ML19322A761

Chapter 13 of Oconee 1,2 & 3 PSAR, Initial Tests & Operations. Includes Revisions 1-6

ML19322A761
Person / Time
Site:	Oconee
Issue date:	12/01/1966
From:	DUKE POWER CO.
To:
References
NUDOCS 7911210785
Download: ML19322A761 (6)

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t l TABLE OF CONTENTS 1

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13 INITIAL TESTS AND OPERATION 13-1

{ 13.1 TESTS PRIOR TO REACTOR FUELING 13-1 i 13.2 INITIAL CRITICALITY 13-1

) 13.3 POSTCRITICALITY TESTS 13-1 i

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l lO LIST OF TABLES Table g 13-1 Prefueling Test Program 13-2 13-2 Posteriticality Test Program 13-3 l

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13 INITIAL TESTS AND OPERATION 13.1 TESTS PRIOR TO REACTOR FUELING A comprehensive Oconee Nuclear Station field testing program will be carried out to insure that equipment and systems perform in accordance with design criteria.

The test program will begin 9 to 12 months prior to reactor fueling. As installation of individual components and systems is completed, they will be tested and evaluated. The testing program will be carried out according to detd. led predetermined testing techniques and procedures. Field analysis and more detailed office analysis of cest results will be made to' verify that systems and components are performing satisfactorily or to recommend necessary corrective action.

In general, the types of tests will be classified as hydrostatic, operational, electrical and functional.

Operational tests will involve actual operation of the system and equipment under design conditions, or simulated design conditions. Functional tests will verify that the system or equipment is capable of performing the func-tion for which it is designed. A summary of the prefueling test program is given in Table 13-1.

13.2 INITIAL CRITICALITY Fuel loading will begin when all prerequisite unit tests and operations have been satisfactorily completed. Core components will be loaded in a predeter- ,

mined sequence. Changes in core suberitical multiplication will be measured l and evaluated; a detailed checkoff list will be followed; and periodic checks made to insure proper status of all equipment, conditions and core components.

Initial criticality will take place by control rod withdrawal and core boron i concentration adjustment.

13.3 POSTCRITICALITY TESTS A series of posteriticality tests will be conducted at ambient and hot zero power and at various power levels up to rated power. These tests will be used to evaluate temperature, pressure, power and boron reactivity coeffi-cients; control rod reactivity worths; the reactivity worth of xenon-135; and core reactivity depletion versus burnup. The reactor coolant system flow will be evaluated and the external and incore nuclear instrumentation systems calibrated at various power levels. The unit response characteristics to step and ramp load changes will be evaluated and adjustments made to the con-trol systems as required. A complete shield survey will be conducted. Field analysis and a more detailed office analysis of test results will be made.

A summary of the posteriticality tests is given in Table 13-2. ,

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Prefueling Test Program i

Type of Test Opera- Elec- Func-

Hydro tional trical tional

1. Reactor Building and Penetrations '

Leak Rate Test x l

2. Electrical Systems Continuity x l

3. Control Rod Drive Assemblies x x x l

4. Reactor Building and Component '

l Cooling System x x x  !

5. Recirculated Cooling Water System x x x

6. Reactor Building Spray System x x x )

7. Cooling Water Systems x x x

8. Low Pressure Injection and Decay Heat Removal System x x x x

9. Quench Tank x x

10. Reactor Coolant System Relief Valves x x

11. Chemical Addition and Sampling System x x x

12. High Pressure Injection ard Purifica-tion System x x x x

13. Reactor Coolant Pumps x x x

14. Nuclear Instrumentation Cable Tests x

15. Nuclear Instrumentation and Protec-tive Systems x x

16. Integrated Reactor-Boiler-Turbine Control System x x

17. Reactor and Auxiliary Systems Nonnuclear Instrumentation x x x

13. Reactor Coolant System x s 19. Reactor Coolant System Hot Func-tional Test x x x 13-2

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Table 13 continued Type of Test Opera- Elec- Func-Hydro tional trical tional

20. Reactor Building Fuel Handling System x x x

21. Fuel Handling and Storage Area Fuel Handling System x x x

22. Area Radiation Monitoring Systems x x

23. Incore Instrumentation System x x x

24. Waste Disposal System x x x

25. Spent Fuel Cooling System x x x

26. Emergency Power Systems Tests x x x

27. Initial Fuel Loading x

$T. CcRE ft.coONVG $yST M K h A Table 13-2 Posteriticality Test Program

1. Initial criticality and Excess Reactivity

2. Reactivity Coefficients and Rod Worths

3. Stuck Rod Margin Verification

4. Power Coefficient and Power Defect

5. Reactivity Coefficients at Power

6. Xenon Reactivity Worths .

7. Reactor Coolant System Flow Test

8. Incore and External Nuclear Instrumentation Calibration

9. Unit Load Steady State and Transient Tests

10. Biological Shield Survey

11. Unit Loss-of-Electrical-Load Tests

12. Core Reactivity Depletion Rate Versus Burnup 13-3 ,,,.

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