ML20091P698

Nonproprietary Version of Suppl 1 of Sbwr Test & Analysis Program Description Suppl 1- Discussion of Pirt Parameters. W/Disk

ML20091P698
Person / Time
Site:	05200004
Issue date:	08/31/1995
From:	Andersen J, Blaesig H, Shiralkar B GENERAL ELECTRIC CO.
To:
Shared Package
ML20091P690	List: ML20091P686 ML20091P698
References
NEDO-32391-S01, NEDO-32391-S1, NUDOCS 9509010306
Download: ML20091P698 (11)

Text

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GENuclearEnergy

} NEDO-32391 Supplement 1 DRF A70-00002 Class 1 August 1995 '

) Licensing Topical Report SBWR Test and Analysis Program Description l

Supplement 1 - Discussion of PIRT Parameters

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August 31,1995 MFN 170-95 Docket STN 52-004 4

Document Control Desk

U. S. Nuclear Regulatory Commission

. Washington DC 20555 Attention: Theodore E. Quay, Director Standardization Project Directorate

Subject:

SBWR - Test and Analysis Program Description Supplement 1 - Discussion 3

of PIRT Parameters, NEDO-32391, Supplement 1 (Non-proprietary) i

Reference:

1. MFN 167-95, J. E. Quinn (GE) to T. E. Quay (NRC), SRWR - Test and Analysis Program Description Supplement 1 - Discussion of PIRT

• Parameters, NEDC-32391P, Supplement 1 (Proprietary), August 28,1995.

l This letter transmits the non-proprietary version of Supplement 1 of the SRWR Test and Analysis Program Description (TAPD) report (Reference 1), for your review. The Reference 1 supplemental report provides details of the method of development and supporting data and analyses relative to the Phenomena Identification and Ranking Tables (PIRT) parameters, which were developed for and used in SBWR Test Program.

If you have any questions regarding this report, please contact John Leatherman of our staff on (408) 925-2023.

Sincerely, lI

[2.lNu O h

^

I James E. Quinn, i

Projects Manager

Enclosure:

Test and Analysis Program Description Supplement 1 - Discussion of PIRT Parameters, NEDO-32391, Supplement 1, August 1995 1

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\s GENuclearEnergy MFN 170-95 cc: P. A. Boehnert ' (NRC/ACRS) - [2 paper copies w/ encl., plus E-Mail w/o encl.] .

'I. Catton (ACRS) - [1 paper copy w/ encl., plus E-Mail w/o enc 1] .

S. Q. Ninh . (NRC) - [2 paper copies w/ encl., plus E-Mail w/o enc 1]

J. H. Wilson ' . (NRC) - [1 paper copy w/ encl., plus E-Mail w/o enc 1] -

r. - _ _ - - _ - _ _ - _ - _ _ _ _ - _ _ - _ - _ _ _ _ - -

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NEDO-32391 Supplement 1 DRF A70-00002 Class 1 August,1995 I

SBWR Test and Analysis Program Description

, Supplement 1 - Discussion of l PIRT Parameters l

l B. S. Shiralkar J. Andersen H. Blaesig W. Marquino J. R. Fitch l

l Approved: -

[JameM,' Projects Manager

/ LMR and SBWR Programs l l

NEDO-32391, Supplement 1 4

-IMPORTANT NOTICE REGARDING -

CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The only undertakings of the General Electric Company (GE) respecting information in this document are contained in the contract 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 of this information by anyone other than the customer orfor any purpose other than that for which it is i intended, is not authorized; and with respect to any unauthorized use, i GE makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information containedin this document.

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NEDO-32391, Supplement 1 TABLE OF CONTENTS S1.0 Introduction...................................................................................................... S1-1 S1.1 Purpose.............................................................................................................. S1-1 S1.2 Definition of PIRT Phenomena Listed in TAPD Section 2.................................. S1-1 S1.3 Discussion of PIRT Phenomena and Rankings ................ ................ .................. S1-1 S1.3.1 Loss-of Coolant Accidents (Reactor Vessel and Core)............................. Sl-1 S 1.3.2 Loss-of Coolant Accidents (Containment)............................................... S1-1 S 1. 3. 3 Trans ien ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .S1-1 .............

S1.3.4 Anticipated Transients Without Scram (Pressurization Transients)..... .... S1-1 S 1. 3. 5 S tabili ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S1-1 S1.4 Synopsis of the Identified Phenomena and SBWR Unique Features and In te rac tions . . . . ... . . . .. . . .. . . . . . . .. . . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . .. . . . . .. . . .. . .. . . . ... . . .. . S1-2 S1.5 Corresponding Sections in TRACG Model Description Reports, (NEDE-3 217 6P Rev. O and Rev. 1 ) . . .. . . . .. . . .. .. . .. ........ .... . .... .. .... . ... .. ... .. .. . . . .. . S1-2 S1.6 References...................................................................................................... S1-2 1

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NEDO-32391, Supplement 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 CrP 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 Downcomer 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 lii L____ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _____ _ _

NEDO-32391, Supplement 1 ABBREVIATIONS AND ACRONYMS (Continued)

GEXL General Electric Critical Quality Boiling Length Correlation GIRAFFE Gravity-Driven Integral Full-Height Test for Passive Heat Removal GIST GDCS Integral System Test HCU Hydraulic Control Unit '

HVAC Heating, Vendladng and Air Condidoning 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 l LPCI Low Pressure Coolant Injecdon

! MCPR Minimum Critical Power Rado l MIT Massachusetts Institute of Technology MPL Master Parts List

. MSIV Main Steamline Isolation Valve MSL Main Steamline MW Megawatt N'BS Nuclear Boiler System NRC Nuclear Regulatory Commission ORNL Oak Ridge National Laboratory P&ID Process and Informadon Diagram PANDA Passive Nachwarmeabfuehr-und Drueckabbau-Testanlage (Passiv; Decay Heat Removal and Depressurization Test Facility)

PANTHERS Performance Analysis and Testing of Heat Removal Systems PAR Passive A utocatalytic Recombiners

! PCCS Passive Containment Cooling System l PCT Peak Cladding Temperature PIRT Phenomena Identification and Rankmg Tables PSTF Pressure Suppression Test Facility j QDB Qualificadon Data Base l RC&IS Rod Control and Infonnation System l RPV Reactor Pressure Vessel

( RWCU Reactor Water Cleanup SB Small Break l

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NEDO-32391, Supplement 1 ABBREVIATIONS AND ACRONYMS (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 / Relief Valve 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-Hydraulic Test Facility TLTA Two-Loop Test Apparatus TPS Turbine Protection System TRAC Transient Reactor Analysis Code TRACG Transient Reactor Analysis Code, GE version TT Turbine Trip UCB University of Califomia, Berkeley VB Vacuum Breaker WW Wetwell i

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NEDO-32391, Supplement 1 S1.0 Introduction S1.1 Purpose Supplement 1 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].

S1.2 Definition of PIRT Phenomena Listed in TAPD Section 2 This section provides definitions of phenomena considered in TAPD Section 2.

S13 Discussion of PIRT Phenomena and Rankings This section provides a discussion of PIRT Phenomena and Rankings.

S13.1 Loss-of Coolant Accidents (Reactor Vessel and Core) l This section provides a discussion of the detailed phenomena considered for LOCA l (Reactor Vessel and Core).

S13.2 Loss-of Coolant Accidents (Containment) l This section provides a discussion of the detailed phenomena considered for LOCA (Containment).

S133 Transients l

i This section provides a detailed discussion of the phenomena considered for transients.

S13.4 Anticipated Transients Without Scram (Pressurization Transients)

This section presents a discussion of the detailed phenomena considered in ATWS (Pressurization Transients).

S13.5 Stability This section provides a discussion of the detailed phenomena related stability as provided in TAPD Sections 2.2.4 and 2.3.4.

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NEDC 32391, Supplement 1

' 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.

St.5 Correspondence Between Sections in TRACG Model Description Reports, (NEDE-32176P Rev. O and Rev.1)

This section provides discussions relating the TRACG Model descriptions to those ptovided in TAPD Section 2.

St.6 References (l] 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.

Shum, K.M. Vierow. NEDE-32176P, 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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