ML20086H502

Rev 1 to 25A5677, Giraffe Helium Test Specification Legend or Description of Group

ML20086H502
Person / Time
Site:	05200004
Issue date:	05/10/1995
From:	Ahmann R, Fortin A, Herzog M GENERAL ELECTRIC CO.
To:
Shared Package
ML20086H490	List: ML20086H487 ML20086H502
References
25A5677, NUDOCS 9507180170
Download: ML20086H502 (32)

Text

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P-N 25A5677 SH NO.1 W

GENuclearEnergy nev.1 REVISION STATUS SEEET DOC TITLE GIRAFFE HELIUM TEST SPECIFICATION LFGEND OR DESCRIPTION OF GROUPS TYPE: TEST SPECIFICATION FMF:

SBWR MPL NO: T15-3070 REVISION C

0 RM-01652 01/27/95 l

A. FORTIN MAY 101995 RJA CN02604 GENERAL DOCUMENT CHANGE l

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PRINTS TO

.\\tA D I:. B Y APPROVALS CENERAL ELECTRIC COMPANY 175 CURTNER AVENUE A. FORTIN 1/11/94 M.HERZOG 1/27/95 SANJOSE, CALIFORNIA 95125 CHKBY ISSUED N/A R. AHMANN 1/27/95 CONT ON SHEET 2 MS-WO RD 9507180170 950714 PDR ADOCK 05200004 A

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GIRAFFE TEST SPECIFICATION TABLE OF CONTENTS SHEET NO.

i 1.

INTRODUCTION 4

2.

TEST PURPOSE / OBJECTIVES 4

l 3.

TEST FACILITY DESCRIPTION 5

4.

TEST PIANT CONTROL AND SAFETY CONSIDERATIONS 10 I

i 5.

TESTINSTRUMENTATION 10 6.

DATA ACQUISITION SYSTEM AND RECORDING 13 7.

DATA ANALYSIS 13 8.

SHAKEDOWN AND PIANT CHARACTERIZATION 15 9.

TEST MATRIX 16 10.

PRETEST PREDICTIONS / ACCEPTANCE CRITERIA 24 11.

REPORTING 24 12.

RECORD RETENTION 25 13.

QUAIIIYASSURANCE REQUIREMENTS 29 14.

FJ.FERENCES 31

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LIST OF FIGURES j

FIGURE SHEET NO.

I S-1 GIRAFFE Test Facility Schematic 8

3-2 GIRAFFE PCC Test Unit and Instrumentation 9

f LIST OF TABLES TABLE SHEET NO.

5.3-1 GIRAFFE Instmmentation Accuracy Requirements 14 9-1 GIRAFFE He Integral Systems Tests Initial Conditions 20 42 GIRAFFE He Integral Systems Test Matrix 21 i

9-3 GIRAFFE He Tie-back Test Initial Conditions 22 9-4 GIRAFFE He Test T2 Initial Conditions 23 I

12-1 GIRAFFE Test File and Design Record File Table of Contents 26 l

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@NUCNM 25A5677 SH NO. 4 REV.I 1.

INTRODUCFION This document specifies the requirements for tests to be performed in the GIRAFFE test facility. The tests relate to long-term post accident decay heat removal from the Simplified Boiling Water Reactor (SBWR) containment. The tests are termed the " Helium or He" tests.

This facility has been designed and built by the Toshiba Nuclear Engineering Laboratory in Kawasaki City, Japan.

These tests will provide Design Basis Data for use m calculations of safety related features of I

the SBWR.

2.

TMT PURPOSE / OBJECTIVES The purpose of the GIRAFFE /He tests is to demonstrate the operation of the passive containment cooling system (PCCS) operating in post-accident containment environments with the presence of a lighter-than-steam non-condensable gas. The tests will demonstrate SBWR containment thermal-hydraulic performance, heat removal capability and systems l

interactions and will provide additional data for the qual'. >

n of containment response l

predictions in the presence oflighter-than-steam non-condensable gases by the TRACG computer program.

The He tests are primarily focused on simulating the response of the SBWR containment cooling systems during the part of the post-accident transient which follows the injection of water into the reactor vessel from the Gravity Driven Cooling System (GDCS). This period

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starts at approximately one hour after reactor scram. At this time in the LOCA, the reactor vessel is depressurized and in approximate equilibrium with the drywell. During this period, the principal means of removing decay heat from the containment is via the PCCS.

The objectives of the GIRAFFE /He Test Program are:

l 1.

Demonstrate the operation of a passive containment cooling system with the presence of a lighter-than-steam non-condensable gas, including demonstrating the process of purging non-condensables from the PCC condenser.

2.

Provide a database for computer codes used to predict SBWR containment system performance in the presence of a lighter-than-steam non-condensable gas, including potential systems interaction effects. (IntegmlSystems Tests) 4

GENuclturr Erreig}r 25A5677 SH NO. 5 REV.1 l

3.

Provide a tie-back test, which includes the appropriate Quality Assurance documentation; to repeat a previous GIRAFFE test, thereby reinforcing the validity of the previous GIRAFFE testing.

3.

TEST FACIIIIY DESCRIPTION 3.1 General Description The tests specified in this document will be performed in the GIRAFFE facility, a large scale, integral system test facility which models the SBWR systems which are important to the long-term containment cooling following a LOCA.

4 The facility has been designed to exhibit thermal-hydraulic behavior similar to SBWR under i

LOCA conditions beginning approximately one hour after scram. The global volume scaling of the facility is approximately 1:400 with a nominal height scaling of1:1. The SBWR components which are modeled in the facility are: the Passive Containment Cooling System (PCCS), the Isolation Condenser (IC) System, the Gravity Driven Cooling System (GDCS),

the Reactor Pressure Vessel (RPV), the Drywell (DW), the Wetwell (WW) and the connecting piping and valves. Rigorous geometric similarity between SBWR containment and reactor vessel volumes and test facility vessels is not necessary to capture the fundamental features of the containment and RPV response and has not been attempted.

l Design specifications, design drawings, analytical backup information, verifications, and l

design review documentation, as appropriate shall be filed in the Test and Design Record Files identified in Section 12.

The GIRAFFE vessels are connected with scaled piping components to represent the connecting lines in the SBWR. The test facility vessels and piping connections for the He tests, are shown schematically in Figure 3-1.

The SBWR RPV is simulated by an approximately full height vessel. The actual SBWR height from the top of the core to the main steam line elevation is maintained in order to simulate RPV to PCC and RPV to GDCS pool vertical elevation differences. The RPV volume is scaled to 1:400, even though the upper and lower parts of the RPV are shortened. Electric heaters provide a variable power source to simulate the core decay heat. The core decay heat is scaled to 1:691,in order to match the scale for the PCC condenser heat transfer capability.

@MUMMef9)f 25A5677 SH NO. 6 REV.1 t

The upper dnwell, including the annular portion of the drywell, is represented by one l

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apprc <imately full height vessel; the volume is scaled to 1:400. Cross sectional area variation with height is included to simulate the actual SBWR configuration. The vacuum breakers I

between the dnwell and wetwell are represented by a ball valve connected to a pipe line

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between the drywell and the wetwell. The ball valve will open when the wetwell pressure is 3240 Pa higher than the drywell pressure. The ball valve will close when the pressure i

difference is less than 2060 Pa. The vacuum breaker line connects the upper drywell to the i

l wetwell air space for all tests, except for the He tie-back test which is described in Section 9.2.

i The wetwell is represented by one full height vessel. The wetwell air space volume and l

suppression pool volume are scaled to 1:400. The bottom of the wetwell vessel is filled with water to the same relative elevation above the top of active fuel as the SBWR suppression j

pool.

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The GDCS pool is represented by one full height vessel. The GDCS air space and the drywell l

vessel are connected by a line in order to equalize their pressures. The SBWR GDCS vessel l

volurae is scaled to 1:430. The GIRAFFE GDCS vessel was scaled down from the original SBWR GDCS pool volume with three interconnected GDCS pools. The interconnected pool design was later replaced with 3 separate CDCS pools with a total volume approximately 5%

greater than the previous design.

i The GIRAFFE facility includes one scaled PCC condenser. The condenser is a full length,

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three tube heat exchanger. This single condenser represents the three condensers found in the SBWR, the condenser heat transfer capability is scaled 1:691. Figure 3-2 shows the PCC i

condenser test unit and instrumentation. The PCC condenser is mounted above the drywell l

vessel at the same elevation above the Top of Active Fuel (TAF) as in SBWR. The PCC 1

condenser is connected to the dgwell, wetwell and GDCS pool as shown in Figure 3-1. The condense'r is installed in a pool composed of a makeup pool with a chimney and cavity l

arrangement in which the PCC unit is set. The makeup pool represents the SBWR IC/PCC

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pools adjacent to the SBWR PCC pool.

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1 NNUbbN 25A5677 SH NO. 7 REV.1 3.2 Functional Capability.

The design of the facility provides the capability for establishment ofinitial and boundary conditions which address the test objectives stated in Section 2. The tests will be conducted at temperatures and pressures representative of SBWR postulated LOCA conditions after initiation of the GDCS. To assure these conditions can be tested in GIRAFFE, the RPV has been designed for 1.70 MPa (absolute) and the other facility vessels have been designed to 0.60 MPa (absolute) and 1590C. These conditions exceed SBWR LOCA conditions after initiation of the GDCS.

The test facilityis designed to supply sufficient energy to the simulated RPV to represent the scaled decay heat and reactor stored energy release at approximately I hour after a scram.

Water can be supplied for pools and vessels, and steam, nitrogen and helium are available to establish the inidal pressure and gas concentrations in the drywell and werwell gas space. All piping is valved to provide maximum flexibility and ease of re-configuring the system.

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Instrumentation will be installed to measure the parameters ofinterest. A description of measurement requirements is given in Section 5.

f Heat losses from the facility to the surroundings have been minimized. Vessels, piping and flanges are encased by fiberglass insulation covered with metaljackets. In order to further minimize heat losses, microheaters are installed on the dgwell vertical walls, wetwell vertical walls and roof, and GDCS pool vertical walls. These microheaters are installed beneath the fiberglass insulation. Heat loss tests will be performed during facility characterization testing.

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P PRESSURE DP OlFFERENTIAL PRESSURE S NON-CONDENSABLE GAS t

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PCC POOL

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I WETWELL FIGURE S-1. GIRAFFE Test Facility Schematic

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TEMPERATURE P

PRESSURE DP DIFFERENTIAL PRESSURE WP T

STEAM BOX

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(STEAM INLET) 970 3

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WATER BOX 28 X 1 (N VENT) 2 18 X 1 (CPCC RET)

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CPCC TUBE FIGURE 3-2. GIRAFFE PCC Test Unit and Instrumentation

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4.

TEST PLAbTT CONTROL AND SAFETY CONSIDERATIONS Capability will be included in the facility to aid the operator in controlling the initial test I

conditions. During the tests, a control of the power to the RPV to simulate the decay heat dependence on time is required, as is a system to control the addition rate of helium. Similar control systems are required to establish the test initial pressure, temperature, level and non-

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condensable gas concentrations.

i Special safety conditions associated with the test shall be identified in the Test Plans and Procedures. Test facility safety requirements, will be included in the Test Plans and Procedures.

5.

TEST INSTRUMENTATION 5.1 General Requirements.

The test facility shall have sufficient instrumentation to measure parameters needed to achieve the test objectives defined in Section 2. Test instrumentation shall be provided by Toshiba and shall be calibrated as necessa:7 against traceable standards, i.e. the U.S.

National Institute of Standards and Technology, Japanese standards or equivalent.

5.2 Instrumentation Description.

f The GIRAFFE test facility shall have the capability to measure the following physical parameters: tempemtures, flow rates, pressures, differential pressures, liquid levels, and electrical power. The expected ranges for the various parameters to be measured shall be l

defined in the Test Plans and Procedures. The following provides an overview of the measurenient capability planned for the facility.

GENuclearEnergy 2 sass 77 sn no.11 REV.1 4

5.2.1 Temperature i

There will be capability to measure the following fluid temperatures :

-in the gas and liquid regions of vessels,i.e.

-par

-dqwell

-wetwell

-IC/PCC pool

-GDCS pool

-in the$ cam and water box of the PCC unit I

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-inside one of the PCC unit tubes j

In addition there will be capability to measure metal temperature:

-along the length of one of the PCC condenser tube walls 4

5.2.2 Flow rate There will be capability to measure flow rates in GIRAFFE at the following locations:

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- the PCC supply lines

- the PCC drain line to GDCS pool

- the GDCS line to RPV

- the Helium continuous supply line 5.2.3 Pressure l

There will be capability to measure pressure at the following locations:

-in the RPV

-in the drywell vessel

-in the wetwell vessel (gas space)

-in the PCC steam box

-in the GDCS vessel (gas space) 1

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5.2.4 Water Level l

There will be capability to measure the actual water levels using differential pressure transducers at the following locations:

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-wetwell vessel l

- drywell vessel

-RPV

- PCC pool tank

- PCC unit tube

- PCC unit water box

- GDCS pool

- PCC vent line to wetwell

- LOCA vent line to wetwell 5.2.5 Non<ondensable Gas Concentration During the He series of tests, perform direct measurements of the concentrations (mass-fractions) of non-condensable gases in the drywell and the suppression chamber at the approximate locations indicated in Figure 3-1.

In addition, the non<ondensable gas distribution will be estimated within the drywell vessel from temperature and pressure measurements, assuming saturated conditions and thermodynamic equilibrium exist.

5.2.6 Miscellaneous.

Wattmeters will be used to measure the electrical power to the RPV heaters, simulating the core, and microheaters installed on the drywell, wetwell and GDCS pool walls to minimize heat losses.

o 5.3 Specific Requirements The instrumentation required for performance of particular tests,i.e. number ofinstruments and accuracy requirements for the measurements, shall be specified in the Test Plans and

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GENuclearEnergy esAs6,7 su no.1s REV.1 l

Procedures documents for each test series. Accuracy requirements are specified in Table 5.3-1.

6.

DATA ACQUISITION SYSTEM AND RECORDING A digital data acquisidon system, of sufficient capacity to monitor and record specified measurements shall be used for the GIRAFFE tests. The measurements shall be recorded in digital format, on magnedc tape or disk, for subsequent reference and analysis. The required measurement frequency is one hertz.

7.

DATA ANALYSIS The processing and analysis of the recorded test data will be done in two phases in support of preparation of test reports. Equipment and software necessary for the specified data processing will be provided by Toshiba. Toshiba will prepare a plan for verification of the accuracy of the data acquisition and data reduction software.This plan and verificadon will be completed prior to the start of testing.

The following general data reduction software capabilities will be available:

Conversion of all recorded rignals to digital values in engineering units (metric).

Print tables of digital values of recorded signals in engineering units for selected time periods.

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t Table 5.3-1 GIRAFFE Instrumentation Accuracy Requirements j

Measurement Type Accuracy Requirement Temperature 1.0K i

Pressure 0.2% of full range Differential Pressure 0.2% of full range Flow Rate 2%

Heater Power 2%

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NonCondensable Gas Concentration 3%

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ENUChMef9V 25A5677 SH NO.15 REV.1 Capable of performing simple arithmetic operations between test variables.

Calculate and prepare tables of mean, standard deviation, minimum and maximum value for any measurement (in engineering units) during a specified time period.

Plot graphs of any selected test variable as a function of time (time history) for any selected test time window. Be able to plot groups of test variables on a single graph.

The first data processing and analysis phase has the purposes of providing representative results from the most significant measurements to be used in the Apparent Test Results report, specified in Section 11, and to aid in defining the details of the remainder of the analysis. Time history plots of key parameters shall be prepared and examined to determine time periods of significant interest for more detailed analysis. For the He tests those parameters are: PCC tube bulk fluid temperature, D/W and W/W pressures, suppression pool surface temperature, D/W temperature, PCC inlet flow rate, nitrogen vent line water level and LOCA vent line water level. Summary plots and digital data tables of typical results will be prepared. This first phase is expected to be completed approximately two weeks after each test.

The plots and tables for the Final Test Report, described in Section 11, will be generated during the second data processing and analysis phase to be completed three months after the test. The purpose of this phase is to organize the data in a form that provides an integrated interpretation of the test results to show the performance of the system and demonstrate that the test objectives have been achieved.

8.

SHAKEDOWN AND PLANT CHARACTERIZATION Facility shakedown and plant characterization tests will be performed. The plant characterization tests will consist of tests to quantify specific characteristics of the facility such as vessel heat loss and line pressure drop tests. These will be done by Toshiba using Toshiba procedures and the records will be included in the GIRAFFE Toshiba test file in accordance with Table 12-1.

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su so.1, REV.1 The following provides the purpose and additional descriptive information for each of the helium tests:

- Test H1 The purpose of this test is to provide a base case with nominal initial conditions for the SBWR containment at one hour from the initiation of a LOCA caused by a guillotine rupture of one of the main steam lines. The initial conditions for Test H1 are based on the results of a post-LOCA calculation performed using the TRACG computer program. At the start of this test, the drywell will contain a mixture of steam and nitrogen at a total pressure of approximately 300 KPa. This case will demonstrate the operation of the PCCS system without the presence of a lighter-than-steam non-condensable gas.

- Test H2 The purpose of this test is to demonstrate the efTects of a lighter-than-steam non-g condensable gas on the operation of the PCC system. This test is a repeat of Test i

j H1, but with helium replacing the total volume of nitrogen in the drywell.

j Therefore, the results from this test can be compared with the Test H1 results in j

order to determine the effects of a lighter-than-steam non<ondensable gas on the l

operation of the PCCS system.

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- Test H3 The purpose of this testis to demonstrate the effects of a high concentration of a l

lighter-than-steam non<ondensable gas on the operation of the PCC system. This test will confirm the effectiveness of the PCC system for conditions similar to whatis j

expected to occur as a result of a 100% SBWR metal water reaction. During a 100%

l S,BWR metal water reaction, GE expects, that as hydrogen is generated and flows into l

the drywell, the hydrogen will be purged by the PCCS from the drywell into the suppression chamber. For a main steam pipe break, the hydrogen will be released f

from the broken main steam line into the upper drywell. GE expects the hydrogen

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to first collect in the upper drywell and then when the drywell pressure builds up, the PCCS will purge the steam and non-condensable gases from the drywell. GE j

does not expect hy& ogen to permanently build up in the drywell. For this test an i

estimated initial bounding concentration of hydrogen is postulated. The initial mass of helium in the drywell is based on assuming that approximatefy 20% of the

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REV.1 hydrogen generated by a 100% SBWR metal water reaction is initially in the dgwell.

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The initial conditions, including the initial total drywell pressure for this test are the same as those for Tests H1 and H2. Therefore, the results from this test can be compared with the results from Tests H1 and H2 to determine whether the buoyancy

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characteristics of the helium will cause the helium to collect in the upper header of the PCCS condenser where it could inhibit steam flow through the PCCS.

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- Test H4 The purpose of this test is to confirm the assumption that the hydrogen generated by a metal water reaction will not permanently build up in the dqwell or PCCS condenser upper header, and instead will be periodically purged by the PCCS from the drywell to the suppression chamber. In order to confirm this, helium will be injected into the dqwell for the first hour of the test. The helium injection will be terminated when the total mass of helium added is equal to the initial dqwell helium mass for Test H3. Test H4 will start with the same initial conditions, including i

l drywell total pressure as for Test Hl. Therefore, the results from this test can be compared with the results from Test H1 to determine the effects of a lighter-than-steam noncondensable gas on the operation of the PCCS system.

System response from the four tests will be compared with each other to establish the effects oflighter-than-steam, or a mixture oflighter-than-steam and heavier-than-steam non-condensables, on the effectiveness of heat rejection by the PCC heat exchanger.

GIRAFFE tests H1 through H4 will demonstrate the operation of the PCCS with the presence of a lighter-than-steam non-condensable gas. These tests meet the requirements of Test Objective 1.

GIRAFFE tests H1 through H4 provide data for TRACG qualification that meets Test Objective 2.

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The facility configurations will be defined in the Test Plan and Procedures document. The l

facility configuration definition shall include the detail data needed for creating a TRACG l

model of GIRAFFE to be used to perform the TRACG post-test analysis.

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L 9.2 He Tie-back Test i

Test T1 will be a tie-back test to repeat a previous GIRAFFE Main Steam Line Break test, including appropriate Quality Assurance documentation to reinforce the validity of the l

previous GIRAFFE testing. Initial conditions are specified in Table 9-3. The vacuum breaker line will be connected to the middle drywell, which is where it was located for the previous MSLB test.

This test meets the requirements of Test Objective 3.

1 The detailed facility configurations will be defined in the Test Plan and Procedures document.

9.3 He TestT2 i

Test T2 will demonstrate the PCCS operation with an initial nitrogen concentration in the j

drywell that is approximately midway between that for Tests H1 and T1. The vacuum breaker line will be connected to the upper drywell in the same a.anner as for tests H1 through H4.

. Initial conditions are specified in Table 9-4.

The detailed facility configurations will be defined in the Test Plan and Procedures document.

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GENuchrEng 25A5677 SH NO. 20 F

Table 9-1. GIRAFFE He Integral Systems Tests Initial Conditions Parameter Value Tolerance RPV Pressure (KPa) 295 6KPa Initial Heater Power (Kw) 41+ heat loss compensation IKw RPV Water Level (m)*

12.0 0.150m Drywell Pressure (KPa) 294 4KPa Wetwell Pressure (KPa) 285 4KPa j

Wetwell Nitrogen Pressure (KPa) 240 4KPa GDCS Gas Space Pressure (KPa) 294 4KPa GDCS Nitrogen Pressure (KPa) 274 4KPa Suppression Pool Temperature (K) 352 2K PCC Pool Temperature (K) 373 2K GDCS Pool Temperature (K) 333 2K GDCS Pool Level * (m)

Suppression Pool Level * (m) 3.25 0.075m PCC Pool Collapsed Water Level * (m) 23.2 0.075m PCC Vent Line Submergence (m) 0.95 0.075m Referenced to the Top of Active Fuel (TAF).

GDCS pool level should be positioned in hydrostatic equilibrium with the RPV level (including an appropriate adjustment for temperature difference).

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GENuclearEnergy 25A5677 SH No. 21 j

REV.1 Table 9-2. GIRAFFE He Integral Systems Test Matrix Daywell Initial Partial Pressures (KPa) ( 2KPa)

GIRAFFE Helium Test No.

Injection Rate Nitrogen Steam Helium (Kg/sec)

H1 0

13 281 0

H2 0

0 281 13 H3 0

13 214 67 H4 0.00027 13 281 0

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25A5677 SH NO. 22 REV.1 Table 9-3. GIRAFFE He Tie-back Test Initial Conditions Parameter Value Tolerance RPV Pressure (KPa) 189 6KPa RPV Collapsed Water Level (m)*

9.1 0.150m Initial Heater Power (Kw) 96 IKw Drywell Total Pressure (KPa) 188 4KPa Drywell Nitrogen Partial Pressure (KPa) 53 4KPa Drywell Steam Partial Pressure (KPa) 135 4KPa Wetwell Pressure (KPa) 174 4KPa Wetwell Nitrogen Pressure (KPa) 164 4KPa GDCS Pool Gas Space 188 4KPa Total Pressure (KPa)

GDCS Pool Gas Space 151 4KPa Nitrogen Partial Pressure (KPa)

Suppression Pool Temperature (K) 326 2K PCC Pool Temperature (K) 373 2K

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GDCS Pool Temperature (K) 350 2K GDCS Pool Level * (m) 14.1 0.075m Suppression Pool Level * (m) 3.5 0.075m PCC Pool Collapsed Water Level * (m) 23.2 0.075m PCC Vent Line Submergence (m) 0.90 0.075m Referenced to the TAF.

GENuclear Errerg)r 25a5677 su so. 23 REV.1 Table 9-4. GIRAFFE He Test T2 Initial Conditions Parameter Value Tolerance RPV Pressure (KPa) 267 6KPa RPV Water Level (m)*

12.0 0.150m Initial Heater Power (Kw) 41+ Heat loss comp.

1Kw Dgwell Total Pressure (KPa) 266 4KPa Drywell Nitrogen Partial Pressure (KPa) 38 4KPa Dowell Steam Partial Pressure (KPa) 228 4KPa Wetwell Pressure (KPa) 257 4KPa Wetwell Nitrogen Pressure (KPa) 212 4KPa GDCS Pool Gas Space 266 4KPa Total Pressure (KPa)

GDCS Pool Gas Space 246 4KPa Nitrogen Partial Pressure (KPa)

Suppression Pool Temperature (K) 352 2K PCC Pool Temperature (K) 373 2K GDCS Pool Temperature (K) 333 2K 0.075m GDCS Pool Level * (m)

Suppression Pool Level * (m) 3.25 0.075m PCC Pool Collapsed Water Level * (m) 23.2 0.075m PCC Vent Line Submergence (m) 0.95 0.075m

• Referenced to the TAF.

• • GDCS pool level should be positioned in hydrostatic erguilibrium with the RPV level (including the appropriate adjustment for temperature difTerence).

GE&clearErseryy 2 sass 7, su no.24 REV.1 10.

PRETEST PREDICTIONS / ACCEPTANCE CRITERIA Pretest calculations need not be performed for any of the He matrix tests planned for SBWR i

certification.

The acceptance criteria will be specified in the Test Plans and Procedures. This acceptance i

criteria will define the tolerance on the initial conditions and any other input test conditions l

(such as simulated decay heat) which can influence the test results. The acceptance criteria will also define the instrumentation performance required in order'to consider the test as acceptable.

11.

REPORTING I

11.1 Data Transmittal.

j Toshiba will provide a copy to GE of all test data on 3-1/2 inch floppy disks in a DOS readable format. This data will be provided in engineering units.

l 11.2 Reports.

i A brief Apparent Test Results (ATR) report will be prepared by Toshiba for each test or each test series and will be completed in approximately two weeks. The ATR will contain test data to be integrated into the Final Test Report. The ATR will not include any evaluation of the i

test data. The ATR will include a description of test anomalies and will include a list of any failed instruments and the review and disposition of these anomalies. The ATR shall be j

reviewed by the Toshiba responsible manager and the GE GIRAFFE responsible engineer.

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Fm' al Test Report (FTR) prepared by Toshiba and GE will contain the data, analysis and j

results of all tests. The FTR will include a complete description of the test facility and l

components tested.

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12.

RECORD RETDTFION i

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All test records, analyses and verification records will be filed by Toshiba into a test file for a t

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storage period of at least 60 years. The GE Nuclear Energy Design Record File (DRF) will be i

mamtained for at least 60 years. The DRF number is T15-00013, and the DRF custodian is q

M. Herzog. The data stored electronically will be in a form suitable for long term storage, i.e.

I 60 years. Table 12-1 gives the table of contents for the Toshiba test file and the GE DRF.

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i ENUMrbef9)f 25A5677 SH NO. 26 REV.1 TABLE 12-1 GIRAFFE TEST FILE AND DESIGN RECORD FILE TABLE OF CONTENTS Toshiba GE Test Fue DEE 1.

TEST REQUIREMENTS DOCUMENTS X

X 1.1 TestSpecification X

X 1.2 Quality Assurance Program X

X 1.3 Test Plans and Procedures X

X 1.4 Testand Analysis Program Document X

X 1.5 Meeting Minutes X

X 2.

TEST FACILF1Y DESIGN X

2.1 Facility Design Drawings X

2.2 Design Review X

2.3 Procurement X

3.

TEST FACILITYCHECKOUT X

X 3.1 As-Built Drawings X

X*

3.2 Shakedown Test Procedure X

X 3.2.1 Helium Leak Test X

X 3.2.2 Heat Loss Tests X

X 3.2.3 Line Pressure Drop Tests X

X*

4.

INSTRUhENTATION 4.1 Instrumentation List (include serial number)

X 4.2 Range and Accuracy Requirements X

4.3 Manufacturers' Specifications X

4.4 Uncertainty Analysis X

4.5 Calibration 4.5.1 Plan / Procedures X

4.5.2 Records X

4.6 Exact Location on Test Facility X

(drawings or sketches and tables)

The as-built drawings in the GE-DRF will include the detail data needed for creating a

. i TRACG model of GIRAFFE to be used to perform the TRACG post-test analysis. Test facility documents used to define orifice. loss coefficients will be included in GE-DRF.

• • To be included in Test Plan and Procedure document.

- -.. ~

v

ENUMMM 25A5677 SH NO. 27 REY.1 TABLE 121. CONTIhTED Toshiba GE Test File D.EE 5.

DATA ACQUISITION SYSTEM 5.1 DAS Hardware Requirements X

5.2 DAS Hardware Description X

5.3 Wire / Cable Lists-DAS Hookup X

5.4 Wire / Cable Lists Verification X

5.5 DAS Software X

5.6 DAS Software Verification X

6.

TEST MATRIX X

X 6.1 Facility Configuration X

X 6.2 Initial Conditions / Acceptance Criteria X

X 6.3 Test Schedule Plan X

X 7.

SHAKEDOWN TEST RESULTS X

X l

7.1 Facility Configuration X

7.2 Initial Conditions / Data Printouts / Acceptance Criteria X

X 7.3 Non<onformance Items X

X 8.

TEST OPERATION X

8.1 Pre-test Checklists / Procedures X

8.1.1 Preconditioning / Final Valve Alignment X

8.1.2 Initial Condition Acceptance X

8.1.3 DAS/ Instrumentation Acceptance X

8.2 Post-test Checklists / Procedures X

8.2.1 Test Logs X

8.2.2 Non-conformance Items X

X 8.3, Data Printouts X

8.4 Raw Data Storage Information X

X 9.

POSTTEST DATA REDUCTION X

X 9.1 Data Reduction Plan X

9.2. Data Reduction Software and Verification X

X 9.3 Reduced Data Records X

X l

• • To be included in Test Plan and Procedure document.

a Y

GENuclearEnergy 2 sass,,

sn uo.28 REV.1 TABLE 12-1. CONTINUED Toshiba GE Test File DBf 10.

TEST REPORTS X

X 10.1 Apparent Test Results Reports X

X 10.2 Final Test Reports X

X 10.2.1 Analytical Basis / Supporting Data X

X 10.2.2 Draft Report Comment Resolution X

X 10.2.3 ReportVerification X

X 11.

AUDIT REPORTS X

X 12.

PERSONNEL TRAINING, PROCEDURES X

X I

AND DOCUMENTATION 13.

REFERENCES X

X O

k l

k_

_m._______m_

MMUC/SabM 25A5677 SH NO. 29 REV. I 13.

QUALflYASSURANCE REQUIREMENTS 13.1 References.

The GIRAFFE tests will be performed in conformance with the Toshiba SBWR QA program, AS-50092, Rev.1 (Reference 14.la) and the GIRAFFE Quality Assurance Plan, AS-50128-E, Rev.1 (Reference 14.lb), which are based on the requirements ofJapanese National StandardJEAG-4101 (Reference 14.2a) and ANSI /ASME NQA-1/la-1983 (Reference 14.2b).

The procedures to implement the QA requirements will be included in the Test Plans and Procedures document.

13.2 Review and Audit Requirements GE Nuclear Energy may perform reviews to verify that Toshiba's quality assurance program is in place and being followed. A facility Quality Assurance Readiness Assessment will be performed prior to the start of matrix testing. Toshiba QA personnel will perform an internal audit to verify compliance with the quality assurance requirements specified in the TP&P document.

13.3 Notification.

Toshiba has the responsibility to notify GE Nuclear Energy with documentation of:

(a) any changes in the test procedure, (b) any failure of the test device (s) or system (s) to meet performance requirements, (c) any revisions or modifications of the test device (s) or system (s),

(d) the dates when tests are expected to be performed, and (c) any changes to the QA requirements specified in the Toshiba SBWR QA program (Reference 14.la), GIRAFFE Quality Assurance Plan (Reference 14.lb) and Test Plans and Procedures document.

13.4 Test Plan and Procedures.

The tests will be performed in accordance with the Test Plan and Procedures (TP&P) document to be prepared by and issued by Toshiba. The GE GIRAFFE responsible engineer and responsible manager shall review and approve the TP&P. The Toshiba GIRAFFE

a GENudenne Ersery}r esass77 snuo.so REV.I responsible test engineer will change the TP&P to reflect changes in how test data is obtained. The GE GIRAFFE responsible engineer and responsible manager shall review and agree with any changes to the TP&P. The TP&Ps shall be a traceable and retrievable document of test requirements consisting of the following parts:

a.

Test Plan.

Document how test is to be set up and performed to meet the Test Specification and any special safety conditions associated with the test.

b.

QA Plan.

Specify quality assurance requirements per the test specification and describe how they are met,includinginstrumentation (calibration and adequacy), confirmation of test facility configuration and the test equipment status, test record information (date, performer, results, anomalies, corrective actions, etc.), certification of test personnel, and establishment of test equipment conditions, data logging, data acquisition systems, and others needed to satisfy test requirements.

c.

Test Procedures.

Document the specific procedures required to perform the test.

d.

Test Records.

Include requirements for filing facility checkout and shakedown records, instrument calibration records, verified as-built drawings for test facility, Data Acquisition System wire list verifications, pre-and post-test checklists, test logs, disposition of test or instrumentation anomalies, engineering units printout of data records, and electronic media data storage information in the Toshiba Test File and GE DRF as specified in Table 12-1.

e.

Instrumentation.

Document the measurements required on the test facility. Include an instrument list

~

and its basis, measurement accuracy requirements and analyses, calibration requirements and methods and pre-test acceptability criteria (zero shift acceptability, identification of critical instruments, etc.).

4 l'

ENUM 25A5677 SH NO. 31 REY. I f.

Personnel Certification.

Document the qualification requirements for test personnel and evidence that test personnel meet these requirements.

g.

Data Acquisition System Documentation.

Include the total number of measurements and scan rates, hardware and software descriptions, cabling, filtering, multiplexing, etc. Include requirement *. hat software listings, wiring diagrams or hook-up lists, and software or systems validation requirements and procedures shall be filed in the Toshiba Test File as specified in Table 12-1.

f h.

Data Reduction.

Document data reduction software, if used. Include the analytical basis for equations used in data manipulations, software coding listings, and software validation procedures and documentation,if used. Include requirement that data reduction inputs, reduced data printouts, and electronic storage media information shall be filed in the Toshiba Test File and the GE DRF as specified in Table 12-1.

i.

Data Analysis and Reports.

Include the requirement that backup information, such as data analysis, to support conclusions drawn, comments and comment resolutions, and verifications as appropriate shall be filed in the Toshiba Test File and the GE DRF as specified in Table 12-1, 14.

REFERENCES 14.1 Toshiba Documents:

Quality Assurance Program for Simplified Boiling Water Reactor Document a.

No. AS-50092, Rev.1, issued 01 Feb 95.

b.

GIRAFFE Quality Assurance Plan (TOGE-110 Test Programs), Document No. TOGE-110-TO1 AS-50128-E, Rev.1, issued April 1995.

O GENuclearEnw 2 sass,,

su so.32 REY.1 FINAL

' 4.2 Other Documents:

Japanese National StandardjEAG-4101-1990," Guide for Quality Assurance of Nuclear a.

Power Plants" b.

ANSI / ash 1E NQA-1-1983 and Addenda NQA-la-1983.

e e