ML19269B153

Forwards marked-up Fsar,Section 13.2.2.3 Revising Licensed Operator Requalification Training Program,In Response to J Jaudon Request.Revs Will Be Incorporated Into Future FSAR Amend

ML19269B153
Person / Time
Site:	River Bend
Issue date:	03/01/1985
From:	Booker J GULF STATES UTILITIES CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RBG-20-271, NUDOCS 8503110214
Download: ML19269B153 (8)

Text

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9 GULF STATES UTILITIES COME>ANY

• G PO$T OFrICL box 2951 - DEAUMONT. TCXAS 77704 AREA CODE 713 838 6631 March 1, 1985 RBG- 20,271 File No. G9.5 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

River Bend Station - Unit 1 Docket No. 50-458 Enclosed is the Gulf States Utilities Company (CSU) response to the verbal request from Mr. Jons Jaudon (Nuclear Regulatory Commission, Region IV) regarding the River Bend Station (RBS) Licensed Operator Requalification Training Program. These revisions to Section 13.2.2.3 of the Final Safety Analysis Report (FSAR) simply provide additional clarifications for programs already in use at RBS and reflected in approved Nuclear Training Department procedures. The revisions included in Enclosure 1 will be incorporated into a future FSAR amendment.

Sincerely,

f. $,

J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group JEB/WJR/JWL/j e Enclosure Cit 24R'%cya f 6 8503110214 850301 PDR ADOCK 0b000458 V PDR

4 RBS FSAR Individual study on the part of each operator is ..

_ encouraged. A requalification program based solely upon the use of films, videotapes, and/or individual study is not an acceptable substitute for the lecture series.

3. On-the-job training' - The requalification program includes on-the-job training so that:

a. Each licensed operator at RBS manipulates the plant controls and each' licensed Senior -

Operator shall either manipulate the controls or direct the activities of individuals during plant control n anipulations in any combination of reactor startups, reactor shutdowns or other control manipulations which demonstrate skill and/or familiarity - with reactivity control systems./ The on-the-job training with respect to reactivity control manipulations, /y will incorporate the guidance specified in Enclosure 4 of H. R. Denton's letter dated March 28, 1980. / The use of a simulator for yearly retraining may fulfill the 10 reactivity control manipulation requirements, and will include as a minimum 12 days per year on a 3-day-per-quarter basis. During this segment, emphasis will be placed on polishing and refining operational skills and knowledge necessary to control the plant during normal, abnormal, and emergency conditionc. Special emphasis will be directed toward observed trouble areas or upcoming evaluations.

Additionally, the use of procedures and other administrative documents will be stressed as part of the requalification program.

Insert

b. Each licensed RO and SRO demonstrates satisfactory understanding of the operation of all apparatus and mechanisms and knows the operating procedures in each area for which he is licensed,

c. Each licensed RO and SRO is cognizant of facility design changes, procedure changes, and facility license changes.

d. Each licensed RO and SRO reviews the content an annual of all abnormal and emergency procedures ony aJF

'regulcrly ccheduled basis.

Amendm.ent 11 13.2-40 January 1984 CE)

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Insert for page 13.2-40 The following control manipulations will be performed at least once every two years:

1. Plant shutdown

2. Any reactor power change of 10% or greater where load change performed with load limit control

3. Loss of instrument air

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

5. Loss of condenser vacuum

6. Loss of shutdown cooling

7. Loss of component cooling system or cooling to an individual component

8. Loss of normal feedwater or normal feedwater system failure

9. Loss of protective system channel

10. Mispositioned control rod or rods (or rod drops)

11. Inability to drive control rods

12. Conditions requiring use of standby liquid control system

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

14. Turbine or generator trip

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

16. Malfunction of reactor coolant pressure / volume control system

17. Reactor trip

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

19. Nuclear instrumertation failure (s) (SRM/IRM/LPRM/APRM)

20. Loss of plant service water (normal / standby)

21. Diesel generator failure

22. Excessive feedwater addition at power

The following control manipulations will be performed at least once every year:

1. Plane or reactor start-ups to include a range that reactivity feedback from nuclear heat addition is noticeable and heatup rate is established

2. Manual control or feedwater during startup and shutdown

3. Any significant (greater than 10%) power changes in manual recirculation flow

4. Loce of coolant including:

a. Inside and outside primary containment

b. Large and small, including leak-rate determination

5. Loss of core coolant flow / natural circulation

6. Loss of all feedwater (normal and emergency)

7. Total station blackout (loss of offsite and onsite A.C.)

RBS FSAR

4. Evaluation Cn.e .%sfxt integral part of the continuous and ongoing 48

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An Operator Requalification Program will be gn annual performance evaluationr " Thic evalu r:ri e:d will normally be completed based on an individual's performance on the Simulator. However, as available, input from the licensed individual's supervisor (s) will be incorporated into the performance evaluation.

Key elements to be addressed in completing the' evaluation will include:

a. The ind'ividual's ability to recognize and diagnose abnormal / emergency situations,

b. The ability of the individual to progress from the recognition of the abnormal / emergency situation to the appropriate plant procedure (s) designed to cope with or mitigate the consequences of the existing condition.

c. The ability of the individual to use and/or adapt the applicable procedure (s) to the situation at hand, f..

s T' d. The ability of the individual to perform competently the steps of the applicable procedure (s).

e. The ability of the individual to relate the existing condition (s) to established Administrative Policies / Guidelines including the Plant Emergency Plan and the River Bend Technical Specifications.

Documentation of the above evaluations will be reviewed by the Operator Training Evaluation Committee. The results of this review will be utilized to upgrade the content of the Operator Requalification Program.

Following completion and review of an individual's Annual Performance Evaluation an / r the results of the annual written examination, a determination by the Operator Training Evaluation Committee will be made as to the competency of a licensed individual to execute the duties associated with his/her job.

If the determination is such that the competency of

, Amendment 11 13.2-41 January 1984

Insert for page 13.2-41 Evaluation of licensed R0 and SRO personnel consists of an annual written examination and an annual performance apprais~al.

The written examination is formulated to examine the topical areas discussed in Section 13.2.2.3.2 and is divided fato the same categories as the NRC administered reactor operator and senior reactor operator examinations. The criteria for a passing grade for the annual requalification examination shall be 80% overall and 70% for each category.

RBS FSAR the individual is deemed inadequate, he/she will be

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removed from independent shift assignment until g g.

deficient areas are corrected. The correction could consist of either documented classroom lectures, required reading, or simulator / training.

The ongoing program of evaluation and feedback is implemented via direct feedback at meetings with plant staff and supervisory personnel, in-class evaluation of instructors and students, and review of student performance. Training effectiveness, and changing training needs, meeting course performance objectives are stressed in the evaluation phases.

13.2.3 Training Program Documentation Records are maintained to document each person's participation in this program. / These records include:

Insert

1. Attendance records

2. Copies of all operator requalification examinations given with acceptable answers

3. Copies of the answers to these examinations

4. Results of performance evaluations of licensed CP operrtors

5. Records of any additional training given to correct exhibited deficiencies of licensed operators

6. On-the-job training records

7. Copies of licenses of all operators

8. Records for personnel other than operators as addressed in ANS 3.1-1978.

13.2.4 Applicable NRC Documents The River Bend Station training program follows the regulations and considers the guidance listed below:

1. 10CFR Part 50, Domestic Licensing of Production and Utilization Facilities

2. 10CFR Part 55, Operators' Licenses Amendmant 11 13.2-42 January 1984

Insert for page 13.2-42 These records will be maintained in the Permanent Plant File for a minimum of two years.