Requalification Program for NRC Licensed Personnel. Revised Version of 750221 ReptML19322B686 |
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Oconee |
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02/21/1975 |
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DUKE POWER CO. |
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ML19322B685 |
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NUDOCS 7912040702 |
Download: ML19322B686 (9) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20151T2571985-12-20020 December 1985 Mechanical Maint Technical Rept, Unit 3 Containment Bldg Tendon Surveillance, Jul 1977 - Jul 1980 ML20135G5891985-09-0303 September 1985 Rev 0 to B&W Owners Group Emergency Operating Procedures Technical Bases Document. W/Three Oversize Drawings ML20151K2671984-03-31031 March 1984 Final Rept:Failure Modes & Effects Analysis of Integrated Control Sys/Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Vol 1 - Main Rept & Vol 2 - App a ML20151K2491984-03-29029 March 1984 Draft Oconee-1 AC Electrical Distribution Control & Protection Design Features ML20151K2761983-10-28028 October 1983 Failure Modes & Effects Analysis for Oconee 1 Nuclear Power Station Makeup & Purification Sys ML20080E0101983-10-0303 October 1983 Failure Modes & Effects Analysis for Oconee 1 Nuclear Power Station Makeup & Purification Sys, Preliminary Draft ML20080E6061983-08-26026 August 1983 Failure Modes & Effects Analysis of Integrated Control Sys/ Non-Nuclear Instrumentation Electric Power Distribution Circuitry, Interim Rept ML20072B7961983-02-15015 February 1983 Control Room Review Plan for Oconee,Mcguire & Catawba Nuclear Stations,Duke Power Co ML20117J3641983-01-31031 January 1983 Evaluation of Oconee Nuclear Station,Duke Power Co ML20117J3571981-07-31031 July 1981 Evaluation of Oconee Nuclear Power Station ML19323A1621980-03-26026 March 1980 TMI-Plus One:Toward a Safer Nuclear Power Program. ML19249D8631979-09-30030 September 1979 Description of Proposed Mod to Radiological Effluent Treatment Facility, Preliminary Rept.Oversize Drawings Encl ML19308A7471979-09-27027 September 1979 Jocassee Development Rept on 790825 Earthquake & Effects on Jocassee Structures. ML19322B8741979-08-24024 August 1979 Addl Info to 790824 Response to IE Bulletin 79-05C Nuclear Incident at TMI Including Supplemental Small Break Analysis ML19312C1281979-08-16016 August 1979 Mgt & Technical Resources:Experience & Qualifications of Steam Production Dept General Office Staff. ML19312C7981979-07-30030 July 1979 Response to IE Bulletin 79-05C, Nuclear Incident at Tmi. ML19259C4821979-05-0909 May 1979 Effect of Closing Oconee Nuclear Plants on Ability to Meet Summer Peak Demands. ML19312C5841978-07-14014 July 1978 Proposed Mod of Hpis. ML19316A1201978-07-14014 July 1978 Rept on Seismic Activity at Lake Jocassee,780301-0531. ML19316A1351978-04-0404 April 1978 Rept on Seismic Activity at Lake Jocassee,771201-780228 ML19319A7261978-03-0101 March 1978 Info & Evaluation Re Fracture Toughness of Steam Generator & Reactor Coolant Pumps Support Matls. ML19354C2851978-02-28028 February 1978 Possible Geologic/Seismicity Relationships in Vicinity of Facility from Available Data & Repts. Oversize Maps Encl ML19354C2861978-01-19019 January 1978 Rept on Preliminary Investigation of Seismicity Near Lake Keowee,Oconee County,SC,771230-780115. ML19317E6991978-01-16016 January 1978 Fire Protection Program Comparison to NRC Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls & Qa. ML19316A1231977-11-30030 November 1977 Rept on Seismic Activity at Lake Jocassee,770901-1130. Oversize Earthquake Charts Encl ML19317E7261977-10-14014 October 1977 Fuel Assembly 1D40. ML19312C5811977-09-24024 September 1977 Generator Tube Leak Status Rept. ML19316A1301977-09-0202 September 1977 Jocassee Dam Northwestern Sc:Estimate of Existing Strain & Cracking Potential from Hypothetical Foundation Displacements. ML19319A7301977-08-31031 August 1977 Safety Assessment of Steam Generator Tube Leakage. ML19316A1361977-08-31031 August 1977 Rept on Seismic Activity at Lake Jocassee,770601-0831. Oversize Map Encl ML19316A1291977-08-26026 August 1977 Steam Generator Tube Leak Status Rept. ML19308A8381977-07-18018 July 1977 Requalification Program for NRC Licensed Personnel, 731211.Revised on 740703,750107,0221,760930 & 770718 ML19316A3121977-04-21021 April 1977 Evaluation of Potential for Turbine Bldg Flooding. ML19312C3611977-03-30030 March 1977 Qualification of Power Distribution Connector for Use in 15kV Rated Medium Voltage Electrical Penetrations. ML19312C1251977-03-22022 March 1977 Rept on Seismic Activity at Lake Jocassee Between 760601 & 770228. ML19316A1131976-12-31031 December 1976 Response to App a to Branch Technical Position Apcsb 9.5.1, Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to 760710. ML19317D7041976-10-14014 October 1976 Evaluation of Potential Reactor Vessel Overpressurization. ML19308B2771976-10-0101 October 1976 Engineering Geology of Keowee-Toxaway Project. ML19260C1781976-09-30030 September 1976 Jocassee Hydro-Station Seismic Studies Summary Rept. Cover Ltr & Oversize Drawings Encl ML19312C1591976-08-0606 August 1976 Evaluation of Post-LOCA Boric Acid Concentration Control Sys for Facility Reactors. ML19340A1241976-04-16016 April 1976 Criticality Evaluation for Dry Storage of Fresh Fuel Assemblies in Oconee Unit 3 Spent Fuel Pool. ML19316A1171976-04-13013 April 1976 Attachment A:Structural Analysis of Worn Surveillance Specimen Holder Tubes. ML19340A1571976-04-12012 April 1976 Surveillance Holder Tube Rept. ML19322B6161975-12-18018 December 1975 Methods to Prevent Boron Precipation in Long-Term Following Postulated Loca. ML19322B6121975-11-14014 November 1975 Reactor Vessel Support Evaluation for LOCA Loadings. ML19312C8231975-08-12012 August 1975 Safety Evaluation Supporting Util Application to Amend License DPR-55 for Mod of Spent Fuel Storage Facility ML19317E5061975-08-0101 August 1975 Partial Loop ECCS Analysis. 1998-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20247L9041997-12-31031 December 1997 1997 Annual Rept for Duke Energy Corporation & Saluda River Electric Cooperative,Inc,Financial Statements as of Dec 1997 & 1996 Together W/Auditors Rept ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20134N7121997-02-20020 February 1997 Safety Evaluation Accepting Relief Request 96-04 for Plant ML20138L2151997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Oconee Nuclear Station,Units 1,2 & 3 ML20138L2281996-12-31031 December 1996 Revised Monthly Operating Repts for Dec 1996 for Oconee Nuclear Station,Units 1,2 & 3 ML20133C1231996-12-23023 December 1996 Informs Commission of Staff Review of Request for License Amends from DPC to Perform Emergency Power Engineered Safeguards Functional Test on Three Oconee Nuclear Units ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted ML20107M8931995-10-31031 October 1995 Nonproprietary DPC Fuel Reconstitution Analysis Methodology ML17353A4341995-10-31031 October 1995 Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. ML17264A1181995-07-31031 July 1995 Response to Part (1) of GL 92-01,Rev 1,Suppl 1. ML20086M0851995-06-29029 June 1995 DPC TR QA Program ML20077R3631994-12-31031 December 1994 Monthly Operating Repts for Dec 1994 for Bfnpp ML20236L5971994-12-29029 December 1994 SER in Response to 940314 TIA 94-012 Requesting NRR Staff to Determine Specific Mod to Keowee Emergency Power Supply Logic Must Be Reviewed by Staff Prior to Implementation of Mod ML20064L2001994-01-31031 January 1994 Final Rept EPRI TR-103591, Burnup Verification Measurements on Spent-Fuel Assemblies at Oconee Nuclear Station ML20062K7481993-12-0101 December 1993 ISI Rept for Unit 2 McGuire 1993 Refueling Outage 8 ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20046C1291993-08-0202 August 1993 LER 93-007-00:on 930701,determined That Unit 1 Ssf Rc Makeup Sys Inoperable in Past Due to Design Deficiency.Operations Procedures Revised to Reflect Newly Calculated Operating Limits for Rc Makeup Pump,Rcps & RCS.W/930802 Ltr ML20056G0131993-07-27027 July 1993 Rev 0 to ISI Rept Unit 2 Oconee 1993 Refueling Outage 13 ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20097G0421992-05-31031 May 1992 Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 ML20077D0671991-11-15015 November 1991 Nonproprietary Version of Rev 0 to Boric Acid Corrosion of Oconee Unit 1 Upper Tubesheet ML20067A5241990-12-31031 December 1990 Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' ML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML19332D5391989-10-31031 October 1989 Core Thermal-Hydraulic Methodology Using VIPRE-01. ML20042F2321989-08-31031 August 1989 Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20245B6061988-08-31031 August 1988 Inadequate NPSH in HPSI Sys in Pwrs, Engineering Evaluation Rept ML20239A6991987-11-30030 November 1987 Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum) ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20236Q9491987-10-31031 October 1987 Monthly Operating Repts for Oct 1987 ML20235W9611987-09-30030 September 1987 Monthly Operating Repts for Sept 1987 ML20234B1861987-08-31031 August 1987 Monthly Operating Repts for Aug 1987 ML20237K4761987-07-31031 July 1987 Monthly Operating Repts for Jul 1987 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20235S6311987-06-30030 June 1987 Monthly Operating Repts for June 1987 1999-01-05
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.g-Al-75 DUKE POWER (X)MPANT OCONEE NUCLEAR STATION REQUALIFICATION PROGRAM FOR NRC LICENSED PERSONIEL DECEMBER 11, 1973 Revised July 3, 1974 7 I January 7, 1975 February 21, 1975 7912040gC l l
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.l Table of Contents Section h 1.0 Introduction 1 2.0 Definitions 1 2.1 Reactivity Change 1 2.2 Licensed Operator 2 2.3 Backup Licensee 2 2.4 Training Supervisor 2 3.0 Examinations / Lectures 3 4.0 On-The-Job Training 4 5.0 Evaluations 6 6.0 Records 7 7/3/74
DUKE POWER COMPANY OCONEE NUCLEAR STATION REQUALIFICATION PROGRAM FOR . NRC LICENSED PERSONNEL l 1.0 Introduction Recent changes to 10 CFR 55 requires all licensed operators to participate in an approved requalification program. The re ,
qualification program for the Oconee Nuclear Station is designed to maintain and demonstrate the continued competence of all licensed operators and senior operators. This progre:s will be conducted on an annual basis and will include a comprehensive exam, formal requalification lectures, on-the-job training and simulator operation. The program will be implemented so as to minielze scheduling difficulties that will be incurred by site management.
2.0 Definitions 2.1 Reactivity Change A licensed Reactor Operator that performs, or a licensed Senior Reactor Operator that performs or directs, ten (10) reactivity changes from those listedbelow, in accordance with Section 4.0, On-The-Job Trai gn Subsection 4.2, meets the requirements. of 10 CFR 55, Appendix A Section 3(a).
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1 a) Critical approach from suberitical on source range instrumentation ;
to critical at the point of adding heat on the intermediate range instrumentation. l I
b) Any power level change (increase or decrease) of 10% of rated )
l power or greater with control rods in manual. I I
c) Reactor shutdown from critical at 15% of rated power to subcritical, '
l shutdown on source range instrumentation, l 1
d) Boration or deboration during critical operation. - '
e) Operation of refueling bridge to change core geometry during refueling.
2.2 Licensed Operator Individuals who maintain Operator or Senior Operator licenses and who are i actively and extensively engaged in the day-to-day operation of the plant.
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Any licensed operator who has not been actively performing the functions of an operator or senior operator for a period of four months or longer, shall, prior to resuming licensed activities, participate in an appropriate requalifiestion program pursuant to 10CFR 55.31(e).
2.3 Backup Licensee l
Individuals who maintain Operator or Senior Operator licenses for the purpose of providing backup capability to the Operating Staff.
2.4 Training Supervisor A supervisor normally assigned no other duties except instructing, coordinating, and record keeping for pre-license operator training programs and licensed operator requalification program.
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3.0 Fxaminations/ Lectures Annually, all SRO and RO licensed personnel will take a written exami-nation which closely parallels the hE written exanination. The exami- l nation will be given in three segments approximately three months apart following the lecture series for that segment.
Any operator who scores less than 70 percent overall on the Annual Re-qualification exam shall be removed from licensed duties and placed in an accelerated requalification program. The individual will be reevaluated by a comprehensive written exam paralleling the annual exam in format and by an oral interview with the Training Supervisor to detetmine his knowledge level. The results of the oral and written exam will be forwarded to the Operating Superintendent for determination of return to licensed duties.
Requalification lectures are intended to be given on an annual basis for all licensed operators in three segments of approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> duration each, corresponding to the segments of the annual exam. The lecture schedule prior to each annual evamination segment will be determined based on weak areas shown from preceding annual exam.
Following the completion 'of all the annual exam segments, requalification lectures will be determined by the results of the annual exam (i.e.,
categories in which individuals received less than 80 percent). Attendance for all SRO and RO licensed personnel at these lectures will be based on the results of the annual requalification exam (i.e., less than 80 percent on a category requires mandatory attendance at lectures on topics of that category).
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_4 Following the completion of each segment of the annual exam, a special individualized study program will be instituted for anyone scoring less I
than 70 percent on a category to enable the individual to increase his knowledge level for that category in a timely fashion. This program will be in addition to the lectures following completion of all segments of the annual examination but will occur immediately following completion of the segment for which a grade of less than 70 percent was attained.
The individualized study program would be no more. than five (5) weeks induration and an examination to evaluate the retrainin;g would occur at the completion of the individualized study program.
Any individual f ailing a re-examination of a segment of the annual examination following an individualized study program will be evaluated by the Superintendent of Operations to determine the course of action.
This action will be documented in the individual's training record.
Periodic written or oral quizzes will be administered throughout the lecture program with a required passing grade of 80%. Lecture attendance will be based on 80% categorical grades from the annual requalification exam.
" Quality Assurance for Operation" is now a topic covered as part of the pre-license training and as such would be considered as a topic for requalification lectures.
l contingency meetings are an integral part of nuclear plant operation and l are normally scheduled as the need arises by plant management.
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4.0 On-The-Job Trainina 4.1 In order to insure the continued proficiency of licensed operators in meeting all operating situations, on-the-job training will play a major role in the Oconee requalification program. Technical Specifications, Operating Procedures and Emergency Procedures will be reviewed on shif t according to a formal schedule. Short oral and/or written quizzes will be used tc demonstrate the effectiveness of this review with a passing grade of 80% required. All changes to Operating Procedures, f acility design changes and revisions to Technical Specifications will be reviewed on shif t also. Documentation of the specified reviews is filed in the individual's trainine records as per Section 6.0, Records. .
~4.2 All licensed Operators will participate, to the marium extent possible, in plant evolutions involving reactivity changes. These will include those items defined as reactivity changes in Section 2.0, Definitions. During the two-year license term, a minimum of ten such evolutions shall be conducted by each licensed Operator and either conducted or directed by each licensed Senior Operator with no more than three (3) such evolutions being any combination of Items 2.l(d) and 2.l(e) of Section 2.0, Definitions, Subsection 2.1, Reactivity Change.
4.3 All licensed personnel will partica . ate in a one-week (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) simulator training course, consisting of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> classroom and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> simulator, at an approved facility such as the B&W simulator, Lynchburg, Virginia, during the two-year license term.
! The B&W simulator is considered the only existing simulator ap-propriate for use by Oconee personnel in meeting the requirements of Appendix A to 10 CFR Part 55. However, we retain the option to use other simulators that become available in the future and are l
rpproved by the NRC for use by Oconee personnel.
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This training will include operation.during emergency or abnormal conditions including the following:
a) Reactor Startup l b) 15-100% PWR Meneuver I 2/21/75 l
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c) 100%-15% PWR Maneuver i d) Power Operations (Manual and Auto) e) Plant Shutdown /Cooldown j f) Reactor Trip g) Turbine Trip h) Steam Line Rupture
- 1) RC System Leaka ,
4.4 Control manipulations at the simulator will be credited the same as manipulations on the Oconee units.
4.5 Fackup licensees will acquire 4 hrs./ month on shift assigned the
(.uties of Assistant Shift Supervisor or Assistant Control operator, which are positions requiring a Senior Operator's and Operator's license respectively, at this f acility. The assignment to Assistant Shift Supervisor or Assistant Control Operator will be consistent with the license held by the backup licenses.
5.0 Evaluations 5.1 The performance and competency of Operators and Senior operators will be evaluated by the annual written exam as well as with personal evaluations from supervisors and training staff personnel. ,
i 5.2 Semi-annually each Shift Supervisor will submit a report to the Operating Superintendent, evaluating the performance of each man under his supervision during normal and abnormal operating conditions.
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oso 5.3 The performance of Operators and Senior Operators will be evaluated by the simulator training staff follbwing simulator training. Evaluations of personnel will be made by several sources as noted above. The ultimate evaluation will be based on operators performance of his licensed duties at the Oconee Nuclear Station.
5.4 The Operating Superintendent will review these reports semiannually.
On the basis of the evaluations, the Operating Superintendent can j I
l recommend special traising classes and removal from shift duties if necessary. Prior to the license renewal date, the Operating Superintendent will review each Operator's training record. Based on this evaluation he will make recommendations for license renewal or specialized training prior to license renewal.
6.0 Records 6.1 Training records for each Operator and Senior Operator will be maintained and shall contain the followingt a) Copies of the graded annual exam.
b) Re-examinations given s'.ter regna14fication lectures.
c) Evaluations made by Supervisors.
d) Evaluations made by simulator personnel.
e) Documentation of all trainlag participation.
f) Any miscellaneous quizzes given by the training staff. l g) Records of the number and type of reactivity changes.
l 6.2 Training records will be retained for a minimum of six (6) years.
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