ML19329D995
| ML19329D995 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/31/1967 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8004090523 | |
| Download: ML19329D995 (10) | |
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O TABLE OF CONTENTS 13.
INITIAL TESTS AND OPERATION Section Page 13.1 TESTS PRIOR TO REACTOR FUELING 13.1-1 13.2 INITIAL CRITICALITY 13.2-1 13.3 POSTCRITICALITY TESTS 13.3-1 l
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LIST OF TABLES Table Ntrmber Title 13.1-2 13.1-1 Prefueling Test Program 000 0150 l
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00 Amendment 3 13-1
13.
INITIAL TESTS AND OPERATION 13.1 TESTS PRIOR TO REACTOR FUELING A comprehensive field testing program for the Rancho Seco Plant Unit I will be carried out to ensure that equipment and systems perform in accordance with design criteria.
The test program for the unit will begin nine months before reactor fuel-ing.
As the installation of individual components and systems is completed, they will be tested and evaluated. The testing program will 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 systems and components are performing satisfactorily or to recommend necessary corrective action.
In general, the types of tests will be classified as hydrostatic, opera-tional, 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. The prefueling test program is summar.ized in Table 13.1-1.
O 00r 000 015; 13.1-1
Tests Prior to Reactor fueling TABLE 13.1-1 PREFUELING TEST PROGRAM Type of Test Component Tested Func-Elec-Opera-Hydro tional trical tional 1.
Reactor Building and Penetra-tions Leak Rate Test x
2.
Electrical Systems Continuity x
3.
Control Rod Drives x
x x
4.
Reactor Building Cooling System x
x x
5.
Component Cooling Water System x
x x
6 Reactor Building Spray System x
x s
7.
Decay Heat Removal System x
x x
x 8.
Pressurizer Relief Tank x
x 9.
Reactor Coolant System Relief Valves x
x 10.
Chemical Addition and Sampling System x
x x
11.
Makeup and Purification System x
x x
x 12.
Reactor Coolant Pumps x
x x
13.
Nuclear Instrumentation Cable Tests x
14 Nuclear Instrumentation and Protection Systems x
x 15.
Integrated Control System x
x 16.
Reactor and Auxiliary System Non-nuclear Instrumentation x
x x
17.
18.
Reactor Coolant System Hot Yunctional Test x
x x
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Tests Prior to Reactor Fueling Table 13.1-1 continued Type of Test Comnonent Tested Func-Elec-Opera-Hydro tional trical tional 19.
Core Flooding System x
20.
Reactor Building Fuel Handling S ys tem x
x x
21.
Fuel Storage Building Fuel Handling System x
x x
22.
Area Radiation Monitoring Systems x
x 23.
Incore Monitoring System x
x x
- 24. Waste Disposal System x
x x
25.
Spent Fuel Cooling System x
x x
g 26.
Emergency Power Systems Tests x
x x
27.
Initial Fuel Loading x
28.
Nuclear Service x
x x
x Cooling Water System 9
29.
Nuclear Service
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Raw Water System x
x x
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Amendment 2 13.1-3 A
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13.2 INITIAL CRITICALITY t
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Fuel loading will begin when all prerequisite unit tests and operations have been satisfactorily completed and the facility operating license has l
been obtained. Core components will be loaded in a predetermined sequence.
i Changes in core subcritical multiplication will be measured and evaluated-8 a detailed checkoff list will be followed; and periodic checks will be j
made to ensure proper status of all equipment, conditions, and core com-i ponents.
Initial criticality will take place by control rod withdrawal l
and core boron concentration adjustment.
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13.2-1
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13.3 POSTCRITICALITY TESTS A series of posteriticality tests will be conducted at ambient and hot zero power, and at various power levcis. These tests will be used to evaluate temperature, pressure, power, and boron reactivity coefficients; control rod reactivity worths; and the reactivity worth 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 responso characteristics to step and ramp load changes will be evaluated, and the control systems will be adjusted as required.
A com-plete biological shield survey will be conducted.
Field analysis and a more detailed office analysis of test results will be made.
The posteriticality tests are summarized as follows.
a.
Initial Criticality and Excess Reactivity b.
Reactivity Coefficients and Rod Worths c.
Stuck Rod Margin Verification d.
Power Coefficient and Power Defect e.
Reactivity Coefficients at Power
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f.
Xenon Reactivity Worths
\\.s g.
Reactor Coolant System Flow Tests h.
Incore and External Nuclear Instrumentation Calibration 1.
Unit Load Steady State and Transient Tests J.
Biological Shield Survey k.
Unit Loss-of-Electrical-Load Tests 000 0155 o
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000 13.3-1