ML19329E146

Chapter 13 of AR Nuclear 1 PSAR, Initial Tests & Operation. Includes Revisions 1-18

ML19329E146
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/24/1967
From:	ARKANSAS POWER & LIGHT CO.
To:
References
NUDOCS 8005300730
Download: ML19329E146 (5)

Text

TABLE OF CONTE:ITS Section Pg 13 INITIAL TESTS AND GPERATI0ti 13-1 13.1 TESTS PRIOR TO REACTOR FUELING 13-1 13.2 INITIAL CRITICALITY 13-1 13.3 POSTCRITICALITY TESTS 13-1 m

oW-8005300 ]lj3Q 13-1

LIST OF TABLES Table Pace 13-1 Prefueling Test Program 13-2 y 13-2 Posteriticality Test Program 13-3 l

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i 13 INITIAL TESTS AND OPERATION 13.1 TEST PRIOR TO REACTOR FUELING A comprehensive field testing progra= for the Russellville nuclear Unit will be carried out to insure that equipment and systems perform in accordance with design criteria.

The test program vill begin about nine months before reactor fueling. As the installation of individual compenents and systems is completed, they will be tested and evaluated. The testing program vill be carried out according to detailed predetermined testing techniques and procedures. Field analysis and more detailed office analysis of test results will be made to verify that sys-tems and components are performing satisfactorily or to recommend necessary corrective action.

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

Operational tests will involve actual operation of the syste= and equipment under design conditions, or simulated design conditions. Functional tests will verify that the system or equipment is capable of performing the function for which it is designed. The prefueling test program is summarized in Table 13-1.

13.2 INITIAL CRITICALITY Fuel loading vill begin when all prerequisite unit tests and operations have been satisfactorily completed and the "acility operating license has been ob-tained. Core components vill be leaded in a predetermined sequence. Changes in core suberitical multiplication vill be measured and evaluated; a detailed checkoff list will be followed; and periodic checks will be made to insure proper status of all equipment, conditions, and core cc=ponents. Initial crit-icality will take place by control red withdrawal and core boren concentration adjustment.

13.3 POSTCRITICALITY TESTS A series of posteriticality tests vill be conducted at ambient and hot zero pcVer, and at various pcVer levels. These tests vill.be used to evaluate tem-perature, pressure, power, and boron reactivity coefficients; control red re-activity worths; and the reactivity worth of xenon-135 The reactor coolant system flow will be evaluated, and the external and incere nuclear instrumenta-tion systems will be calibrated at various power levels. The unit response characteristics to step and ramp load changes vill be evaluated, and the con-trol systems will be adjusted as required. A complete biological shield survey will be conducted. Field analysis and a more detailed office analysis of test results will be made.

The posteriticality tests are su==arized in Table 13-2.

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l I Table 13-1 Prefueling Test Program Type of Test Func- Elec- Opera-Hydro tional trical tional l' . Reactor Building and Penetra- '

tions Leak Rate Test x

2. Electrical Systems Continuity x

3. Control Rod Drives x x x

h. Reactor Building Cooling System x x x 5 Intermediate Cooling System x x x

6. Reactor Building Spray System x x x 7 Service Water System x x x

8. Decay Heat Removal System x x x x 9 Quench Tank x x -

10. Reactor Coolant System Relief j Valves x x

11. Chemical Addition and Sampling System x x x

12. Makeup and Purification System x x x x

13. Reactor Coolant Pumps x x x

14. Nuclear Instrumentation Cable Tests x 15 Nuclear Instrumentation and Protection Systems x x

.16. Integrated Control System x x 17 Reactor and Auxiliary. Systems Nonnuclear Instrumentation x x x

-18. Reactor Coolant System x 19 Reactor Coolant System Hot Functional Testing x x x

20. CoreFloEdingSystem x ~x; 13-2 0294

Table 13-1 (Cont'd)

Tyre of Test Func- Elec- Opera-Hydro tional trical tional

21. Reactor Building Fuel Handling System x x x

22. Auxiliary Building Fuel Handling System x x x 23 Area Radiation Monitoring Systems x x

24. Incore Monitoring System x x x 25 Waste Disposal System x x x

26. Spent Fuel Cooling System x x x 27 E=ergency Power Systems Tests x x x

28. Initial Fuel Loading x 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 Tests

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 025 13-3