAR TRAINING PROCEDURE PROCEDURE NO-NTP-10 TRAINING OF LICENSED OPERATOR CANDIDATES DATE AND INITIALS APPROVALS SIGNATURES REVISION 0 REVISION 1 REVISION 2 Training Superintendent NMP Nuclear Station K.F.Zollitsch Operations Supervisor NMP Unit 41 J.C.Aldrich Operations+pe,r&
{{#Wiki_filter:Enclosure II15 NINE MILE POINT NUCLEAR STATION NUCLEAR TRAINING PROCEDURE PROCEDURE NO-   NTP-10 TRAINING OF LICENSED OPERATOR CANDIDATES DATE AND   INITIALS APPROVALS           SIGNATURES                   REVISION 0   REVISION 1     REVISION 2 Training Superintendent NMP Nuclear Station K. F. Zollitsch Operations Supervisor NMP Unit 41                                                         g~/i)~
NNP t2 g~/i)~Poli<3/I General Superintendent of Nuclear Operation Chairman of S.O.R.T.J.Perkins u'll~/T~
J. C. Aldrich Operations+pe,r&
NNP       t2                                         Poli<
u'll~/T~
3 /I General Superintendent of Nuclear Operation Chairman of S.O.R.
T. J. Perkins


==SUMMARY==
==SUMMARY==
OF PAGES Revision 1 (Ef fective~Pa e 1 2~4~6 1,2,3,5 ate December 1985 April 1985 February 19868+QQ28P292 86 py I p pDR ADOCK p o pDR P NIAGARA MOHAWK POVER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER~i CH 1988 SUBJECT TO PERIODIC REVIEW  
OF PAGES Revision     1 (Ef fective
                          ~Pa e                             ate 1                               December 1985 2~4~6                             April  1985 1,2,3,5                         February 1986 NIAGARA MOHAWK POVER CORPORATION THIS PROCEDURE NOT TO     BE USED AFTER   ~i   CH 1988 SUBJECT TO PERIODIC REVIEW 8+QQ28P292 86 o py I p pDR ADOCK p        pDR P


TRAINING OF LICENSED OPERATOR CANDIDATES 1.0 PURPOSE This procedure describes the training program for replacement of licensed operator personnel as called for in ANSI N 18.1-1971, ANSI/ANS 3.1-1978 and 10CFR-55.
TRAINING OF LICENSED OPERATOR CANDIDATES 1.0 PURPOSE This procedure describes the training program for replacement of licensed operator personnel as called for in ANSI N 18.1-1971, ANSI/ANS 3.1-1978 and 10CFR-55.


==2.0 REFERENCES==
==2.0 REFERENCES==


2.1 2.2 2.3 2.4 P2.6 2.7 2.8 ANSI N 18.1-1971 for NMP Unit I 10CFR-55 NUREG 0094 USNRC Letter, Harold Denton to all Power Reactor Applicants and Licenses.Sub)ect: Qualifications of Reactor Operators, Narch 28, 1980 NUREG 0737.ANSI/ANS 3.1-1978 for NMP Unit II NUREG 1021 INPO Tg.3 and TQ.4-January 1985-"Performance Ob)ectives and Criteria for Operating and Near-Term Operating License Plants" 3 0 TRAINING PROGRAM 3.1 Technical training for candidates for the NRC Operating License shall consist of scheduled classroom sessions to cover the following subjects: 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 Theory and principles of reactor operation.
2.1   ANSI N 18.1-1971     for NMP Unit I 2.2  10CFR-55 2.3  NUREG 0094 2.4  USNRC Letter, Harold Denton to all Power Reactor Applicants and Licenses.
General and specific plant operating characteristics.
Sub)ect: Qualifications of Reactor Operators, Narch 28, 1980 NUREG 0737 P2. 6 .ANSI/ANS 3.1-1978 for NMP Unit II 2.7 NUREG 1021 2.8 INPO Tg.3 and TQ.4 January 1985 "Performance Ob)ectives                 and Criteria for Operating and Near-Term Operating License Plants" 3 0 TRAINING PROGRAM 3.1   Technical training for candidates       for the   NRC Operating License shall consist of scheduled classroom           sessions   to cover   the following subjects:
Plant instrumentation and control systems.Plant protection system.Engineered safety systems.Normal, abnormal and emergency operating procedures.
3.1.1       Theory and   principles of reactor operation.
3.1.7 3.1.8 Radiation Protection and Site Emergency Plan and Procedures.
3.1.2      General and   specific plant operating characteristics.
Technical specifications.
3.1.3      Plant instrumentation and control systems.
3.1.9 Applicable portions of Title 10, Chapter 1, Code of Federal Regulations.
3.1.4      Plant protection system.
3.1.10 3.1.11 3.1.12 3.1.13 Heat transfer, fluid flow and thermodynamics.
3.1.5      Engineered safety systems.
Use of installed plant systems to control or mitigate an accident in which the core is severely damaged.Reactor and plant transients and accidents.
3.1.6      Normal, abnormal and emergency operating procedures.
Plant Chemistry NTP-10-1 February 1986  
3.1.7       Radiation Protection and Site Emergency Plan and Procedures.
3.1.8      Technical specifications.
3.1.9       Applicable portions of     Title 10, Chapter 1, Code of Federal Regulations.
3.1.10     Heat transfer, fluid flow   and thermodynamics.
3.1.11      Use of installed plant systems to control or mitigate an accident in which the core is severely damaged.
3.1.12      Reactor and plant transients and accidents.
3.1.13      Plant Chemistry NTP-10   -1   February 1986


3.2 Technical training for candidates for NRC Senior Operator License will consist of scheduled classroom sessions in addition to those listed in 3.1 above.These sessions shall include and place increased emphasis on the following sub)ects: 3.2.1 3.2.2 3.2.3 Reactor Theory Heat Transfer, Fluid Flow and Thermodynamics.
3.2 Technical   training for candidates for NRC Senior Operator License will consist of scheduled classroom sessions in addition to those listed in 3.1 above.           These sessions       shall include and place increased emphasis on the following sub)ects:
Procedures and equipment available for handling and disposal of radioactive materials and effluents.
3.2.1     Reactor Theory 3.2.2     Heat Transfer, Fluid Flow     and Thermodynamics.
3.2.4 3.2.5 Specific operating characteristics of the operating plant.Mitigation of Core Damage, Reactor and Plant Transients and Accidents.
3.2.3      Procedures     and     equipment     available for handling         and disposal of radioactive materials and effluents.
3.2.6 3.2.7 Fuel handling and core parameters.
3.2.4     Specific operating characteristics of the operating plant.
Administrative Procedures, Conditions and Limitations.
3.2.5      Mitigation of   Core Damage,     Reactor and Plant Transients     and Accidents.
3.3 Technical training for candidates for Shift Technical Advisor (STA)Certification will consist of all areas listed in Sections 3.1 and 3.2 and, additionally, STA responsibilities and authority.
3.2.6     Fuel handling and core parameters.
3.4 ON-SHIFT TRAINING/OJT 3.4.1 Candidates who are not already assigned to a regular operating shift shall be given an assignment which will provide for regular participation in day-to-day operations.
3.2.7      Administrative Procedures, Conditions         and Limitations.
Operations shall include manipulation of the reactor and reactor equipment controls.3.4.2 Senior operator candidates shall have three (3)months of shift training as an extra person on shift.3.4.3 Reactor operator candidates shall have three (3)months training on shift as an extra person in the Control Room.3.4.4 Each candidate shall be furnished a training manual which shall contain tasks to be completed prior to the candidate being presented for the written and operating tests as outlined in 10CFR55.Information relative to the completion of the manual shall be included.The manuals shall be kept in a centralized location as designated by the Training Supervisor.
3.3 Technical training for candidates         for Shift Technical Advisor (STA)
NTP-10-2 February 1986  
Certification will consist of all areas listed in Sections 3.1 and 3.2 and, additionally, STA responsibilities and authority.
: 3. 4 ON-SHIFT TRAINING/OJT 3.4.1     Candidates who are not already assigned                 to a regular operating shift shall be given an assignment which will provide       for regular         participation       in day-to-day operations.     Operations shall include manipulation of the reactor and reactor equipment controls.
3.4.2     Senior operator candidates         shall have three (3) months of shift training     as an   extra person on shift.
3.4.3     Reactor   operator     candidates   shall have   three   (3) months training on shift   as an extra person     in the Control   Room.
3.4.4     Each   candidate shall be furnished a training manual which shall contain tasks to be completed prior to the candidate being presented for the written and operating tests as outlined in 10CFR55.               Information relative to the completion of the manual shall be included. The manuals shall be kept in a centralized location as designated by the Training Supervisor.
NTP-10     -2   February 1986


3.4.5 Whenever a candidate performs a plant evolution he/she shall log the date of the exercise and note whether he/she actually performed or simulated the manipulation.
3.4.5     Whenever     a candidate     performs   a plant evolution he/she shall log the date of the exercise and note whether he/she actually performed or simulated the manipulation. Bach entry shall be initialed by the Licensed Operator or Licensed senior Operator supervising the training.
Bach entry shall be initialed by the Licensed Operator or Licensed senior Operator supervising the training.3.4.6 The Training Supervisor or his designee shall review each individuals training manual quarterly.
3.4.6     The   Training Supervisor or his designee shall review           each individuals training manual quarterly.
3.5 Reactor Operator and Senior Reactor Operator candidates shall have successfully completed the appropriate training manuals prior to being presented for the written and operating tests as outlined in 10CFR55.For those Senior Reactor Operator candidates who have not previously held a Reactor Operator License, they shall, in addition, complete task qualification on selected tasks, as identified by 3ob analysis, for which they may be responsible.
3.5 Reactor Operator and Senior Reactor Operator candidates shall have successfully completed the appropriate training manuals prior to being presented for the written and operating tests as outlined in 10CFR55. For those Senior Reactor Operator candidates who have not previously held a Reactor Operator License, they shall, in addition, complete task qualification on selected tasks, as identified by 3ob analysis, for which they may be responsible.
3~6 SIMULATOR TRAINING A simulator shall be used to supplement the technical and on-shift training specified in Section 3.0.Detailed records of this simulator training shall be placed in the individual's training file.When a simulator is used, the candidate shall actually perform all logged operations listed below:*3.6.1 Plant or reactor start-ups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.
3 ~6 SIMULATOR TRAINING A simulator shall be used to supplement the technical and on-shift training specified in Section 3.0. Detailed records of this simulator training shall be placed in the individual's training file. When a simulator is used, the candidate shall actually perform all logged operations listed below:
*3.6.2 3.6.3 Plant shut-down.
    *3.6.1     Plant   or   reactor     start-ups   to   include   a range   that reactivity     feedback     from nuclear       heat   addition   is noticeable and heatup rate is established.
Manual control of feedwater during start-up and/or shutdown.*3.6.4 Any significant
      *3.6.2   Plant shut-down.
(>10%,)power changes in manual rod control or recirculation flow.*3.6.5 Loss of coolant including:
3.6.3    Manual   control of feedwater during start-up and/or shutdown.
1)2)Inside and outside primary containment.
      *3.6.4     Any significant (>10%,)     power changes   in manual rod control or recirculation flow.
Large and small, including leak-rate determination.
      *3.6.5     Loss of coolant including:
3.6.6*3.6.7 3.6.8 3.6.9 Loss of instrument air.Loss of electrical power (and/or degraded power sources).Loss of core coolant flow.Loss of condenser vacuum.3.6.10 Loss of service water.3.6.11 Loss of shutdown cooling..3.6.12 Loss of RBCLC.*3.6.13 Loss of normal feedwater or normal feedwater system failure.NTP-10-3 February 1986  
: 1)   Inside and outside primary containment.
: 2)    Large and small, including leak-rate determination.
3.6.6     Loss  of instrument air.
      *3.6.7     Loss of electrical   power   (and/or degraded power sources).
3.6.8    Loss of core coolant flow.
3.6.9    Loss of condenser   vacuum.
3.6.10   Loss of service water.
3.6.11   Loss of shutdown cooling..
3.6.12   Loss of RBCLC.
      *3.6.13   Loss of normal feedwater or normal feedwater system failure.
NTP-10     -3     February 1986


3.6.14 Loss of all feedwater.
3.6.14   Loss of all feedwater.
3.6.15 Loss of protective channel.".3.6.16 Mispositioned control rod or rods (or rod drops).3.6.17 Inability to drive control rods.3.6.18 Failure of Reactor to Scram.3.6.19 Fuel cladding failure or high activity in reactor coolant or offgas.*3.6.20 Turbine or generator trip.*3.6.21 Malfunction of automatic control system(s)which afEect reactivity (unexplained react1vity changes).*3.6.22 Malfunction of reactor pressure control system.*3.6.23 Reactor scram.*3.6.24 Main steam line break (inside or outside containment).
3.6.15   Loss of protective channel.
3.6.25 Nuclear instrumentation failure(s).
        ".3.6.16   Mispositioned control rod or rods (or rod drops).
3.6.26 Inadvertent isolation of MSIV while at power.<<3.6.27 Inadvertent opening of relief valve.<<3.6.28 Turbine bypass valve failure to open following trip.*3.6.29 Demonstration oE natural recirculation capabilities.
3.6.17     Inability to drive control     rods.
<<Special emphasis to be placed on these items by SRO License Candidates and Shift Technical Advisors Certification Candidates.
3.6.18     Failure of Reactor to Scram.
4.0 EVALUATIONS 4.1 Periodic Audits cons1sting of written and/or oral exams shall be conducted.
3.6.19     Fuel cladding failure or high         activity in reactor coolant or offgas.
Continued trainee participation recommendat1ons will be based on these audits utilizing walk throughs and weekly quizzes and the NRC established 80/70 criteria.4.2 The Training Supervisor or his appointed representative shall conduct oral examinations and evaluations of demonstrated or s1mula ted performance Eor each candidate prior to formal presentation to the licensing examiner.On the bas1s of these examinations and demonstrations, a written evaluation shall be placed 1n the indiv1dual's training file.4.3 Certifications completed, pursuant to Section 55.10 (a)(6)of 10CFR-55 shall be signed by the Vice President-Nuclear Generation.
        *3.6.20   Turbine or generator     trip.
-4 April 1985  
        *3.6.21   Malfunction of automatic         control system(s)     which afEect reactivity   (unexplained react1vity changes).
        *3.6.22   Malfunction of reactor pressure control system.
        *3.6.23   Reactor scram.
        *3.6.24   Main steam   line break (inside or outside containment).
3.6.25   Nuclear instrumentation     failure(s).
3.6.26   Inadvertent isolation of       MSIV while at power.
        <<3.6.27   Inadvertent opening of     relief valve.
        <<3.6.28   Turbine bypass valve failure to open following         trip.
        *3.6.29   Demonstration     oE natural recirculation capabilities.
  <<Special emphasis to     be placed on these     items by   SRO License Candidates   and Shift Technical Advisors Certification Candidates.
4.0 EVALUATIONS 4.1 Periodic Audits cons1sting of written and/or oral exams shall be conducted. Continued trainee participation recommendat1ons will be based on these audits utilizing walk throughs and weekly quizzes and the NRC established 80/70 criteria.
4.2 The Training Supervisor or his appointed representative shall conduct oral   examinations and evaluations of demonstrated or s1mula ted performance Eor each candidate prior to formal presentation to the licensing examiner.         On   the bas1s     of these examinations and demonstrations,     a written evaluation           shall be placed 1n the indiv1dual's training file.
4.3 Certifications completed, pursuant to Section         55.10 (a) (6) of 10CFR-55 shall be signed by the Vice President           Nuclear Generation.
                                    -4   April 1985


1~~r 5.0 DOCUMENTATION 5.1 An individual training file shall be maintained for each candidate for the NRC Operator or Senior Operator License.This file shall contain the following materials:
1 ~ ~ r
S.l.l checklist listing the formal training lectures presented, length of lecture, the instructor presenting the lecture and the date of attendance.
: 5. 0 DOCUMENTATION 5.1 An   individual training file shall be maintained for each candidate for the NRC Operator or Senior Operator License. This file shall contain the following materials:
5.1.2 A log of tests administered which shall include the general sub)ect or system covered and the specific items, if applicable.
S.l.l     checklist listing the formal training lectures presented, length of lecture, the instructor presenting the lecture and the date of attendance.
Results shall be recorded as to whether the candidate has mastered the sub)ect or requires further study.5.1.3 5.1.4 A log of reading assignments.
5.1.2     A   log of tests administered which shall include the general sub)ect or system covered and the specific items,                 if applicable. Results shall be recorded as to whether the candidate has mastered the sub)ect or requires further study.
A checklist used to document the manipulations or evolutions which the candidate should be required to demonstrate or simulate is shown on pages 7 S 8.The results of this evaluation is used to determine whether or not the candidate has successfully mastered the operation or requires additional practice and/or study.This record may be obtained in part from the candidate's training manual and On-the-Job Training Manual.5.1.5 5.1.6 Transcript of off-site training results.A general evaluation of the candidates readiness to be presented for the written examinations and operating tests outlined in 10CFR, Sections 55.21 and 55.22 and 55.23.A.APPENDICES A.l Appendix A-Requirements Education and Ex erience for a Reactor 0 erator License RO Candidates must comply with the requirements of 10CFR55, NUREG 1021 and any other applicable regulations and/or guides.A.l.2 Education and Ex erience for a Senior Reactor 0 erator t.!cense SRO candidates must comply with the requirements in 10CFR55, NUREG 1021 and any other applicable regulations and/or guides.NTP-10-5 February 1986}}
5.1.3     A   log of reading assignments.
5.1.4      A     checklist   used     to   document   the manipulations   or evolutions     which   the   candidate   should be required to demonstrate or simulate is shown on pages 7 S 8. The results of this evaluation is used to determine whether or not the candidate has successfully mastered the operation or requires additional practice and/or study. This record may be obtained         in part from the candidate's training manual and On-the-Job Training Manual.
5.1.5     Transcript of     off-site training results.
5.1.6      A   general evaluation of the candidates readiness to be presented for the written examinations and operating tests outlined in 10CFR, Sections 55.21 and 55.22 and 55.23.
A. APPENDICES A.l Appendix A Requirements Education and Ex erience       for a Reactor 0 erator License RO Candidates     must comply with the requirements of 10CFR55, NUREG 1021     and any other applicable regulations and/or guides.
A.l.2     Education and Ex erience       for a Senior Reactor 0 erator t.!cense SRO   candidates   must comply       with the requirements in 10CFR55,   NUREG   1021 and any     other applicable regulations and/or guides.
NTP-10     -5     February 1986}}

Latest revision as of 06:47, 30 October 2019

Rev 1 to Nuclear Training Procedure NTP-10, Training of Licensed Operator Candidates.
ML17055B542
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/14/1986
From: Aldrich J, Michael Jones, Zollitsch K
NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17055B512 List:
References
NTP-10, NUDOCS 8604280292
Download: ML17055B542 (12)
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Text

Enclosure II15 NINE MILE POINT NUCLEAR STATION NUCLEAR TRAINING PROCEDURE PROCEDURE NO- NTP-10 TRAINING OF LICENSED OPERATOR CANDIDATES DATE AND INITIALS APPROVALS SIGNATURES REVISION 0 REVISION 1 REVISION 2 Training Superintendent NMP Nuclear Station K. F. Zollitsch Operations Supervisor NMP Unit 41 g~/i)~

J. C. Aldrich Operations+pe,r&

NNP t2 Poli<

u'll~/T~

3 /I General Superintendent of Nuclear Operation Chairman of S.O.R.

T. J. Perkins

SUMMARY

OF PAGES Revision 1 (Ef fective

~Pa e ate 1 December 1985 2~4~6 April 1985 1,2,3,5 February 1986 NIAGARA MOHAWK POVER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER ~i CH 1988 SUBJECT TO PERIODIC REVIEW 8+QQ28P292 86 o py I p pDR ADOCK p pDR P

TRAINING OF LICENSED OPERATOR CANDIDATES 1.0 PURPOSE This procedure describes the training program for replacement of licensed operator personnel as called for in ANSI N 18.1-1971, ANSI/ANS 3.1-1978 and 10CFR-55.

2.0 REFERENCES

2.1 ANSI N 18.1-1971 for NMP Unit I 2.2 10CFR-55 2.3 NUREG 0094 2.4 USNRC Letter, Harold Denton to all Power Reactor Applicants and Licenses.

Sub)ect: Qualifications of Reactor Operators, Narch 28, 1980 NUREG 0737 P2. 6 .ANSI/ANS 3.1-1978 for NMP Unit II 2.7 NUREG 1021 2.8 INPO Tg.3 and TQ.4 January 1985 "Performance Ob)ectives and Criteria for Operating and Near-Term Operating License Plants" 3 0 TRAINING PROGRAM 3.1 Technical training for candidates for the NRC Operating License shall consist of scheduled classroom sessions to cover the following subjects:

3.1.1 Theory and principles of reactor operation.

3.1.2 General and specific plant operating characteristics.

3.1.3 Plant instrumentation and control systems.

3.1.4 Plant protection system.

3.1.5 Engineered safety systems.

3.1.6 Normal, abnormal and emergency operating procedures.

3.1.7 Radiation Protection and Site Emergency Plan and Procedures.

3.1.8 Technical specifications.

3.1.9 Applicable portions of Title 10, Chapter 1, Code of Federal Regulations.

3.1.10 Heat transfer, fluid flow and thermodynamics.

3.1.11 Use of installed plant systems to control or mitigate an accident in which the core is severely damaged.

3.1.12 Reactor and plant transients and accidents.

3.1.13 Plant Chemistry NTP-10 -1 February 1986

3.2 Technical training for candidates for NRC Senior Operator License will consist of scheduled classroom sessions in addition to those listed in 3.1 above. These sessions shall include and place increased emphasis on the following sub)ects:

3.2.1 Reactor Theory 3.2.2 Heat Transfer, Fluid Flow and Thermodynamics.

3.2.3 Procedures and equipment available for handling and disposal of radioactive materials and effluents.

3.2.4 Specific operating characteristics of the operating plant.

3.2.5 Mitigation of Core Damage, Reactor and Plant Transients and Accidents.

3.2.6 Fuel handling and core parameters.

3.2.7 Administrative Procedures, Conditions and Limitations.

3.3 Technical training for candidates for Shift Technical Advisor (STA)

Certification will consist of all areas listed in Sections 3.1 and 3.2 and, additionally, STA responsibilities and authority.

3. 4 ON-SHIFT TRAINING/OJT 3.4.1 Candidates who are not already assigned to a regular operating shift shall be given an assignment which will provide for regular participation in day-to-day operations. Operations shall include manipulation of the reactor and reactor equipment controls.

3.4.2 Senior operator candidates shall have three (3) months of shift training as an extra person on shift.

3.4.3 Reactor operator candidates shall have three (3) months training on shift as an extra person in the Control Room.

3.4.4 Each candidate shall be furnished a training manual which shall contain tasks to be completed prior to the candidate being presented for the written and operating tests as outlined in 10CFR55. Information relative to the completion of the manual shall be included. The manuals shall be kept in a centralized location as designated by the Training Supervisor.

NTP-10 -2 February 1986

3.4.5 Whenever a candidate performs a plant evolution he/she shall log the date of the exercise and note whether he/she actually performed or simulated the manipulation. Bach entry shall be initialed by the Licensed Operator or Licensed senior Operator supervising the training.

3.4.6 The Training Supervisor or his designee shall review each individuals training manual quarterly.

3.5 Reactor Operator and Senior Reactor Operator candidates shall have successfully completed the appropriate training manuals prior to being presented for the written and operating tests as outlined in 10CFR55. For those Senior Reactor Operator candidates who have not previously held a Reactor Operator License, they shall, in addition, complete task qualification on selected tasks, as identified by 3ob analysis, for which they may be responsible.

3 ~6 SIMULATOR TRAINING A simulator shall be used to supplement the technical and on-shift training specified in Section 3.0. Detailed records of this simulator training shall be placed in the individual's training file. When a simulator is used, the candidate shall actually perform all logged operations listed below:

  • 3.6.1 Plant or reactor start-ups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.
  • 3.6.2 Plant shut-down.

3.6.3 Manual control of feedwater during start-up and/or shutdown.

  • 3.6.4 Any significant (>10%,) power changes in manual rod control or recirculation flow.
  • 3.6.5 Loss of coolant including:
1) Inside and outside primary containment.
2) Large and small, including leak-rate determination.

3.6.6 Loss of instrument air.

  • 3.6.7 Loss of electrical power (and/or degraded power sources).

3.6.8 Loss of core coolant flow.

3.6.9 Loss of condenser vacuum.

3.6.10 Loss of service water.

3.6.11 Loss of shutdown cooling..

3.6.12 Loss of RBCLC.

NTP-10 -3 February 1986

3.6.14 Loss of all feedwater.

3.6.15 Loss of protective channel.

".3.6.16 Mispositioned control rod or rods (or rod drops).

3.6.17 Inability to drive control rods.

3.6.18 Failure of Reactor to Scram.

3.6.19 Fuel cladding failure or high activity in reactor coolant or offgas.

  • 3.6.20 Turbine or generator trip.
  • 3.6.21 Malfunction of automatic control system(s) which afEect reactivity (unexplained react1vity changes).
  • 3.6.22 Malfunction of reactor pressure control system.
  • 3.6.24 Main steam line break (inside or outside containment).

3.6.25 Nuclear instrumentation failure(s).

3.6.26 Inadvertent isolation of MSIV while at power.

<<3.6.27 Inadvertent opening of relief valve.

<<3.6.28 Turbine bypass valve failure to open following trip.

  • 3.6.29 Demonstration oE natural recirculation capabilities.

<<Special emphasis to be placed on these items by SRO License Candidates and Shift Technical Advisors Certification Candidates.

4.0 EVALUATIONS 4.1 Periodic Audits cons1sting of written and/or oral exams shall be conducted. Continued trainee participation recommendat1ons will be based on these audits utilizing walk throughs and weekly quizzes and the NRC established 80/70 criteria.

4.2 The Training Supervisor or his appointed representative shall conduct oral examinations and evaluations of demonstrated or s1mula ted performance Eor each candidate prior to formal presentation to the licensing examiner. On the bas1s of these examinations and demonstrations, a written evaluation shall be placed 1n the indiv1dual's training file.

4.3 Certifications completed, pursuant to Section 55.10 (a) (6) of 10CFR-55 shall be signed by the Vice President Nuclear Generation.

-4 April 1985

1 ~ ~ r

5. 0 DOCUMENTATION 5.1 An individual training file shall be maintained for each candidate for the NRC Operator or Senior Operator License. This file shall contain the following materials:

S.l.l checklist listing the formal training lectures presented, length of lecture, the instructor presenting the lecture and the date of attendance.

5.1.2 A log of tests administered which shall include the general sub)ect or system covered and the specific items, if applicable. Results shall be recorded as to whether the candidate has mastered the sub)ect or requires further study.

5.1.3 A log of reading assignments.

5.1.4 A checklist used to document the manipulations or evolutions which the candidate should be required to demonstrate or simulate is shown on pages 7 S 8. The results of this evaluation is used to determine whether or not the candidate has successfully mastered the operation or requires additional practice and/or study. This record may be obtained in part from the candidate's training manual and On-the-Job Training Manual.

5.1.5 Transcript of off-site training results.

5.1.6 A general evaluation of the candidates readiness to be presented for the written examinations and operating tests outlined in 10CFR, Sections 55.21 and 55.22 and 55.23.

A. APPENDICES A.l Appendix A Requirements Education and Ex erience for a Reactor 0 erator License RO Candidates must comply with the requirements of 10CFR55, NUREG 1021 and any other applicable regulations and/or guides.

A.l.2 Education and Ex erience for a Senior Reactor 0 erator t.!cense SRO candidates must comply with the requirements in 10CFR55, NUREG 1021 and any other applicable regulations and/or guides.

NTP-10 -5 February 1986

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