ML20054E335

Forwards Response to NRC 820518 Request for Addl Info on NUREG-0737,Items I.A.2.1 Re Upgraded Reactor & Senior Reactor Operator Training & II.B.4 Re Training for Mitigating Core Damage

ML20054E335
Person / Time
Site:	Cooper, Fort Calhoun
Issue date:	06/01/1982
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Vassallo D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.2.1, TASK-2.B.4, TASK-TM LQA8200023, NUDOCS 8206110083
Download: ML20054E335 (4)

Text

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COOPER NUCLEAR S TAHON Nebraska Public Power District

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LQA8200023 June 1, 1982 Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Upgraded SRO and R0 Training and Training for Mitigating Core Damage - Request for Additional Information

Reference:

(1)

D. B. Vassallo letter of May 18, 1982, same subject (2)

H. R. Denton letter of March 28, 1980, Qualification of Reactor Operators (3) NUREG-0737 Item Nos. I.A.2.1 and II.B.4 for the Cooper Nuclear Station

Dear Mr. Vassallo:

The response of Cooper Nuclear Stari6n to reference (1) is included in the enclosure to this letter. The response pertains to those specific items of references (2) and (3).

Sincerely,

1. P11 ant Director of Licensing and Quality Assurance JMP:KRW:cg Attach.

cc:

br. R. T. Liner w/ attach.

Science Applications, Inc.

1710 Goodridge Drive McLean, Virginia 22102

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I 8206110083 820601 DR ADOCK 05000285 p

PDR

I, Additional Information es Raqussted in May 18, 1982 Paga 1 of 2 Letter Fron D. B. Vaccallo to J. M. Pilent 1.

Instruction in heat transfer, fluid flow, and thermodynamics is required in the CNS Training Program for all licensed operators and covers all the concepts and topics called out in enclosure 2 of d

l Denton's March 28, 1980 letter.

Requalification instruction in heat transfer, fluid flow, and thermodynamics is required whenever the results of the annual licensed operator requalification exam-ination demonstrates the need for such instruction.

2.

The elements of the CNS Training Program for licensed operators which are pertinent to BWR accident mitigation involving a degraded core address all of the areas identified in enclosure 3 of Denton's March 28, 1980 letter. Many of the areas are addressed in the abnormal and emergency procedures which all licensed operators are required to review annually. Formal classroom requalification training on accident mitigation involving a degraded core will i

include all pertinent areas in enclosure 3 of Denton's March 28, 1980 letter.

3.

The CNS Training Program elements which include heat transfer, fluid flow, thermodynamics, and accident mitigation involve 80 4

contact hours or more when presented to personnel having little previous background in these subjects. Presentation of these same subjects to personnel having extensive technical backgrounds on a requalification program may require less time based on the ability l

of the class to progress through the elements of instruction.

4.

The CNS Licensed Operator Training Program has been modified to provide increased emphasis on reactor and plant transients. This has been accomplished by:

a.

Increased emphasis in plant systems training, on the tran-sients produced by system malfunctions, and the effect on the system of transients produced external to the system.

I b.

Increased emphasis on the integrated response of reactor plant systems to both normal operating transients and abnormal /

accident transients.

l c.

Annual simulator training with emphasis on. reactor and plant I

response to normal and abnormal (accident) transients has been l

scheduled for the year 1982 with tentative annual dates es-tablished through 1985.

5.

All but one of the instructors conducting the CNS Training at.J Requalification Programs are licensed operators or senior reactor operators who are enrolled in the CNS Licensed Operator Training i.

Program which, in conjunction with their daily duties, keeps them aware of current plant operating history, problems, and changes in administrative limits. The one instructor who is not licensed l

teaches plant theory and instrumentation.

He !s kept aware of appropriate plant conditions and changes by reviewing all design j

changes, Technical Specification changes, procedure changes, and j

daily review of control room logs. Additionally, this individual reviews all Operations Department required reading,

Page 2 of 2 6.

Lectures and quizzes on accident mitigation were given to the following:

Station Superintendent Assistant to Station Superintendent Technical Assistant to Station Superintendent Operations Supervisor Shift Supervisor /STA (5)

Shif t Supervisor / Training (1)

Shif t Supervisor (1)

STA/ Engineer (2)

Licensed Operators The training was also given to the following plant personnel:

Engineering Supervisor Chemistry & Health Physics Supervisor Maintenance Supervisor Quality Assurance Supervisor Training Coordinator (Educational Specialist)

Instrument and Control Supervisor Maintenance Coordinator Reactor / Nuclear Engineers Instrument and Control Engineer Electrical Engineer Mechanical Engineer Quality Assurance Specialists Plant Engineer Plant Chemist Station Operators 7.

In response to the concern involving our letter of October 1, 1980 requesting exemptions concerning control manipulations for super-visory personnel maintaining SRO licenses, the following procedures have been implemented:

Simulator training is now scheduled on an annual basis cur-a.

rently through 1985. Senior supervisory SRO qualified per-sonnel have been assigned along with the crews to participate in and evaluate the necessary manipulations at the simulator.

b.

A log of such activities is also being maintained in the i

control room whereby supervisory personnel indicate their direction or evaluation of actual manipulations performed on this plant.

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Q, CNS ORGANIZATION CHART 1

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