ML20045F737

Summary of 930618 Meeting W/Westinghouse Re Testing Program Supporting Application for Final Approval & Design Certification for AP600 Design.List of Attendees & Viewgraphs Encl

ML20045F737
Person / Time
Site:	05200003
Issue date:	06/28/1993
From:	Kenyon T Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9307080319
Download: ML20045F737 (78)

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UNITED STATES

[ (jf_L[tj NUCLEAR REGULATORY COMMISSION

• I WASHINGTON, D.C. 205EE0001 gv /

• • • v June 28, 1993 Docket No.52-003 APPLICANT: Westinghouse Electric Corporation FACILITY:

AP600

SUMMARY

OF MEETING TO DISCUSS THE AP600 TESTING PROGRAM On June 18, 1993, representatives of the Nuclear Regulatory Commission (NRC) ana Westinghouse met to discuss the testing program supporting the application for final design approval and design certification for the AP600 design. is a list of attendees. is the slide presentation provided by Westinghouse.

Westinghouse provided a design overview of the AP600, emphasizing the design of the passive safety systems. The applicant then discussed the basis for the AP600 test and analysis program, stressing that the program addresses the adequacy of the design of unusual features of the plant. Westinghouse indicated that the testing program includes separate effects tests, low-pressure integral systems tests, and full-height, full-pressure integral systems tests.

The process for developing test specifications, the types of tests being performed, the supporting analysis, and the test facility designs were then discussed.

The applicant discussed the current schedule for the planned tests.

The participants then discussed the Westinghouse /ilRC interface, addressing timing and mission of the NRC staff observing the tests.

At the close of the meeting, the staff and Westinghouse agreed to undertake the following action items:

1.

Westinghouse will provide detailed testing schedules within the next several weeks; 2.

The staff will provide a written indication of the acceptability of the test matrices; 3.

The staff will apprise Westinghause of the guidance it will be providing its test monitors for observing important milestones during the tests; and 4.

The staff and Westinghouse will develop an outline of the contents of

" Quick Look Reports" that will be issued shortly after the tests are completed, but before analysis of the results is completed.

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The meeting ended with tours of the local test facilities, including some of ~

l those supporting evaluation of the adequacy of the passive containment cooling system and the core makeup tank system.

(Original signed by)

Thomas J. Kenyon, Project Manager l

Standardization Project Directorate Associate Director for Advanced Plants and License Renewal Office of Nuclear Reactor Regulation

Enclosures:

As stated l

l cc w/ enclosures:

l See next page l

DISTRIBUTION w/ enclosures:

Docket File PDST R/F DCrutchfield TKenyon PDR FHasselberg PShea DISTRIBUTION w/o enclosures:

RBorchardt TEssig JMoore, 15B18 GGrant, 17G21-l EJordan, MNBB3701 ACRS (11)

DMcPherson CHoxie JKelly t

Pg/ fOSfiADARSC:PD9 :ACAR fP 0FC:

LA:PDST:ADAR PSheg TK0dyon TEssig NAME: 06/gr/yy 06ge/93 0649 /93 93 DATE:

i 0FFICIAL RECORD COPY: MTSMTEST.TK j

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t 2-June 28, 1993 The meeting ended with tours of the local test facilities, including some of those supporting evaluation of the adequacy of the passive containment cooling system and the core makeup tank system.

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Thomas J. Kenyon, Project Manager Standardization Project Directorate Associate Director for Advanced Plants and License Renewal Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/ enclosures:

See next page l

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e Docket No.52-003 Westinghouse Electric Corporation cc: Mr. Nicholas J. Liparulo Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. B. A. McIntyre Advanced (dant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. John C. Butler Advanced Plant Safety & Licensing Westinghouse Electric Corporation Energy Systems Business Unit Box 355 Pittsburgh, Pennsylvania 15230 Mr. M. D. Beaumont Nuclear and Advanced Technology Division Westinghouse Electric Corporation One Montrose Metro 11921 Rockville Pike Suite 350 Rockville, Maryland 20852 Mr. Sterling Franks U.S. Department of Energy NE-42 Washington, D.C.

20585 Mr. S. M. Hodro EG&G Idaho Inc.

Post Office Box 1625 Idaho Falls, Idaho 83415 Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W.

Room 8002 Washington, D.C.

20503 i

Mr. Frank A. Ross U.S. Department of Energy, NE-42 Office of LWR Safety and Technology 19901 Germantown Road Germantown, Maryland 20874

e AP600 Testing Program Overview Meeting Attendees June 18, 1992 NAME ORGANIZATION L

John C. Butler E AP600 Ucensing Chris L Hoxie NRC/NRR/DSSA/SCSB Thomas Kenyon NRC/NRR/ADAR/PD5T Don McPherson NRC/NRR/DSSA Joe M. Kelly NRC/RES/RPSB Brian A. McIntyre E AP600 Licensing Larry Hochreiter E Nuclear Safety Ucensing Terry Schulz E Systems Engineering Gene Piplica ETest Engineering 9

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t WESTINGHOUSE ELECTRIC CORPORATION PRESENTATION TO UNITED STATES NUCLEAR REGULATORY COMMISSION AP600 DESIGN CERTIFICATION TESTING PROGRAM OVERVIEW FT1 a

S Ei WESTINGHOOSE ENERGY CENTER JUNE 18,1993 b

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INTRODUCTION B. A. MclNTYRE, MANAGER ADVANCED PLANT SAFETY AND LICENSING 4

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AGENDA WESTINGHOUSE /NRC MEETING AP600 DESIGN CERTIFICATION TESTING PROGRAM OVERVIEW 8:30 INTRODUCTION B. A. MclNTYRE 8:45 AP600 OVERVIEW T. L. SCHULZ 9:30 BASIS FOR AP600 TEST AND ANALYSIS PROGRAM L. E. HOCHREITER 10:15 AP600 TESTING PROGRAMS E. J. PIPLICA 11:30 LUNCH 12:30 AP600 TEST ANALYSIS PLAN L. E. HOCHREITER 1:00 WINRC INTERFACE, INFORMATION FLOW J.C. BUTLER 1:30 DRIVE TO W SCIENCE & TECHNOLOGY CENTER 2:00 TEST FACILITY TOUR ALL 2:45 DRIVE TO W WALTZ MILLS FACILITY

-3:30 CORE MAKEUP TANK FACILITY TOUR ALL

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AP600 OVERVIEW T. L. SCHULZ, FELLOW ENGINEER SYSTEMS AND EQUIPMENT ENGINEERING

y AP600 SYSTEMS DESIGN Greatly Simplify Systems to improve Safety, Cost, Construction, Maintenance, & Operation Provide Simple Passive Safety Systems

- Dedicated safety systems, not used for normal operation

- Use." natural" driving forces only

- One-time alignment of active valves

- No support systems after actuation

- 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

- Reduced risk to utility & public

n-vma AP600 SAFETY SYSTEMS Provide Passive Safety Systems

- Greatly simplified construction, maintenance, operation, ISI / IST

- Mitigate design basis accidents without use of NNS systems

- Meet NRC safety goals w/o NNS systems (EPRI)

- Meet EPRI safety goals w/ NNS systems Safety Systems Design Features

- Only passive processes; no " active" equipment

- Significant design margins

- Redundancy to meet single failure criteria

- PRA based redundancy / diversity

- Greatly reduced need for operator actions Safety Equipment Design Features

- Reliable / experience based equipment

- Improved inservice testing / inspection

- Reg Guide 1.26 Quality Group A, B, or C

- Seismic I design; Qualified Equipment

- Availability controlled by Tech Spec with shutdown requirements

- Reliability Assurance Program

- Tier i description and ITAAC

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AP600 NON-SAFETY SYSTEMS Provide Non-Safety Systems

- Reliably support normal operation

- Minimize challenges to passive safety systems

- Not required to mitigate design basis accidents

- Not required for NRC PRA goals

- Used to meet EPRI safety goals Non-Safety Systems Design Features

- Redundancy for more probable failures

- 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 1.26 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 i description and ITAAC

AP600 PASSIVE SAFETY FEATURES Passive Decay Heat Removal Natural circulation HX connected to RCS Passive Safety injection N2 pressurized accumulators Gravity drain core makeup tanks (RCS pressure)

Gravity drain refueling water storage tank (containment pressure)

Automatic RCS depressurization Passive Containment Cooling Steel containment shell transfers heat to natural circulation of air and evaporation of water drained by gravity Passive HVAC Compressed air for habitability of main control room Concrete. walls for heat sink (MCR and l&C rooms) 4 4

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Startup Feedwater System 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 IRWST, 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 Automatic actuation of CMT on high RCS temp with low SG level a

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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 Also PRA backup to CMT & CVS Two CMT, two Accumulators and one IRWST provide makeup Four stages ADS provide controlled depressurization of RCS S

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AP600 ADS DESIGN APPROACH 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 Reliable I&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 occurrences Aux equip. designed or located such that they are not flooded / damaged Restart in 2 weeks without 4th stage opening

AP600 CONTAINMENT COOLING 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 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 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 Boiling of water sprayed on outside of containment vessel from fire protection pumps Natural circulation of air, without any water m..

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Assessed the new features Determined if data existed for code validation o

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AP600 Testing Programs o

Design Certification Tests Passive Core Cooling System Tests Passive Containment Cooling System (PCCS) Tests o

Engineering Tests.

Component Design Verification Tests l

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Provide data for computer codes used for SSAR analysis:

Models Correlations Verification o

Generally, a thermal-hydraulic test Performed to understand and explain T/H phenomena Can be system or separate effects test o

Highest quality assurance pedigree NQA-1. applies,10CFR21 applies Test specification required l

Test operating procedures required l

Test facility design documentation required l

Quality records required l

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o Examples Large Scale PCCS Heat Transfer tests Integral Systems tests (SPES-2, OSU)-

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Verify' component performance o

Generally mechanical tests Performance data Wear data High quality assurance standards o

NQA-1 applies Test specification optional Test operating procedures required Test facility design documentation required Quality records required o

Examples High Inertia Rotor tests

. RCP Flow tests (alt & water)

Check Valve tests L

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Experimental in nature Generally bench tests performed at universities o

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 design documents required o

Examples University of Wisconsin condensation tests University of Tennessee Reactor Vessel Air Visualization tests Bench Wind Tunnel test

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

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Containment Analysis AP600 Uniqueness Cont. Validation -

AP600 Specific Validation Containment Behavior w.r.t. W Plants Does it Exist?

Needed Comments Evaporative Film Cooling Yes No PCCS Tests,1/8 Scale Tests, Currently Planned Heated Plate Tests Tests Will Meet Needs Condensation, with Non-No Yes, not AP600 Same as above, plus other -

Same as above Condensibles.

Specific date, CVTR, U. of Wisconsin -

l Air Cooling of Steel Shell Yes No Same as above Same as above Internal Circulation No Yes, not AP600 Same as above -

Same as above Patterns in Containment Specific Effect of Hydrogen on No Yes, not AP600 Same as above Same as above -

Containment Heat Specific Transfer Liquid Film Distribution Yes No.

Film Flow Experiments Will Prototypical Design the Water System Will be on Containment Distribution Tested '

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No-Small Scale Wind Tunnel Goalis to make Data Exists, Additional Tests. design Wind Wind. Velocity on Air are Planned Neutral Flow over Steel Shell L

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Perform Scaled - Full Scale Design Verification Tests of New Critical Components o

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Analysis Codes for Gravity Drain / Core Cooling System Behavior when Passive l'

Systems would be most challenged (OSU)

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After discussions with the NRC staff and the ACRS; Westinghouse proposed to o

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

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Small Break LOCA SBLOCA Model AP600 Uniqueness Validation -

AP600 Specific Validation LOCA Process w.r.t. E Plants Does it Exist?

Needed Comments ADS Blowdown Yes No ADS tests, modeled with Criticalitem for AP600 SBLOCA code to Process develop / verify model Pressurizer Model to Yes Yes, LOFT May need to verify Pressurizer model has to pressurizer model to be be verified to Handle ADS consistent with ADS accommodate larger breaks Core H.T.

No Yes None Structure H.T.

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

Small Break LOCA (continued)

SBLOCA Model AP600 Uniqueness Validation -

AP600 Specific Validation LOCA Process

w. rot. W Plants Does it Exist?

Needed Comments Critical Flow Yes, ADS valves No ADS tests will test actual Need to develop valve valves, sparger critical flow model, sparger model Loop Draining Yes, 2HL, 4CL Not directly None, code can handle (licensed NOTRUMP for Behavior CE 2x4 design)

SB SG Behavior No Yes None Cooldown with PRHR Yes No PRHR Tests Examine PRHR effect on system response l

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The test program is extensive Many successful results to date confirm design features o

Test data has been/will be incorporated into analysis codes which in turn confirm o

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

Test program is highly responsive to USNRC and the Utilities o

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Safety Related Tests o

Non-Safety Related Equipment Tests 4

o Basic Research Tests 3

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AP600 Passive Containment Cooling Systems Tests Completed Tests o

Bench Wind Tunnel Experiment Assessed effects of wind on shield building design (inlet / outlet location) o Air Flowpath Pressure Drop Test Obtained pressure drop data through the downcomer and annulus o

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' 1 AP600 Test Analysis Plan Core Makeup Tank Test Scaling logic will be provided to verify that the key thermal-hydraulic phenomena will o

be captured in the scaled CMT test Engineering analysis of the'CMThas been proceeding using WCOBRA/ TRAC to help o

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

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Thermal Stratification / Mixing effects Void fraction with depressurization Natural circulation behavior SSAR codes (.W_ COBRA / TRAC and NOTRUMP) will be used to analyze the CMT tests o.

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SPES-2 Full Height, Full Pressure Integral Systems Tests Scaling analysis has been performed to size loop components o

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Scaling logic presented in WGOTHIC topical report (WCAP-13246) j o

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instrumentation, examine flow patterns-Large scale baseline tests have been analyzed with EGOTHIC o

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o A comprehensive AP600 test and analysis program has been developed and is in progress o

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

State-of-the-art safety analysis methods employed The combined test and analysis program will meet AP600 licensing o

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' Reactor coolant pump / steam generator channel head air flow test o

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' Demonstrated IIS will not be affected by Control Rod Drive Mechanism (CRDM) electromagnetic interference Reactor vessel flow visualization o

No abnormal flow distribution I

Check Valve Mechanical Test o

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AP600 Testing Programs Key Tests for Design Certification o

Separate Effects Tests Automatic Depressurization Test - Phase B Core Makeup Tank Tests o

integral Tests OSU 1/4 Height Scaled Pressure Test SPES-2 Full-Height, Full-Pressure Test PCCS Large Scale Heat Transfer Tests

ADS Phase B Test o

Organization - ENEA o

Location - VAPORE Facility, Casaccia, Italy o

Key Features Separate effects test Full scale, prototypic hardware o

Purpose of Tests Evaluate valve performance Obtain piping load data o

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Location - Waltz Mill Site, Madison, PA o

Key Features Separata effects test at full pressure and temperature Simulated CMT (10 ft high x 2 ft diameter)

Simulated 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

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Purpose of Tests Provide T/H data for code verification at low pressure operation and during long term cooling o

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I Location - SPES Facility, Placenza, Italy o

o Key Features 1/395 volume scale, full pressure, full height facility 2250 psig, 600'F t

Full simulation of AP600 features Two cold legs / one hot leg per loop Two CMTs,'Two accumulators j

ADS simulation Two active steam generators Full height heated core

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

Steam line break Steam generator tube rupture Design basis with/without active systems to mitigate Beyond design basis events o

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J. C. BUTLER, PRINCIPAL ENGINEER ADVANCED PLANT SAFETY AND LICENSING u

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Interactive environment The current test program has benefited from comments and discussions with the NRC o

and Industry The test program schedule 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 o

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W/MRC Interface, Information Flow Steps taken to ensure that high quality information is provided in 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 Hold joint meetings with NRR, RES, ACRS staff and consultants o

to discuss test plans, analysis plans, instrumentation requirements, design and schedules Provide information in advance of meetings o

to obtain feedback and comments during the meetings and to allow for more meaningful discussion

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to keep the NRC apprised of progress and to assist in plans for test reviews, visits and witness points Minimize Proprietary claims on submitted Information o

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W/NRC Interlace, Information Flow AP600 Testing Program Review Meetings (December '92 - May '92)

OSU Tests, Detailed Review December 9,1992 SPES-2 Tests, Detailed Review December 10,1992 Testing Program Overview December 14,1992 CMT Tests, Detailed Review & Facility Visits February 25,1993 Test Program Review & Facility Visits March 9-10,1993 Containment Tests, Detailed Review & Facility Visits March 23-24,1993 ADS Tests Review and Facility Visit April 20,1993 SPES-2 Tests Review and Facility Visit April 22,1993 ADS Phase A Test Results Review May 4,1993 May 26-27,1993 ADS Tests, Detailed Review to 4

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