ML20073F467
| ML20073F467 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 09/28/1994 |
| From: | Ahmann R, Fortin A, Torbeck J GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20073F469 | List: |
| References | |
| 25A5587, NUDOCS 9410030108 | |
| Download: ML20073F467 (26) | |
Text
.
587 SH NO. I REVISION STATUS SHEET DOCUMENT TITLE PANDA TEST SPECIFICATION LEGEND OR DESCRIPTION OF GROl'PS TYPE:
TEST SPECIFICATION FMF:
SBWR MPL NO:
T10-5010
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REVISION l
I A
RM-01528 t
PRINTS TO MADE BY APPROVALS GE NUCLEAR ENERGY A. FORTIN 9/27/94 J.TORBECK 9/27/94 175 CURTNER AVENUE SAN TOSE CALIFORNIA 95125 CHKD BY:
ISSUED A. FORTIN 9/27/94 R. AHMANN CONT ON SHEET 2 SH.NO.1 9410030108 940929 PDR ADDCK 05200004 A
EN 25A5587 SH NO. 2 REV.A PANDA TEST SPECIFICATION TABLE OF CONTENTS 1.
INTRODUCTION j
2.
TEST PURPOSE / OBJECTIVES 3.
TEST FACILITIDESCRIPTION 4.
TEST PLANT CONTROL AND SAFEn' CONSIDERATIONS i
5.
TEST INSTRUMENTATION 6.
DATA ACQUISITION SYSTEM AND RECORDING 7.
DATA ANALYSIS 8.
SHAKEDOWN AND PLANT CHARACTERIZATION 9.
TEST MATRIX 10.
PRETEST PREDICTIONS / ACCEPTANCE CRITERIA 11.
REPORTING 12.
RECORD RETENTION 13.
QUALITYASSURANCE 14.
REFERENCES
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l
@M 25A5587 SH NO.3 REV.A LIST OF FIGURES FIGURE SHEET NO.
3-1 PANDA Experimental Facility Schematic 3-2 PANDA Experimental Facility Configuration of Vessels 3-3 PANDA Experimental Facility PCC/IC Condensers LIST OF TABLES TABLE SHEET NO.
9-1 PANDA Steady-State PCC Performance Test Matrix 9-2 PANDA Integral Systems Test Matrix 12-1 PANDA Design Record File Table of Contents I
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25A5587 SH NO. 4
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REY.A 1.
INTRODUCTION This document specifies the top-level requirements for tests related to long-term post-LOCA decay heat removal from the containment of the Simplified Boiling Water Reactor (SBWR) to be performed in the PANDA test facility. This facility has been designed and built by the Paul Scherrer Institute (PSI) in Switzerland. The PANDA Test Plans and Procedures define the detailed or specific test requirements.
These tests are classified as " safety related" per EOP 65-2.10 and " Design Basis Data" test type per EOP 35-3.00 Appendix B.
2.
TEST PURPOSE / OBJECTIVES The purpose of the PANDA tests is to evaluate the performance of the passive containment cooling system (PCCS) operating in typical post-LOCA containment emironments. The tests will demonstrate SBWR containment thermal-hydraulic performance, heat removal capability and systems interactions and will provide additional data for confirmation of the TRACG computer models used to analyze SBWR performance.
The tests are primarily focused on simulating the response of the SBWR containment cooling systems during the part of the post-LOCA transient which follows the injection of water into the reactor vessel from the Gravity Driven Cooling System (GDCS). This period starts at r
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 test objectives of the PANDA Test Program are:
- 1. Provide additional data to: (a) support the adequacy of TRACG to predict the quasi-steady heat rejection rate of a P_CC heat exchanger, and (b) identify the effects of scale on PCC performance. (Steady-StateSeparateEffects)
- 2. Provide a sufficient database to confirm the capability of TRACG to predict SBWR containment system performance, including potential systems interaction effects.
(Integral Systems Tests)
- 3. Demonstrate startup and long-term operation of a passive containment cooling system. (ConceptDemonstration)
- m
@M 25A5587 SH NO. 5 REY.A
- 3. TEST FACILI~IY DESCRIPTION 3.1 General Description The tests specified in this document will be performed in the PANDA facility, a large scale, integral system test facility which models the SBWR compartments and systems which are important to the long-term containment cooling following a LOCA.
The facility has been designed to exhibit thermal-hydraulic behavior similar to SBWR under LOCA conditions beginning approximately one hour after scram. The global volume scaling of the facility is approximately 1:25 with a nominal height scaling of 1:1. The SBWR components which are modeled in the facility are: the Passive Containment Cooling System (PCCS), the Isolation Condenser (IC) Syuem, the Gravity Driven Cooling System (GDCS),
the Reactor Pressure Vessel (RPV), the Dawell (DW), the Wetwell (WW) and the connecting piping and valves. Electric heaters provide a variable power source to simulate the core decay heat and the stored energy in the reactor structures. Rigorous geometric similarity between SBWR containment volumes and test facility vessels is not necessary to capture the fundamental features of the containment response and has not been attempted.
The PANDA vessels are connected with scaled piping components to represent the connecting lines in the SBWR. The test facility vessels and piping connections are shown schematically in Figure 3-1. The arrangement, elevations and volumes of the major vessels are shown in Figure 3-2.
The SBWR RPV is simulated by a vessel containing electric heaters. The top of the heaters is at a relative elevation which represents the top of the active fuel (TAF). With the RPV simulator partially filled with water the heaters will generate steam which is discharged to vessels representing the SBWR drywell. The dr)wellis represented by two vessels connected by a large diameter pipe. The wetwellis also represented by two vessels. The bottom of the wetwell vessels are filled with water to the same relative elevation above TAF as the SBWR suppression pool. The wetwell vessels are connected by two large diameter pipes, one in the gas space and onejust below the water surface. The purpose of using two connected wetwell/drywell vessels is to permit a simulation of multi-dimensional or asymmetric conditions (temperature, gas fraction).
The elevation scaling of 1:1 has been applied to the parts of the system which are above the top of the SBWR core. The PANDA scaling is evaluated in Appendix B.5 of NEDC-32391P (Reference 14.1.c).
The PANDA facility includes three scaled PCC condensers and one scaled IC unit (representing the scaled capacity of two SBWR IC units). These are mounted above the drywell vessels at the same elevation above the TAF as in SBWR. Two of the PCC units
@h 25A5587 SH.NO. 6 REY.A t
are connected to one of the dowell/wetwell vessels and the third PCC is connected to the i
other dnwell/wetwell. The IC unit is connected to the simulated RPV. All four condensers are submerged in water in tanks representing the PCC/IC pools. Figure 3-3 shows the j
IC/PCC condenser test units.
l The SBWR GDCS pools are represented in PANDA by a single GDCS vessel. The elevation of the GDCS vessel is representative of SBWR, but the volume of the GDCS vessel is not scaled the same as other PANDA vessels. It is not necessary to scale the volume of GDCS water in order to model the part of a SBWR LOCA transient to be tested, because the GDCS tanks priman' function during the l
time period to be tested is to act as a collection tank for the PCC condensate drain flow.
i 3.2. Functional Capability.
l The design of the facility provides the capability for establishment ofinitial and boundary conditions which address the test objectives stated in Secdon 2. The tests will be conducted at temperatures and pressures representative of SBWR postulated LOCA conditions after initiation of the GDCS. To
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assure these conditions can be tested in PANDA, the facility has been designed to 10 bar (145 psia) i and 1800 C (3560 F). These conditions exceed SBWR LOCA conditions after initiation of the l
GDCS.
i The test facility is designed to supply sufficient energy to the simulated RPV to represent the t
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 and air are available to establish the initial pressure and gas concentrations in the dnwell and wetwell gas space. All piping is valved to provide maximum flexibility and ease of re-configuring the system. Instrumentation will be l
installed to measure the parameters ofinterest. A description of measurement requirements is l'
given in Section 5.
Heat losses from the facility to the surroundings have been minimized. The design goal is for heat losses to be less than 10 percent of(fie energy input rate for decay heat up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following scram. Heat loss tests will be performed to confirm this design goal is met.
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25A5587 sH NO. 7 REV.A
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FIGURE S-3. PANDA Experimental Facility-IC / PCC Test Units
U, GENuclearEnergy 25A5587 SH sn 10 REv.A 4.
TEST PLANT CONTROL AND SAFETY CONSIDERATIONS Capability will be included in the facility to aid the operator in controlling the test conditions.
Control systems which can be used to control flow rates and pressures are desirable. A control system to control the power to the RPV to simulate the decay heat dependence on time for the transient tests is required.
The facility design has included safety valves on pressure vessels. In addition the test procedures should assure that no pressure differences or thermal stresses are introduced into the facility which were not considered in the design.
- 5. INSTRUMENTATION 5.1. General Requirements.
The test facility shall have sufficient instrumentation to measure all parameters needed to achieve the test objectives defined in Section 2. All test instnimentation shall be provided by PSI and shall be calibrated as necessary against traceable standards, i.e. the U.S. National Institute of Standards and Technology or equivalent.
5.2. Instrumentation Description.
The PANDA test facility shall have the capability to measure the following physical parameters: temperatures, flow rates, pressures, differential pressures, liquid levels, gas concentrations, and electrical power. PSI document TM-42-92-18 (Reference 14.2a) defines the ranges expected for the various parameters to be measured. The following provides an oveniew of the measurement capability planned for the facility.
5.2.1. Temperature There will be capability to measure the following fluid temperatures :
-in the gas and liquid regions of vessels, i.e.
.RPV
- drywells and connecting line between drywells
- wetwells and two connecting lines between wetwells
- GDCS pool
- IC/PCC pool i
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25A5587 SH NO.11 REV.A
- in the system lines and piping, i.e.
-lines from the RPV to the dr>well and the IC
-lines from the drywell to the PCCs
- LOCA vent lines
- PCC vent lines
-IC, PCC and GDCS drain lines
- vacuum breaker lines between the dnwells and wetwells
- wetwell/RPV equalization lines
-in the upper and lower headers of the IC and the PCC units
-inside some of the tubes in all four condensers.
In addition there will be capability to measure metal temperature:
- along the length of some of the IC and PCC condenser tube walls
-in the walls of key vessels and lines.
5.2.2. Flow rate Capability to measure flow rates in PANDA is planned for the following locations:
- the PCC drain lines to the GDCS (for PCC3 steady-state tests, only)
- the GDCS drain line to the RPV
- the IC drain line to the RPV
- the equalization line between the RPV and suppression pool
- the main steam lines
- the IC and PCC supply lines ~
- the PCC vent lines
- the bypass leakage lines between the dowells and wetwells
-air flow supplied to the PANDA facility by the auxiliary air system.
5.2.3. Pressure It is planned to have the capability to measure pressure at the following locations:
-in the RPV
-in the dowell vessels
- in the wetwell vessels (gas space)
I
SM 25A5587 SH NO.12 I
REv.A
-in the IC and PCC supply lines near the upper headers
-in the GDCS tank
- the atmospheric pressure.
5.2.4. Differential pressure.
Capability to measure the pressure differences is planned for the following locations:
-between the gas spaces of the major vessels,i.e.
- RPV to DW1
- RPV to DW2
- DW1 to WW1
- DW2 to WW2
-along the length of key lines, i.e.
- PCC inlet, vent and drain lines
-IC inlet and drain lines
- GDCS drain line
- WW1 and WW2 to RPV equalization line
- between upper and lower headers of the IC and PCC condenser units.
5.2.5. Water Level The capability to measure the actual water levels is planned for the following vessels:
- both drywell vessels
- both wetwell vessels
- the GDCS tank.
The equivalent " collapsed" liquid levels will be measured in locations which may have gas (steam or air) below the water surface. These are:
-in the RPV
-in each of the four compartments of the IC/PCC pool tank.
Capability to measure the liquid level is also planned for the following lines:
- the LOCA vent lines
- the vent lines for the PCC condenser units.
5.2.6. Fluid Phase Indicator
N 25A5587 sH No.13
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REY.A Probes will be used to determine whether the fluid phase is liquid or gas at the following locations:
- near the bottom (exit) of the LOCA vent lines from the DW to the WW
-at the inlet and outlet of the vent lines for each of the three PCC condensers.
5.2.7. Gas concentration / humidity.
Two oxygen analyzers which have the capability to determine the oxygen partial pressure can be mounted at four locations in the dowells. These can be used to determine the concentration (mass-fraction) of non-condensable gas in the dnwell.
In addition, non-condensable gas distribution may be determined within the dnwell vessels from temperature and pressure measurements, assuming saturated conditions exist. The oxygen analyzers will be used to validate ute non-condensable concentrations inferred with this approach.
5.2.8. Miscellaneous.
Wattmeters will be used to measure the electrical power to the RPV heaters.
5.3. Specific Requirements The instrumentation required for performance of particular tests, i.e. number of instruments and accuracy requirements for the measurements, will be specified in the Test Plans and Procedures documents for each test series.
- 6. DATA ACQUISITION SYSTEM AND RECORDING A digital data acquisition system, of sufficient capacity to monitor and record specified measurements shall be used for the PANDA tests. The measurements shall be recorded in digital format, on magnetic tape or disk, for subsequent reference and analysis.
- 7. DATA PROCESSING / ANALYSIS REQUIREMENTS.
The processing and analysis of the recorded test data shall be done in two phases in support of preparation of test reports. Equipment and software necessary for the specified data processing shall be provided by PSI. PSI will prepare a plan for verification of the accuracy of all data acquisition and data reduction software. This plan and verification shall be completed prior to the start of testing.
q Eh 25A5587 SH NO.14
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REV.A j
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The following general data reduction software capabilities shall be available:
i Conversion of all recorded signals to digital values in engineering units.
Print tables of digital values of recorded signals in engineering units for selected time periods.
Calculate and prepare tables of mean, standard deviation, minimum and maximum value for any measurement (in engineering units) during a specified time period.
1 Plot graphs of any selected test variable as a function of time (time history) for any j
selected test time window. Be able to plot groups of test variables on a single graph.
j 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 f
in Section 11, and to aid in defining the details of the remainder of the analysis. It may be that the most convenient way to do this analysis is interactively with the data reduction computer. Time i
history plots of key parameters shall be prepared and examined to determine time periods of significant interest for more detailed analysis. Summary plots and digital data tables of typical results shall be prepared. Time periods and parameters of most significance shall be selected for processing during the data processing and analysis for the Final Test Report. This first phase is i'
expected to be completed approximately one week after the test.
t 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 a few 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.
i 8.
SHAKEDOWN AND PLANT CHARACTERIZATION I
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 l
as vessel heat loss and line pressure drop tests. These will be done by PSI using PSI procedures and the records will be included in the test file.
]
'l Shakedown or debugging of the facility and its test measurement and recording system will be achieved by running tests ptior to running the " matrix" tests. These shakedown tests will be run in a manner which will expose the facility components and auxiliary systems to conditions similar to those expected during the " matrix" tests. These shakedown tests will be run with test procedures prepared for the " matrix" tests in order to identify any corrections required in the test procedures.
.k EMbuyyf 25A5587 SH NO.15 REV.A
- 9. TEST MATRIX 9.1 Steady-State Performance Tests
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A series of steady-state tests will be conducted using one of the PANDA PCC condensers.
The facility will be configured to inject known flow rates of saturated steam and air directly to the PCC3 heat exchanger. The condenser inlet pressure will be maintained at 300 kPa for all tests by controlling the wetwell pressure. The steam and air flow to the heat exchanger will i
be controlled and measured. In addition, the condenser drain flow will be measured.
Table 9-1 shows the PANDA Steady-State PCC Performance test matrix.
Six test conditions are included. The independent parameters are the steam and air mass flow rates.
Conditions were chosen so that a direct comparison can be made to PANTHERS and i
GIRAFFE test points.
Table 9-1 identifies the test condidons in PANDA and the corresponding PANTHERS and GIRAFFE tests.
- Five Test Conditions (Test Condidons S1 through S5) are planned with various constant air flows and a constant steam flow of 0.20 kg/sec. In addition, one test will be run with a pure steam flow equivalent to that expected to match the steam condensing capacity of the condenser (Test Condition S6).
- PANDA Test Conditions S1 through S6 provide a data base for TRACG qualification to meet the requirements of Test Objective 1(a).
- The results of PANDA Test Conditions S1 through S6 will be compared with the PANTHERS and GIRAFFE steady state performance data as noted in Table 9-1 to meet the requirements of Test Objective 1(b).
f
EM 25A5587 SH NO 16 REV.A 9.2 Transient Integral Systems Tests A series of tests is planned for the PANDA facility to provide an integral systems database for PCC system performance with conditions representative of the long-term post-LOCA SBWR containment response. Table 9-2 provides the test matrix summarizing the key characteristics of each test, and data use:
The following provides the purpose and additional descriptive information on each PANDA transient test:
- Test All is a simulation of a break in the main steamline of the SBWR. The initial conditions in the containment will be the same as those tested in the GIRAFFE Phase 2 main steamline break test.
These initial conditions are similar to SBWR containment conditions consisting of a mixture of air and steam at one hour into the LOCA. One-third of the steam from the break will be directed to dnwell DW1 which has one PCC condenser, and two-thirds of the steam will be directed to DW2 with two PCC condensers. These test conditions represent a symmetrical situation in the PANDA facility PANDA test M1 will be compared with GIRAFFE Phase 2 5 fain Steamline Break Test to assess the effects of facility scale on integral system performance.
- Test Af2 is a repeat of Test M1 with all of the break flow steam directed into dowell DW2. DW2 has two PCC condensers, and this test maximizes the steam content of DW2 and the air content of DW1. Test M2 results will be compared with Test M1 results to quantify asymmetric effects on PCCS containment performance.
- Test 3f3 is very similar to Test M1, but with nominal initial containment conditions as calculated for the SBWR under SSAR assumptions at one hour into the LOCA. The initial dowell pressure will be approximately 300 kPa (43.5 psi). This test will provide a base case for comparison to all other tests.
Test 3H is a repeat of test M3 to demonstrate transient system response repeatability.
j
- Test Af5 is a repeat of M3, but with continuous water supply flow to the RPV. In the l
SBWR, if AC power is available, an operator might use the Fuel and Auxiliary Pools Cooling System, for example, to provide active core cooling.
This test will demonstrate potential systems 1nteraction effects for cases with continuous cold water addition to the RPV. Continuous water supply flow to the RPV will result in filling of the RPV and flow of relatively cold water out of the break and into the dnwell. This, in turn, is expected to result in opening of the drywell-to-wetwell vacuum breakers and reintroduction of air from the wetwell into the dowell. This test will provide data on PCC performance when air is reintroduced to the heat exchangers following essentially pure steam operation.
l
- Test Af6 is a repeat of Test M3 but with the IC operating in parallel with the three PCC condensers throughout the test period. This test will provide data showing the interaction between the PCC condensers and the IC, as well as the effect of the additional heat removal by the IC on containment and reactor system performance.
- Test Af7 will utilize the same nominal initial conditions as Test MS, but with the dowells and PCC units filled with air at the start of the transient. Additionally, this
N 25A5587 SH NO.17 REv.A test will begin as early in the SBWR transient as is possible with the PANDA facility design. This test will provide data to demonstrate the PCC condenser startup characteristics when initially blanketed with noncondensable gas.
- Test M8 is a repeat of Test M3, but with drywell-to-wetwell bypass leakage. This test will provide the effect of bypass leakage on containment performance.
- Test M9is a combination of tests $15 and 517, with cold water injection into the RPV, and this test will begin as early as possible in the SBWR LOCA scenario, consistent with the PANDA facility design.
PANDA tests M1 through 519 provide a database for TRACG qualification that meets Test Objective 2.
PANDA tests M1 through M9 address long-term operation of the PCCS. Tests M5 through M7 and M9 address systems interaction and PCCS restart issues. These tests meet the requirements of Test Objective 3.
F The detailed facility configurations and conditions to be tested will be defined in Test Plan and Procedures documents to be prepared for each test series.
i e
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25A5587 SH NO.18 REV.A Table 9-1. PANDA Steady-State PCC Performance Test Matrix PANTHERS GIRAFFE PANDA Steam Flow Air Flow Test Condition Phase 1, Step 1 Test No.
(kg/s)
(kg/s)
No.
Test No.
S1 0.20 0
41 2
S2 0.20 0.003 9
4 S3 0.20 0.006 15 6
S4 0.20 0.016 18 8
S5 0.20 0.034 23 10 S6 0.26 0
43 3
i i
=
@MM 25A5587 SH NO.19 REY.A Table 9-2. PANDA Integral Systems Test Matrix Panda RPV No.
Bypass Test Break No. of Water of Leakage Initial No.
Type PCC Supply IC Area Conditions Comments Flow M1 MSL 1 in 0
0 0
GIRAFFE Repeat of
-33% to DW1 Giraffe Phase DW1 2 MSLB Test
-67% to U
DW2 M2 MSL 1 in 0
0 0
GIRAFFE Repeat of
-0% to DW1 Giraffe Phase DW1 2 MSLB Test
-100 %
with D\\
to DW2 asymmetric steam flow to DW1 and 2 M3 Same as 1 in 0
0 0
SSAR Repeat of M1 M1 DW1 with SSAR conditions 2in DW2 M4 Same as 1 in 0
0 0
SSAR Repeat of MS M1 DW1 2 in DW2 M5 Same as 1 in Yes 0
0 SSAR Repeat of MS M1 DW1 with continuous RPV water DT injection
[
M6 Same as 1 in 0
1 0
SSAR Repeat of MS M1 DW1 with IC l
2 in DW2 i
i
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25A5587 SH NO. 20 REY.A Table 9-2. PANDA Integral Systems Test Matrix (continued)
Panda RPV No.
Bypass Test Break No. of Water of Leakage Initial No.
Type PCC Supply IC Area Conditions Comments Flow M7 Same as 1 in 0
0 0
PCC filled Repeat of MS M1 DW1 with air, with PCC early start blanketed with air D\\
M8 Same as 1 in 0
0 TBD SSAR Repeat of MS M1 DW1 with D W to WW bypass leakage D\\
M9 Same as 1 in Yes 0
0
- SSAR, Cold water M1 DW1 carly start injection to open vacuum 2in breaker DW2 o
E 25A5587 SH NO. 21 REV.A i
10.
PRETEST PREDICTIONS / ACCEPTANCE CRITERIA A set of pretest calculations will be performed for some of the matrix tests planned for SBWR l
certification. This activity will include development of a TRACG input model for the PANDA facility, verification of the input model against as-built test facility data, design review of the i
input model, calibration of the input model using heat loss and pressure drop data from test facility characterization testing, selection of the test conditions for simulation, performance of the calculations, and documentation of the results. It is intended that these calculations are performed before the tests are run, or, in any event, with the test data withheld from the analyst. A design record file, separate from the test design record file, shall be maintained.
This file will document the development of the input model, the model verification, and the results of the analyses.
In addition to the pretest prediction, before each matrix test is run, an acceptance criteria will be specified. This will be specified in the Test Plans and Procedures in most cases. This acceptance criteria will define the tolerance on the initial conditions and any other input test conditions (such as simulated decay heat) which can influence the test results. The i
acceptance criteria will also define the instrumentation performance required in order to consider the test as acceptable.
t 11.
REPORTS i
11.1. Data Transmittal.
PSI shall provide a copy to GE of all test data, in a format to be specified in the Test Plans and f
Procedures.
I 1.2. Reports.
l A brief Apparent Test Results (ATR) report will be prepared for each test or each test series if the test series will be completed in approximately one week. The ATR will be issued within i
approximately one week following performance of the test (s).
Final Test Reports (FTR) will contain the data, analysis and results of all tests and shall be transmitted to GE per the schedule to be specified in the Test Plans and Procedures.
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@hM 25A5587 SH NO. 22 REV.A 12.
RECORD RETENTION.
All test records, analyses and verification records shall be organized by PSI into a test file which will become a GE Nuclear Energy Design Record File (DRF). The DRF number is XX, and the GE Test Requestor is the DRF custodian. The data stored electronically will be provided to GE-in a form suitable for long term storage, i.e. 40 years. Table 12-1 gives the table of contents for the test file.
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4 25A5587 SH NO. 23 REV.A TABLE 12-1 PANDA DESIGN RECORD FILE TABLE OF CONTENTS 1.
TEST REQUIRE 51ENTS DOCU51ENTS 1.1 Test Specification 1.2 Quality Assurance Program 1.3 Test Plans and Procedures 2.
TEST FACILITY DESIGN 2.1 Facility Design Drawings 2.2 Design Resiew 3.
TEST FACILITY CHECKOUT 3.1 As-Built Drawings 3.2 Commissioning Tests 3.2.1 Hydrotests 3.2.2 Heat Loss Tests 3.2.3 Line Pressure Drop Tests 3.2.4 Other 4.
INSTRUSIENTATION 4.1 Instrumentation List 4.2 Range and Accuracy Requirements 4.3 51anufacturers' Specifications 4.4 Uncertainty Analysis 4.5 Calibration 4.5.1 Plan / Procedures l
4.5.2 Records 4.6 Exact Location on Test Facility (drawings or sketches and tables) 5.
DATA ACQUISITION SYSTEM 5.1 DAS Hardware Requirements 5.2 DAS Hardware Description 5.3 Wire / Cable Lists-DAS Hookup 5.4 Wire / Cable Lists Verification 5.5 DAS Software 5.6 DAS Software Verification
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N 25A5587 SH NO. 24
\\
REV.A TABLE 12-1. CONTINUED
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6.
TEST MATRIX i
6.1 Facility Configuradon 6.2 Initial Conditions / Acceptance Criteria 7.
SilAKEDOWN TESTS 7.1 Facility Configuration 7.2 Initial Conditions / Acceptance Criteria 7.3 Nonconformance Items 8.
TEST OPERATION 8.1 Pre-test Checklists / Procedures 8.1.1 Preconditioning / Final Valve Alignment 8.1.2 Initial Condition Acceptance 8.1.3 DAS/Instmmentation Acceptance 8.2 Post-test Checklists / Procedures 8.2.1 Test Logs 8.2.2 Facility Shutdown Records 8.2.3 Nonconformance Items 8.3 Data Printouts 8.3.1 Pre-test 8.3.2 Post-test 8.4 Data Storage Information i
9.
POST TEST DATA REDUCTION i
9.1 Data Reduction Plan 9.2 Data Reduction Software 9.3 Reduced Data Records 10.
TEST REPORTS 10.1 Apparent Test Results Reports. _
10.1.1 Analytical Basis / Supporting Data 10.1.2 Draft Report Comment Resolution 10.2 Final Test Reports 10.2.1 Analytical Basis / Supporting Data 10.2.2 Draft Report Comment Resolution 10.2.3 Report Verification 11.
AUDIT REPORTS
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E 25A5587 SH NO. 25 REV.A
- 13. QUAllW ASSURANCE REQUIREMENTS I
13.1. References.
The PANDA tests shall be performed in conformance with the PSI QA Handbook for the ALPHA Project (Refence 14.2b) which is based on the requirements of 10 CFR 50 Appendix B (Reference I
14.3a) and ANSI /ASME SQA-1/la-1983 (Reference 14.3b).
13.2. Audit Requirements GE Nuclear Energy reserves the right to perform audits to verify that PSI's quality assurance program is in place and being followed. A facility Operational Readiness Review will be performed prior to the start of matrix testing.
13.3. Notification.
PSI has the responsibility to notify GE Nuclear Energy with documentation of:
(a) any changes in the test procedure, t
(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 (e) any changes to the GE accepted PANDA QA Program (Reference 14.2b)..
t 13.4. Test Plan and Procedures.
The tests shall be performed in accordance with Test Plan and Procedures (TP&P) documents to be prepared by GE Nuclear Energy and PSI and issued by PSI. The TP&Ps shall be traceable and retrievable documents of test requirements consisting of the following parts:
a.
Test Plan.
Describes how the test is to be set up and performed to meet the quality assurance requirements, any special or unique safety or chemical hazard conditions associated with the test, and the test requirements specified in this Test Specification.
b.
Test Procedures.
Describes the specific procedures required to perform the test in accordance with test and quality assurance requirements.
9 25A5587 SH NO. 26 REV.A F1NAL I
14.
REFERENCES.
14.1. GE-Nuclear Energv Documents:
a.
EOP 35-3.00 b.
EOP 65-2.10 NEDC-32391P, SBWR Test and Analysis Program Description, August 1994 c.
14.2. Paul Scherrer Institute Documents:
PANDA: Specification of the Physical Parameter Ranges, and the Experimental Initial a.
Conditions, T.\\1-42-92-18 b.
ALPHA Project, Quality Assurance Handbook,later 14.3. Other Documents:
b.
ANSI /AS.\\lE NQA-1-1983 and Addenda NQA-la-1983
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