ML19319C268

Chapter 13 to Davis-Besse PSAR, Initial Tests & Operation.

ML19319C268
Person / Time
Site:	Davis Besse
Issue date:	08/01/1969
From:	TOLEDO EDISON CO.
To:
References
NUDOCS 8002110732
Download: ML19319C268 (6)

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TABLE OF CONTENTS

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Section g 13 INITIAL TESTS AND OPERATIoq 13-1 1

13.1 TESTS PRIOR TO REACTOR FUELING 13-1

13.2 INITIAL CRITICALITY 13-1 -

i 13.3 POSTCRITICALITY TESTS 13-1 i

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D-B LIST OF TABLES D, Table Page 13-1 Prefueling Test Progrms 13-2 13-2 Posteriticality Test Program 13-3

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D-B 13 INITIAL TPSTS AND OPERATION 13.1 TESTS PRIOR TO REACTOR FUELING A comprehensive field testing program for the Davis-Besse Station vill be car-ried out to insure that equipment and systems perform in accordance with de-sign criteria.

The test program vill begin about nine months before reactor fueling. As the installation of individual components 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 compcnents are performing satisfactorily or to reccmmend necessary corrective action.

In general, the types of' tests will be classified as hydrostatic, functional, electrical, and operational. l Operational tests vill involve actual operation of the system and equipment l under design conditions, or simulated design conditions. Functional tests vill 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

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Fuel loading vill begin when all prerequisite unit tests and operations have 1 i

been satisfactorily completed and the facility operating license has been ob- '

tained.  ! ore components vill be loaded in a predetermined sequence. Changes in core s .beritical multiplication vill be measured and evaluated; a detailed checkoff .ist vill be followed; and periodic checks vill be made to insure i proper status of all equipment, conditions, and core components. ~

Initial crit- l icality vill take place by control rod withdrawal and reactor coolant boron con-centration adjustment.

13.3 POSTCRITICALITY TESTS A series of posteriticality tests will be conducted at ambient and hot zero power, and at various power levels. These tests vill be used to evaluate reactivity coefficients; control rod reactivity worths; and the reactivity l vorth of xenon-135 The reactor coolant system flow will be evaluated, and the external and incore nuclear instrumentation systems will be calibrated at various power levels. The unit response characteristics to step and ramp load changes vill be evaluated, and the' control systems will be adjusted as  ;

required. A complete biological shield survey will be conducted. Field d analysis and a more detailed office analysis of test results will be made.

The posteriticality tests are summarized in Table 13-2.

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Table 13-1 -

Prefueling Test Program Type of Test Func- Elec- Opera-Hydro tional trical tional

1. Containment Vessel and Penetrations Leak Rate Test x

2. Electrical Systems Continuity x 3 Control Rod Drives x x x

h. Containment Vessel Energency Cooling System x x x 5 Intermediate Cooling Syste x x x x

6. Containment Vessel Spray System x x x 7 Nuclear Services Cooling Water System x x x x

8. Decay Heat Removal System x x x x 9 Reactor Coolant D ain Tank x x 1

10. Reactor Coolant System Relief l

Valves x x l

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11. Chemical Addition System x x x x l

12. Makeup and Purification System x x x x j

13. Reactor Coolant Pu=ps x x x i lb. Nuclear Instrumentation Cable Tests x 15 Safety Features Actuation System

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16. Nuclear Instru=entation and Protection Systems x x 17 Integrated Control System x x x

18. Reactor and Auxiliary Systess Nonnuclear Instrumentation x x x

19. Reactor Coolant System x .

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D-B l' Table 13-1 (Cont'd)

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

20. Reactor Coolant System Hot Functional Testing x x x

21. Core Flooding System x x

22. Containment Vessel Fuel Handling System x x x

23. Fuel Handling System for Fuel Handling Building x x x

24. Area Radiation Monitoring Systems x x 25 Incore Monitoring System x x x

26. Waste Disposal System x x x x 27 Spent Fuel Cooling System x x x

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28. Sampling System x x x x 29 E=ergency Power Systems Tests x x x

30. 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 Reactivity Coefficients at Power 5 Xenon Reactivity Worths

6. Reactor Coolant System Flow Tests 7 Incore and External Nuclear Instrumentation Calibration

8. Unit Load Steady State and Transient Tests 9 Biological Shield Survey q

10. Unit Loss-of-Electrical-Load Tests 0940 13-3