ML19253B004

Forwards Responses to Two Operator Licensing Branch Questions Transmitted by 790810 Ltr to Hg Parris.Responses Will Be Included in Amend 62

ML19253B004
Person / Time
Site:	Sequoyah
Issue date:	09/10/1979
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Rubenstein L Office of Nuclear Reactor Regulation
References
NUDOCS 7909140343
Download: ML19253B004 (3)

Text

TENNESSEE VALLEY AUTHORITY CH ATTANCCGA. TrNNESSEE 374o1 400 Chestnut Street Tower II September 10, 1979 Director of Nuclear Reactor Regulation Attention: Mr. L. S. Rubenstein, Acting Chief Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory CoI:nission Washington, DC 20555

Dear Mr. Rubenstein:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 Enclosed are responses to the two Operator Licensing Branch questions transmitted by your letter to H. G. Parris dated August 10, 1979.

These responses will be incorporated in Amendment 62 of the Sequoyah Nuclear Plant Final Safety Analysis Report as questions 13.18 and 13.19.

We expect to provide responses to the remaining questions of your August 10, 1979, letter no later than September 14, 1979.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosures 343161

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OPERATOR LICENSING BRANCH (441.1) 13.18 Amendment 59 fails to describe the Hot License Program.

Infornation should describe the training and length of courses involving lecture series, on-the-job training, reactivity changes, and simulator training.

Response

The applicant must meet all requirements to qualify for the hot-license examinations as specified in Appendix F, " Eligibility for Examination with No Reactor Startup Demonstration," of the NRC Operator Licensing Guide, NUREC-0094.

The hot-license operator training program is designed to prepare the trainee for the NRC reactor operator written examination and operating test. The first 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> include classroom lectures, and an audit-type examination presented at the plant to prepare the trainee for the Nuclear Regulatory Commission (NRC) written examination.

The last 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of training, which include 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> for review and certification examination, are scheduled at the Power Production Training Center. This training shall satisfy reactor startup eligibility require-ments to qualify for the NRC examiniation and prepare the trainee for the NRC operating test. Simulator instruction is limited to no more than four trainees in the control room at one time.

Presentations totaling 500 lecture hours listed in ANSI N18.1-1971, Section 5.2.1 relate to subjects and prerequisite courses. This 500-hour requirement is included in the Nuclear Student Operator Training Program as described in section 13.2.1.1.

A certification examination is administered at the end of the simulator training session.

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OPERATOR LICENSING BRANCH (441.2) 13.19 Specify the reactivity control manipulations that will be performed by licensed personnel as part of the retraining program. NRC must approve the control manipulations purcuant to 10 CFR .' art 55, Appendix A.

Response

The following control manipulations are used at the plant during normal operation and/or at the simulator to meet the required 10 reactivity control manipulations. Employees with SRO licenses are credited with these activities if they direct or evaluate control manipulations as they are performed. A minimum of 10 reactivity control manipulations in any combinations of startup, shutdowns, or other manipulations will be performed by eac h operator each year.

1. Plant or reactor startups to include a range that reactivity feedback from nuclear heat addition is noticeable.

2. Plant shutdown.

3. Manual control of steam generators during startup and shutdown.

4 Operation of turbine controls in manual during startup.

5. Boration during power operation.

6. Dilution of the reactor coolant system.

7. Refueling operations where fuel is moved into the core.

8. Rod drop timing tests.

9. Significant (> 10%) power changes in manual rod control.

10. Manual rod control bufore and during generator synchronization.

11. Plant and reactor operation that involves emergency or transient procedures where reactivity is changing.

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