ML20003F093

Startup Test Revisions.

ML20003F093
Person / Time
Site:	Sequoyah
Issue date:	04/13/1981
From:	TENNESSEE VALLEY AUTHORITY
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ML20003F091	List: ML20003F090 ML20003F093
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NUDOCS 8104200145
Download: ML20003F093 (23)

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l Enclosure 1 STARIUP TEST REVISICES CEQUOYAH NUCLEAR PIRTf UNIT 2 We following tests were deleted:

1. SU 7.6 - Ibd Control Cluster Assembly (ROCA) Pseudo Ejection at Zero Power and SU 8.2 - FCCA Pseudo Ejection and ROCA Above Bank Position Measurement The calculation model was verified as a result of the unit 1 startup.

Unit 2 is identical to unit 1; therefore, the model verification test need not be performed. Regulatory Guide 1.68 does not require this test on the identical unit.

2. SU l.1 - Loss of Offsite Power and SU l.2 - Shutdown frm Outside Control Room The tests are performed for operator training and verification of adequate Emergency Operating Instructions (EDI's) and instrumentation outside the control room to shut down the plant. Werefore, the testing run on unit 1 satisfies this requirement.

3. SU 9.4, Part B - Generator Trip frm 100-Percent Power The purpose of this test is to verify the ability of the automatic control and protection system to sustain a' net electrical load loss without exceeding turbine design overspeed. Part A of the test will be performed on unit 1 which verifies the ability of the automatic control and protection system to sustain a trip from 100 percent. The unit 1 test will verify that unit 2 can sustain an electrical load loss due to similar units.

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4. SU 8.1 - Power Coefficient and Integral Power Defect Measurement The calculation model was verified as a result of the unit 1 startup program. Unit 2 is identical to unit 1; therefore, the model arification test need not be performed.

l S. SU 7.7 - Minimum Shutdown Verification and Stuck Rod Worth Measurement

. The calculation model was verified as a result of the unit 1 startup

. program. Since unit 2 is identical to unit 1, the model verification test need not be performed.

The following test was added:

1. SU l.3 Bod Worth Using Rod Swap Measurement The test will verify the integral worths of all rod banks. Each rod bank is individually inserted to full insertion while withdrawing the reference bank to compensate for the reactivity change. The similarity of the unit 2 rod bank worth to the unit 1 rod bank worths will be confirmed by cmparing the test results to baseline data obtained during the unit 1 startup test program.

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W e following tests were revised:

1. SU 7.4 - Ibd and Boron Worth Measurements During Boron Dilution and SU 7.5 - Bad and Boron Worth Measurements During Boron Addition The test determines the differential and integral worth of the highast worth Itr bank and determines the differential boron worth over the range of the highest worth ROC bank.

The nuclect design predictions for Rod Cluster Control Assembly (ROCA) group differential worths are validated. Ibds are inserted or withdrawn as boron is constantly added or diluted. We worth of the rods is compensated for by boron. Ibd movement will cause step changes in reactivity which are measured on a reactivity emputer.

Differential boron worth measurements are made by increasing or decreasing reactor coolant boron concentration. Cmpensation for reactivity effect of boron concentration change will be made by withdrawing or inserting respective control rods to maintain power level and observing the result and accumulatwl change in core reactivity corresponding to these successive rod movements. Both of these measurements are done simultaneously.

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ENCILSURE 2 SEQUOYAH NUCLEAR PLANT FINAL SAFEIY ANALYSIS REPORP TABLE 14.1-2a (new)

REFLECTING REVISED STARIUP C PROGRAM MR UNIT 2 l

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v TABLE 14.1-2 a -

LIST OF STARTUP TESTS - Unit 2 Test Objectives

> Summary of Testing and Title of Test Test Prerequisites ' Acceptance Criteria I. Core-Loading Program

! SU-6.2 Core-Loading Pre- llot functional test program com- The objective of this instruction is j requisites pleted. Plant being readied for to ensure the ope ability of equip-

core loading. ment and . systems necessary for a j safe and expeditious core loading.

4 Temporary neutron monitoring channels to be utilized during core loading ,

will be checked and demonstrated to f be operable.

H i f' . SU-6.3 Reactor Systems. Reactor vessel head removed and The test verifies correct and uni-Y Sampling Prior to vessel water level.,is above.the form boron concentration, prior to i

[* and During Core centerline of the outlet nozzles . core loading... in all parts of the y Loading in preparation for core loading. . . . reactor coolant system and directly '

Reactor cooling system and con- connected auxiliary systems and nected auxiliary systems have verifies equipment status and plant been borated to specified con- conditions during core loading to centrations. The CVCS Systen, ensure that planned conditions are RIIR System, Safety Injection being maintained. .

System, and component cooling system are in service with R11R System circulating coolant through the vessel.

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7 TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS .- Unit 2 Test Objectives

' Summary of Testing and Test Prerequisites Acceptance Criteria Title of Test I. Core-Loading Program (cont'd.)

SU-6.1 Initial Core Loading Nuclear instrumentation and com- The instruction establishes the con-munications required for core load- ditions under which installation of j ing installed and verified opera- the initial nuclear fuel charge is tional. Reactor vessel is ready to be accomplished and specifies the to receive fuel and required fuel sequence of events which constitutes

. handling tools are available for the initial core-loading program.

use. Startup test SU-6.2 has The instruction includes a core-been completed and RllR Sys tem is loading sequence which specifies the r loading in a step-by-step fashion f' in service. Equipment door and at least one door in each person- with the appropriate precautions and 7"

nel airlock are closed. At least prerequisites for each step listed.

[l one flow path for emergency bora-p tion is available. All required

' preloading tests have been com-pleted and the requirements of SU-6.3 have been satisfied.

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Table 14.1-2a(continued)

LIST OF STARTUP TESTS - Unit 2 s

Test Objectives Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria II. Precritical Testing (Tests to be completed after Core Loading) '

Preoperational Tests:

Pressurizer Spray and lleater Capability and . ,

Continuous Spray Flow

[ Setting See Table 14.1-1 w

da Reactor Coolant System

[ Flow Measurement See Table 14.1-1 Reactor Coolant Flow Coastdown See Table 14.1-1 Resistance Temperature Detector Bypass Loop Flow Verification See Table 14.1-1 Rod Drive Mechanism Timing See Table 14.1-1 1

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. Table 14.1-2a (c ont inued ) -

LIST OF STARTUP TESTS - Unit 2 I

Test Objectives Summary of Testing and 4 Title of Test Test Prerequisites Acceptance Criteria II. Precritical Testing (Tests to be completed after Core Loading) (Continued)

Rod Control System See Table 14.1-1 Rod Drop Time Measurements See Table 14.1-1 Rod Position See Table 14.1-1 Indication System '

5 g, Incore Movable Detectors See Table 14.1-1

., f C Adjustment to Reac tor and See Table 14.1-1

{ Turbine Control Systems

. STARTUP TESTS SU-1.0 Plant Measurements- Reactor Core loaded in pre- The test implements a program of Operational and Baseline Data paratica for startup testing gathering and analyzing baseline and operational data. Radiation surveys are performed at various steps during the power escalation to determine radiation dose-levels at preselected locations throughout the plant to evaluate the adequacy of plant shielding. A chemical and radio -

chemical program of sampling and

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Table 14.1-2a (continued)

LIST OF STARTUP TESTS - Unit 2 s

Test Objectives Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria II. Precritical Testing (Test to be Completed Af ter Core Loading) (Continued)

STARTUP TESTS s

SU-1.0 Plant Measurements-Operational and Baseline Data - .

(Continued)' .., -

analysis will be implemented coin-r

• ' cident with core loading. Specified analyses will be performed at major 7' steps of the startup program to

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gather biseline chemical / radio-E chemical data and to demonstrate that plant water chemistry require-ments can be maintained. Coin-cident with initial criticality, an e ffluent monitoring and analysis program will be implemented to

, , ensure that plant effluents

' potentially containing radioactive materials are monitored and the effluent monitors are calibrated and operational.

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TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS- Unit 2 Test Objectives Sdmmary of Testing and Test Prerequisites Acceptance Criteria Title of Test III. Inital Criticality and Low Power Testing SU-7.1 NSSS Startup Sequence Installation of nuclear steam sup- This instruction prescribes the se-ply system, all components of tur- quence of operations constituting bine steam system, and supporting the plant startup testing program. .

control and auxiliary systems is The sequence of operations is pre-complete. All pre-operational sented in tabular form as the NSSS

>> testing except as outlined in this Startup Sequence, in which detailed I' sequence shall have been succous . instructions, specific plant condi--

fully completed or specifically tions, and test procedures are in-I waived for this sequence of tests. cluded.

U Reactor Coolant System at ambient temperature and borated to required concentration. Adequate makeup I water available for extensive dilution. Concentrated boric acid available in sufficient quantity f or extensive boration. All special test equipment required

• for this testing sequence is avail-able and operational.

4 SU-7.2 Initial Criti- Plant at hot shutdown with at leant The objective la to bring the reac-calicy 2000 ppm horon In the lu:S . 'th e tur eritteal I or t.he I i rat time source and Intermediate range nucicar from the plant conditions specified.

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TABLE 14.1-2a(continued) ,

LIST OF STARTUP TESTS - Unit 2 Test Objectives

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Summary of Testing and l

Test Rerequisites ,

Acceptance Criteria Title of Test III. Initial Criticality and

' Low Power Testing (cont'd.)

instrumentation channels are op- All rods are withdrawn except the

! SU-7. 2 Inital Critical- erational with 3 of 4 power range last controlling group, which is icy (cont'd.)

channels in operation. left partially inserted for control once criticality is achieved by boron dilution. At preselected points in rod withdrawal and boron i dilution, data is taken and inverse g *

• count rate plots made to enable

f' - extrapolating to the expected criti-y -

cal point. When the inverse count

[* rate ratio reaches a preselected p 'value, dilution is stopped and the system allowed to mix. If critical-ity is not achieved during mixing, bank D control rods are withdrawn until criticality is achieved.

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' SU-7.3 Nuclear Design Plant at zero power. These tests The test establishes the boron con-are run as part of the zero power centration endpoint with various rod Check Tests configurations, determines the iso-physics test program. The RCC con-trol selector switch is on bank thermal temperature coefficient of control. The temperature is reactivity, and determines the neu-547 t 5 and pressure is tron flux distribution at various 2235

• 50 psig. rod configurations.

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3 LIST OF STARTUP TESTS - Unit 2 3

Test Objectives

' Summary of Testing and Test Prerequisites Acceptance Criteria Title of Test

.I III. Initial Criticality and 1

Low Power Testing (cont'd.)

l The boron endpoints are measured by SU-7.3 Nuclear Design determining the boron concentration Check Tests of the coolant system with the rods i (cont'd.) partially inserted. The rod is then j quickly pulled and reinserted with

( no boron adjustment. The change in

,I reactivity is measured and the end-g , ,

point calculated.

.f The isothermal moderator temperature

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l El coefficient is determined by heating ao the coolant system at a constant rate and then cooling down at a. constant rate.

The total temperature swing is about

! 5'F. The temperature versus reac-tivity is plotted and the slope of

'4 the lines generated is the isothermal moderator temperature coefficient.

p The neutron flux distribution is de-9 C .

termined by inserting miniature flux

-, detectors into core locations with i the flux indicated on strip chart I

recorders.

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TABLE 14.1-7a(continued)

LIST OF STARTUP TESTS - Unit 2

', Test Objectives Summary of Testing and 4

h Acceptance Criteria Test Prere'quisites Title of Test

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III. Initial Criticality and Low Power Testing (cont'd.)

Reactor just critical at zero The test determines the differential

• SU-7.4 Rod and Boron and integral worth of the highest Worth !!easure- power. Rod banks positioned as ments During specified in startup sequence worth RCC bank and determines the Boron Dilution (SU-7.1). RCC control on bank differential boron worth over the control. Reactor coolant system range of the highest worth RCC bank.

• SU-7.5 Rod and Boron pressure at 2235 50 psig; cool-The nuclear design predictions tor Worth Measure- ant system temperature at 547 d: 5 '/P g ments During - Flux signal from one Rod Cluster Control Assembly (RCCA)

Boron Addition power range detectog connected to group 'dif f erential worths are vali-

[. reactivity computer. dated. Rods are inserted or with-y drawn as boron is constantly added ,

p-or diluted. The worth of the rods is compensated for by boron. Rod movement will cause step changes in reactivity which are measured on a reactivity computer.

Differential boron worth measurements are made by increasing or decreasing reactor coolant baron concentration.

Compensation for reactivity effect of boron concentration changu will be

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made by withdrawing or inserting, re-spective control rods to maintain l

• Test Objectives, Summary of Testing, and Acceptance Criteria applies for both SU-7.4 and SU-7.5. '

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. TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS - Unit 2 Test Objectives Summary of Testing and Title of Test

• Test Prerequisites Acceptance Criteria III. Initial Criticality and Low Power Testing (cont'd.)

• SU-7.4 Rod and Baron '.. ,

Worth Measure- power level . . and observing ments During the result-and accumulated change in Boron Dilution core rea.ctivity corresponding to these successive rod movements. Both

• SU-7.5 Rod and Boron of these measurements'are done sim-

- Worth Measure-

• ultaneously.

f' ments During '

, T' Boron Addition .

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• Test Objectives, Summary of Testing, and .

Acceptance Criteria applies,for both j SU-7.4 and SU-7.5.

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LIST OF STARTUP TESTS - Unit 2 1

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, ., Test Objectives '

Title of Test f Summary of Testing and Test Prerequisites Acceptance Criteria III.

• Initial Criticality and Low Power Testing < ~ ,

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(cont'd.) .

SU-1.3 Rod Worth Reactor is just critical at Measurement The test will verify the integral-zerp power. The rod banks Using Rod Swap are positioned with worths of all rod banks. Each rod the bank is individually inserted to r.

highest worth rod bank (ref- .

full insertion while withdrawing

. erence bank) near full inser- the reference bank to compensate

[, tion'and all'other bank with- for the reactivity change. The y drawn. The rea'ct'or coolant similarity of the unit 2 rod bank

'~ system is at 2235 + 50 psi 8 worth to the unit I rod bank worths and 547 + 5 F. The flux signal will be confirmed by comparing the

' from one power range detector test results to baseline data is connected to the reactivity obtained during the unit I startup computer.

test program.

SU-1.0 Plant Measurements- Reactor core, loaded in pr'eparation The test implements a program of

.Operatibnal and for startup testing. gathering and analyzing baseline and Baseline Data. , operational data. Radiation surveys are performed at various steps dur-ing the power escalation to detenmine radiation dose-levels at preselected i

locations throughout the plant to evaluate the adequacy of plant e

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s TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS- Unit 2 Test Objectives

Tu= mary of Testing and Title of Test Test Prerequisite Acceptance Criteria III. Initial Criticality and Low Power Testing (cont'd.)

SU-1.0 Plant Measurements- Reactor core loaded in preparation shielding. A chemical and radio-Operational and for startup testing, chemical program of sampling and Baseline Data analysis will be implenented coin-(cont'd). cident with core loading. Specified analyses will be performed at major ,

y steps of the startup program to gather baseline chemical /radiochem-7' . ical data and to de=onstrate that a plant water chemistry requirements Z can be maintained. Coincident with initial criticality, an effluent mon-itoring and analysis program will be implemented to ensure that plant effluents potentially containing ra-dioactive materials are monitored and the effluent monitors are calibrated

and operational.

IV. Power Level Escalation Testing .

SU-8.1 Power Coeffielent Plant at power level specified by The test measures the differential and Integral Power s tartup sequence (SU-7.1). RCC power coefficient of reactivity and Defect Measurements banks positioned as required by measures the integral power defect.

During Power Level s tar ting se que nce . RCC selector The generator electrical load is Increase on manual control. Reactivity decreased and increased at a rate

, computer input flux of approximately one-percent per minute. The reactor -

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TABLE 14.1-2a(continued) l ?

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LIST OF STARTUP TESTS - Unit 2 Test Objectives

. Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria IV. Power Level Escalation Testing SU-8.4 Incore - Exore Plant is stable at power level The test determines a relationship Dectector Cali- specified in startup sequence between incore and excore. generated bration (SU-7.1). RCC selector is on man- axial offsets and AI. Moveable de-

ual control Controlling RCC bank tector maps, excore detector cur- ,

positioned as required by rents, thermocouple maps, and Calori-l s tartup sequence. metric data are taken with the re-

r. actor having an axial power imbalance f' . . ranging from zero to large negative 7 .,

. 'and positive values. The axial off-C sets are accomplished by a xenon oscil-

? lation initiated by bank D. From the da ta taken, the relationship between the excore and incore detectors is determined and the offset and AI circuits are calibrated.

SU-8.5 Nuclear and The Nuciear Instrumentation Sys- The objectives of this test ara to Temp erature tem is aligned for 100 percent obtain data for:

' Instrumentation _ power. Sensor fer measuring feed-Calibration and water tempctature to each steam Thermal Power

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generacor shall be installed, in- '1) Determining nuclear instrumenta-Measur ement dependent of the signals to the tion channel overlap; computer. The plant will be at 2) Verifying linearity and uniform various power levels.' detector outputs under flat power conditions;

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TABLE 14.1-2a(continued) l LIST OF STARTUP TESTS - Unit 2

., Test Objectives j

4 Summary of Testing and

- Test Prerequisites Acceptance Criteria ,

Title of Test IV. Power Level Escalation Testing (cont'd.)

3) Determining operational settings SU-8.5 Nuclear and of instrument compensating volt-Tempera ture In'strumentation ages and test current values; Calibration and 4) Setting power and intermediate Thermal Power range detector voltages; Measurement

5) Calculating thermal power in order to set power range channels; 4

y (cont'd.) *

6) Aligning AT and T average instru-f-

' mentation;

7) Setting overtemperature and over-h power AT instrument trip points; a 8) Verifying calibration of RTD's under isothermal conditions and determining installation correc-tions for each RTD for use in calibrating process instrumenta-tion.

The detector trip setpoints are

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values.

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• TABLE 14.1-2 c(continued)

T OF STARTUP TESTS - Unit 2 l Test Objectives Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria IV. Power Level Escalation Testing (cont'd.)

SU-8.5 Nuclear and After initial criticality and during Temp eratur e escalation into the intermediate and; ,

Instrumentation power ranges, detector currents are Calibration and taken to verify overlap between the Thermal Power source, intermediate, and power range Measurement , channels. This data is collected (cont'd.) , until the overlaps are firmly estab-5 lished. During low power escalation, 1 L. the power range detector currents are 1 monitored and compared with the in-O termediate range currents to verify response of the power range detec-tors. The power range channels will be calibrated based on a calorimetric measurement across the steam gener-l ator. The power delivered by each steam generater will be determined by measurement of feed-water. flow,

- feedwater temperature, and steam I pressure. AT and AT setpoints are

[ established by comparing AT incore with the RTD readings at isothermal conditions. The AT instrumentation is set at 0.0*F in this case.

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TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS - Unit 2 l

Test Objectives Summary of Testing and Title of Test Test Prerequisities Acceptance Criteria IV. Power Level Escalation Testing (cont'd.)

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r U SU-9.1 Load Swing Tests The following systems have been~ The objective of this test is to o checked and placed in automatic verify the nuclear plant transient control: response, including automatic con-

1) Reactor rod control trol systems performance, when step-

2) Steam generator level control load changes are introduced at the-

3) Pressurizer pressure control turbine generator. Step-load changes

4) Pressurizer level control will be initiated from steady-state

5) Steam dump control (T average conditions at approximately 30-per mode) -

percent, 75-percent, and 100-percent j , power. The plant is at steady-state conditions and the turbine governor valves are rapidly repositioned for a 10-percent load decrease. Plant parameters are monitored on high-All control rods positioned speed strip chart recorders. A new as specified in the startup se- equilibrium condition is reached and

, quence (SU-7.1). Plant must be the load is increased back to the able to deliver 30 percent, 75 per- original condition.

cent, or 100 percent of rated ca-pacity as required.

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h TABLE 14.1-2 a(continued)

LIST OF STARTUP TESTS - Unit 2 4

. Test Objectives

' Summary of Testing and ,

Test Prerequisities Acceptance Criteria Title of Test 1 IV. Power Level Escalation

' Testing (cont'd.)

The recordings are analyzed for i

SU-9.1 Load Swing . control systems behavior, and re-j Tests (con'd.) quirements for realignment.

The following systems have beca The objectives of this test are:

SU-9.3 Large Load Reduc-checked and placed in automatic IJ To verify the ability of the tion Tests primary and secondary plant and control:

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,, 1) Reactor Rod Control System the Automatic Reactor Control Systems to sustain a 50-percent j f-

. 2) Pressurizer Level Control Sys-- step-load reduction from 75-tem percent and 100-percent of full i d-U 3) Pressurizer Pressure Control power

" System 4)' Steam Generator Level Control

2) To evaluate the interaction be-tween the control systems System

5) Steam Pump Control System 3) To evaluate test data to deter-mine if possible setpoint changes (T average control mode) are required in the control sys-tems in order to improve transient The plant is in steady-state con- response.

dition at the required power level with controlling bank positioned These tests are performed to deter-4 as required by SU-7.1. . mine if the reactor or turbine will

' trip and to verify that safety valves do not lift, turbine speed responds normally, and the steam dump system functions correctly. The turbine governor valves are repositioned for l

a 50-percent load change. Plant .

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TABLE 14.1-2 a(continued) .

LIST OF STARTUP TESTS - Unit 2 Test Objectives Summary of Testing and Title of Test Test Prerequisities Acceptance Criteria i

IV. Power Level Escalation -

Testing (cont'd)

SU-9.3 Large Load Reduc- parameters are recorded on a high-l speed strip chart recorder.

i tion Tests (co n t 'd . )

SU-9.4 Plant Trip From Plant is at 100 percent power with This test is performed in two parts with 100 Percent Power control bank D positioned as re- each part being a separate test.

• quired by 50-7.1. The following Part A 4  % syste:.s are functioning properly The objectives of this test are:

. and have been placed in automatic 1) To verify capability of the primary L control: and secondary plant to sustain a i Dl 1) Rod Control System;

trip from 100 percent power and to

1. bring the plant to stable conditions

2) Steam Generator Level Control System; following the transient;

3) Pressurizer Pressure Control 2) To determine the overall response System; time of the reactor coolant hot leg

4) Pressurizer Level Control Sys- RTD's; and tem; 3) To evaluate the data resulting from

- 5) Steam Dump Control system (T this test to determine possible average control mode). changes in control system setpoints in order to improve transient response.

The plant is tripped form a steadystate, 100 percent power level by manually

, j tripping the turbine. The following criteria will be used to determine successful test completion.

1) Pressurizer and steam generator safety valves do not lift;

2) Safety injection is not initiated and turbine trips; i

'* Only Part A is going to be performed on Unit 2

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TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS - Unit ?

Test Objectives

• Summary of Testing and Test Prerequisites Acceptance Criteria

. Title of Test r

' IV. Power Level Escalation .

Testing (cont'd)

SU-9.4 Plant Trip From 3).'The overall RTD response time does not exceed a specified time; 100 Percent

4) Nuclear Flux drops to 15 percent Power (cont'd.) within 2.5 seconds af ter turbine trip

5) .All full-length RCCA;s release and drop.

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1 TABLE 14.1-2a(continued)

• i LIST'OF STARTUP TESTS - Unit 2 Test Objectives

, , Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria j SU-9.5 Rod Group Drop The plant shall be operating at a This test is to confirm that the neg-

. and Plant Trip steady-state level of 50 percent. ative rate trip circuit will trip the reactor as a result of dropping two rods in a group that is most difficult to detect by the power range detectors. .

Also, to obtain preliminary data for systems response to plant trip before performing the turbine trip and reactor trip f rom 100 percen't.

SU-1.0 Plant Measurements See test description under Phase "Il Z

Operational and tecti ig .

~ Baseline Data

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I l TABLE 14.1-2a(continued)

LIST OF STARTUP TESTS - Unit 2

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Test Objectives

, Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria SU-10.1 NSSS Acceptance Test The plant is at 100 percent power. The NSSS is operated for 300 continuous All preoperational tests have been hours at rated thermal output to verify compl et ed . All startup physics that the plant is acceptable. Operation testing is complete, of plant systems and components are verified and monitored during this time ,

period.-

SU-10.2 Steam Generator The Power level is at 100% of full The test objective is to determine the Moisture Carryover power . . . moisture carryover performance of the-Measurement . . steam generators. This measurement is obtained by using Sodium-24 as the 5

source. The acceptance criteria is that the moisture carryover measured be less k than or equal to the warranted value of U

n 0.25% by weight'.

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TABLE 14.1-2a(continued) i LIST OF STARTUP TESTS - Unit 2 I

I Test Objectives Summary of Testing and Tes; Prerequisities Acceptance Criteria i Title of Test IV. Power Level Escalation Testing (cont'd.)

• Automatic Steam .

Generator Level Control See Table 14.1-1

• Dynamic Automatic .

Steam Dump Control See Table 14.1-1 ,, ,

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• Calibration of '

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Steam and Feed-

{ [ water Flow Instru-E' mentation at Power See Table 14.1-1 4

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*Preoperational tests completed during startup l test program.

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