ML19309C550
| ML19309C550 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/01/1967 |
| From: | JERSEY CENTRAL POWER & LIGHT CO., METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 8004080751 | |
| Download: ML19309C550 (6) | |
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13 INITIAL _..T_E.ST_S _AND OPERATION 13-1 y
13 1 TESTS PRIOR TO REACTOR FUELING 13-1 13 2 INITIAL CRITICALITY 13-1 1
f 13 3 POSTCRITICALITY TESTS 13-1
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0 0001 278 13-1
O LIST OF "A'LES Table Page 13-1 Prefueling Test Program 13-2 13-2 Posteriti:ality Test Pregram 13-3 O
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13 INITIAL TESTS AND OPERATICNS 13 1 TESTS PRIOR TO REACTOR IUELI'IG A ce=prehensive field testing progra= for the Three Mile Island Nuclear Station vin be carried cut to insure that equi;=ent and syste=s perfer=
in accordance with design criteria.
The test progra= vin begin 9 to 12 =cnths before reactor' fueling. As the installatics of individual ec=penents and syste=s is ce=pleted, they.
will be tested and evaluated. The testing progran vill be carried out according to detailed pradetermined testing techniques and procedures.
Field analysis and = ore detailed office analysis of test results vin be
=ade to verify that systems and cc=penents are perfor=ing satisfactorily or to recc==end necessary corrective action.
In general, the types,of tests vill be classified as hydrostatic, opern-ticnal, electrical, and functional.
Operational tests win involve actual operation of the syste= and equip-ent under design conditions, er si=ulated design cenditiens. Functional tests vin verify that the system er equipment is capable of perfor=ing the r.metica for which it is designed.
The prefueling test program is su==arized in Table 13-1.
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13 2 INITIAL ';RITICALITY V
Fuel leading v1.1.1 begin when all prerequisite Station tests and operations have been satisfactorily ec=pleted and the facility operating license has been obtained. Core ec=ponents vill be leaded in a predetermined sequence.
Changes in core suberitical =ultiplicatien vin be measured end evaluated; a detailed checkoff list vill be folleved; and periedic checks will be made to insure proper status of all equipment, conditions, and core ec=-
ponents.
Initial criticality win take place by centrol red withdreval and core boren concentration adjustment.
13 3 POSTCRITICALITY TESTS A series of posteriticality testa vill be conducted at ambient and het zero pcVer, and at various power levels. Tr.ese tests will be used to evaluate te. perature, pressure, pcVer, and be..On reactivity coefficients; control red reactivity vorths; the reactivity worth of xenen-135; and core reactivity depletien versus bu=up.
The reacter ecolant syste= flov vill be evaluated, and the extemal and incere nuclear instru=entation syste=s vin be calibrated at various power levels. The Statien response charac-teristics to step and ra=p 1 cad changes vin be evaluated, and the centrol syste=s vill be adjusted as required. A ce=plete biological shield survey vill be conducted. Field analysis and a =cre detailed office analysis cf test results vill be =ade.
The pcS* criticality tests are su== art:ed in Table 13-2.
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Tabl.e 13-1 O
Prefueling Test Program Type of Test Opera-Elec-Func-Hydro tional trical tional_
l.
Reactor Building and Penetra-ticas Leak Pate Test x
2.
Electrical Systems Continuity x
3 Control Rod Drives x
x x
4.
Reactor Bu11 din 6 Ccoli 6 System x
x x
5 Inte=ediate Coolin6 System x
x x
6.
Reactor Building Spray System x
x x
7 Nuclear Services Coolin6 Water System x
x x
8.
Decay Heat Removal System x
x x
x O
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10.
Reactor Coolant System Relief Valves x
x 11.
Chemical Addition and Sa=plir4 System x
x x
12.
Makeup and Purification System x
x x
x 13 Reacter coolant Pumps x
x x
1k.
Nuclear Instrumentation Cable Tests x
13 Nuclear Instrumentation and Protection Systems x
x 16.
Integrated Centrol System x
x i
17 Reacter and Auxiliary Systems Nennuclear Instrumentation x
x x
18.
Reactor Ccolant System x
19 Reactor Coolant System Hot l
Functional Test x
x x
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Table 13-1 (Cont'd)
O Type of Test Opera-Elec-Fune-Hydro tional trical tional 20.
Core Ficoding Syste=
.x 21.
Reactor Building Fuel Handlin6 System x
x x
22.
Fuel Stora6e Bu11 din 6 Fuel Handlir4 System x
x x
23 Area Radiation Monitoring Systems x
x 24 Incore Monitoring' System x
x x
23 Waste Disposal System x
x x
26.
Spent Fuel Cooling System x
x x
27 Ener6ency Power Syste=s Tests x
x x
28.
0 Initial Fuel Leading x
Table 13-2 Posteriticality Test Program i
1.
Initial Criticality and Excess Reactivity 2.
Reactivity Coefficiente and Rod Werths 3
Stuck Rod Margin verification 1
4.
Power Coefficient and Power Defect 3
Reactivity Coefficients at Pcver j
6.
Xencn Reactivity Worths 7
Reactor Cociant System Flev Test 8.
Incore and External Nuclear Instrumentatica Calibration 9
Station Iosd Steady State and Transient Tests i
10.
Biological Shield Survey 11.
Station Loss-of-Electrical-Lead Tests 12.
Core Reactivity Depletion Rate Versus Burnup 1
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