ML20046A471

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Forwards Presentation Matls Used During 930618 Meeting in Monroeville,Pa to Discuss AP600 Testing Program.List of Attendees & Presentation Matls Encl
ML20046A471
Person / Time
Site: 05200003
Issue date: 06/28/1993
From: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ET-NRC-93-3910, NUDOCS 9307280155
Download: ML20046A471 (84)
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4 2 Westinghouse Energy Systems Box 355 Electric Corporat!on Pinsbu@ Pennsylvania 15230-0a55 ET.NRC-93 3910 NSRA-APSI 93-0223 Docket No.: STN-52-003 June 28,1993 Document Control Desk U.S. Nuclear Regulatory Commission Wasnington, D.C. 20555 ATTENTION: R.W.BORCHARDT

SUBJECT:

PRESENTATION MATERIALS FROM THE JUNE 18,1993 MEETING ON THE AP600 TESTING PROGRAM

Dear Mr. Borchardt:

Attached are presentation materials used during the June 18,1993 meeting in Monroeville, PA to discuss the AP600 Testing Program. The following materials are attached:

Attachment 1 Meeting attendance list from June 18,1993 meeting Attachment 2 Presentation materials, June 18,1993 meeting The Westinghouse Electric Corporation copyright notice is also attached.

Please contact Brian A. McIntyre on (412) 374-4334 if you have any questions concerning this-transmittal.

A .he N. J. Liparulo, Manager Nuclear Safety & Regulatory Activities

/nja Attachment cc: R. Hasselberg, NRC -

T. Kenyon, NRC (w/o enclosures)

B. McIntyre, Westinghouse (w/o enclosures) 270053 10t4A -

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9307280155'930628-17 3 PDR ADOCK 05200003- }5 (

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, COPYRIGIIT NOTICE I The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection not withstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, D.C. and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose. The NRC is not authorized to make copics for the personal use of members of the public who make use of the NRC public document rooms. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

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. WESTINGHOUSF/NRC MEETING i AP600 TESTING PROGRAM OVERVIEW -

JUNE 18,~ 1993 NAME- ORGANIZATION ' PIIONE ~

John C. Butler _ W AP600 Ucensing - (412) 374-5268-

- Chris L. Hoxie NRC/NRR/DSSA/SCSB (301) 504 3138 Thomas Kenyon NRC/NRR/ADAR/PDST - (301) 504-1120-Don McPherson NRC/NRR/DSSAL (301) 504-2865 -

Joe M. Kelly _ NRC/RES/RPSB (301) 492-3545 s

Brian A. McIntyre. W AP600 Licensing - (412) 374-4334 Larry Hochreiter .WNuclear Safety Licensing  : (412) 374-5158 Terry Schulz W Systems Engineering -~ (412) 374-5120 Gene Piplica W Test Engineering . (412) 374-5310 a

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WESTINGHOUSE ELECTRIC CORPORATION PRESENTATION TO <

UNITED STATES NUCLEAR REGULATORY COMMISSION  !

AP600 DESIGN CERTIFICATION TESTING PROGRAM OVERVIEW  !

i WESTINGHOUSE ENERGY CENTER JUNE.18,1993

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AGENDA l

WESTINGHOUSE /NRC MEETING AP600 DESIGN CERTIFICATION TESTING PROGRAM OVERVIEW B. A. MclNTYRE 8:30 INTRODUCTION T. L. SCHULZ 8:45 AP600 OVERVIEW l

L. E. HOCHREITER 9:30 BASIS FOR AP600 TEST AND ANALYSIS PROGRAM E. J. PIPLICA 10:15 AP600 TESTING PROGRAMS 11:30 LUNCH l

L. E. HOCHREITER 12:30 AP600 TEST ANALYSIS PLAN W/NRC INTERFACE, INFORMATION FLOW J.C. BUTLER 1:00 _

1:30 DRIVE TO W SCIENCE & TECHNOLOGY CENTER ALL i 2:00 TEST FACILITY TOUR 2:45 DRIVE TO W WALTZ MILLS FACILITY ALL 3:30 CORE MAKEUP TANK FACILITY TOUR

ll INTRODUCTION B. A. McINTYRE, MANAGER ADVANCED PLANT SAFETY AND LICENSING O

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!"$!l AP600 OVERVIEW i

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T. L. SCHULZ, FELLOW ENGINEER SYSTEMS AND EQUIPMENT ENGINEERING

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! - Greatly Simplify Systems to improve Safety, Cost, 1

Construction, Maintenance, & . Operation l

. Provide Simple Passive Safety Systems

- Dedicated safety systems, not used for normal operation

- Use " natural" driving forces. only. -

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- One-time alignment of ~ active valves a

- No. support systems after actuation L - Reduced operator dependency

- Provide Non-Safety Systems .

- Redundant active equipment powered by nonsafety diesels

- "First line of defense"; redundant active Minimize unnecessary use of: passive safety systems.

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- Reduced risk to utility & public-

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AP600 SAFETY SYSTEMS ance, operation, ISI / IST it Provide Passive Safety Systems- Greatly simplifie t ms (EPRI)

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- Meet EPRI safety goals w/ NNS sys e

" uipment Safety Systems Design Features- Only passive iteria

- Significant design margins- Redundancy to meet s ti ns

- PRA based redundancy./ diversity- Greatly r

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Safety Equipment Design ti n Features-- Reliable /

- Improved inservice testing / inspec oA, B, or C t

- Reg Guide 1.26 Quality Group- Seismic I design

- Availability controlled by Tech Spec w

- Reliability Assurance Program

- Tier i description and ITAAC

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- Provide Non-Safety Systems Reliably support normal operation

- Minimize challenges to passive safety systems

- Not required to. mitigate design basis accidents a

- Not required for NRC PRA-goals

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- Used to meet EPRI-safety goals Non-Safety Systems Design Features Redundancy for more probable failures -

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- Connections to the non-safety diesels

! - Automatic actuation-and controls-

- Separated from safety systems

- Separation within:NNS systems not required .

- Non-Safety Equipment-Design Features

- Reliable / experienced based equipment

- Reg Guide t26 Quality Group D ,

- Uniform Building Code, not seismic 1 ,

- Availability controlled by procedures-(50.59) w/o shutdown requirements

- Reliability:. Assurance- Program - ,

- Less detailed Tier 1-description and ITAAC l - _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ . , , _

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LAP 600 PASSIVE SAFETY FEATURES _

.- Passive Decay Heat Removal Natural circulation HX connected to RCS l - Passive Safety injection N2 pressurized accumulators

- Gravity drain core makeupLtanks (RCS pressure) ,

- Gravity drain. refueling water storage tank (containment pressure)

- AutomaticLRCS depressurization ,

Passive Containment Cooling Steel containment-shell transfers heat to natural circulation of air-andl evaporation of water drained by gravity .

- Passive HVAC-  :

- Compressed air for habitability of main' control room L

Concrete: walls for heat sink-(MCR.and I&C rooms) '

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- 'Non-safety feedwater for normal shutdowns and transients

- Two motor driven pumps feed all SGs

- Water supplied from deaerating heater or CST

- Automatic start and flow control, auto load on NNS diesels

. Passive RHR Heat Exchanger

- Safety cooling when SFW is unavailable and non-LOCA accidents

- Two heat exchangers connected directly to RCS

- Forced flow with RCP; natural circ without RCP

- Automatic actuation; two fail-open valves

- PRHR HX located in IRWS'. , provides heat sink, subcooled for 2-3 hrs.

- Passive containment cooling provides ultimate heat sink

- RCS Feed and Bleed

- Provides backup to SFW and PRHR HX for PRA events

- Feed from CMT/ Accumulator /lRWST, bleed from ADS

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AP600 RCS MAKEUP

. CVS Makeup Pumps

- Non-safety makeup for normal plant operation Can accommodate 3/8" break without SI

- Two motor driven centrifugal pumps Automatic start and connection to diesel

- Core Makeup Tanks

- Safety makeup to RCS when CVS unavailable or with larger leaks

- Two tanks provide makeup by gravity at any RCS pressure

- Automatic actuation by opening redundant air operated valves, fail open, for each CMT

- Provides significant makeup before ADS actuation; 3 gpm leak for 40 hr

- PXS Tanks and ADS

- Safety injection for LOCA l - Also PRA backup to CMT & CVS

- Two CMT,' two Accumulators and one IRWST provide makeup

- Four stages ADS provide controlled depressurization of RCS

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ijEi! iiill AP600 ADS DESIGN APPROACH "i ."

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- Reliable Operation \'

- Provide redundancy and diversity Single failure for DBA, multiple for PRA

- _ Experience based designs; gate / globe valve bodies with DC motor / air piston operators

-- AP600 ADS tests for valves, sparger &. IRWST

- Minimize Actuations

- Goal of less than 1 ADS-actuation in 600; years 1

- Reliable l&C; 2/4 logic, appropriate interlocks.

- Reduced real challenges; no RCP seals or Pressurizer PORV, reliable normal makeup, large.CMT.  ;

- RNS injection prevents 4th stage opening and containment flooding

- Minimize Consequences Major RCS equip.: designed for no damage with multiple occurre'nces

- Aux equip. designed or located:such that they are not flooded / damaged

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- . Restart in 2 weeks without 4th-stage opening i

AP600 CONTAINMENT COOLING

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- Containment Fan Coolers  :

- Nonsafety heat removal during normal operation and transients

- 2 coolers, each with 2 fans

- Chilled water provides heat sink

- Automatic control and loading on NNS diesels l

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- Passive Containment Cooling System

- Safety heat removal when fan coolers are unavailable or during large energy releases

- Steel containment shell cooled by air flow / water evaporation L

- Water drains by gravity from elevated tank, air circulates by natural circulation

- Automatic actuation opens redundant air operated valves, fail open Other Containment Cooling Features i

- Boiling of water sprayed on outside of containment vessel from fire protection pumps-

- Natural circulation of air, without any water

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! BASIS FOR AP600 TEST AND ANALYSIS PROGRAM i

L. E. HOCHREITER, CONSULTING ENGINEER NUCLEAR SAFETY ANALYSIS AND STRATEGIC DEVELOPMENT r +  % , - - - ,-- -- *r -- __ m___. - _ _ ____ -

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Basis for AP600 Test and Analysis Program _

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i Things We Considered When Structuring the AP600 Test Program ,

,-i o What systems are different?

o What design information is needed to evaluate performance?

i-o What phenomena would be important for safety analysis assessment?

l o What data are needed for modeling?

l o What data exist for code validation?

o Which codes or models'should we use?

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_ _ . . . _ . .-- _ ~ . . _ . , .-

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Basis for AP600 Test and Analysis Program '

o We examined the key phenomena for

- Large break LOCA

- Small break LOCA

- Transient analysis ,

- Containment analysis

- Long-term cooling L

o Assessed the new features l

o Determined if data existed for code validation t

I i o if no data was available or if was insufficient, a specific test was developed

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Small Break LOCA SBLOCA Model AP600 Uniqueness Validation - AP600 Specific Validation Needed Comments w.r.t. W Plants Does it Exist?

LOCA Process ADS tests, modeled with Criticalitem for AP600 Yes No ADS Blowdown SBLOCA code to Process develop / verify model May need to verify Pressurizer model has to Yes Yes, LOFT Pressurtzer Model to pressurizer model to be be vertfled to Handle ADS accommodate larger consistent with ADS breaks l

Yes None

Core H.T. No Yes, Reflector Yes, not specific None Structure H.T. ,

to AP600 No CMT component test, HHSI Delivery, Signal, Yes along with ADS tests Behavior, Delivery should show signal rate generation and flow rates Yes None Two phase loop AP's No Yes, no loop seals Yes None Loop Seal Behavior CCTF, UPTF data should No CMT tests, UPTF, CCTF HHSI Delivery Yes, delivery in be available. Model downcomer Location downcomer these tests with WC/T

Small Break LOCA (continued)

SBLOCA Model AP600 Uniqueness Validation - AP600 Spect!!c Validation Does it Exist? Needed Comments .

LOCA Process w.r.L W Plants -

ADS tests will test actual Need to develop valve Yes, ADS valves No critical flow model,-

Critical Flow valves, sparger sparger model Not directly None, code can handle Loop Draining Yes, 2HL, 4CL (llconsed NOTRUMP for Behavior CE 2x4 design) i No Yes None SB SG Behavior PRHR Tests Examine PRHR effect on i Yes No

- Cooldown with PRHR system response l

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Nooded Comments

' w.r.t. W Plants Does it Exist? ,

Containment Behavior __

No PCCS Tests,1/8 Scale Tests, Currently Planned U Eveporative Film CooIIng Yes Tests Will Meet Heated Plate Tests

, Needs-Yes, not AP600 Some as above, plus other Same as above Condensation, with Non- No Specific data, CVTR, U. of Wisconsin -

Condensibles Same as above Same as above Air Cooling of Steel Shell Yes No f' Same as above -

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- Yes, not AP600 Same as above -

Internal Circulation No Specific

' Patterns in Containment -

Same as above Same as above

- No Yes, not AP600 Effect of Hydrogen on .

Specific Containment Heat'

Transfer .

Film Flow Experiments Will- Prototypical Yes~ No System Will be l Liquid Film Distdbution Design the Water on Containment Distrtsution Tested :

o Plate Tests o Large Scale Film Flow Tests Small Scale Wind Tunnel Goalis to make

. Effects of Buildings and Yes- No Data Exists, Additional Tests design Wind Wind Velocity on Air are Planned . Neutral  ;

Flow over Steel Shell -

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! Basis for AP600 Test and Analysis Program This Process Led Us To:

i o- Perform Scaled - Full Scale Design Verification Tests of New Critical Components o Perform Separate-effects Tests on Large - Full Scale Hardware to Reduce Scaling--

Concerns o Perform Low Pressure Integral Systems Test at Reduced Scale to Verify Safety Analysis Codes for Gravity Drain / Core Cooling System Behavior when Passive  :

Systems would be most challenged (OSU) .

o Emphasize containment performance using small scale tests for model development -

and two larger. scale systems tests for model verification ,

- Use best estimate thermal-hydraulic system codes o

o After discussions with the NRC ar.aff and the ACRS; Westinghouse proposed to -

perform full height, full pressure integral systems tests to remove any residual doubt on passive safety system performance (SPES-2) i

Basis for AP600 Test and-Analysis Program Tests on Passive Core Cooling Systems

, o Used to verify computer models Passive Residual Heat Removal _ System Heat Exchanger tests to obtain heat ,

transfer data for PRHR performance ,

i Core Makeup Tank test to verify condensation and gravity drain models -

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- Automatic Depressurization System tests OSU integral Systems tests will verify long-term cooling flow path with gravity.

feed at medium-teow pressures +

- - SPES Integral Systems. tests will examine high pressure integral systems effects for SBLOCA, SGTR and MSLB situations A

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Basis for AP600 Test and Analysis Program Tests on Passive Containment Cooling Systems l

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l o Used to assess and verify safety analysis methods

- Develop / confirm evaporative heat transfer tests for interior of containment

- Containment wind tunnel tests

- Full scale segment of the containment dome to investigate water distribution

- Passive containment cooling tests,3 ft. diameter by 25 ft. high vessel

- 1/8 th scale containment cooling tests,15 ft. diameter by 25 ft. high vessel which simulates AP600 containment, used for code verification at larger scale e as

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l AP600 TESTING PROGRAMS E. J. PIPLICA, MANAGER -

TEST ENGINEERING

1 AP600 Testing Programs ,

Summary o The test program is extensive o Many successful results to date confirm design features o Test data has been/will be incorporated into analysis codes which in turn confirm l

plant performance o Program includes two integral tests at high and low pressure i

o Test program is highly responsive to USNRC and the Utilities f-

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' AP600 Testing Programs Test Categories l

o Safety Related Tests 1

o Non-Safety Related Equipment Tests I

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0 Basic Research Tests i

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. Safety Related Tests _

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o Provide data for computer codes used for SSAR analysis: i

- Models 1

- Correlations 1

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" - Verffication

.o Generally, a thermal-hydraulic test 3

- Performed to understand and explain T/H phenomena  ;

' - Can be system or separate effects test L o Highest quality assurance pedigree

- NQA-1 applies,10CFR21 applies

- Test specification required .

Test operating procedures required

- . Test facility design documentation required

- Quality records required o Examples

- Large Scale PCCS Heat Transfer tests

- Integral Systems tests (SPES-2, OSU) ,

- Separate Effect Tests (ADS, CMT) :l'

nmij Non-Safety Related Equipment Tests , . . .

o Provide design information on specific components

- Feasibility of design Manufacturability

- Verify component performance n

o Generally mechanical tests

- Performance data

- Wear data i

l o High quality assurance standards I.

- NQA-1 applies

- -. Test specification optional

- -Test operating procedures required

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' - r Test facility design documentation required

- Quality records required o- Examples

- High inertia Rotor tests

- RCP Flow tests (air & water)

- Check Valve tests i

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l Basic Research Tests ,

.o Experimental in nature 3

o Generally bench tests performed at universities i

- Investigate specific phenomena in detail -

- Answer specific questions of performance or feasibility

- Provide guidance for further testing o Quality requirements

- Test plan required

- Test facility det.'gn documents required .

i o Examples

- University of Wisconsin condensation tests ,

- University of Tennessee Reactor Vessel Air Visualization tests ,

- . Bench Wind Tunnel test f

AP600 Test, Analysis & Design Process __

TEST REQUIREMENTS

. Analysis (Models, codes)

. Designverencanon e NRC/Uoensing Requirements k

TEST SPECIFICATION e Fadlity Requirements e Prolininary Test Maartx y

r Test Design Scaling Analysis Tm FW W

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Faditty Construction

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  • Final Test Matrix Test Operasing Procedures k

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1 l-AP609 Testing Programs

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L l o Design Certification Tests

- Passive Core. Cooling System Tests

- Passive Containment Cooling System (PCCS) Tests o Engineering Tests

- Component Design Verification Tests L--__...__-___-__--_--__

llRj AP600 Testing Programs 3,eno PASSIVE CORE COOLING SYSTEM TESTS l

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AP600 Passive Core Cooling System Tests .

o Passive Residual Heat Removal Heat Exchanger Tests

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Automatic Depressurization System Phase A Tests o Integral Systems Tests o Departure from Nucleate Boiling Tests o Core Makeup Tank Tests o Automatic Depressurization System Phase B Tests t 1

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AP600 Passive Core Cooling System Tests Completed Tests .

o- ' Passive Residual Heat Removal Heat Exchanger Test

- Confirmed heat transfer performance ,

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! o Automatic Depressurization System (ADS) Phase A Test:

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- Sparger blowdown characteristics have been tested L

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AP600 Passive Core Cooling System Tests Ongoing and Planned Tests o Two separate Integral System Tests examine the behavior of the plant and interconnected systems

- Full-height, full-pressure test at SPES facility in Italy models two AP600 loops with CMTs, accumulators, passive heat exchanger, IRWST, and automatic depressurization system -

- A quarter-scale lower pressure (~400 psig) test at Oregon State University will model'the NSSS, passive safety features, and important non-safety features o Departure from Nucleate Boiling (DNB) Test

- The AP600 pump design includes a high inertia rotor to control flow coastdown

- Ample margin to DNB eliminates design impaci o Core Makeup Tank Test o ADS Phase B Test

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AP600 Testing Program Passive Containment Cooling System Tests S

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Completed Tests (continued) o- Heated Plate and Integral PCCS Tests

- Confirmed heat transfer capability o Large - %th scale PCCS Heat Transfer Tests

- Detailed interior / exterior heat transfer performance characteristics 1

-o Water. Distribution' Tests

- Measured prototypical water coverage o Wind Tunnel Test

-- Confirmed natural circulation'with site wind conditions present

- Optimized air inlet and exhaust arrangements -

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AP600 Passive Containment Cooling System Tests Ongoing and Planned Tests  ;

o Heat Transfer Tests f

- The 1/8th scale facility includes modeling of internal containment structures to assess steam distribution effects t Results from completed baseline tests and from previous fests incorporated 1

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- Measure water coverage using water distribution system -  :

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- Repeat at high'Reynolds numbers Site geography effects.will be assessed with a smaller model which varies site t

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AP600 Testing Program Component' Design Verification Tests l

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AP600 Component Design Verification Tests Completed Tests o Reactor coolant pump / steam generator channel head air flow test

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- Determined dynamic / horsepower characteristics l

o incore Instrumentation System (IIS) Test Demonstrated ilS will not be affected by Control Rod Drive Mechanism (CRDM) i electromagnetic interference o Reactor vessel flow visualization

- No abnormal flow distribution o Check Valve Mechanical Test l - Demonstrated low pressure performance

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' Key Tests for Design Certification o Separate Effects Tests l - Automatic Depressurization Test - Phase B

- Core Makeup Tank Tests L

o Integral Tests

- OSU 1/4 Height Scaled Pressure Test

- SPES-2 Full-Height, Full-Pressure Test

- PCCS Large Scale Heat Transfer Tests l

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o Organization - ENEA o Location - VAPORE Facility, Casaccia, Italy o Key Features

- Separate effects test

- Full scale, prototypic hardware o Purpose of Tests l

l - Evaluate valve performance l-

- Obtain piping load data l

o Progress o Schedule l

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-o Organization - Westinghouse o- Location - Waltz Mill Site, Madison, PA o Key Features

- Separate effects test at full pressure and temperature

- Simulated CMT (10 ft high x 2 ft diameter)

- Simulatec8 cold leg and pressurizer balance lines o Purpose of Tests

- Evaluate CMT performance Evaluate CMT level instrumentation

- Obtain T/H data for code verification o Progress o Schedule

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- Complete RCS and Passive Core Cooling System model

- 1/4 scaled height

- 400 psig maximum pressure

- Stainless steel components and piping o Purpose of Tests

- Provide T/H data for code verification at low pressure operation and during long term cooling o Progress o Schedule

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o Purpose of Tests

- ' Obtain T/H data at high pressure for computer code verification o The SPES-2 test matrix will address:

- SBLOCA simulations (break size, location, interactions w/ nonsafety systems)

- Steam line break

- Steam generator tube rupture

- Design basis with/without active systems to mitigate

- Beyond design basis events o Progress o Schedule

.SPES-2 Full-Height, Full Pressure Tests o Organization - SIET supported by ENEA, ENEL, and Ansaldo o Location - SPES Facility, Placenza, Italy o Key Features

- 1/395 volume scale, full pressure, full height facility

- 2250 psig,600 F

- Full simulation of AP600 features

- Two cold legs / one hot leg per loop

- Two CMTs,Two accumulators

- ADS simulation

- Two active steam generators

. Full height heated core

- PRHR modeled

- IRWST modeled L . Direct vesJet injection u___ _

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I Core Makeup Tank Test-b o Scaling logic will be provided to verify that the key thermal-hydraulic phenomena will be captured in the scaled CMT test-o Engineering analysis'of the CMT has been proceeding using WCOBRA/ TRAC to help "

size components, design the tests, place instrumentation as well as to test the code ,

o The CMT data will be analyzed to determine:  !

- Mass / energy balances '

- Wall condensation heat transfer coefficients

- Interfacial heat transfer.

- Thermal Stratification / Mixing effects

-- Void fraction with depressurization

- Natural circulation behavior o SSAR codes ( WCOBRA/ TRAC and NOTRUMP) will be used to analyze the CMT tests

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~ AP600 Test' Analysis Plan SPES-2 Full Height, Full Pressure integral Systems Tests

< o Scaling analysis has been performed to size loop components o Engineering analysis of the' facility is being performed by Ansaldo using -

RELAP5/ Mod 3, to verify scaling and to establish test operating procedures o Currently setting up a NOTRUMP model for SPES-2 o SPES-2 tests will be analyzed to determine:

- Transient system behavior for different SBLOCA break locations, sizes, system failures; Steam generator tube rupture; and Main steam line break o Tests will be analyzed using NOTRUMP and WCOBRA/ TRAC

AP600 Test Analysis Plan Oregon State University (OSU) Low Pressure Integral Systems Test. - .

o A detailed scaling analysis has been performed to design the reduced pressure, reduced height facility i

-- o Engineering analysis is being performed with NOTRUMP to help size the components,  ;

verify the pressure scaling approach and plan the tests o The OSU tests will be~ analyzed to determine:  !

- Transient system behavior for different break locations, sizes, and system failures -

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- --Test facility transient mass / energy balance

- Flow' regime characteristics .

o Tests.will be ' analyzed using NOTRUMP and WCOBRA/ TRAC 1 l

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I AP600 Test Analysis Plan Large Scale Containment Tests 0 Scaling logic presented in WGOTHIC topical report (WCAP-13246) o Feasibility tests analyzed with WGOTHIC i

- University.of Wisconsin condensation tests

- Heated plate tests t p

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! o Integral (small scale) PCCS tests have been analyzed with WGOTHIC and COMPACT l

L o Engineering _ analysis of Large Scale tests was down with COMPACT to help place instrumentation,'_ examine flow patterns o Large scale baseline tests have been analyzed with WGOTHIC o - Currently performing protest / engineering analysis with .W_ GOTHIC to establish test conditions ,

o Large scale test data will be analyzed to obtain

- test mas.s/ energy _ balances inside and outside of containment

- local heat flux, heat transfer coefficients

-- non-condensible distribution o- Large scale tests will be analyzed using WGOTHIC .

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AP600 Test Analysis Plan ngsoo Conclusions o A comprehensive AP600 test and analysis program has been

! deve':>ned and is in progress l

o Key new features are being tested L

o Tests will characterize the unique features at large scales so that computer models.can.be developed or verified

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o State-of-the-art safety analysis methods employed

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o The combined test and analysis program will meet AP600 licensing needs

W/NRC Interface, Information Flow ,

o Westinghouse is committed to conducting the AP600 test program in an open interactive environment

-o The current test program has benefited from comments and discussions with the NPC and Industry o The test program schedu!e is demanding and success oriented o The need for close and frequent interaction is crucial to the success of this schedule.

) o The need for ample time to for NRC review of the test programs and test results is

! recognized .

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W/NRC Interface, Information Flow Steps taken to ensure that high quality information is providec ?n a timely manner o Submit all test documents related to tests as they are created

- e.g., test plans or specifications, scaling rationale, facility description reports, instrumentation plans, facility / component drawings, test data reports, test analysis reports o Hold joint meetings with NRR, RES, ACRS staff and consultants

- to discuss test plans, analysis plans, instrumentation requirements, design and schedules o Provide information in advance of meetings to obtain feedback and comments during the meetings and to allow for more meaningful discussion

W/NRC Interface, Information Flow Steps taken to ensure that high quality information is provided in a timely manner (continued) o Provide test data on an ongoing basis

. rather than providing solely at the conclusion of the test program o Provide updated test schedules on a monthly basis

- to keep the NRC apprised of progress and to assist in plans for test reviews, visits and witness points -

o Minimize Proprietary claims on submitted information

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L W/NRC Interface, Information Flow _

AP600 Testing Program Review Meetings (December '92 - May '92)

December 9,1992 - OSU Tests, Detailed Review December 10,1992 - SPES-2 Tests, Detailed Review December 14,1992 - Testing Program Overview February 25,1993 - CMT Tests, Detailed Review & Facility Visits March 9-10,1993 - Test Program Review & Facility Visits

March 23-24,1993 - Containment Tests, Detailed Review & Facility Visits April 20,1993 - ADS Tests Review and Facility Visit April 22,1993 - SPES-2 Tests Rev ew and Facility Visit May 4,1993 - ADS Phase A Test Results Review May 26-27,1993 - ADS Tests, Detailed Review

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