ML20028F095

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Forwards Response to NRC 821116 Request for Addl Info Re NUREG-0737,Items I.A.2.1.4, Upgrading of Reactor Operator & Senior Reactor Operator Training, & II.B.4, Training for Mitigating Core Damage.
ML20028F095
Person / Time
Site: Brunswick  
Issue date: 01/26/1983
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
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 NUDOCS 8301310145
Download: ML20028F095 (3)


Text

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O Cp&L Carolina Power & Light Company JAN 261983 Director of Nuclear Reactor Regulation Attention: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 NUREG-0737 ITEMS I. A. 2.1.4 AND II.B.4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION

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Dear Mr. Vassallo:

We have received your November 16, 1982 letter concerning NUREG-0737 Items I. A.2.1.4, Upgrading of R0 and SRO Training, and II.B.4, Training for Mitigating Core Damage, for the Brunswick Steam Electric Plant, Unit Nos. I and 2. You requested Carolina Power & Light Company (CP&L) to provide certain additional information needed for you to couplete your review of the above items. Accordingly, you will find enclosed responses to the questions raised concerning these items.

If you need any additional information, please contact our staff.

Yours very truly, fttw S. IG-Z mmerman Manager Licensing & Permits WRM/ mag (5999C13T1)

Enclosure cc: Mr. D. O. Myers (NRC-BSEP)

Mr. J. P. O'Reilly (NRC-RII)

Mr. S. D. MacKay (NRC) 8301310145 830126 PDR ADOCK 05000324 P PDR Q 411 Fayetteville Street

  • P. O. Box 1551
  • Raleigh, N. C 27602

ENCLOSURE BRUNSWICK STEAM ELECTRIC PLANT NUREG-0737 ITEMS I. A.2.1.4 AND II.B.4 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC QUESTION NO. 1:

Item II.B.4 of NUREG-0737 requires training for mitigating core damage to be provided to the manager and technicians in the instrumentation and control, health physics, and chemistry areas commensurate with their responsibilities. Describe in detail the program to provide training / retraining to these personnel.

CP&L RESPONSE:

The programs to provide training / retraining to managers and technicians in the instrumentation and control (I&C), health physics, and chemistry areas commensurate with their responsibilities have been revised to incorporate

" mitigating core damage" training. The training of management personnel includes classroom training which provides accident mitigation wopics.

Health physics and chemistry personnel received, and will receive on an annual basis as part of their required classroom time, a lecture on mitigating core damage which includes topics such as (1) reactor core inventory, (2) types of fuel failure, (3) expected fission product distribution and concentrations resulting from an accident, (4) hydrogen generation under accident conditions, (5) radiation monitors, and (6) need for radiation surveys and chemistry sampling.

I&C Technicians received a lecture specifically on accident mitigation with core damage. Items pertaining to the topic have been included in specific related lesson plans. For example, the following modules pertain to the topic : EN00lG, Transducers; EN003G, Electronic Recorders; PN001G, Basic Pressure Theory; and others.

NRC QUESTION NO. 2:

[ Carolina Power & Light Company in TI-200 allows any operator who j ". . . clearly shows he would have passed an NRC exam . . ." on a particular l subject (with a score of PC' or greater) to be exempt f rom lectures on that j subj ec t. Explain or define how this determination is made without taking the l test.

l CP&L RESPONSE:

The quotation f rom TI-200, on exempting licensees (i.e. , licensed operators) fron lectures on a specific subject, is taken from the section describing results of the annual requalification exam. The results of the exam atu used

i to (1) schedule the following year's training, (2) determine the required accelerated training for deficient operators, and (3) allow exemption from retraining lectures. Although the option allowing exemption f rom the following year's lectures has been in the program since its original approval in 1974, operators have not exercised this option since 1976. La other words ,

if a licensee scores 80% or better on a topic on the annual exam, he does not have to attend lectures on that topic during the following year's scheduled requalification lectures. In actual practice, however, licensees have not used this option, because they are s till required to be examined on the topic

! each year.

NRC QUESTION NO. 3:

Carolina Power & Light Company did not require the Plant Operations Manager, Maintenance Manager, Environmental and Radiation Control (E&RC) Manager, or General Manager to take a test following accident mitigation training.

Carolina Power & Light Company should demonstrate how a determination is made that the above personnel know the subject matter required by Enclosure 3 to Denton's March 28, 1980 letter.

NOTE: The TER states that the Manager-Plant Operations and General Manager took the exams; however, the CP&L letter to NRR dated May 10, 1982, stated that the test was not taken by these two people.

CP&L RESPONS_E:

As of May 10, 1982, neither of the managers listed had been tested. However, the Plant Operations Manager and General Manager were tested af ter they completed the lecture they missed.

The Maintenance Manager and E&RC Manager are presently enrolled in the Hot License Class, where they will be evaluated on this topic along with the other topics in the course. Other supervisory personnel who have assumed positions requiring this training and have not received the required training will attend the appropriate sessions during the current licensing class.

Part of the Brunswick Improvement Program is to provide additional systems training, including written tests, to all management personnel on a continuing basis.

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