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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17059C7911999-09-30030 September 1999
Proposed Tech Specs Re Rev B to Conversion of Unit 2 Current TS to ITS
ML20211P5931999-09-10010 September 1999
Marked-up Tech Specs Pages Reflecting Conforming Administrative License Amend Associated with Proposed Transfer of Facilities to Amergen Energy Co,Llc
ML20211H2231999-08-26026 August 1999
Proposed Tech Specs,Supporting Implementation of Noble Metal Chemical by Raising Reactor Water Conductivity Limit in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b
ML18041A0731999-07-27027 July 1999
Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2.
ML20206P2661998-12-30030 December 1998
Proposed Tech Specs Making Application of Emergency Condenser Vent Ng Activity Monitor Channel Operability Requirement & Daily Sensor Check SR Consistent with Conditions Stated in LCO 3.1.3.a Re Emergency Cooling Sys
ML20197K1041998-12-0404 December 1998
Revised Proposed TS Bases Reflecting Previous Removal of Condenser Low Vacuum Scram Function from TS as Well as Plant Design & Changes to EDG Ratings,Design Basis Load Limits & Loading Profiles
ML20196H0671998-11-30030 November 1998
Proposed Tech Specs,Correcting LCO & Associated Bases for TS Section 3.1.2, Liquid Poison Sys, That Had Been Incorporated Into TS as Part of NMP Unit 1 TS Amend 101
ML20196D2081998-11-24024 November 1998
Proposed Tech Specs B 2.1.1, Fuel Cladding - Safety Limit, B 3.2.5 & 4.2.5, Reactor Coolant Sys Leakage Rate
ML20154R1101998-10-16016 October 1998
Proposed Ts,Revising LCO 3.7.1.1 & Associated Actions & SRs to Provide Assurance That Four SW Pumps Are Operable & Are Operating within Acceptable Sys Parameters,With Divisional Cross Connect Valves Open
ML20217N7911998-04-24024 April 1998
Revised Pages 2-1,3/4 4-1 & B2-1 to Replace Previously Submitted Pages Contained within Attachment a of 971215 Proposed Change to TS to License NPF-49
ML20202G3751998-02-0505 February 1998
Proposed Tech Specs Pages,Reflecting References to 10CFR50.55a(f) & (G) as Well as Terminology Used in Second Ten Year Isi/Ist,Beginning on 980405
ML20197H3371997-12-15015 December 1997
Proposed Tech Specs Revising SLMCPR from 1.07 to 1.09 for Two Recirculation Loop Operation & from 1.08 to 1.10 for Single Loop Operation
ML20211M5231997-10-0707 October 1997
Proposed Tech Specs Section 4.9.6,reflecting New Setpoints Due to Difference in Weights of Two Existing Triangular Refueling Platform Masts
ML20217G9011997-07-31031 July 1997
Proposed Tech Specs Changing Wording in Action 36 of TS Table 3.3.3-1, Emergency Core Cooling Sys Actuation Instrumentation
ML20148A7751997-04-30030 April 1997
Proposed Change to Tech Specs,Removing Section 3.3.7.3 & Associated Surveillance Section 4.3.7.3,associated Tables 3.3.7.3-1 & 4.3.7.3-1,Bases Section 3.4.3.7.3 & Revising Section 0.0 (Index) Pages VII & Xvii
ML17059B2911996-09-0404 September 1996
NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan.
ML20116D8121996-07-26026 July 1996
Proposed Tech Specs Re Option B of App J to 10CFR50
ML20115H1521996-07-12012 July 1996
Proposed Tech Specs Section 6.2.2.i Re App a
ML20117F9501996-05-15015 May 1996
Proposed Tech Specs Section 3/4.3.2 Re Isolation Actuation Instrumentation
ML20101F4281996-03-20020 March 1996
Proposed TS 3/4.3.1 Re RPS Instrumentation,Deleting Operability Requirements for APRM Neutron flux-upscale, Setdown & Inoperative Functions in Operational Conditions (Oc) 3 & 4 & Modifying Operability Requirements in Oc 5
ML20101D7551996-03-15015 March 1996
Proposed Tech Specs Section 4.6.2 Re Depressurization Sys - Suppression Pool
ML20097D2391996-02-0707 February 1996
Proposed Tech Specs Re Administrative Controls
ML20100C1021996-01-25025 January 1996
Proposed Tech Specs Table 3.3.3-1 Re Emergency Core Cooling Sys Actuation Instrumentation
ML20096G8401996-01-17017 January 1996
Proposed Tech Specs,Representing Revs to Specs 3/4.3.1, 3/4.3.2,3/4.3.3,3/4.3.4.2 & Associated Bases to Relocate Response Time Limit Tables from TSs to Plant USAR
ML20094B5421995-10-25025 October 1995
Proposed Tech Specs Re Position Title Changes & Reassignments of Responsibilities at Upper Mgt Level
ML20091Q9571995-08-28028 August 1995
Proposed TS 3.6.1.7,increasing Time 12-inch & 14-inch Containment Purge Sys Supply & Exhaust Valves May Be Open in Operational Condition 1,2 & 3 from 90 H Per 365 Days to 135 H Per 365 Days & Deleting Expired Footnotes for Clarity
ML20081E2491995-03-0909 March 1995
Proposed Tech Specs,Revising SR 4.6.1.2.a,allowing Second Primary Containment ILRT (Type a) to Be Performed at Refueling Outage 5 or 72 Months After First Type a Test
ML17059B0221995-02-15015 February 1995
Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore.
ML17059B0211995-02-10010 February 1995
Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions.
ML17059B0201995-02-10010 February 1995
Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions.
ML17059A8881995-01-18018 January 1995
Rev 0 to Field Disposition Instruction 0245-90800, Shroud.
ML20077N1591995-01-0606 January 1995
Proposed Tech Specs Re Min Gallons of Fuel Oil Required in Day Tanks & Storage Tanks
ML20077N2071995-01-0606 January 1995
Proposed Tech Specs Re Deletion of Certain Instruments Not Classified as Category 1
ML20078Q9241994-12-13013 December 1994
Proposed Tech Specs Re Change to Table 3.6.1.2-1 That Will Allow Maximum Leakage of 24.0 Scfh for Each of Eight MSIVs
ML20077E1561994-12-0202 December 1994
Proposed TS Page 3/4 1-20,reflecting Rev of SLCS Relief Valve Setpoint to Show Influence of Back Pressure & Rev of Bases Page B3/4 5-2 to Show That Hpsc Sys Designed to Supply 517 Gpm Flow Rate at 1,200 (Instead of 1,175) Psid
ML20078J3781994-11-14014 November 1994
Proposed Tech Specs Reducing Leak Rate Test Pressure for Safety Related ADS Nitrogen Receiving Tanks from 385 Psig to 365 Psig
ML17059A5661994-11-0909 November 1994
Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys.
ML20078E0331994-10-28028 October 1994
Proposed Tech Specs 1.0, Definitions, 3/4.3.2, Isolation Actuation Instrumentation & 3/4.9.3, Control Rod Position
ML20078B9841994-10-21021 October 1994
Proposed Tech Specs SR 4.8.1.1.2.e.8,reflecting Addition of Footnote Re 24 H Functional Test of DGs
ML20073L8781994-10-0505 October 1994
Proposed TS Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation
ML20072U3491994-09-0202 September 1994
Proposed Tech Specs Re 18 Month Operability Test of Svc Water Pumps Sys & Resistance Test of Intake Deicing Heater Sys
ML17059A4471994-09-0101 September 1994
Proposed Tech Specs Section 3.2.2, Minimum Reactor Vessel Temperature for Pressurization, & Associated Bases
ML20072P6211994-08-26026 August 1994
Proposed TS 3/4.6.1.3, Primary Containment Air Locks, Allowing Continued Plant Operation If Interlock Becomes Inoperable as Long as Operable Door Locked Shut & Periodically Checked as Being Locked Shut
ML17059A4241994-07-0606 July 1994
Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML20071G2771994-07-0101 July 1994
Proposed Tech Specs Surveillance Requirements 4.6.5.1.c.1 & 4.6.5.1.c.2
ML20029D4001994-04-27027 April 1994
Proposed Tech Specs Re Drawdown Time Testing & Inleakage Testing for Secondary Containment Integrity
ML18040A2941993-12-17017 December 1993
Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML20058N3491993-12-14014 December 1993
Proposed Tech Specs 3/4.8.2, DC Sources, 3/4.8.4, Electrical Equipment Protective Devices & Bases for 3/4.6.3, Primary Containment Isolation Valves
ML17059A0971993-10-25025 October 1993
Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan.
ML20056G9391993-09-0202 September 1993
Proposed Tech Specs Section 3/4.1.3.5, CR Scram Accumulators
1999-09-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18041A0731999-07-27027 July 1999
Rev 1 to NMP2-ISI-006, Second Ten Year Interval Inservice Insp Program Plan for Nine Mile Point Nuclear Power Station Unit 2.
ML17059B2911996-09-0404 September 1996
NMP Nine Mile Point Nuclear Station Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan.
ML17059B0221995-02-15015 February 1995
Rev 0 to UT-NMP-311V0, Procedure for Manual Ultrasonic Exam of Nozzles Inner Radius & Bore.
ML17059B0201995-02-10010 February 1995
Rev 0 to UT-NMP-703V0, Procedure for Geris 2000 Ultrasonic Exam of RPV Nozzle Inner Radius & Bore Regions.
ML17059B0211995-02-10010 February 1995
Rev 0 to UT-NMP-309V0, Procedure for Manual Ultrasonic Exam of Planar Flaw Sizing for Nozzle Inner Radius & Bore Regions.
ML17059A8881995-01-18018 January 1995
Rev 0 to Field Disposition Instruction 0245-90800, Shroud.
ML17059A5661994-11-0909 November 1994
Rev 2 to Emergency Plan Maint Procedure EPMP-EPP-08, Maint, Testing & Operation of Oswego County Prompt Notification Sys.
ML17059A4241994-07-0606 July 1994
Rev 14 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML18040A2941993-12-17017 December 1993
Rev 13 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML17059A0971993-10-25025 October 1993
Rev 4 to NMP2-IST-001,NMP,Nine Mile Point Nuclear Station, Unit 2,Pump & Valve First Ten-Yr Inservice Testing Program Plan.
ML20056G6691993-02-25025 February 1993
Rev 8 to Odcm
ML17056C2971992-06-30030 June 1992
NMPNS - Unit 2 Odcm.
ML17056B9841992-06-26026 June 1992
Rev 9 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML18038A4851991-10-0101 October 1991
Rev 3 to First 10-Yr ISI Program Plan. W/910930 Ltr
ML17058A9561991-05-0202 May 1991
Rev 5 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program.
ML18038A3531991-05-0101 May 1991
Rev 3 to NMP2-IST-001, Niagara Mohawk Power Corp,Nine Mile Point Nuclear Station Unit 2 - Pump & Valve First Ten Year Inservice Testing Program Plan. W/910501 Ltr
ML20070U3621991-04-0101 April 1991
Cover Page to Rev 1 to Issue 2 to Nuclear Security Training & Qualification Plan
ML17058A9541991-03-0606 March 1991
Rev 4 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program.
ML18038A3271990-06-30030 June 1990
Rev 3 to Nine Mile Point Requalification Program Action Plan.
ML17056B9831990-06-15015 June 1990
Rev 8 to Nine Mile Point Nuclear Station Unit 1 Odcm.
ML17056A9671990-04-0303 April 1990
Rev 8 to Odcm.
ML18038A3241990-02-28028 February 1990
Rev 5 to Odcm.
ML17056A9661990-02-27027 February 1990
Rev 7 to Odcm.
ML18038A2921989-09-12012 September 1989
Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program.
ML17055E5581989-03-0202 March 1989
Rev 1 to Restart Action Plan.
ML19325C1741989-02-14014 February 1989
Rev 1 to AP-3.7.1, Process Control Program.
ML17055E4771989-01-16016 January 1989
Second 10-Yr Interval Inservice Testing Program.
ML18038A4231988-05-31031 May 1988
Rev 6 to Offsite Dose Calculation Manual. W/Two Oversize Figures
ML17056A9651988-02-23023 February 1988
Rev 6 to Odcm.
ML20059F8751988-02-0505 February 1988
Rev 4 to Odcm
ML20236G8161987-07-31031 July 1987
Revised Preservice Insp Plan for Nuclear Piping Sys & Reactor Pressure Vessel
ML20236G8111987-07-31031 July 1987
Revised Preservice Insp Plan for Nuclear Piping Sys & Component Supports
ML18038A2721987-05-21021 May 1987
Rev 3 to Offsite Dose Calculation Manual.
ML18038A2491987-04-13013 April 1987
Revised Emergency Procedures,Consisting of Rev 5 to Emergency Action Procedure EAP-1, Activation & Direction of Emergency Plan, & Rev 9 to Emergency Plan Implementing Procedure EPP-20, Emergency Notification. W/870413 Ltr
ML20205S2311987-03-31031 March 1987
Rev 0 to Pump & Valve Inservice Testing Program
ML18038A4221987-02-27027 February 1987
Rev 4 to Offsite Dose Calculation Manual. W/Two Oversize Figures
ML20211P4501986-12-13013 December 1986
Rev 0 to Preoperational Test Procedure N2-POT-1-2, Msivs
ML17055D1821986-08-19019 August 1986
Rev 0 to Administrative Procedure AP-3.7.1, Process Control Program.
ML18038A1671986-05-31031 May 1986
Rev 1 to Offsite Dose Calculation Manual. W/One Oversize Encl
ML17055B5331986-04-11011 April 1986
Rev 1 to Technical Dept Procedure TDP-5, Administration of Operational Engineering Assessment Items.
ML17055B5431986-04-0101 April 1986
Rev 0 to Maint Instruction Procedure S-MI-GEN-002, Maint Instructions for Writing Procedures.
ML17055B5301986-03-20020 March 1986
Rev 0 to Site Administrative Procedure AP-6.1, Procedure for Mod & Addition.
ML17055B5441986-03-14014 March 1986
Rev 1 to Nuclear Training Procedure NTP-11, Licensed Operator Retraining.
ML17055B5421986-03-14014 March 1986
Rev 1 to Nuclear Training Procedure NTP-10, Training of Licensed Operator Candidates.
ML17055B5171986-03-10010 March 1986
Rev 4 to Administrative Procedure AP-2.0, Production & Control of Procedures.
ML17055B5411986-03-10010 March 1986
Rev 3 to Vol IV to SWEC Pp 94, Review of Changes & Effect on Environ/Mechanical/Seismic/Hydrodynamic Qualification of Equipment.
ML17055B5461986-03-0202 March 1986
Rev 2 to Maint Instruction Procedure MI-4.0, Maint Instructions for Review & Implementation of Technical Requirements in Maint Procedures.
ML17055B5251986-03-0101 March 1986
Draft Rev 4 to Administrative Procedure AP-4.0, Administration of Operations.
ML17055B5381986-02-28028 February 1986
Rev 0 to Technical Dept Procedure TDP-8, Post-Maint Testing Criteria.
ML20140D3341986-02-28028 February 1986
Rev 2 to Offsite Dose Calculation Manual. W/Two Oversize Maps
1999-07-27
[Table view] |
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.
3.6.3 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
