ST-HL-AE-1610, Rev 0 to Interdepartmental Procedure IP-8.9, Licensed Operator Requalification

Rev 0 to Interdepartmental Procedure IP-8.9, Licensed Operator Requalification

ML20154B681
Person / Time
Site:	South Texas
Issue date:	01/09/1986
From:	Wisenburg M HOUSTON LIGHTING & POWER CO.
To:	Noonan V Office of Nuclear Reactor Regulation
References
CON-#186-256 IP-8.9, OL, ST-HL-AE-1610, NUDOCS 8603040363
Download: ML20154B681 (24)

Text

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SOUTH TEXAS PROJECT ELECTRIC CENERATIND STATION !"

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rp_g,9 INTERDEPARTMENTAL PROCEDURE 1

22 LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 0 1-15-86 Sponsoring Department Approval:

f/ ff;tro Date:

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Manager, Nuclear T ainin epar ment i

Date:

} 9 3(3 Cohcurrence:

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Plant Manager, South Texas Proj t

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NUCLEAR PLANTOPERATION eg3 los$ *o$h9g8 Document Control Ce tfr o

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INTERDEPARTMENTAL PROCEDURE 2

22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 1.0 PURPOSE This South Texas Proj ect Electric Generating Station (STPEGS)

Interdepartmental Procedure establishes the responsibilities associated with and provides instruction for the conduct of Licensed Senior Reactor Operator and Reactor Operator, Requalification.

This training is providpd to assure continuous operator competence and to ensure that the licenses' activities are conducted in compliance with the te rms and conditions of their licenses, as well as the facility operating license.

2.0 SCOPE This procedure applied to all NRC licensed personnel and all NRC certified Instructor personnel for this facility.

3.0 DEFINITIONS 3.1 Requalification Training That training implemented to maintain licensed operators at a level of knowledge and proficiency required for continued safe operation of STPEGS.

This training also assures that all training requirements are met for timely reapplication and renewal of licenses for Reactor Operators and Senior Reactor Operators.

4 3.2 Annually - 12 months f; 3 months not to exceed 36 f; 3 months over a three year period.

3.3 Licensed Personnel - All personnel who hold a current NRC license on STPEGS either RO or SRO, regardless of staff position.

3.4 On-the-Job training That training required by this procedure, other than classroom training, required for completion of the Requalification program. OJT may include but is not limited to:

1.

Control manipulations 2.

Assigned required reading 3.

Assigned simulator training

4.0 REFERENCES

4.1 10 CFR 55, " Operator Licenses" 4.2 ANSI 3.1-1978 4.3 NUREG 1021, " Operator Licensing Examiner Standard" 4.4 ANSI /ANS 18.1-1971

HL&P 9000 (Sae)

NU.L ER REV SOUTH TEXAS PRT1 JECT ELECTRIC CENERATINS STATISN IP-a.9 N

3 22 PAGE OF LICENSED OPERATOE REQUALIFICATION EFFECTivt DATE 01-15-86 4.5 NUREG 0737 " Clarification of TMI Action Plan Statements" 4.6 NRC (H. Denton) letter - March, 1980 4.7 Final Safety Analysis Report, Section 13.2 4.8 IP-8.5, Training Waiver Requests 5.0 RESPONSIBILITY 5.1 Nuclear Plant Operations Department 5.1.1 Vice President, Nuclear Plant Operations The Vice President, Nuclear Plant Operations certif Les that all licensed individuals have completed the approved Requalification Program as required by Section 50.54 (1-1) of 10 CFR 50, and have discharged their licensed responsibilities competently and safely.

5.1.2 Plant Manager The Plant Manager assumes overall responsibility for the following:

5.1.2.1 Ensuring that an adequate number of licensed operators are available to operate the plant in accordance with regulations and attend Requalification training in accordance with this procedure.

5.1.2.2 Assuring that Requalification

training, in accordance with this procedure, will maintain technically competent licensed personnel.

5.1.3 Reactor Operations Manager The Reactor Operations Manager is responsible for the following:

5.1.3.1 Reviewing the Licensed Operator Performance Evaluations (Attachment IP-8.9-3) conducted by the Reactor Operations-staf f and forwarding a copy of those performance evaluations to the Manager, Operations Training Division (OTD).

5.1.3.2 Providing feedback to NTD, i.e., identifying needs for training.

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IlfrERDEPARTMErrAL F N 4

22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 5.1.3.3 Routing of required reading within NPOD when it is used for training purposes and forwarding the documented completion to NTD for records keeping.

5.1.3.4 Documenting reactivity manipulations performed by licensed personnel on the plant and forwarding that documentation to NTD for records keeping.

5.1.3.5 Providing assistance to the

Manager, OTD in reviewing the content and scheduling of Requalification training to ensure availability to all licensed personnel and ensuring that licensed personnel are available to attend training for which they are scheduled.

5.1.3.6 Monitoring personnel performance and initiating or approving corrective action for non performance.

5.1.4 NRC Licensed or NRC Instructor Certified Personnel Once the Requalification training schedule has been approved, all licensed and certified personnel are responsible for:

5.1.4.1 Ensuring they complete the scheduled Requalification training.

5.1.4.2 Ensuring their licenses are renewed in a timely manner.

5.1.4.3 Reporting any change in health which may affeet the validity of their

licenses, as stipulated in 10 CFR 55, to Manager, OTD.

5.2 Nuclear Training Department 5.2.1 Manager, Nuclear Training Department The Manager, NTD is responsible for the following:

5.2.1.1 Ensuring the Requalification Training Program meets regulatory requirements and that the Nuclear Training Department conducts training in accordance with this procedure.

5.2.1.2 Certifying that all licensed personnel have completed the approved Requalification program as required by Section 50.54 (1-1) of 10 CFR 50 and discharged their licensed responsibilities competently and safely.

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' PAGE OF LICENSED OPERATOR REQUALIFICATION y,,,gyg DATE Q }.15-86

'5. 2. 2 Manager, Operations Training Division The Manager, OTD is responsible for the following 5.2.2 1 Establishing content and developing thu overall Requalification Training Fr,'graw 5.2.2.2 Scheduling and conducting of training.

5.2.2.3 Evaluation of student progress during the program and submitting regular reports of progress to the Reactor Operations Manager.

5.2.2.4 Maintaining retrievable training records.

5.2.2.5 Reporting any change in health of licensed personnel whlch may affect the validity of their licenses to the NRC.

6.0 REQUIREMENTS 6.1 Participation 6.1.1 All licensed personnel shall be required to porticipate in Requalification training.

6.1.2 Any newly licensed personnel shall enter the Requalification training program within 90 days of the etfective date of his/her license.

6.1.3 Any waivers of the scheduled Requalification training program shall be processed in accordance with IP-8.5.

Additionally, all requests for waiver of Requalificati0n training must be received by the Manager, OTD no later than 7 days prior to the date the training is scheduled.

6.1.4 All Iicensed personnel shall participate in all portions of OJT.

6.1.5 All NRC certified perscanel shall participate in OJT to the extent required to maintain their certification.

6.2 Requalification Training Requalification training shall be conducted for a continuous period, not to exceed two years, and upon conclusion shall be promptly

followed, pursuant to a

continuous

schedule, by successive requalification training.

Requalification training on an annual

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INTERDEPARTMENTAL PROCEDURE

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.22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE 0 1-15-86 basis shall consist of the following with emphasis placed on those areas where weaknesses have been demonstrated on previous license or requalification examinations:

o Classroom Training o

On-the-Job Training o,

Simulator Training o

Self Study o

Annual Examination / Evaluation 6.2.1 Classroom Training 6.2.1.1 Lectures Classroom requalification training lectures shall be scheduled to be given throughout the requalification period.

Periodic examinations shall be given at appropriate intervals to evaluate each individual's progress throughout the requalification program.

A minimum of six preplanned lectures per year shall be scheduled to cover all subjects within a year that are necessary to maintain operator proficiency.

Emphasis shall be placed on those areas where Requalification and/or license examinations indicate generic weaknesses in operator knowledge.

The general subj ect areas to be covered are:

o Theory and Principles of Operation o

General and Specific Plant Operating Characteristics o

Plant Instrumentation and Control Systems o

Plant Protection Systems o

Engineered Safety Systems Features o

Normal, Abnormal, and Emergency Operating Procedures o

Radiation Control and Safety o

Technical Specifications o

Applicable portions of 10 CFR o

Heat Transfer, Fluid Flow, and Thermodynamics o

Mitigating Core Damage In addition, pre-planned lectures may be conducted in thcsc areas identified by the Training or Operations Department as needing special emphasis.

These may include, but are not limited to major design changes, I&E Bulletins, LERs, Operating

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22 PAGE OF

-LICENSED OPERATot p g.IVECATION EFFECnVE DATE 01-15-86 Experience

Reports, Procedure and Technical Specification changes.

T:aining aids, such as films and sideo tapes, may be used to conduct certain portions of the lecture series.

These are particularly suitable to training on a specific piece of equipment or general information training. The use of such aids may be used only to supplement the lecture series and under no circumstances may they comprise more than 50% of the total lecture series. In addition, when utilizing supplemental training aid.s, the i

presentation shall be supervised by an instructor.

6.2.1.2 Required Reading During an assigned retraining week the Manager, OTD ciay assign items as required reading with time allotted for completion.

These required reading assignments may include, but are not limited to the j

following:

o Plant Procedures, Procedure Changes or New Procedures o

Plant Design Changes o

Plant License Changes o

Operating Experience Reports o

Portions of or changes to Technical Specifications 6.2.2 On-the-Job Training 6.2.2.1 Annually Licensed and certified personnel (each shift cycle) may be assigned to read specific Off-Normal, Eme rgency, and/or Applicable Security procedures.

These assignments shall be made by the Manager, OTD such that every year, personnel participating in Requalification training shall have reviewed the contents of all Off-Normal, Emergency, and/or applicable Security procedures which are not utilized during the staulator training session or i

are not covered during the classroom training.

6.2.2.2 Proficiency i

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3 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 All licensed personnel must actively perform the functions of an RO or SRO en shift to maintain proficiency.

The minimum time acceptable on shif t is one 8-hour shift day per month or three 8-hour shif t days per quarter.

All certified personnel must actively engage in the day to day shift operations to the extent required by their certification.

1 6.2.2.3 Control Manipulations All licensed personnel shall document the performance or supervision of the performance in the plant of any control manipulations required by section 6.2.3.1 of this procedure. Each entry into the control manipulation log nhall be dated and initialed by the Shift Supervisor or Unit Supervisor on duty at the time of the control manipulation.

Each completed control manipulation log sheet (Attachment 8.9-1) shall be forwarded to the Manager, OTD.

The Reactor Operations Manager should, to the extent possible, rotate personnel with equivalent qualification between diiferent stations to maximize the variation of plant control manipulations performed.

A control manipulation which may be performed as part of normal plant evolutions shall either be performed on the plant or a simulator which reproduces the. general operating characteristics of the plant.

6.2.3 Simulator Training The purpos'e 'of simulator training is to assure that all licensed personnel demonstrate proficiency in plant mac.ipulations, evolutions, and casualty operations.

All RO licensed personnel shall manipulate the controls to accomplish the control manipulations required in section 6.2.3.1 of this procedure..All SRO licensed personnel shall either manipulate the controls or direct the activities of individuals during plant control manipulations.

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I)tt1EDEPAR11tENTAL PROCIDU"AE 9

22

PAGE OF LICENSED OPERATOR EEQUALIFICATION

, WFtcTM DATE 01-15-86 Each control manipulation performed on the simulator shall be documented on a simulator training session observation record similar to Attachment IP-8.9-2 by the simulator instructor in charge of the training session.

NOTE:

This procedure assumes the operability of the STPZGS plant specific simulator, If the STPECS si:nulator is inoperab.',a, control manipulations may be performed by:

1.

Walkthrough actions in the control room or using simulated control boards.

2.

Simulation on a non plant specific simulator.

Training on the STPEGS.simulato; vould be scheduled as s?on as possible.

All licensed and certified personnel shall be assigned to a minimum of a five-day retraining course annually.

6.2.3.1 Control Manipulations The following control manipulations and plant evolutions are acceptable for meeting the control

nanipulations required.

The starred items are to be performed annually; all other items are to be performed on a two year cycle.

At least one multiple failure casaalty shall be included annually.

The use of Technical Speciffcations should be maximized during simulator control manipulations.

• o Picnt or reactor startupp to include a range such that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.

o Plant shutdown o

Manual control of steam generators and/or feedwater during startup and shatdown o

Boration and dilution during power operation o

Any significant (10 percent) power changes with rod control in manual

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SOUTH TEXAS PROJECT ELECTRIC CENERATIN3 STATlHN 1p.g,9 p.

INTERDEPARTMENTAL PROCEDURE 10 22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86

• o Loss of coolant including:

1.

Significant steam generator tube leak 2.

Inside and outside containment 3.

Large and small, including leakrate determination 4.

Saturated reactor coolant response

• o Loss of instrument air

• o Loss of electrical power (or degraded power sources, or both)

• o Loss of core coolant flow / natural circulation

• o Loss of condenser vacuum o

Loss of essential cooling water

• o Loss of all feedwater (normal and auxiliary) o Loss of residual heat removal o

Loss of component cooling system or cooling to an individual component o

Loss of normal feedwater or normal feedwater system failure o

Loss of protective system channel o

Mispositioned control rod or and rods (or rod drops)

\\

o Inability to drive control rods o

Conditions requiring the use of emergency boration o

Fuel cladding failure or high activity in reactor coolant or off gas o

Turbine or generator trip o

Malfunction of automatic control system (s) which affect reactivity t

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INTERDEPARTMENTAL PROCEDURE H

22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE

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O1-15-86 o

Malfunction of reactor coolant pressure / volume control system o

Reactor trip o

Main steam line break (inside or outside containment) e o

Nuclear instrumentation failure (s) 6.3 Program Evaluation 6.3.1 Written examinations shall be administered at appropriate intervals throughout the Requalification Program.

The Written examinations shall evaluate the subjects addressed by the preplanned lecture series and may include questions regarding any required reading which has been completed.

The minimum acceptable grade is 80%.

If a licensed

~

individual scores less than 80%,

he/she will require additional retraining.

6.3.2 Observations During each requalification year, each licensed individual shall be evaluated by their appropriate department head or his/her designee and document this evaluation using attachment IP-8-9 3.

This evaluation, in conjunction with supporting docucentation from simulator obse rvations (completed by NTD staff) shall be reviewed by the Manager, OTD.

If an area of unacceptable performance is noted, the Reactor Operations Manager shall be notified.

In addition, each individual that receives an unacceptable evaluation shall be entered into an accelerated Requalification training program as outlined in section 6.3.4 of this procedure.

6.3.3 Annual Examinations Annual written Requalification exams shall be administered to all licensed personnel. The annual written examination shall be comparable in scope and degree of difficulty to an NRC examination consistent with the type of license held.

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SOUTH TEXAS PROJECT ELECTRIC CENERATIN3 STATIEN IP-8.9 F-IFTERDEPARTMENTAL P N 12 22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE

""T" 01-15-86 6.3.4 Accelerated Requalification Training Should an operator score less than 70% on any section or less than 80% overall on the annual Requalification examination or fail the oral examination, he/she shall immediately be entered into and.

successfully complete accelerated requalifaction training.

Accelerated Requalification training shall be determined on an individual basis by the Manager, OTD.

The Reactor Operations Manager shall take the necessary actions for the individual to be relieved of all licensed duties until he/she successfully completes the assigned accelerated Requalification Training Program.

Accelerated Requalification training shall be given in the categories required or areas identified in the written or oral examination.

The assignment of accelerated Requalification training shall be made by means of a letter to the individual from the Manager of OTD via the Reactor Operations Manager.

Successful completion of the program i

shall be measured by a

re-examination of individual categories, completing an entire written examination or completing an oral examination as appropriate. A score of at i

least 70% on each previously failed section or 80% overall must be achieved.

l 6.4 Training Personnel NTD personnel who hold Operator Licenses / Instructor certifications, and other license holders who conduct training (classroom or simulator) or evaluation (develop, administer, review for approval, or grade examinations either oral or written) shall be credited with that portion of the Requalification program.

6.5 Proficiency If a licensed operator has not been actively performing licensed functions for the past four months, re-certification must be requested and approved by the NRC prior to allowing the individual to perform his/her licensed functions.

7.0 DOCUMENTATION j

The following documentation of the Licensed Operator Requalification Program shall be maintained for as long as each individual is employed at STPEGS.

In any event, each of the below listed records will be maintained in an auditable fashion for a minimum of five years.

F

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SOUTH TEXAS PROJECT ELECTRIC CENERATINO STATION INTERDEPARTMENTAL PROCEDURE g3 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE 01-15-86 7.1 Copies of written exams including answers and results 7.2 Copies of oral exam results 7.3 Documentation of additional training received 7.4 S,ummation of individual deficiencies 7.5 Copy of medical examinations / reports 7.6 Copy of performance evaluations conducted by the Reactor Operations staff 8.0 ATTACHMENTS 8.1 Attachment IP-8.9-1, Control Manipulation Logsheet 8.2 Attachment IP-8.9-2, Simulator Training Session Observation Record 8.3 Attachment IP-8.9-3, License Performance Evaluation l

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INTERDEPARTMENTAL PROCEDURE 14 22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 ATTACEMENT IP-8.9-1 CONTROL :1ANIPULATION LOGSHEET PAGE 1 0F 3 I.

PERSON PERFORMING CONTROL MANIPULATION:

RO/SRO (name)

(employee number) circle one SS/US Initial Date 1.

Plant or reactor startup to include a range that reactivity feedback from nuclear heat is noticeable and heatup rate is established.

2.

Plant shutdown.

3.

Manual control of steam generators and/or feedwater during startup or shutdown.

4.

Boration during power operation.

5.

Dilution during power operation.

6.

Any significant (> 10%) power change with rod control j

in manual.

7.

Loss of coolant including:

1.

Significant steam generator tube leak 2.

LOCA inside containment 3.

LOCA outside containment 4.

Large LOCA including leak rate determination 5.

Small LOCA including leak rate determination 6.

LOCA with saturated reactor coolout response

HL&PWW9640 NUlBER R EV.

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INTERDEPARTMENTAL PROCEDURE 15 22 PAGE OF LICENSED OPERATOE REQUALIFICATIt'i EFFECTIVE

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0 1-15-86 ATTACHMENT IP-8.9-1 CONTROL MANIPULATION LOGSHEET PAGE 2 0F 3 SS/US Initial Date 8.

Loss of instrument air.

9.

Loss of electrical power sources (or degraded power sources, or both).

10.

Loss of core coolant flow / natural circulation.

11.

Loss of condenser vacuum.

12.

Loss of Essential Cooling Water.

13.

Loss of all feedwater (normal and auxiliary).

14.

Loss of Residual Heat Removal.

15.

Loss of Component Cooling System or cooling to an individual component.

16.

Loss of normal feedwater or normal feedwater system failure.

17.

Loss of a protective system channel.

18.

Mispositioned control rod or rods (or rod drops).

19.

Inability to drive control rods.

20.

Conditions requiring the use of emergency boration.

21.

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

22.

Turbine or generator trip.

I 23.

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

24.

Malfunction of reactor coolant pressure / volume control system.

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SOUTH TEXAS PR? JECT ELECTRIC CENERATIN3 STATION 1p.g,9 p.

INTERDEPARTMENTAL PROCEDURE 16 22 PAGE OF LICENSED OPERATOR REQUALIFICAT1001 EFFECTIVE DATE 01- ;-86 ATTACHMENT IP-8.9-1 CONTROL MANIPULATION LOGSHEET PAGE 3 0F 3 SS/US Initial Date 25.

Reactor Trip.

26.

Main steamline break (inside or outside containment).

27.

Nuclear Instrumentation failure (s).

NOTES:

1.

• indicates annual requirement; all others required biannually 2.

All R0 licensed personnel are required to manipulate the controls; All SRO personnel shall either manipulate the controls or direct the activities of individuals during plant control manipulations.

INSTRUCTIONS FOR COMPLETING FORM:

1.

Place name and employee number in Block I.

2.

Circle either RO or SRO.

3.

Have the Shift Supervisor or Unit Supervisor on shift at the time of the control manipulation initial and date in the. columns provided for the control manipulations completed.

4.

NTD personnel will collect the cocpleted forms and supply new forms on a monthly basis.

ML&P 8680 (S84)

NULSER REV.

SOUTH TEXAS PROJECT ELECTRIC CENERATIN3 STAT 15N 1p_g,9 ga I

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,Ag, OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 ATTACHMENT IP-8-9.2 SIMULATOR TRAINING SESSION OBSERVATION RECORD PAGE 1 0F 5 Instructors:

Date:

Length in Hours:

Exercise / Practice /Scentrto/ Exam #-

Emergency, Abnormal Security Procedures Used/ Reviewed Shift Assignments Employee #

Reactivity Manipulations Completed SS Us R0 R0 STA Other EVALUATION A.

Supervisory Ability (N/A for RO, STA)

SS US RO RO STA 1.

Ef fectively directs operation of I

plant.

2.

Effectively directs actions of operators and utilization of resources.

3.

Ensures communication between j

operators passing along information 1

accurately and promptly.

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INTU DEPARTMENTAL PROCEDURE l8 22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 ATTACHMENT IP-8-9.2 SDEILATOR TRAINING SESSION OBSERVATION RECORD PAGE 2 0F 5 SS US RO RO STA 4

B.

Critical Response 1.

All operators communicate between other work station, passing along information accurately and promptly.

2.

Responds promptly and correctly to annunciators.

3.

Uses proper procedure, follows steps as designated.

4.

Coordination and dexterity:

Systematic and logical approach to operations, performs multiple tasks coincidentally.

5.

Periodic.v checks indications.

6.

Alertness - aware of plant conditions / evolutions.

7.

Team work aorks well as a team member.

C.

Diagnostic Ability 1.

Uses available instruments to diagnose problems correctly.

2.

Correctly prioritizes multiple casualties in order of importance.

3.

Monitors for trends to predict approaching problems.

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SOUTH TEXAS PR2 JECT ELECTRIC CENERATIN3 STATION IP-8.9 D2-INTERDEPARTMENTAL P N 19 22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 ATTACHMENT IP-8-9.2 SIMULATOR TRAINING SESSION OBSERVATION RECORD PAGE 3 0F 5 EVALUATION CRITERIA SATISFACTORY Operator perfor ance in this area is fully acceptable (e.g., takes appropriate actions on time).

• %\\RGINAL Operator performance in this area is acceptable, but some weaknesses are evident (e.g., improper action, but recovers before " loss of control" or delayed action).

• UNSATISFACTORY Operator perfe mance in this area is not acceptable (e.g.,

improper actions, no recovery or no action when required).

• Comments are required for all Marginal and Unsatisfactory ratings.

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2 INTERDEPARTMElfrAL PROCEDURE PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 ATTACHMENT IP-8-9.2 SDNITJLTOR TRAINING SESSION OBSERVATION RECORD PAGE 4 0F 5 SIMULATOR SESSION C000GNIS:

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PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE

,'" 01-15-86 ATTAC W.NT IP-8-9.2 SIMILATOR TRAINING SESSION OBSERVATION RECORD PAGE 5 0F 5 SESSION CRITIQUE: OVERALL GROUP EVALUATION:

SAT UNSAT N/A l

l STUDENT CopeENTS:

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INSTRUCTOR SIGNATURE:

I i

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l SOUTH TEXAS PR2 JECT ELECTRIC CENERATIN 3 STATEN rp_g,9 gA INTERDEPARIMEarfAL PROCEDURE 22 22 PAGE OF LICENSED OPERATOR REQUALIFICATION EFFECTIVE DATE 01-15-86 ATTACIDG!NT IP-8-9.3 LICENSE PERFORMANCE EVALUATION NAME:

R0 SRO NOTE: Observation / Evaluation of Individual Operator Performance to include actions taken during actual or simulated, normal, abnormal, and y

emergency conditions.

Evaluation: Actual Simulated

==

Description:==

Operator Performance: Satisfactory Unsatisfactory Comments:

If Performance Unsatisfactory - Corrective Action Recommendation:

Evaluation Performed By:

Date

• When complete forward Via Reactor Operations Manager to Manager OTD.

Reactor Operations Marrager Review:

Date Corrective Action Taken:

Corrective Action Completed By:

Date Reviewed:

nanager uiu vate neactor vperations uate Manager

a The Light COIII%

llouston Lighting & li wer !!O. Ilox 1700 1Iouston, Texas 77001 (713) 228-9211 February 27, 1986 ST-HL-AE-1610 File No.: G2.5 Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5 U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Licensed Operator Requalification Program

Dear Mr. Noonan:

During your staff's review of the South Texas Project Electric Generating System Nuclear Training Program late last year, your reviewer requested a copy of the Licensed Operator Requalification Program. At that time the program was in draft and we provided a draft copy to the reviewer. We have now issued Revision 0 of the program for use at STPEGS. Accordingly, we are forwarding the attached copy of Revision O.

There are no significant differences between the draft we provided last year and the attached.

If you should have any questions on this matter, please contact Mr. M. 3. McBurnett at (512) 972-8530.

Verytrulyyours, M. R. Wisynburg Manager, Nuclear Licensing MAM/1jm

Attachment:

Licensed Operator Requalification Program Rev. 0

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(D@)

l L3/NRC/cc

ST-HL-AE-1610 o-

' File No.: G2.5 l

Houston Lighting & Power Company l

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Hugh L. Thompson, Jr., Director Brian E. Berwick, Esquire Division of PWR Licensing - A Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 i

Robert D. Martin Lanny A. Sinkin Regional Adninistrator, Region IV Christic Institute Nuclear Regulatory Commission 1324 North Capitol Street 611 Ryan Plaza Drive, Suite 1000 Washington, D.C.

20002 Arlington, TX 76011 Oreste R. Pirfo, Esquire N. Prasad Kadambi, Project Manager Hearing Attorney U.S. Nuclear Regulatory Commission Office of the Executive Legal Director l

7920 Norfolk Avenue U.S. Nuclear Regulatory Commission i

Bethesda, MD 20814 Washington,'DC 20555 l

l Claude E. Johnson Charles Bechhoefer, Esquire Senior Resident Inspector /STP Chairman, Atomic Safety &

c/o U.S. Nuclear Regulatory Licensing Board l

Commission U.S. Nuclear Regulatory Commission P.O. Box 910 Washington, DC 20555 Bay City, TX 77414 Dr. James C. Lamb, III M.D. Schwarz, Jr., Esquire 313 Woodhaven Road Baker & Botts Chapel Hill, NC 27514 i

One Shell Plaza l

Houston, TX 77002 Judgc Frederick J. Shon Atomic Safety and Licensing Board J.R. Newman, Esquire U.S. Nuclear Regulatory Commission Newman & Holtzinger, P.C.

Washington, DC 20555 1615 L Street, N.W.

Washington, DC 20036 Mr. Ray Goldstein, Esquire 1001 Vaughn Building Director, Office of Inspection 807 Brazos and Enforcement Austin, TX 78701 U.S. Nuclear Regulatory Commission Washington, DC 20555 Citizens for Equitable Utilities, Inc.

c/o Ms. Peggy Buchorn T.V. Shockley/R.L. Range Route 1, Box 1684 Central Power & Light Company Brazoria, TX 77422 i

P.O. Box 2121 l

Corpus Christi, TX 78403 Docketing & Service Section l

Office of the Secretary H.L. Peterson/G. Pokorny U.S. Nuclear Regulatory Commission City of Austin Washington, DC 20555 P.O. Box 1088 (3 Copies)

Austin, TX 78767 Advisory Committee on Reactor Safeguards l

J.B. Poston/A. vonRosenberg U.S. Nuclear Regulatory Commission City Public Service Board 1717 H Street P.O. Box 1771 Washington, DC 20555 San Antonio, TX 78296 Revised 12/2/85