ML20100E131
| ML20100E131 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 11/30/1995 |
| From: | Andersen J, Blaesig H, Shiralkar B GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20100E127 | List: |
| References | |
| NEDO-32391, NEDO-32391-S01-R01, NEDO-32391-S1-R1, NUDOCS 9602120286 | |
| Download: ML20100E131 (11) | |
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NEDO-32391 Supplement 1 DRF A70-00002 Class 1 November 1995 Revision 1 SBWR Test and Analysis Program Description Supplement 1 - Discussion of i PIRT Parameters B. S. Shiralktr J. Andersen H. Blaesig W. Marquino J. R. Fitch Approved: ,
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James E rojects Manager LMR d SBWR Programs hIO $Do o 20 g4 A
NEDO-32391 Supp.1, Rev.1 i
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY ,
l The only undertakings of the General Electric Company (GE) \
respecting information in this document are contained in the contract l between the customer and GE, as identified in the purchase orderfor this report and nothing contained in this document shall be construed as changing the contract. The use ofits information by anyone other than the customer orfor any purpose other than thatfor which it is intended, is not authorized; and with respect to any unauthorized use, GE makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.
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NEDO-32391 Supp.1, Rev.1 TABLE OF CONTENTS S1.0 Introd uction.................... ....... .................................................................. S1-1 S1.1 Purpose.............................................................. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S1-1 Sl.2 Defm' ition of PIRT Phenomena Listed in TAPD Section 2................ . ............... S1-1 !
l S1.3 Discussion of PIRT Phenomena and Rankings...................... .. ... ..................... S1-1 S t.3.1 Loss-of-Coolant Accidents (Reactor Vessel and Core).... . ... ........... ...... S1-1 S1.3.2 Loss-of-Coolant Accidents (Containment).......... . . . .. ....... .................... S1-1 S 1. 3 . 3 Trans i ents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S S1.3.4 Anticipated Transients Without Scram (Pressurization Transients).... ..... Sl-1 l S 1. 3 . 5 S tabi l i ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S1-1 S t.4 Synopsis of the Identified Phenomena and SBWR Unique Features and Interactions. . . . . . ... . .. . . . . .. . . . . ... . . .. . . . . . . . ... . . . .. . . . . . . . . . .. . . .... . . ... . . . . . . . . .S1-2 . . .. . . .. :
I S t.5 Corresponding Section in TRACG Model Description Reports, I (NEDE-3 2176P Rev. O and Rev. 1 ).... . .................... ... ... .......... .... . ...... ... . ...... .. .. . .. . S1-2 S1.6 References........................................................................................................... S1-2 l
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NEDO-32391 Supp.1, Rev.1 ABBREVIATIONS AND ACRONYMS ABWR Advanced Boiling Water Reactor AC Alternating Current ADS Automatic Depressurization System APRM Average Power Range Monitor ARI Alternate Rod Insertion ASME American Society of Mechanical Engineers ATLAS GE's 8.6 MW Heat Transfer Loop ATWS Anticipated Transients Without Scram Bldn Blowdown BO Boiloff BWR Boiling Water Reactor CACS Containment Atmospheric Control System CCFL Counter Current Flow Limiting CISE Centro Informazioni Studi Esperienze COL Combined Operating License CPR Critical Power Ratio CRD Control Rod Drive CTP Core Thermal Power CRIEPI Central Research Institute of Electric Power Industry CSAU Code Scaling, Applicability and Uncertainty CSHT Core Spray Heat Transfer DBA Design Basis Accident DC Dowmcomer DPV Depressurization Valve DW, D/W Drywell EBWR Experimental Boiling Water Reactor ECCS Emergency Core Cooling System EOPs Emergency Operating Procedures FAPCS Fuel and Auxiliary Pool Cooling System FIST BWR FullIntegral Simulation Test FIX Swedish Test Loop Used for Testing External Pump Circulation FMCRD Fine Motion Control Rod Drive FRIGG Research Heat Transfer Loop Operated for Danish Atomic Energy Commission FW Feedwater FWCS Feedwater Control System GDCS Gravity-Driven Cooling System '
GE General Electric Company i
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NEDO-32391 Supp.1, Rev.1 ABBREVIATIONS AND ACRONYMS (Continued) l l
GEXL General Electric Critical Quality Boiling Length Correlation GIRAFFE Gravity-Driven Intergral Full-Height Test for Passive Heat Removal GIST GDCS Integral System Test HCU Hydraulic Control Unit I HVAC Heating, Ventilating and Air Conditioning IC Isolation Condenser ICS Isolation Condenser System INEL Idaho National Engineering Laboratory LASL Los Alamos Scientific Laboratory LB Large Break LOCA Loss-Of-Coolant Accident LOOP Loss Of Offsite Power LPCI Low Pressure Coolant Injection MCPR Minimum Critical Power Ratio MIT Massachusetts Institute of Technology MPL Master Parts List MSIV Main Streamline Isolation Valve l MSL Main Steamline MW Megawatt NBS Nuclear Boiler System NRC Nuclear Regulatory Commission ORNL Oak Ridge National Laboratory P&ID Process and Information Diagram PANDA Passive Nachwarmeabfuehr-und Drueckabbau-Testanlage (Passive Decay Heat Removal and Depressurization Test Facility)
PANTHERS Performance Anclysis and Testing of Heat Removal Systems PAR Passive Autocatalytic Recombiners PCCS Passive Containment Cooling System PCT Peak Cladding Temperature PIRT Phenomena Identification and Ranking Tables PSTF Pressure Suppression Test Facility QDB Qualification Data Base RC&IS Rod Control and Information System RPV Reactor Pressure Vessel RWCU Reactor Water Cleanup SB Small Break iv
NEDO-32391 Supp.1, Rev.1 ABBREVIATIONS AND ACRONY.MS (Continued)
SBWR Simplified Boiling Water Reactor S/C Suppression Chamber (wetwell)
SDC Shutdown Cooling SIET Societa Informazioni Esperienze Termoidrauliche SLCS Standby Liquid Control System SPERT Special Power-Excursion Reactor Tests SRV Safety /ReliefValve SSAR Standard Safety Analysis Report SSLC Safety System Logic Control SSTF Steam Sector Test Facility TAPD Test and Analysis Program Description TCV Turbine Control Valve THTF Thermal-IIydraulic Test Facility TLTA Two-I.oop Test Apparatus TPS Turbine Protection System TRAC Transient Reactor Analysis Code TRACG Transient Reactor Analysis Code, GE version TT Turbine Trip UCB University of California, Berkeley VB Vacuum Breaker WW Wetwell l
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NEDO-32391 Supp.1, Rev.1 S1.0 Introduction S1.1 Purpose The process of Top-Down analysis and qualification of the performance of the SBWR starts with the identification of the important physical phenomena. For this purpose, Phenomena Identification and Ranking Tables (PIRT) were developed. This was done by assembling a team of experts knowledgeable about thermal-hydraulics and transient analysis, and obtaining consensus on the relative importance of various phenomena. Phenomena were given a rank between 0 and 9 based on their importance. The ranking was done on a conservative basis (i.e.,
generally, phenomena were given a higher rank if there was any uncertainty as to its importance).
This resulted in a large number of highly ranked phenomena. It is expected that a much smaller subset will actually prove to be "important" after the tests and sensitivity studies are completed.
Tables were developed for small break LOCAs, large break LOCAs, pressurization transients, depressurization transients and reactivity insertion due to cold water injection. Plant startup was also treated as a category of operational transients because of the focus on the potential for l geysering. Tables were also developed for ATWS (pressurization events) and for stability during i normal operation and transients. In each case, the importance of the phenomena was evaluated I for each reactor region: lower plenum, core, upper plenum / chimney, downcomer, etc., as well as for the containment. For the LOCA events, the tables were further subdivided into the blowdown, GDCS and long-term periods of the transients.
l Additional information regarding the PIRT process is provided by [4].
lTAPD Supplement 1 [5] provides a discussion of the Phenomena Identification and Ranking Tables (PIRT) parameters described in Section 2 of the SBWR Test and Analysis Program Description (TAPD) [1].
This supplement is organized as follows: first, a short definition of each parameter is provided in I the TAPD Supplement 1, Section Sl.2; then parameters for each of the categories of transients are discussed and the rationale for their ranking is outlined; finally, a master list of all parameters considered in TAPD Sections 2 and 3 is presented. The master list also shows the correspondence of the parameters derived from the Top-Down (PIRT) and Bottom-Up processes.
St.2 Definition of PIRT Phenomena Listed in TAPD Section 2 This section provides defimitions of phenomena considered in TAPD Section 2. l TAPD Supplement 1 Table Sl.1 is a listing of all the phenomena considered in TAPD Section 2. l The phenomena are labeled according to the convention of TAPD Tables 2.3-1 to 2.3-5. A definition of each phenomenon is provided in the third column.
I St.3 Discussion of PIRT Phenomena and Rankings This section provides a discussion of PlRT Phenomena and Rankings.
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NEDO-32391 Supp.1, Rev.1 This section discusses the PIRT phenomena and provides a basis for the rankings. This is done by referring to the event scenario detailed in TAPD Section 2.2. It should be recognized that PIRTs are based on engineeringjudgment and experience. The discussion that follows should be considered in that context. The importance of individual items is subject to re-evaluation if future tests or analysis provide different insights.
S13.1 Loss-of-Coolant Accidents (Reactor Vessel and Core)
This section provides a discussion of the detailed phenomena considered for the LOCA (Reactor Vessel and Core).
The detailed phenomena considered for the LOCA scenario are listed in TAPD Table 2.3-1.
They are grouped in the table by the regions of the reactor vessel and containment. In describing the phenomena, it is convenient to group them into major categories.
St.3.2 Loss-of-Coolant Accidents (Containment)
This section provides a discussion of the detailed phenomena considered for the LOCA (Containment).
In TAPD Table 2.3-2, the phenomena are grouped by the various regions of the containment.
The TAPD Supplement I discussion provides a description of the individual phenomena and their importance.
S133 Transients This section provides a detailed discussion of the phenomena considered for transients.
In TAPD Table 2.3-3, the PIRT parameters applicable to transients are listed by the region of the reactor vessel. Because of the neutronic coupling, the core region is by far the most important region for the operational transients. The TAPD Supplement I discussion provides a description of the individual phenomena and their importance.
S13.4 Anticipated Transients Without Scram (Pressurization Transients)
This section presents a discussion of the detailed phenomena considered in ATWS (Pressurization Transients).
The PIRT for a pressurization event (MSIV closure, turbine trip) with failure to scram is shown in TAPD Table 2.3-4. Because the event is initiated as a normal pressurization event, a large number of phenomena typical of the early phases of the transient are the same as those in the first column of TAPD Table 2.3-3 for operational transients. The description of these common phenomena and their relevance will not be repeated here. Only those phenomena that are different, or have a different significance, are discussed in TAPD Supplement 1.
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NEDO-32391 Supp.1, Rev.1 St.3.5 Stability This section provides a discussion of 'he detailed phenomena related stability as provided in TAPD Sections 2.2.4 and 2.3.4.
The phenomena affecting decay ratio and the likelihood of oscillations are summarized in TAPD Table 2.3-5.
St.4 Synopsis of the Identified Phenomena and SBWR Unique Features and Interactions This section provides further discussions of the PIRT evaluations in TAPD Sections 2 and 3.
Based on the results of the ranking evaluation in the PIRT (Top-Down approach, TAPD Section
- 2) and the results of the identification of the SBWR-unique features (Bottom-Up approach, TAPD Section 3) a composite list was developed. Items ranked high were carried through for further analysis in TAPD Section 4. In addition, those ranked medium in importance were also examined, but in less detail. This consolidation is documented in TAPD Supplement 1, Table !
SI-9. The table aix Nludes a complete evaluation of all phenomena for the specific scenarios, l 4 while in TAPD Tables 2.3-1 to 2.3-5, only the most important ones are presented. '
St.5 C9rrespondence Between Sections in TRACG Model Description Reports (NEDE- l 32176P Rev. O and Rev.1) 1 This section provides discussions relating the TRACG Model descriptions to those provided n i TAPD Section 2. '
In TAPD Tables 2.3-1 to 2.3-6, the right-hand column indicates the sections of the TRACG Model Description Report (NEDE-32176) [3] that pertain to the particular phenomenon. This TAPD section provides the corresponding numbers from NEDE-32176, Rev. O. The models are described in Revision 0, and they will be amplified in Revision 1, particularly with respect to documentation of the basis and the range of applicability. The correspondence is shown in TAPD Supplement 1, Table Sl-10.
St.6 References
[1] SBWR Test and Analysis Program Description, NEDC-32391P, Revision C, August 1995.
[2] TRACG Qualification, J.G.M. Andersen, Md. Alamgir, J.S. Bowman, Y.K. Cheung, L.A.
Klebanov, W. Marquino, M. Robergeau, D.A. Salmon, J.C. Shaug, B.S. Shiralkar, F.D.
l Shem, K.M. Vierow. NEDE-32177P, Licensing Topical Report, January 1993.
[3] TRACG Model Description, J.G.M. Andersen, Md. Alamgir, Y.K. Cheung, L.A.
Klebanov, J.C. Shaug. NEDE-32176P, Licensing Topical Report, January 1993.
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NEDO-32391 Supp.1, Rev.1
[4] SBWR Test and Analysis Program Description, NEDO-32391, Revision C, August 1995.
[5] SBWR Test and Analysis Program Description, NEDC-32391P, Supplement 1, August 1995.
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