ML20069A376
| ML20069A376 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 05/06/1994 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20069A372 | List: |
| References | |
| NUDOCS 9405250122 | |
| Download: ML20069A376 (25) | |
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ltem . . . . . . . . -.. .. -.. . . . - . . . . . . . . . . . NTESTN No, - 2 TEST DESCRFTION ? J FACILITY LOCATION [ [ SCALE) cCATEGORY).. iSTATH PASSNE CONTAINMEPR COOLING SYSTEM TESTS IN SUPPORT OF AP600 DE'SIGNI- ' ~ 1 Air Flow Path Delta P Test W Science & Technology Center - Churchill, PA 1:6 linear Basic Research Compled 2 Water Film Forrnation Test W Science & Technology Center - Churchill, PA N/A Basic Research Completec 3 Heated Plate Test W Science & Technology Center - Churchill, PA MA Basic Research Completec 4 Bench Wind Tunnel Experiment W Science & Technology Center - Churchill, PA 1:120 linear Basic Research Completec 5 Condensation Tests - Bare surface upward University of Wisconsin - Madison, WI MA Basic Research Completec M 6 Condensation Tests - Bare surface downward University of Wisconsin - Madison, WI N/A Basic Research Complefd 7 Condensation Tests - Painted surf ace down University of Wisconsin - Madison, WI MA Basic Research Completed 8 Condensation Tests - Light noncondensbles University of Wisconsin - Madison, WI N/A Basic Research Completer 9 Condensation Tests - Stagnation Flow University of Wisconsin - Madison, WI N/A Basic Research Comploy Conditions i 10 Condensation Tests - Stagnatior61ight Uruversity of Wisconsin - Madison, WI N/A Basic Research Completh noncondensibles ' 11 Condensation Tests - 2D condensation University of Wisconsin - Madison, WI N/A Basic Research in Progk l PASSNE COPRAINMENT COOLING SYSTEM TESTS IN SUPPORT'OF AP600 DESIGN CERTIRCATION c p- 12 Integral (small scale) Tests - Phase 1 W Science & Technology Center - Churchill, PA 1:3 height Safety Related Complet% (Feasibility) 1:40 ; diameter i j 13 Integral (small scale) Tests - Phase 2A W Science & Technology Center - Churchill, PA 1:3 height Safety Related Compie (Extension Tests) 1:40 diameter l n 14 integral (small scale) Tests - Phase 2B W Science & Technolooy Center - Churchill, PA 1:3 height Safety Related Completek (Continuation Tests) 1:40 diameter
, 15 1/8th Scale Heat Transfer Test Phase 1 W Science & Technology Center - ChurchilI, PA -1:8 linear Safety Related Completec (Baseline) 16 1/8th Scale Heat Transfer Test - Phase 2 W Science & Technology Center - Churchill, PA -1:8 linear Safety Related Completec (Confirmatory) 4 17 Water Distnbutton System Test - Phase 1 (20ft W Waltz Mill Site - Madison, PA 1:1 Safety Related Complete <
Diameter) 18 Water Distribution System Test - Phase 2 (1/8th W Waltz Mill Site - Madison, PA 1:1 Safety Related Completec j Sector) 19 Water Distnbution System Test - Phase 3 (1/8th W Waltz Mill Site - Madison, PA 1:1 Safety Related Complete < sector with selected distribution system) re 20 Wind Tunnel Test - Phase 1 Univ, of Western Ontario - London, Ontario -1:100 linear Safety Related Completed 21 Wind Tunnel Test - Phase 2 Univ. of Westem Ontario - London Ontario -1:100 linear Safety Related Completek 22 Wind Tunnel Test - Phase 4 A CNRC Wind Tunnel - Ottawa, Canada 1:30 linear Safety Related Compk L 23 Wind Tunnel Test Phase 4B Un:v. of Western Ontano - London, Ontario 1:500 linear Safety Related Compte 1 1' l b. L
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e-i Westinghouse Elsetric Corporation I-AP600 DESIGN CERTIFICAT Revision 6, May 5,1994
'AP600 TEST PROGRAMS: ~ TABLE 1 W TEST PROGRAM OVERVIEW (PART 1) .
Nem . . STESTING J Noe TEST DESCRIPTION ' ' FACIUTY, LOCATION --
' . SCALE - iCATEGORY3 > STATUS PASSIVE CORE COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION x 24 PRHR Heat Exchangor Test Phase 1 W Science & Technology Center - Churchill, PA 1:1 height Safety Related Completed 25 PRHR Heat Exchanger Test - Phase 2 W Science & Technology Center Churchill, PA 1:1 height Safety Related Completed 26 Automatic Depressurization System Test- Phaso ENEA (VAPORE facildy) - Casaccia, Itaty 1:1 Safety Related Completed A (sparger) 27 Automatic Depressurization Systems Test - ENEA (VAPORE facility) . Casaccia, Italy 1:1 Safety Related Planned Phase B s 28 Core Makeup Tank Test -W Waltz Mill Site - Madison, PA -1:8 diamoter Safety Related in Progresi
~1:2 height 29 DNBR Tests Columbs University - Now York, NY 1:1 Safety Related Completd 30 Los Pressure 1/4 Height integral Systems Oregon State University . Corvallis, OR 1:4 height Safety Palated Planned Tests 1:192 volume
, 31 Full Pressure Full Height integral Gystems SIET (SPES-2 Facility) Piacenza, Italy 1:1 height Safety Related in Progres Tests 1:395 volume l; m I!' s> f (
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Wcstinghouse Electric Corporation novision s, may 5,1994 AP600 DESIGN CERTIFICA'] f' f AP600 TEST PROGRAMS: TABLE 2 - TEST PROGRAM OVERVIEW (PART 2) TEST SCHEDULE ttem No. TEST NAME Start End SCHEDULE PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN f 1 Air Fkiw Path Delta P Test January 1988 February 1988 Completed M'A
- t. 2 Water Film Formation Test February 1988 March 1988 Completed it'A g 3 Heated Plate Test April 1988 June 1988 Completed N/A w
- k. 4 Bench Wind Tunnel Expenment August 1988 September 1988 Completed M'A 5 Condensation Tests - Bare surface upward September 1988 December 1988 Completed N/A E
g 6 Condensation Tests - Bare surface downward September 1989 December 1999 Completed it'A 7 Condensation Tests - Painted surf ace downward September 1990 Decernber 1990 Completed M'A f 8 Condensation Tests - Light noncondensibles September 1991 December 1991 Completed N/A k 9 Condensation Tests - Stagnation flow conditions September 1992 March 1993 Completed M'A 10 Condensation Tests - StagnatsorVUght noncondensibles March 1993 July 1993 Completed N/A 11 Condonsation Tests - 2D Condensation January 1994 June 1994 In Proyess N/A { PASStVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION f 12 Intngral (small scale) Tests - Phase 1 (Feasibility) May 1989 October 1989 Completed M'A 13 Integral (small scale) Tests - Phase 2A (Extension Tests) January 1990 June 1990 Completed M'A p 14 Intogral (small scale) Tests - Phase 2B (Continuation Tests) June 1992 August 1992 Comploted N/A 15 1/8th Scale Heat Transfer Test - Phase 1 (Baseline) February 1992 June 1992 Completed N/A 16 1/8th Scale Heat Transfar Test - Phase 2 (Confirmatory) June 1993 September 1993 Completed N/A f 17 Water Distnbuton System Test - Phase 1 (20ft Diameter) June 1991 August 1991 Completed N/A l 4. 18 Wa;er Distnbution System Test - Phase 2 (1/8th Sector) September 1991 February 1992 Completed it'A y- 19 Water Distnbution System Tost - Phase 3 September 1993 September 1993 Completed M'A E s 20 Wind Tunnel Test Phase 1 June 1991 August 1991 Complotnd M'A 21 Wind Tunnni Test - Phase 2 February 1992 March 1992 Completed M'A g i 22 Wind Tunnel Tnst - Phase 4 A June 1993 August 1993 Completed N/A 23 Wind Tunnel Tost Phase 4B September 1993 September 1993 Completed M'A ] j PASStVE CORE COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION I $ l 24 PRHR Heat Erchanger Test - Phase 1 November 1989 January 1990 Completed MA 25 PRHR Heat Exchanger Test - Phase 2 July 1990 November 1990 Cornpleted M'A 26 Automatic Depressuraation Systam Test - Phase A (sparger) June 1992 November 1992 Compieted N/A { 27 Automatic Depressurinrtion Systems Test - Phase B July 1994 November 1994 Chart 1 Table 4 l [ 28 Core Makeup Tank Test February 1994 August 1994 Chart 1 Table 5 l 29 DNBR Tests June 1993 February 1994 Completed f1'A 30 Low Pressure 1s4 Height integral Systems Tests July 1994 February 1995 Chart 1 Table 6 i 1 31 Full Pressure Full Height integral Systems Tests February 1994 November 1994 Chart 1 Table 7 l
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Westinghouse Electric Corporation Revision 6,' May 5,1994 AP600 DESIGN CERTIFICA% f l AP600 TEST PROGRAMS: TABLE 3. TEST' PROGRAM OVERVIEW (PART 3)L r
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-{, No.1 TEST DESCRIPTION - MEETINGS ) Report - PASSIVE CONTAINMEPR COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN ! 1 Air Flow Path Deha P Test - N/A N/A N/A N/A 2 Water Film Formation Test - MA N/A N/A N/A 3 Heated Plate Test - N/A N/A N/A N/A ) 4 Bench Wind Tunnel Expenment N/A N/A N/A N/A l 5 Condensation Tests Bare surface tpward - Reference 5.3 N/A N/A MA 6 Condensation Tests - Bare surface downward - Reference 6.3 N/A N/A N/A i ., 7 Condensation Tests - Painted surf ace - WCAP-13307 N/A N/A N/A downward , 8 Condensation Tests - Light noncondensibles - Reference 8.2 N/A N/A N/A ] 9 Condensation Tests - Stagnation flow - Roference 9.2 MA N/A N/A conditions 10 Condensation Tests Stagnation / light - Reference 10.2 N/A N/A N/A noncondensibles 11 Condensation Tests . 2D condensation - 8/94 N/A N/A N/A PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION ' 12 Integral (small scale) Tests Phase 1 - WCAP-12667, MA MA Completed ) (Feasbihty) Rev1 1 13 Integral (small scale) Tests Phase 2A - Presentation N/A WCAP-13315 Completed r (Extension Tests) Mat 1 from
! 3/17/92 meeting L w/ NRC 14 Integral (small scale) Tests - Phase 29 -
Presentation N/A WCAP-13315 Completed (Continuation Tests) Mat 1 from
- j. 3/17/92 meeting w/ NRC l 15 1/8th Scale Heat Transfer Test Phase 1 -
WCAP-13566 WCAP-13246 WCAP 13267 Completed j (Baseline) j 16 1/8th Scale Heat Transfer Test - Phase 2 1 23-24/93 W Letter ET- WCAP-13246 WCAP-13267 Completed (Confirmatory) 2/23 24/94 NRC-93-3845 17 Water Distribution System Test - Phase 1 /20ft - WCAP-13290 N'A WCAP-13290 Completed l Diameter) j 18 Water Distnbution System Test - Phase F - WCAP-13290 MA WCAP-13290 Completed (1/8th Sector) 19 Water Distribution System Test - Phase 3 . WCAP 13816 N/A WCAP-13816 Completed I 20 Wind Tunnel Test - Phase 1 - WCAP-13294 WCAP-13294 WCAP-13318 Completed j 1 21 Wind Tunnel Test - Phase 2 - WCAP-13323 WCAP 13323 WCAP-13318 Completed WCAP-13294 22 Wind lunnel Test - Phase 4A . WCAP-13756 5/94 WCAP-13318 Completed I 23 Wind Tunnel Test Phase 4B . WCAP-14005 //94 WCAP 13318 Completed l l l J J f' l i
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- ~~ Westinghouse Electric Corporation nevision 6, May 5,1994 AP600 DESIGN CERTIFICA'l APG00 TEST PROGRAMS: TABLE 3 - TEST PROGR AM OVEFIVIEW (PART 3) item REVIEW Test Matrix Scaling Test Specification f No. Operating Pr f TEST DESCRIFrTION MEETINGS Report PASSIVE SAFETY SYSTEMS TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION * -FActLITY OPERAT f 24 PRHR Heat Exchangor Test - Phase 1 - WCAo-12666 N/A N/A Completed 1 25 PRHR Heat Exchanger Test - Phase 2 WCAP-12980 N/A WCAP-13368 Completed
- 26 Automate Depressurizaton System Test - 5'26-27/93 WCAP-13342 N/A WCAP-13342 Completed Phase A (Sparger) 27 Automatic Depressurization Systems Test - s'26-27/93 Table 4 N/A WCAP-13342 6/94 y Phase D 2/25/94 To be revised 6/94 28 Core Makeup Tank Test 2/25/93 Table 5 WCAP-13963 WCAP-13345, R2 Series 100 3(
3/14!94 To be revised 5/94 Series 400 5C g 29 DNBR Tests - KA N/A WCAP-12488 Completed 1 4 30 Low Pressure 1/4 Height Integral Systems 12/9/92 Table 6 5/94 WCAP 13234 4/94-6/94 Tests 9/20-21/93 l 31 Full Pressure Full Height integral Systems 12/10 S 2 Table 7 WC AP-13277 WCAP-14053 12/93 5/94 [ Tests [ l r I r i i f i 1 6 I 1 i { t
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220 Saturated Water from bottom of supply tank Stages 1 and 2 open, -1200 to 100 psig. Maximum flow resistance simulated. 12-inch gate vahre pos!tioned to obtain a range of two-phase T/H data. 230 Saturated Water from bottom of supply tank, Stages 1 and 3 open, ~500 to 50 psig. Maximum flow resistance simulated. 12-inch gate valve positioned to obtain a range of two-phase TM data _ 240 Satarated Water from bottom of supply tank, Stages 1,2 and 3 open, ~500 to 50 ps!g, Maximum flow resistance simulated.12-inch gate valve positioned to obtain a range of two-phase TM data. 250 Saturated Water from bottom of supply tank, Stage 2 open (inadvertent opening at full power), ~2235 psig, Maximum flow resestance simulated. 12-inch gate valve positioned to obtain a range of two@ase TM data. 310 Saturated water from bottom of supply tank, Stages 1,2 and 3 open, -500 to 50 psig, Guench tank water initially at 2127 Minimum flow resistance simulated. Maximum ficwfminimum quality for max foods on sparger and quench tank. 320 Saturated water from bottom of supply tank, Stages 1,2 and 3 open, ~500 to 50 psig, Quench tank water at ambient Mnimum flow resistance simulated. Maximum flowhnin! mum quality for max loads on sparger and quench tank. 330 Saturated water fem bottom of supply tank, Stages 1and 2 open,-1200 to 100 psig, Quench tank water initially at 2127, Mnimum flow resistance simulated. Maximum flow / minimum quailty for max loads on sparger and quench tank. 340 Saturated water frorn bottom of supply tank Stage 2 open, -2235 psig, Quench tank water initia!Iy at 212T, unimum flow resistance simulated. Maximum flow / minimum quality for max loads on sparger and quench tank. TABLE 5 - MATRIX TESTS, CORE MAKEUP TANK TEST
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i Westinghouse Electric Corporation Revlsion 6, May 5,1994 AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW TABLE 7 - MATRIX TESTS, FULL PRESSURE FULL HEIGHT INTEGRAL SYSTEMS TEST (SPES-2) TEST CATEGORY TEST NUMBER DESCRIPTION Cold Shakedown Tests C-01 Single phase flow through the pressurtrer suego line,4 flow rates C-02A.B Single phase flow through the pressurizer to core rnakeup tank balance lines,4 flow rates per balance line g C-03A.B Single pisse flow throug* the cold leg to core makeup tank balance lines,4 flow rates per balance fine - C-04A.B Core makeup tank. draindown using cold leg to core rnakeup tank balance line C-05A,B Core makeup tank gravity draindown using pressurizer to core makeup tank balance Rne C-06A,B Safety injection Accumulator blowdown C-07A,B I,wontainment refueling water storage tank gravity draindown, three water levels C-08 Chemical and Volume Control System. Normal Residual Heat Removal System and Startup Feedwater System pump flow rate verification C-09 Operation of primary system with 2 reactor coolant pumps running C-t 0A,B Operation of primary system with 1 reactor coolant pump running C-t 1 FacAity volume measurement Hot shakedown tests H-01 Facility heated and heat at five constant temperatures 4 02 Starting from nominal conditions, power will be shut off and steam generators isolated H-03 Facility operated at normal fu8 pressure, temperature and power-R04 Fecliity trans!tioned from fut power operating conditions to hot shutdown / natural circulation mode of operation H-05 Core makeup tank draindown using pressurtzer to core makeup tank balance line ! H-06 Low pressure, safety eystem actuation using the automatic depressurization system with core makeup tank draindown and accumulator delivery
' H-07 Fu!! power, fut pressure, safety system actuation initiated by the opening of the first stage of the automatic depressurization system Category 1 Matrix Tests 3 2-inch cold leg break with non-safety systems off 1 t-inch cold leg break with non-safety systems off f 4- 2-inch cold leg break with non-safety systems on
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Westinghouse Electric Corporation i nevision s, may s,1994 AP600 DESIGN CERTIFICAT r I i TADLE 8 TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE APG00 TEST PROGRAM RELATED MATERIALS THANSMITTED T
, DESCRIPTION I ; TEST PROGRAM GENERAL 0.1 Response to Novembar 14,1991 Requort for information Regarding AP600 Test Program i
I 0.2 Rosponse to January 15,1992 Request for information Regarding the AP600 Passive Containment Cookng System Tests 3 03 Responses to "AP600 Design issues to be Resolved by High-Pressure, Full-Heght Integral Tosting" 04 Presentation Material from February 25,1992 Westinghouse NRC Meeting on AP600 Testing 05 Response to November 14. 1991 Request for Additional Information Rogarding AP600 Test Program 06 Prosontation Matonal from March 3,1992 ACRS Meeting on AP600 Testing
- O7 Prosentation Matonal from June 1,1992, AP600 Meeting on Integral Systems Testing 08 Prosentation Matenal from June 23,1992 AP600 ACRS Testing Presontation 9
1 [ 09 F NRC Roquest for AdditionalInformation Regardirn the APC40 Testing Program 0.10 AP600 Testing to support Design Certification 9 0 0.11 AP600 Testing Schodule 6 0.12 Prosantation Matenal from Decomter 14,1992 Westinghouse NRC Moeting on AP600 Testmg 0.13 Westinghouse Response to NRC Request for Additional Information on the AP600 Testing Program dated July 21,1992 0 14 Updated Testing Schafules for the APC.00 Testing Program f 0 15 Westinghouso Response to NRC Roquest for Additional Informaton on the AP600 Testing Program dated September 1,1992 2 8 0.1 C Test Schedule for AP600 Automatic Inpressurization System Test - Phase B y 0.17 Presentation Material from the March 9-10,1993 Mooting on the AP600 Testing Program
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[ 0.18 Matonalin Support of March 23 24, 1993 WestinghouwNRC Moeting on Containment Tests for AP600 (Tost Spec additions, Test Matrix, Sch 0 19 Draft AP600 Test' Witness Mainx t
} O 20 Presontation Matorial from the March 23-24,1993 Meeting on the AP600 Containment Tost Pngram i 0 0 21 Updatod Testing Schedulos for the AP600 Testing Program 0 22 Background Materials in Preparation for the July 22-23 Moeting of ACRS Subcommrttee on T/H Phenomena 0 23 Presnotation Matonals from the Juno 18,1993 Mooting on the AP600 Testing Program f 0.24 AP600 Desgn and Design Cortification Test Program Overview, Revision 2 k
0 25 Gonoral Outline for Quick Look Data Roports on AP600 Tests 0 26 APG00 Desrjn and Design Certification Test Pngram Overview, Revision 3 1 0.27 Outhno for AP600 Code Vahdation Process Steps incorporating NRC Request for Single Bhnd Test Prnections l 0 28 Presnntation Materials from the Docemter 10,1993 Meeting on AP600 Test Program issuos 0 29 AP600 Desgn Cortification Test Program Overywrw Revision 4 j f 0 30 AP600 Desgn Certrf cation Program Schedule and Revision 5 of the AP600 Desgn Certification Test Program Overview I
; O 31 Addthonal Information in Suppori of Westirvpouse Response to RAI 952 48 on the AP600 Desgn l
L 0 32 Additonal Infoirr'ation in Support of Westinghouso Rosponse to RAI 952 43 on the AP600 Dnsgn [ 0 33 Additeoruil Information in Support of Westirghouso Rosponso to RAI 952 44-952 46 on the AP600 Desgn 0 34 , Ckmure of APbOO Testirn Program Issuns 1
BON TEST PROGRAM OVERVIEW hNRC) PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-NRC-91-3650, NPP-APSL-91-0286 12 16 91 Murley Yes ET-NRC-91-3656, NPP-APSL-92-0013 12292 Mudey Yes ET-NRC-92-3663, NS RA-APSL-92-0037 21492 Crutchfield Yes ET-N RC-92-3664, NSRA-APSL-92-0047 22492 Mudey No ET-NRC-92-3666, NSRA-APSL-92-0046 22492 Hasselberg u Yes ET-NRC-92-3671, NSRA-APSL-92-0053 3492 Mudey == Yes ET-NRC-92 3713, NSRA-APSL-92-0130 62592 Mudey Yes ET-N RC-92-3716, NSRA-APSL-92-0133 63092 Mudey Yes ET-NRC-92-3750, NSRA-APSL-92-0189 91492 Mudey No ET-NRC-92-3754, NSRA-APSL 92-0200 10592 Ward No ET-N RC-92-3768, NSRA-APSL-92-0239 11592 Mudey Yes ET-N RC-92-3783, NSRA-APSL-92-0264 12 14 92 Murley i No ET-NRC-93-3791 NSRA-APSL-93-0010 11993 Mudey j No ET-NRC-93-3800, NSRA-APSL-93-0011 11993 Mudey No ET-NRC-93-3798, NSRA-APSL-93-0009 11993 Murley j r l No ET-NRC-93-3811, NSRA-APSL-93-0026 2293 Borchardt j No ET-NRC-93-3834, NSRA-APSL-93-0065 3993 Borchardt I Mule) Yes ET-NRC-93-3841, NSRA APSL-93-0076 31693 Borchardt No ET-N RC-93-3848, NSRA-APSL-93-0093 32393 Borchardt Yen ET-N RC-93-384 5, NSRA-APSL-93-0090 32493 Borchardt No ET-NRC-93 3855, NSRA-APSL-93-0109 41393 Bvchardt No ET-N RC-93-3911, NSRA-APSL-93-0224 62893 Boehnert No ET-NRC-93-3910, NSRA-APSL-93-0223 62893 Borchardt No ET-N RC-93-3919 NSRA-APSL-93-0233 7793 Borchardt No ET-N RC-93-3946, NSRA-APSL-93-0305 81693 Borchardt No ET-NRC-93 3947, NSRA-APSL-93-0306 81893 Borchardt No ET-NRC-93-3976 NSRA-APSL-93-0360 92793 Borchardt p[\jQT;~[] Yes ET NRC-93-4029, NSRA-APSL-93-0492 12 16 93 Borchardt g p["4T(Jp E g No NTD-NRC-M 4078, DCP/NRC0017 38M Borchardt
) {ppp No NTD-NRC-94-4084 DCP/NRC0026 32894 Borchardt l f Yes NTD-NRC-94 4106, DCP/NRC0040 42594 Borchardt Yes NTD-NRC-94-4108, DCP/NRC0042 42994 Borehardt MSO /}VailliblQ 00
'VUi&Uid UGTd Yes NTD NRC-94-4114, DCP/NRC0048 42994 Borchardt No NTD-NRC-N-4117, DCP/NRC0051 5394 Crutchfield
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- AP600 DESIGN CE~RTIFICATION w TEST PROGRAM OVERVIEW
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ANSTEC APERTURE CARD hlSo Avsllable on Aperture Card TABLE OF CONTENTS Table 1 - Test Program Overview (Part 1) Table 2 - Test Program Overview (Part 2) Table 3 - Test Program Overview (Part 3) Table 4 - Test Matrix, Automatic Depressurization System Test, Phase B Table 5 - Test Matrix, Core Makeup Tank Test Table 6 - Test Matrix, Low Pressure 1/4 Height Integral Systems Test (OSU) Table 7 - Test Matrix, Full Pressure Full Height Integral Systems Test (SPES-2) Table 8 - Summary cf Westinghouse AP600 Test Program Related Materials Transmitted to NRC Table 9 - Summary of NRC Requests for Additional Information (RAI) Related to AP600 Tests and Analyses Chart 1 - Matrix Testing Schedules 940 5 250122 -b k
; Wcstinghouse Electric Corpor tion mvision 6, May 5,1994 APG00 DESIGN CERTIFICN[
t' AP600 TEST PROGRAMS: TABLE 1 - TEST PROGRAM OVERVIEW (PART 1) ttem TESTith No. TEST DESCRIPTION FAC.lJTY LOCATION SCALE CATEGORY STATU' PASSIVE Coff7AINMENT COOLING SYSTEM TESTS IN SUPPORT OF APGOO DESIGN 1 Air Flow Path Delta P Test W Science & Technology Center - Churchill, PA 1:6 linear Basic Research Complet 2 Water Film Formation Test W Science & Technology Center - Churchill, PA ffA Basic Rosearch Complete < 3 Heated Plate Test W Science & Technology Center - Churchill. P A f4'A Basic Research Complete < 4 Bench Wind Tunrel Experimont W Science & Technology Genter - CFarchill, PA 1:120 Irnear Basic Research Comploto< 7 5 Condensation Te.t - Bare surface upward University of Wisconsin Madison, WI ttA Basic Research Complete < l 6 g Condensation Tests - Bare surface downward University of Wisconsin - Madison, WI PWA Basic Research Completd 7 Condensaton Tests - Painted surface down University of Wisconsin - Madrcon, WI t#A Basic Research Completec e g 8 Condensation Tests Light noncondensibles University of Wisconsin - Madison, WI t&A Basic Research Complete < 9 Condensation Tests - Stagnation Flow University of Wisconsin - Madison, WI ffA Basic Research Comploy Conditions E 10 Condensation Tests - Stagnatiorvlight Unr<ersity of Wisconsin - Madison, WI N/A Bade Research Complep k noncordonsibles i 11 Condensation Tests 2D condensation Universitj of Wisconsin - Madison, WI P4A Basic Research in Progro' PASSIVE COffTAINMEffT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICAliON -j y 12 Integral (small scale) Tests - Phase 1 W Science & Technology Center - Churchill, PA 1:3 height Safety Related Corr pleted g (Foasibility) 1:40 !
& diameter 13 Intagial (small sca'e) Tests - Phase 2A W Science & Technology Center - Churchill, PA 1:3 height Safety Related Complete (Extension Tests) 1:40 diametor 7
14 Integral (small scale) Tests - Phase 2B W Science & Technology Center - Churchill, PA 1:3 height Safety Related Completa l (Continuation Tests) 1'40 s diametor 15 1/8th Scalo Heat Transfer Test - Phase 1 _WSaence & Technology Centor - Churchill, PA ~1:8 linear Safety Related Complete (Baseline) 16 1/8th Scale Heat Transfer Test - Phase 2 W Science & Technology Center - Churchill, PA ~1:8 linear Safety Related Complete (Conbrmatory) 17 Water Distnbution System Test - Phase 1 (20ft W Wat Mell Site - Madison, PA 1:1 Safety Related Complete i Diamator) 18 Water Oistnbanon System Test - Phase 2 (1/8th y/ Wa'tz Mill Srto - Madison. PA 1:1 Safety Related Completer l Secto , I 19 Water Distnbution System Test - Phase 3 (1/8th W Waltz M,11 Site - Madison, PA 1:1 Safety Related Complete sector with Wocted distributeon system) 20 Wind Tunnel Test - Phase 1 Univ. of Wostern Ontario - London, Ontario ~1:100 knear Safety Related Completa 21 Wird Tunnel Tmt - Phase 2 Univ. of Western Ontano - London. Ontario -1:100 knoar Safety Related Complete r- r Wind Tunnel Test - Phase 4 A CtJRC Wird Tunnel - Ottawa, Canada 1:30 knear Safety Related Complete 2.1 Wind Tunnel Test Phase 4B Univ of Western Ontano London. Ontario 1500 knear Safety Related Complete
w-* ' ION TEST PROGRAM OVERVIEW i ADDITIONAL INFORM ATION OBTAINED item TEST PURPOSE (Optional) No. Obtain pressure drop data through the downcomer and ann ius 1 Confirm wettability of coated steel surf ace 2 Confirm Passrve Containment Coohng System heat transfer capabikty [@yy -s, 3 Assess effects of wind on shield building design (inlet' outlet location) k p C D p , p y, 4 i w 5 i i* Ccmparison with past separate effects tests p 3 : , ,,, 5 Obtain hoat transfer coefficients with downward facing surfaces 6 Obtain the effect of AP600 paint on heat transfer performance / lm ft.,p , 3 7 Obtain the effect of Ight noncordensibles on heat transfer performance U J C .h ; p rl w 8 Obtain the heat transfer performance urrier stagnant flow conditions 9 OtAain the heat transfer performance under stagnant flow conditions in 10 the presence of light noncordonsibles Measure condensation beat transfer coefhcient using 2D test model Investgate effect of non-condensibles on heat transfer coefficient and 11 visualize flow field Determine feasibihty of water enhanced containment cooling system Investigate external coohng impact from air velocity, air humidity, 12 temperature and water filrn flow rates Demonstrate operation of Passive Containment Cooling System (PCS) Investgate effect of various annullus wdths and uniform steam 13 over increased range of operating conditions. Conbrm PCS intemal distrinutions. Obtain data on water film behavior on external surface and external heat transfer capabilities (wrth 1:1 scale coohrg air over long vertical heat transfer surf ace. annulus at controllrxl air tornperature & humdty) Demonstrate operation of Passive Containment Coohng System with 14 prototypic steam infecton Obtain heat transfer data for WGOTHlC computer code validation w:th 15 minimal intervals Obtain heat transfer data for WGOTHIC computer code vahdation investigate effect of non-condensibles on PCS heat removal capability 16 and intemal temperature distnbutions invest @ ate performance of passive containment coohng system center Assess containment water coverage at top of dome 17 water delivery /distnbution device Measure containment water coverago using distrubution system Obtain film thickness measurements 18 Measure containment water coverage using selected design distnbution Obtain film thickness measurements 19 system Investigate wind sensitnnty of shield building design Asess effects of srte structures on wir'd loading 20 Assess wind loads on containment baffle Compare wind effects w & w/o internal flow path 21 Verify Phase 1 & 2 test results at higher Reynolds numbers Confirm ba*fle tomado loads 22 investgate srte topography effects on air flow throught PCS annulus investgato effects of large structures on air flow throught PCS 23 annuius l 9405250122-0 -
I~ Westinghouse Electric Corporation
- Revision 6, May 5,1994 AP600 DESIGN CERTIFICAB l g. ,
f AP600 TEST PROGRAMS: TABLE 1. TEST PROGRAM OVERVIEW (PART 1) 5l item J
. . TESTINd r No. ' TEST DESCRIPTION '
FAClllTY 19 CATION ~ ' SCALE ~ : CATEGORY: ~ STATUS PASSIVE CORE COOLfHG SYSTEM TESTS IN SUPrORT OF AP600 DESIGN CERTIFICATION 24 PRHR Heat Exchangor Test - Phase 1 W Science & Technology Center - Churchill, PA 1:1 height safety Related Completd l e2 25 PRHR Heat Exchangar Test - Phase 2 W Science & Technology Center - Churchill, PA 1:1 height Safet) Pietated Completdk 26 Automatx: Deprew .srdation Systern Trut - Phase ENEA (VAPORE facility) - Casaccia, Italy 1:1 Safety Related Completh A (sparger) l 27 Automatic Depressuriz3 tion Systems Test . ENEA (VAPORE facility) . Casacch, Italy 1:1 Safety Related Planned Phase B l t 28 Core Makeup Tank Test W Waltz Mill Sne - Madison PA -1:8 diameter Safety Related in Progre
~1:2 height j 29 DNBR Tests Columbia University - New York, NY 1:1 Safety Related Oomple Jo Low Pressure 1/4 Height integral Systems Oregon State University . Cor* tes, OR 1:4 height Safety Related Planned Tests 1:192 s volume l
31 Full Pressure Full Feight integral Systems SIET (SPES-2 Facility) - Piacenza, Italy 1:1 height Safety Related in Progr Tests 1:395 l volume l. l.. o L _ l~ l i 1 i
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i ON TEST PROGRAM OVERVIEW ! i ADDITIONALINF ,tMATION OBTAINED ' ftem l
- TEST PURPOSE (optional) ' . Noi-N Determine therrnal performance of the PRHR beat exchanger tubes. Assess water mixing in the IRWST and the effects of mixing on heat 24 transfor rates and stearnirg.
I Expand the range of test conditions to more fully detine a PRHR heat Determine the impact of lower inital tank water level on steaming 25 transfer correlabon. Obtain sparger performance data, measure loads imposed on quench Obtain thermal hydraulic data for computer code validation 26 tank for use in confirming IRWST desgn Obtain therma' hydraulic data for computer code validation Piping, structure loads / responses with both 1$ and 24 flow 27 Obtain thermathydraulic data for computer code validation Confirm adequacy of CMT levet instrumentaten 28 Obtain DNB aata at low flow condd;ons Obtain data on fuel assembly flow mixing grds at design flow 29 conditions Obtain thermel-hydrautic data for computer code ve,tdation investigate long term cooling behavior 30 b Obtain thermal-hydraulic data for computer code validation investigate systems interactions during high pressure transients 31
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[~ ~~ ~ Westingirause Electric Corporation i nevision s, May 5,1994 AP600 DESIGN CERTIFICA% 1 AP600 TEST PROGRAMS: TABLE 2 -TEST PROGRAM OVERVIEW {PART 2) ) TEST SCHEDULE ~~ d No. TEST NAME Start End SCHEDULE I PASSfvE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF APCOO DESIGN 1 Air Flow Path Delta P Test January 1988 February 1988 Completed NA l
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2 Water Film Formation Test February 1988 March 1988 Completed N/A l l 3 Heated Plate Test April 1988 June 1988 Completed N'A l t_ 4 Bench Wind Tunnel Expentnent August 1988 September 1988 Completed N/A 5 Condensation Tests - Bare surface upward September 1988 December 1988 Completed MA 6 Condensation Tests - Bare surface downward Septernber 1989 December 1989 Completed WA 7 Condensation Tests - Painted surface downward September 1990 December 1990 Completed WA 1 [' 8 Condensation Tests - Light noncondensibles September 1991 December 1991 Completed N/A l 9 Condensaten Tests - Stagnahon flow conditions September 1992 March 1993 Completed MA f 10 Condensation Tests Stagnation / Light noncondensbles March 1993 July 1993 Completed N/A 11 Condonsat>on Tests - 2D Condensabon January 1994 June 1994 in Progress MA I PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION 12 Integral (smal! scale) Tests - Phase 1 (Feasibility) May 1989 October 1989 Completed N/A 13 Integral (small scalo) Tests - Phase 2A (Extension Tests) January 1990 June 1990 KA Completed j 14 Integral (small scale) Tests - Phase 2B (Continuation Tests) June 1992 August 1992 Completed NA ) 15 1/8th Scale Heat Trarsfer Test - Phase 1 (Baseline) February 1992 June 1992 Completed N/A 16 1/8th Scale Heat Transfer Test - Phase 2 (Confirmatory) June 1993 September 1993 Completed N/A I 17 Water Distnbution System Test - Phase 1 (20ft Diameter) June 1991 August 1991 Completed N/A 18 Water Distnbution System Test - Phase 2 (1/8th Sector) September 1991 February 1992 Completed WA ! 19 Water Distribution System Test - Phase 9 September 1993 September 1993 Completed N/A l k, 20 Wind Tunnel Test - Phase 1 June 1991 August 1991 Completed RA j 21 Wind Tunnel Test - Phase 2 February 1992 March 1992 Completed KA l 22 Wind Tunnel Test - Phase 4 A June 1993 August 1993 Completed N/A 23 Wind Tunnel Test Phase 4B September 1993 September 1993 Completed NA PASSIVE CORE COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION . s- 24 PRHR Heat Exchanger Test - Phase 1 November 1989 January 1990 Completed WA 25 PRHR Heat Exchanger Test - Phase 2 July 1990 November 1990 Completed N/A 26 Automatic Depressunzation Systern Test - Phase A (sparger) June 1992 November 1992 Completx! N/A a, 27 Automatic Depressuttration Sys,tems Test . Phase B July 1994 November 1994 Chart 1 Table 4 28 Core Makeup Tank Test February 1994 August 1994 Chart 1 Table 5 l 29 DNBR Tests June 1993 February 1994 Completed WA j 30 Low Pressure 1/4 Height integral Systems Tests July 1994 February 1995 Chart 1 Table 6 31 Full Pressure Full Height integral Systems Tests February 1994 November 1994 Chart 1 Table 7 ! l l 1 I t i r i 1
---- l ' ION TEST PROGRAM OVERVIEW NRC WITNESS OF KEY TESTS -
1 Rem- 1 dATE1X TEST NAMEMO. DESCRIPTION WEEK OF No. y f itA t#A N'A 1 f N'A PSA N'A 2 f N'A t4'A N'A 3 f itA PSA t4'A 4 ( t4'A t#A ttA 5 f N/A tea N/A 6 toA toA ttA 7 f itA ttA PCA 8 ttA t#A N'A 9 f f N'A ftA. ftA 10 ttA N/A PSA f 11 t. f N/A N/A ttA 12 f f4'A N'A t#A 13 f ttA N'A N'A 14 f4A PSA [iihj,Q"?" n t#A 15 f TEA t4'A l q @ (~-.' M *g _ . N!A 16 I PEA N/A (' 25 ; ,, ,2[ PNA 17 I l N/A PSA N'A 18 N'A P4'A /1,'S O fpj;,;4 .,,_. N/A 19 ; tGA t4'A '!DIlllTQ(Q,,.f ttA 20 t I [ N'A f4 A N'A 21 ! f P4 A PSA N/A 22 N-A PSA PCA 23 N'A l ttA N 'A 24 NA N/A ttA 25 NA ttA N'A 26 210 Saturated water blowdown from 2250 psig, maximum flow 9/7/94 27 resistance 403 Hot CMT draindown during depressurizatico 8.194 28 t4 A PCA PCA 29 S812 SBLOCA - DEG DVIline break 8/17,94 30 1 SBLOCA -iln. Cold Leg Break 57/94 31 11 Steam Generator Tube Rupture 11,t'94 9405250122 - k g .W Le*"Q
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Westinghouse Electric Corporation Revision G, May 5,1994 AP600 DESIGN CERTIFICAd i APG00 TEST PROGRAMS: TABLE 3 TEST PROGRAM OVERVIEW (PART 3) y d item . .
. REVIEW : . Test Matrix. Scaling Test Specification. Operating Prl No. TEST DESCRIPTION - MEETINGS - Report ~h r PASSIVE COfRAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN
[ 1 Air Flow Path Delta P Test - N/A N/A N/A N/A j l 2 Water Film Formation Test - N/A NA N/A N/A i j 3 Heated Plate Test - N/A N/A N/A N/A i 4 Bench Wind Tunnel Experiment - N'A N/A N/A NA 5 Condensabon Tests - Bare surface upward - Reference S.3 N/A N/A RA l' {. 6 Condensabon Tests - Bare surface dowrrward - Reference 6.3 MA N/A RA 7 Condensation Tests - Painted surface - WCAP-13307 N/A N/A MA downward I 8 Condensation Tests - Light noncondensibles - Reference 8.2 N/A N/A N/A
, 9 Condensation Tests - Stagnatx>n flow -
Reference 9.2 N/A JA N/A I cordtions 10 Conder.satx>n Tests - Stagnation / light - Reference 10.2 WA N/A WA noncondensibles 11 Condensation Tests - 2D condensation - 8/94 N/A N/A N/A PASSNE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF APG00 DESIGN CERTIFICATION 12 Integral (small scale) Tests - Phase 1 WCAP-12667, N/A N/A Completed (Feasibilty) Rev1 13 Integral (small scale) Tests - Phase 2A Presentation RA WCAP-13315 Completed (Extenson Tests) Mat 1 from 3/17/92 meeting w/ NRC 14 Integral (small scale) Tests - Phase 2B - Presentation N/A WCAP-13315 Completed (Continuation Tests) Mat 1 from 3/17/92 meeting w/ NRC 15 1/8th Scale Heat Transfer Test - Phase 1 - WCAP-13566 WCAP-13246 WCAP-13267 Completed (Baseline) IG 1/8th Scale Heat Transfer Test - Phase 2 1 23-24/93 W Letter ET- WCAP-13246 WCAP-13267 Completed (Conbrmatory) 2 @ 24 S 4 NRC-93-3845 17 Water Distribution System Test - Phase 1 (20ft - WCAP-13290 MA WCAP-13290 Completed Diameter) 18 Water Drstributx>n System Test - Phase 2 - WCAP-13290 KA WCAP 13290 Completed (1/8th Sector) 19 Water Distribution System Test - Phase 3 . WCAP-13816 RA WCAP-13816 Completed 20 Wind Tunnel Test - Phase 1 - WCAP-13294 WCAP-13294 WCAP-13318 Completed 21 Wind Tunnel Test - Phase 2 WCAP-13323 WCAP-13323 WCAP-13318 Completed WCAP-13294
! 22 Wind Tunnel Test - Phase 4A . WCAP-13756 S9t WCAP-13318 Completed 23 Wind Tunnel Test Phase 4B - WCA P-14005 7/24 WCAP-13318 Completed engs op
h f0N TEST PROGILG1 OVERVIEW , TEST DOCUMEIRS >cedures Facility Desctlption Report Oulck Look Final Test Report Other Relevant Information Reports item No.
* - FACILITY OPERAriNG PROCEDURES ARE MAlfRAINED IN WESTINGHOUSE FILES AND ARE AVAILABLE FOR REVIEW.
WCAP-13328 N/A WCAP-13328 WCAP-13330 1 WC AP-13884 f4 A WCAP-13884 WCAP-13330 2 WC AP-12665 ffA WCAP-12665 WCAP-13330, WC AP-13246 3 1 WCAP-14048 RA WCAP-14048 WOAP-13330 4 O Reference 5.3 rFA Rnfevence 5.3 WCAP-13246 5 f Roference 6 3 ft'A Reference 6.3 WCAP-13246 6 WCAP-13307 ffA WCAP-13307 WC AP-13246 .h. t 'l D l '.- '*d 7
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Referenco 8 2 M'A Referonce 8 2 , 7, r 3 8 Reference 9 2 PFA Rnference 9 2 9 Rolorence 10.2 Nono ## ' Roference 10.2 10 i DCilUiG CEid
& 94 None &D1 11
,1 l
WCAP 12667 Rev.1 frA WCAP-12667, Rov 1 WCAP 13330, WCAP-13246 12
&N None 8cG4 WCAP-13246 13 I
SN None ast WCAP-13246 14 I SN Nmo WCAP-15566 WCAP-13725, WCAP-13246 15 SN 11/93 S 94 8N WC AP-1356.6 16 WC A P-13292 None WCAP-13353 WC AP-13246 17 WC AP-13292 None WCAP-13296 WC AP-13246 18 WCAP 13292 None WCAP-13960 WCAP-13353, WC AP-13296 19 WCAP-13294 None WCAP-13294 WCAP-13246 20 1 WC AP-13323 None WC AP-13323 WCAP-13294, WCAP-13246 21 5% None 59% WC AP-13294, WCAP 13323 22 l
- 7. M Nono 7'94 WCAP-13294, WCAP 13323 23 I
/
I 9405250122-
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Westinghouse Electric Corporation l- Revision 6, May 5,1994 AP600 DESIGN CERTIFICA% AP600 TEST PROGRAMS: TABLE 3 - TEST PROGRAM OVERVIEW (PART 3)--
. item -[ HEVIEW ' Test Matrix . Scaling : Test Specification [ Operating Pe No. - TEST DESCRIPTION i 1 MEETINGS : Report q PASSIVE SAFETY SYSTEMS TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION L U *MACluTY OPE 24 PRHR Hoat Exchanger Test - Phase 1 -
WCAP 12666 M'A M'A Completed 25 PRHR Heat Exchanger Test Phase 2 - WCAP 12980 M'A WCAP 13368 Completed l
"( 26 Automatic Depressurization System Test - S'26-27/93 WCAP-13342 N/A WCAP 13342 Completed Phase A (Sparger)
> 1 1
27 Automatic Depressurization Systems Test - 5/26-27/93 Table 4 M'A WCAP-13342 6,94
, Phase B 2/25/94 To be revised 6.94 28 Core Makeup Tank Test 2/25/93 Table 5 WCAP-13963 WCAP 13345, R2 Series 100 30 3!14/94 To be revised 5194 Series 400 5d *4 29 DNBR Tests - N'A N/A WCAP-12488 Completed 30 Low Pressure 1/4 Height integral Systems 12/9/92 Table 6 5/94 WCAP 13234 494494 Tests 9f20 21/93 31 Full Pressure Full Height integral Systems 12/10.92 Table 7 WC AP-13277 WCAP 14053 12,93 5.94 Tests l
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TON TEST PROGRAM OVERVIEW TEST DOCUMERIS >oedures
- Facility Description Report Gutek Look Final Test Repori Other Relevant Information Reports item No.
NG PROCEDURES ARE MAINTAINED IN WESTINGHOUSE FILES AND ARE AVAILABLE FOfi REVIEW WCAP 1.^f46 N/A WCAP-12f46 24 WCAP 12980 ftA WCAP 12980 25 5/48 N/A 6'94 26 3/95 None 3/95 27 0 Complete 5/94 5/94-9/94 11/94 28 0 6/94 8/94 Nono a'94 29 6/94 8/94-4 95 6'95 30 5/94 5/94-12.94 3/95 31 ANSTEC APERTURE
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i 9' M i 1 West!nghouse Electric Corporation Revistort 6, May 5,1994 AP600 DESIGN AND DESIGN CERTIFICATION M OVERVIEW TEST P TABLE 4 - MATRIX TESTS, AUTOMATIC DEPRESSURIZATION TEST C ATEGORY SYSTEM TEST, PHASE B TEST NO. DESCRIPTION
" Category 2 Mate!x Tests 110
!I 120 Saturated Steam from top of suppy tank, Stage 1 open -2250 to 400 130 Saturated Steam fmm top of supply tank, Stages 1 and 2 open -800e tpeig, Abimum flow resistance s 140 Saturated Steam from top of supply tank, Stages 1 and 3 open -500 to 100 pe!g. Maximum flow resista Saturated Steam from top of suppir tank. Stages o 50 1,2psig.
and 3Ahlmum open flow resistance simulated. Obtain aa eingle phase TM d t 210 Saturated Water from bottom of supply tank. Stage 1 open -2250 t. -500 to 50 psig. Aktmum flow resista obtan a range of two-phase TM data. . o 400 psig. Maxiraum f:ow resistance simulated 220 124nch gate valve positioned to Saturated Water from bottom of supply tank, Stages 1 ano 2 open positioned to obtain a range of two-phase TM da'a. i 230 . -1200 to 100 ps:;, Akimum flow resistance simulated. 12-inch gate valve i Saturated Water from to obtain a range of tw&pt ase TM data. bottom of supply tank, Stages 1 and 3 open 240 . -500 to 50 psig, Maximum flow resistance simu!sted. 124nch gate valv Saturated Water from bottom of supply tank, Stages 1 2 and 3 op positioned to obtain a range of two-phase TM data. , en. -500 to 50 pstg. Maximum flow resistance simulated 250 .12-inch gate valvo Saturated Water from bottom of supply tank Stage 2 open (inad 310 inch gate va!ve positioned to otxain a range a a. of twophase TM d tvertent opening at fuit power), -2235 peJg. Maximu s ance simulated. 12-Saturated water from bottom of supply tank, Stages 1 2 and 3 open 320 simulated. Maximum flow / minimumn quench qualitytank. for mas loads on sparger a d. -500 to 50 psig, Quen k Saturated water from bottom of supply tank, Stages 1 2 and 3 open 330 simubted. Maximum flow / minimum quality for max loads on sparger and. -500 to 50 psig, Quench tan quenchtank. Saturated water from bottom of supply tank, Stages land 2 open 340 simulated. Maximum flow /rrdn! mum r andquality quench tank. for max loads on sparge, -1200 to 100 psig. Quench t Saturated water from bottom of supply tank, Stage 2 open ~2235 J Maximum flow / minimum quality for nch tank.rnax loads on sparger and quepsk . Quench e. tank water initially ag TABLE S - MATRIX TESTS, CORE MAKEUP TANK TEST M 7- --
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COMMENTS STEAM StJPot.Y PRESSURE S). PSIG [ CMT CRAIN RATE TEST NO. TEST TYPE TEST CMT mea 4y conta+ns r*o muer, and s evacuated (no aa). l f CATEGORY 1053 % 8519857235 wth subsequent j N A. CMT d-am rate based on i [- I Cawyyy 1 101 - t CS CMT wa4 steam condensa* ion ate ams &am capressurizaron f condeesaten ath CMT mea @ evacua ed and t"en pressuri:M w th air (or NJ to l Ma ex Tests r caceMty 10 l and wthout 236, L13 and 2.13 psia, respective). l }t 10&t 0B nonconcen s.bte
-*" eM ".q p-W O 9 ' ' ' ^ ?. f l gases C"%" ^ y r }
4464 ' f I SE " T* P :^r 1 I J CO t f CMT ictah 90*. aM 75"t full, CMT %st cont-oi used to l l 10N 35/1085'2235.mth subsequent j N-A - CMT levei hed. Water martam faed CMT Wel i CMT Wa5 and Water dapressuru adon f 201-200 dramed feom CMT ve exteraal path l CMT mosy 50% and 25% fJ. CMT %et coatrod essf to [ l
! Sur* ace Condensanon to match stea n condensation 10135'1085. with sutsequon- reacta:n fixed CMT leve!
[ I {i 209 2?4 depressurizanon i f Lew resstance stea n supo'y Me no,2 uta:ed; den rata i l h 10.135/1085 contro!!ed by d'scha"ge bne reestance r CMi dra:adown at 6/1 t/16h \ s. m , ( 301-312 constant pressure e -- ,,_ _ m n.
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- . 75 5.7 l %~% Low resstance steam supply lee no. 2 et'szwf; dram rate 4 1085 lN1omed by depressurizenon to 20. contro4d by discharge tre resistance.
\ Drscharge line resistance for 6/16 I i 401 402 CMT &a.ndown Category 2 gom Discha ge bee resistance set to p ovde 6Jt6 gom grady es.n f } during Matrm tests depressunzation 2235 fobowed by depressud aton to 20 rate at atmospheric pressure. Dram rete controked by steam j 403 404 supply hee no i res' stance Steam sapp!y hre no 1 s closed. Resentow water levet at Hi" j i 1085 fonowed by cepresaunraton to 20 level Reservoir water tampe ature enta1y 54TF. Staam Discharge !me resstance set for l 501-502 Natural cwcuteon suppty hne no. 2 4 opened to sruhate natwa! c:rculanon un*J fc8 owed by 616 gc.m dain rate Reservow wate kvel is reduced to one-fifth of CMT heared diendown and mwe dramdown. The steam suppiy is soiated and the depressurzahon wateesteam reservow is vented when the CMT ] is &ained to 97 inches A Repeat with natural c+retAation untd one half of CMT beated r 503-504 Repeat m+h ratural c rcutanon unta CMT s comp 4tefy hea ed. (Jt Repeat eth natu*a! cm.:ufaren unta one-tfth of CMT is beated 505 506 M _ 1835 fonowed by depressurzaban to 20 D<ain rate to be chosen based on Repeat with natural ciculaton unt4 one-half of CMT s bea%d. ._ CJt 507 NEW resuhs of tests 501-5C6 O 508 NEW Repeat w.tn natural circulaten unta CMT is corapleteiy bea*ed. j > 9 . . -, , a .~ ~ - . . . . .
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4 Westinghouse Electric Corporetton Rovision 6, May 5,1994 AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW TABLE 6 - MATRIX TESTS, LOW PRESSURE 1/4 HEIGHT INTEGRAL SYSTEMS TES T (OSU) TEST CATEGORY TEST N AME DESCRIPTION Cold P ooperational Tests C01 Core makeup tank graviy drain CO2 Accumulator tank drain C03 in<ontainment refueing wa+er storage tank dmin C04 Chemical and Volume Control System pump flow vs. pressure COS Normal residual heat removal system pump flow vs. pressure C06 Steam generator feed flow versus pressure C07 ADS 1-3 Une Flow Test Cos ADS 4 Line Flow Test C09 RNS Iniection Fiow Test Hoe Pre-Operational Tests HS01 Reactor Coolant Forced Circulatbn Loop Flow Test HS02 Reactor Coo'ent Natural Circuta'lon Loop Flow Test HS03 Reactor Power Calorimetric HSO4 Ambient Heat Loss Determination HSOS PRHR Loss Determination HS06 Steam Genemtor Performance Test HS07 Reactor Coolant System HeatuprCooldown Test Categoy 1 Ma'rix Tests SB1 2-ir.ch cold leg break, bottom of @, loop A with contmurition into long term cooling mode SB4 2-inch cold leg break, bottom of pipe, loop A SB10 Double-ended gui!!otine break of cold leg balance line, vertical loop, loop A with continuation into long term cooling SB12 Double 4nded guillotine break of direct vessel injection Ene SB13 2-inch break of direct vesset injection line
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s I ( l 1 I i Westinghouse Electric Corperation R: vision 6, May 5,1994 APG00 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW TABLE 7 - MATRIX TESTS, FULL PRESSURE FULL HEIGHT INTEGRAL SYSTEMS TEST (SPES-2) TEST CATEGORY TEST NUMDER DESCRIPTION Cold Shakedown Tests C 01 Single phase flow through the pressurizer surge line,4 flow rates C-02A.B Sbg!e phase flow through the pressurizer to core makeup tank balance lines,4 flow rates per balance ime C-03A,B Single phase flow through the cold leg to core makeup tank balance lines,4 flow rates per balance line C-04 A.B Core makeup tank draindown using cold leg to core raskeup tank balance line C-05A,8 Core makeup tank g avity draindown using pressurizer to core makeup tank balance line C G A.B Safety injection Accumu!ator blowdown C-07A.B Ina:ontainment refueling water storage tank gravity draindown, three water levels C-08 Che nical and Volume Control System, Normal Residual Heat Removal System and Startup Feedwate System pump ftew rate verincatsn C-09 Operation of primary system with 2 reactor coolant pumps running C-10A,8 Operation of p imary system with 1 reactor coolant pump running C-11 Facility volume measurement Hol shakedown tests H-01 Facility heated and heat at five constant temperatures H-02 Starting from nominal conditions, power will be shut off and steam generators isolated H-03 Facility operated at normal fut pressure, temperature and power H -04 Facility transitioned from full power operating conditions to hot shutdown / natural circulation mode of operation H-05 Core makeup tank draindown using pressurizer to core makeup tank balance line H-OG Low pressure, safety system actuation using the automatic depressurization systern with core makeup tank draindown and accumulator delive y H-07 Full power, full pressure, safety system actuation initiated by the opening of the first stage of the automatic depressurization system Category 1 Matrix Tests 3 2-inch cold leg break with non-safety systems off 1 1-inch cold leg break with non-safety systerns off 4 2-inch cold leg break with non-safety systems on S 24nch direct vessel injection Ene break w!th non-safety systems off
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Westinghouse Electric Corporation , 1 nevision o, May 5, w94 AP600 DESIGN CERTIFICA9 1 TABLE 8 -TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED M ATERIALS TRANSMITTED T
, DESCRIPTION TEST PROGRAM GENERAL 0.1 Response to November 14,1991 Rwauest for Information Rogarding AP600 Test Program I
i { 0.2 Response to January 15,1992 Request for information Regarding the AP600 Passive Containment Coohng System Tests t 0.3 Responses to "APf40 Design issues to be Resolved by H,gh-Pressure, Full-Height Integral Testing" I 0.4 Presentabon Material from February 25,1992 Westinghouse NRC Meeting on AP600 Testing 05 Response to November 14,1991 Request for Additional Informabon Regarding AP600 Test Program O6 Presentabon Material frorn March 3,1992 ACRS Meeting on AP600 Testing 0.7 Presentation Matenal from June 1,1992, AP600 Meeting on In'egral Systems Testing 0.8 Presentation Material from June 23,1992 AP600 ACRS Testing Presontation 0.9 NRC Request for AdditionalInformation Regarding the AP600 Testing Program 0.10 AP600 Testing to Support Design Certification 0 11 AP600 Testing Schedule 0.12 Presentation Material frorn December 14,1992 Westinghouse NRC Meeting on AP600 Testing f n 0.13 Westinghouse Response to NRC Request for Additionalinformation on the AP600 Testing Program dated July 21,1992 0.14 Updatcd Testing Schedules for the AP600 Tesbng Program W 0.15 Westinghouse Response to NRC Request for AdditionalInformation on the AP600 Testing Program dated September 1,1992 1 0 16 Test Schedulo for AP600 Automatic Depressurization System Test - Phase B 0 17 Presentation Material from the March 9-10,1993 Meeting on the AP600 Testing Program n 0.18 Materialin Support of March 23-24,1993 WestinghousecNRC Meeting on Containment Tests for AP600 (Test Spoc additions, Test Matrix, Sch 0.19 Draft AP600 TestWitness Matrix 0 20 Presentation Matonal from the March 23-24,1993 Meeting on the AP600 Containment Test Program 0.21 Updated Testing Schedules for the AP600 Testing Program I 022 Back0rcund Materials in Preparation for the July 22-23 Meeting of ACRS Subcommittee on T/H Phenomena k 0 23 Presentation Materials from the June 18,1993 Meeting on the AP600 Testing Program 0 24 AP600 Design and Design Certrication Test Program Overview, Revision 2 0.25 General Outline for Quick Look Data Reports on APG00 Tests y- 0 26 AP600 Desgn and Design Certification Test Program Overview, Revison 3 i_ 0.27 Outline for AP600 Code Validaten Process Steps incorporating NRC Request for Single Blind Test Predictions 0 28 Presentaton Materials from the December 10,1993 Meeting on AP600 Test Program Issues 0.29 AP600 Desgn Certificahon Test Program Overview. Revision 4 0.30 AP600 Desgn Certification Program Schedule and Revision 5 of the AP600 Design Certificaton Test Program Overview I 0 31 Aoditional Information in Support of Westinghouse Response to RAI 952 48 on the AP600 Desgn l 6 0 32 Addrtonal information in Support of Westinghouse Response to RAI 952.43 on the AP600 Desgn { 0 33 Add tonal Information in Support of Westinghouse Response to RAI 952 44 952 46 on the AP600 Design 0 34 Closure of AP600 Testing Program Issues I
QON TEST PROGRAM OVERVIEW $NRC) s
- =
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET NRC-91-3650, NPP-APSL 91-0286 12 16 91 Mudey Yes ET-N RC-91-3656, NPP-APSL-92-0013 12292 Mudey Yes ET-N RC-92-3663, NSRA-APSL-92 0037 21492 Crutchfield Yes ET-N RC-92-3664, NSRA-APSL-92 0047 22492 Mudey No ET-N RC-92-3666 NSRA-APSL-92-0046 22492 Hasselberg Yes ET-NRC-92 3671. NSRA-APSL-92 0053 3492 Mudey Yes ET-NRC-92-3713, NSRA-APSL-92-0130 62592 Mudey Yes ET-NRC-92-3716, NSRA-APSL-92-0133 63092 Mudey Yes ET-NRC-92-3750, NSRA-APSL-92-0189 91492 Mudey No ET-N RC-92-3754, NSRA-APSL-92-0200 10592 Ward No ET-NRC-92-3768, NSRA-APSL-92-0239 11592 Mudey = - Yes ET-N RC-92-3783, NSRA-APSL-92-0264 12 14 92 Mudey No ET-NRC-93-3799, NSRA-APSL-93-0010 11903 Murley No ET-N RC-93-3800, NSRA-APSL 93-0011 11993 Mudey No ET-N RC-93-3798, NSRA-APSL-93-0009 11993 Murley No ET-NRC-93-3811, NSRA-APSL-93-0026 2293 Borchardt No ET-NRC 93-3834, NSRA APSL-93-0065 3993 Borchardt 133ule) Yes ET.NRC-93-3341, NSRA-APSL 93-0076 31693 Borchardt No ET-N RC-93-3848, NSRA-APSL-93-0093 32393 Borchardt Yes ET-N RC-93-384 5, NSRA-APSL-93 0090 32493 Borchardt No ET-NRC-93-3855. NSRA-APSL-93-0109 41393 Borchardt No ET-N RC-93-3911, NSRA-APSL-93-0224 62893 Boehnert No ET-N RC-93-3910, NSRA-APSL-93-0223 62893 Borchardt No ET-NRC 93 3919 NSRA-APSL 93-0233 7793 Borchardt No ET NRC-93 3946, NSRA-APSL-93-0305 81693 Borchardt No ET-N RC-93-3947, NSRA-APSL 93-0306 81893 Borchardt No ET-N RC-93-3976,NSRA.APSL-93-0360 92793 Borchardt ET-NRC-934029, NSRA-APL 4 0492 AN9TEO Yes 12 16 93 Borchardt ((3F ATI IR p No NTD-NRC-94 4078, DCP/NRC0017 3894 Borchardt f /\ p No NTD-NRC N-4084, DCP/NRC0026 32894 Borchardt f Yes NTD-NRC-94 4106. DCPiNRC0040 42594 Borchardt MCO AEila' bl3 Of) Yes NTD-NRC-944108. DCP!NRC0042 42994 Borchardt
@UMIO UOICI Yes NTD-NRC-944114, DCPiNRC0048 42994 Borchardt No NTD-NRC 944117, DCP/NRC0051 5394 Crutchfield 9405250122 -
l} _
, p~~ ~ ~
L Westinghouse Electric Corporation nevision 6, May 5,1994 n . _.=-_.-- .. AP600 DESIGN CERTIFICA
.iABLE D TEST PROGRAM REFERENCES (
SUMMARY
SE AP600 TEST PROGRAM RELATED
= frTEDS f Air Flow Delta P Test -=.
1.1 l 1.2
. -WCAP-13328,"Tects of Air Flow for Coobrg the AP600 R eactor Containrnent, Rev. 0" 1.3 WCAP-13329, " Tests of Air Flow for Codirg the AP600 R eactor Containment, Rev. 0"
' 1.4 WCAP-13330, " Natural Convection Coohng of AP600 C -
ontainment, Rev. 0* WCAP-13331, " Natural Convection Coohng of APG00 C ontainment, Rev. 0"
- 2. ' Water Film Formation Test 2.1 WCAP-13330, " Natural Convection Coo 22 of AP600 Containment, Rev. 0" WCAP 13331, " Natural Convection Cool 23 of AP600 Containment, Rev. 0" WCAP-13834, " Water Film Formation on AP600 Re 6 24 actor Containment Surface", Revision 0 f WCAP.13885,
- Water Film Formation on AP600 Reactor
- 3. Heated Plate Test 3.1 -
WCAP 12665, " Test of Heat Transfer and Water Fil 32 _ { 3.3 WCAP-12665, " Tests of Heat Transfer and Water Film EmeEvaporation on a Heated _- 600 Reactor Containment" WCAP-13341, " Tests of Heat Transfer r vaporation and Watoon Fila Heated Plate Simulating Coohng of the AP600 R 3.4 eactor Containment, { { 35 $ WCAP-13330, " Natural Consection Cooling of AP600 Containment R eactor Containment, h 36 WCAP-13331, " Natural Convection Cooling of AP600 C l ontainment, Rev,0" 3.7 WCAP-13246, "Westirghouse-GOTHIC r { A Compute C d h WCAP-13412 " Westinghouse-GOTHIC: o e For Analyses of ThermalHydraulicr Transients fo N (. uclear Plant Containments & Ait f
- 4. Bench Wind Tunnel Experiment A Computer Code For Analyses of ThermalHydraulic Transie 4.1 n s or Nuclear Plant Containments & A 42 WCAP-13330. " Natural Convection Cooyt ol AP600 Containment, Rev. 0" 43 WCAP-13331, " Natural Convection Coohng of AP600 C ontainment, Rev. 0*
WCAP 14048, " Passive Containment Cooling Sy t
- 5. Condensation Tests - Bare Surface Upward s em Bench Scale Wind Tunrol Test" 51 WCAP 13246, " Westinghouse-GOTHIC:
67 WCAP-13412. "Westirghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydrau
.3 5.4 References for Basic Resecrch Tests on CondensatiA Computer Code For A JJ Barry, " Effects of Interiacial Structure on Performed in Support of the AP600 Designnsients for N
- 6. Condensation Tests Bare rSurface Downwa don Film Condensation," PhD Thesis (1987) 6.1 WCAP- 13246, " Westinghouse-GOTHIC:
6.2
. WCAP-13412. ' Westinghouse-GOTHIC: A Computer Code For Analysea of Tharmal Hydra
[ 6.3 Referencec for Basic Research Tests on Corriens tA Computer Code For Ana a ion Performed n s for Nuclear Plant Containments & A in Support of the AP600 Design
- 7. Condensation Tests - Pointed 7.1 ard Surface Downw 72 WCAP-13307, " Condensation In the Presence Of A N l
! 73
' CAP.13308. "Condensaton in the Presence Of A Nooncondensable Gas Expenmentalinvestigation
( WCAP-13412, "Westrghouse-GOTHIC: ncondensable Gas - Expenmental Investigation" 7.4 WCAP-13246 " Westinghouse-GOTHIC: A ComputA Cornputer Code For Analy ~ er Code For Analyses of Thermal Hydraulic Transients for uclear Plant Containments & A
~~w:p b
i JON TEST PROGRAM OVERVIEW .. f ADDRESSEE _ _m
-. ~ l DATE b
) NRC) m--,. TRANSMITTAL LETTER p:. - .c PROPRIETARY Mudey l 43092 ET-NRC-92-3688, NSRA APSL 92-00M Mudey f Yes 43092 I ET-NRC-92-3688, NSRA-APSL 92-0094 Mudey No 43092 f ET NRC-92-3688, NSRA-APSL-92-0094 l Mudey Yes 43092 ET NRC-92-3688, NSRA APSL 92-0094 .- No Mudey 43092 ET-NRC 92-3688, NSRA-APSL-92-0094 Murley
- Yes 43092 I ET-NRC-92-3688, NSRA-APSL 92 0094 Borchardt No 2294 f RC0002
, NTD-NRC-94-4056 DCP/N Borchardt ,
Yes 2294 j No NTD-NRC-94-4056, DCP/NRC0002 J d Donatell 7 't 6 90 APERTURr: ' l NS-NRC-90-3525, NPAP-APSL-90-0048 Mudey Yes 43092 A CARD ET-NRC-92-3688, NSRA- APSL-92-00M 43092 Mudey Yes lov. t' , ET-NRC-92-3688, NSRA-APSL-92-0094 Mudey 43092 No 9O I lev. O' ,
-% y ET-NRC-92-3688, NSRA-APSL-92-00M Mudey Yes .-
43092 ET-NRC-92-3688, NSRA APSL-92-0094 Mudey f
-_ No 73192 ET-NRC-92-3726 j Muriey ]
Yes ,73192 viliary Buildirgs" ET NRC-92-3726
, No dliary Buildirgs" Murley .. f 43092 ET NRC-92-3688, NMA-APSL-92 0094 Mudoy
__ Yes 43092
! ET-NRC-92-3688, NSRA-APSL 92-0094 ; Borchardt 42994 No j DCP/NRC0050 J No l NTD-NRC-944116, __
Mudey 73192 ET-NRC-92-3726 Murley Yes 73192
<iliary Buddirgs" ET-NRC 92-3726 Borchardt No 81693 xiliary Buildirgs" !
ET-NRC-93-3945, NSRA- APSL-93-0304 Borchardt No j 816 93 NSRA-APSL-93-0304 N No j ET-NRC-93 3945, 73192 Mudey f
}}
fYes ET-NRC-92-3726 73192 Mudey ] dliary Buildirgs" ET NRC-92-3726 Borchardt No j 81693 xiliary Buildirgs- l ET NRC-93-3945, NSRA-APSL-93 0304 ] j No Morley 43092 ET NRC-92-3688, NSRA-APSL-92-00M Yes ET-NRC 92-3G88, NSRA-APSL-92-0094
' 43092 Mudey Murley No 73192 No
, ET-NRC-92 3726 73 92 Mudey J diiary Buildirgs" jYes j ET-NRC-92-3726 '
I
~
~ Bu,,d rys-9405250122_ j
~~ ~
Westinghouse Electric Corporation nevision s, May 5,1994 AP600 DESIGN CERTIFICA1
? .
i TABLE 8 TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP000 TEST PROGRAM RELATED MATERIALS TRANSMITTED
, DESCRIPTION ; 8. Condwnstion Tests Light Noncondensibles l 31 Referencos for Basic Research Tests on Condensation Performed in Support of the AP600 Design 82 A. P. Pemsteiner, " Condensation in the Presence of Noncondensblo Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thd 8.3 i K Huhtiniemi, "Cordensation in the Presence of Noncondensble Gas: The Effect of Surface Onentation," Prelim Thesis (1990) 84 1. K. Huhtiniemi,"Condonsabon in the Prosnnce of Noncondonsble Gas: The Effect of Surface Oristation," Prelim Thesis (1990)
- 9. Condensation Tests - Stagnatlon Flow Conditions )
T 91 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design 4 9.2 A P. Pornsteiner " Condensation in the Presence of Noncondensbie Gas: Effet of Helium Concentration," 1993 University of Wisconsin The
- 10. Condensation Tests - Stagnatford.lght Noncondensit>las 10.1 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design 10.2 A. P. Pernsteiner, " Condensation in the Presence of Noncondensble Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thh
- 11. Condensation Tests - 2D Condensation 11.1 References for Basic Research Tosts on Condensation Performed in Support of the AP600 Design j 12. Integral (small scale) Tests - Phase 1 (Feestb411ty) 12 1 WCAP 12667, " Test of Heat Transfer and Water Film Evaporatx>n From a Simulated Containment Tc Jemonstrate the AP600 Pas l
J 12.2 WCAP-13330, " Natural Convoction Cooling of APG00 Containment, Rev. 0" 12.3 WCAP-13331, " Natural Convection Cooling of AP600 Containment. Rev, 0" 12.4 WCAP-13340, " Tests of Heat Transfer and Water Film Evaporation from a Pimulated Containment to Demonstrate the AP600 Passive Contai 1 12.5 WCAP-12667," Tests of Heat Transfor and Water Film Evaporation from a Simulated Containment to Demonstrate the AP600 Passive Contas 12 6 WCAP-13412. " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Contain
! 12.7 WCAP-13246, " Westinghouse-GOTHIC: A Computer Code For Ana!yses of Thermal Hydraulic Transients for Nuclear Plant Containments &
5
- 13. Integral (small scale) Tests Phase 2A (Extension Tests) 13.1 WC AP 13316, "Intogral Containmont Cooling Test Extension - Test Specification, Rev 0" 13 2 WCAP-13315 " Integral Containmont Cooling Test Extension - Test Specificanon Rov,0" I 13 3 WCAP-13412 "Westeryl ouso-GOTHIC A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & k 13 4 WCAP-13246. " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal HydrauSc Transients for Nuclear Plant Containments & A g 14. Integral (small scale) Tests Phase 2 (Continuation Tests) 14 1 WCAP 13315, " Integral Containrnent Coohng Test Extension - Test Specification, Rev. 0" 1
14 2 WC AP-13316, " Integral Containment Cooling Tect Extension Test Specification, Rev. 0" I WC AP-13246, " Westinghouse GOlH!C: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & k g 14 3 14 4 WCAPA3412. "WestinghouseGCTHIC: A Computer Code For Analyses of Therrnal Hydrauhc Transients for Nuclear Plant Containments & k I i a t i I u__
? ION TEST PROGRAM OVERVIEW F3 NRC)
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE No ET-N RC-93-3945, NSRA-APSL-93-0304 81693 Borchardt 312 No ET-N RC-93-4014 NSRA-APSL-93-M48 11 12 93 Borchardt No ET-N RC-93-3MS, NSRA-APSL-93-0304 81693 Borchardt Yes , ET-N RC-93-394 5, NSRA-APSL-93-0304 81693 Borchardt No ET-N RC-93-3945, NSRA-APSL-93-0304 81693 Borchardt gis No ET-NRC-934014, NSRA-APSL-93-0448 11 12 93 Borchardt No ET-N RC-93-394 5, NSRA-APSL-93-0304 81693 Borchardt sis No ET-N RC-93-4014, NS RA-APSL-93-0448 11 12 93 Borchardt No ET-N RC 93-3945, NSRA-APSL 93-0304 81693 Borchardt riment Cooling System" Yes NS-NRC-90-3525, NPAP APSL-90-0048 71690 Donatell Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-NRC 92-3688, NSRA-APSL-92-0094 43092 Murley I No ET-N RC-92-3688, NSRA-APSL-924041 43092 pment Cookrg System, Rev 0" Murley ment Coolirg System, Rev.1" Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley uxiliary Buildings" No ET-N RC-92-3726 73192 Murley uxiliary Buddings" Yes ET-NRC 92-3726 73192 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley uxiliary Buildings" No ET-N RC-92-3726 73192 Murley uxiliary Buddmas" Yes ET-NRC-92 3726 73192 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-NRC-92 3688, NS RA- APSL-92-0094 43092 Murley bxiliary Buildnyp" Yes ET-N RC-92-3726 73192 Murley uxil4ary Buddusp" No ET-N RC-92-3726 73192 Murley I //g<!1N ' C Oi,
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Westinghouse Electric Corporation nevision o, may 5,1994 AP600 DESIGN CERTIFICA'I i r~- l l TABLE 8 - TEST PROGRAM REFERENCES (
SUMMARY
OF WESTlHGHOUSE APG00 TEST PROGRAM RELATED MATERIALS T F , j DESCRIPTION { {15.1/8th Scale Heat Trent.for Tests Phase 1 (Baseline) 15.1 WCAP.13267, " Test Specif#caton: Large Scale Passive Containment Cooling Test, Rev.1" t l 15.2 WCAP 132G3, " Test Specificaton" Large Scale Passive Containment Cooling Test, Rev.1" i __ 15.3 WCAP-13246, " Westinghouse-GOTHIC: A Computer Code For Analyses of Thormal Hydraulic Transients for Nuclear Plant Containments & A. 15.4 WCAP-13412 " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & A. 15.5 WCAP-13566, "APCOO 1/8th Large Scale Passrve Containment Cooling Systom Heat Transfer Test Baseline Data Report," Rev. O, j- 15 6 WCAP 13567, "AP6001/8th Large Scale Passive Containment Cooling System Heat Transfer Test Baseline Data Report," Rev. O k 16.1/8th Scsie Heat Transfer Test - Phase 2 (Confirmatory) 16.1 WCAP-13267, " Test Spncification: Large Scale Passive Containment Cooling Test, Rev 1" i j 16.2 WCAP.13268, " Test Specification" Large Scale Passrve Containment Cooling Test, Rev.1" 16 3 Phase 2 Largo Scale Test Matrix Rationale; Infortrution in Support of Request for Additional Information on the AP600 Design (RAI 480.12) ( I 16 4 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Constant Pressure Tests (Tests 202.3 and 203.3) 1 16 5 Facility "as-built" Drawings for AP600 PCCS Large Scale Test Facility f 16.6 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Tests 212.1 and 213.1 \ 16.7 Heat Sink Data for AP600 PCCS Large Scale Phase 2 Test Facildy j 16 8 Proposed initial Conditions Data and Forcing Functions for Large Scale Phase 2 Test 720.1 ! 16.9 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Tests 214.1 and 215.1 , 16 10 Quick Look Data Rmort for AP600 PCCS Large Scale Phase 2 Tects: Tests 217.1 and 218.1 I i 16 11 Test Desenpton Package for AP600 PCCS Larga Scale Phase 2 Test. Test 220.1 16.12 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 216.1 l l 16 13 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 219.1 16 14 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 221.1 16.15 Presentation Matenals from the February 23-24,1994 Meeting on AP600 PCCS Tests and Anafysis 16.16 Presentation Mater:ab from the March 17,1994 Meeting on AP600 Passive Containment Cooling System Design Basis Analyses l 16 17 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 222.1 16 18 Westinghouse AP600 Letter Report, " Radiation Heat Transfer Through Fog in the PCCS Air Gap" 1619 Westinghouse AP600 Letter Report, " Liquid Film Model Validation" l 16.20 Ouick Look Data R9 ort for AP600 PCCS Large Scale Phase 2 Tests: Tests 222 2,222.3, 222.4 l l l l l l GW mea . e
' ION TEST PROGRAM OVERVIEW O NRC) PROPRIETARY TRANSMITTAL LE1TER DATE ADDRESSEE Yes ET-N RC-92-3688, NSRA-APSL 92-0094 43092 Murley No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley rxdiary Buildirgs' Yes ET-NRC-92 3726 73192 Murley ixiliary Buildirgs" No ET-N RC-92-3726 73192 Murley Yes ET-N RC-93-3801, NSRA- APSL-93-0012 12593 Murley No ET-N RC-93-3801, NSRA-APSL-93-0012 12593 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA APSL-92-0094 43092 Murley Yes ET-NRC-93 3961 NSRA-APSL-93-0334 92393 Borchanft Yes ET-NRC-93-3981, NSRA-APSL-93-0380 10493 Borchardt Yes ET-N RC-93-3983, NSRA-APSL-93-0381 10693 Borchardt Yes ET NRC-93-3991, NSRA-APSL-03-03M 10 15 93 Borchardt Yes ET-NRC-93 3997, NSRA-APSL-93-0405 10 21 93 Borchardt No ET-N RC-93-3998 NSRA-APSL-93-0406 10 22 93 Borchardt Y es ET-NRC-93 4006, NSRA- APSL-93-0421 10 29 93 Borchardt Yes ET-N RC-934012, NSRA-APSL-93-0446 11 12 93 Borchardt Yes ET-N RC-934030, NSRA-APSL-93-0495 12 20 93 Borchardt Yes ET-N RC-94-4035, NSRA-APSL-94 0002 11894 Borchardt Yes NTD-NRC-M4053, SAUNRC0037 12894 Borchardt Yes NTD-NRC-94-4062, DCP/NRC0004 21194 Borchardt Yes NTD-NRC-N 4067, DCP/NRC0009 22394 Borchardt Yes NTD-NRC-94 4083, DCP/NRC0023 32194 Borchardt Yes NTD NRC-944090, DCP/NRC0028 4494 Borchardt Yes NTD-NRC-94-4100, DCP/NRC0035 41894 Borchardt Yes NTD-NRC-M-4100, DCP/NRC0035 [ 41894 Borchardt Yes NTD-NRC-94-4121, DCP/NRC0054 54M f Borchardt \ ANSTEC APERTURE CARD Aten Ava!labb Cl1 ' ! Aperture Caid 9405250122 - [)Oj
i 1 - _~ Westinghouse Electric Corporation t nevision a, May s,1994 AP600 DESIGN CERTIFICA I f { TADLE 8 TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED T 1 DESCRIPTIOff ' 1
- 17. Water Distribution System Test . Phase 1 (20ft Diameter) R 17.1 WCAP-13353, " Passive Containment Cooling System Water Distribution Phase 1 Test Data Report, Rev. 0" 17.2 WCAP-13354," Passive Containment Cooling System Water Distribution Phase 1 Test Data Report, Rev. 0" 17.3 WCAP-13291, " Passive Containment Cooling System Water Distrbution Test, Rev. 0" 17.4 WCAP-13290, " Passive Containment Cooling System Water Distribution Test, Rev. 0" 17.5 WCAP-13293. " Construct >orvTest Plan For the Passive Containment Cooling System Test Articles, Rev. 0" 17 6 WCAP-13292, " Construction / Test Plan For the Passive Containment Cooling System Test Articles, Rev. 0" 17.7 WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & AE 17.8 WCAP-13246, " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Ad
- 18. Water Distribution System Test . Phase 2 (1!8th Sector) :l 18.1 WCAP 13291, " Passive Containment Cooling System Water Distribution Tent, Rev. 0" 18.2 WCAP 13297,"PCS Water Distrbution Test Phase il Test Data Report" 18.3 WCAP-13296. "PCS Water Distribution Test Phase 11 Test Data Report" 184 WCAP-13290, " Pass've Containment Cooling System Water Distribution Test, Rev. 0" 18.5 WCAP 13293, "Constr sctiorvTest Plan For the Passive Containment Cooling System Test Articles, Rev. 0" 18 6 WCAP-13292, "ConstrutiorVTest Plan For the Passive Containment Cooling System Test Articles, Rev,0" 18.7 WCAP-13246,"Westingt ouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Ai.
10.8 WCAP-13412,"Westinghcuse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Aq
- 19. Water Distribution System Test Phase 3 19 1 WCAP-13292, " Construction / Test Plan For the Passive Containment Cooling System Test Articles, Rev. 0" !
19.2 WCAP-13293, "ConstructiorvTest Plan For the Passive Containment Coohng System Test Articles, Rev. 0" 19.3 WCAP 13816. " Phase 3 Passrve Containment Cooling System Water Distribution Test" 19 4 WCAP-13817, Phase 3 Passive Containment Cooling System Water Distribution Test" 19.5 WCAP-13960, "PCS Water Jistribution Phase 3 Test Data Report," Revision 0 f 19.6 WCAP-13961,"PCS Water Distrbution Phase 3 Test Data Report" Revision 0 l l 20. Wind runnel Test. Phase 1 ~ 20.1 WCAP-13294,
- Phase i Wind Tunnel Testing For the Westinghouse AP600 Reactor" l 20.2 WCAP-13295. " Phase I Wind Tunnel Testing For the Westinghouse AP600 Reactor" I 20 3 WCAP 13318 " Passive Containment Cooling System Wind Tunnel Test Specification, Rev. 0"
! \ 20 4 WCAP-13412 " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & A 20 5 WCAP-13246. " Westinghouse GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Ak f 1
, i I
! l l i
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ION TEST PROGRAM OVERVIEW 3 NRC) - PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-N RC-92-3688, NSRA-APSL 92-00M 43092 Mudey No ET-NRC-92 3688, NSRA-APSL 92-0094 43092 Mudey No ET-NRC-92 3688, NS RA- APSL-92-00M 43092 Murley Yes ET-NRC-92 3688, NSRA-APSL-92 00M 43092 Mudoy No ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley ; Yes ET-N RC-92-3688, NSRA-APSL-92 0094 43092 Murley xilirry Buildirgs' No ET-N RC-92-3726 73192 Murley diary Budirgs' Yes ET NRC-92-3726 73192 Mudey 1 No ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL 92-00M 43092 Murley Yes ET-N RC-92-3688 NSRA-APSL-92-00M 43092 Murley No ET-N RC-92-3688. NS RA- APSL-92-0094 43092 Mudey Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley xiliary Buridings" Yes ET-N RC-92-3726 73192 Murley dory Buildirgs" No ET-N RC-92-3726 73192 Mudey Yes ET-W RC-92-3688, NS RA-APSL-92-0094 43092 Mudey No ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Mudoy Yes ET-N RC-93 -3952, NS RA-APSL-93-0318 81993 Borchardt No ET-N RC-93-3952, NSRA-APSL 93-0318 81993 Borchardt Yos NTD NRC-94-4056, DCP/NRC0002 22N Borchardt No NTD NRC M4056, DCP/NRC0002 2294 Borchardt Yes ET-N RC-92-3688, NSRA APSL-92-00M 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET NRC-92-3688 NSRA-APSL-92-0094 43092 Mudey nihary Buddirgs" No ET NRC-92-3726 73192 Murley .iliary Buildmgs" Yes ,,, < ET-N RC-92-3726 73192 Murley j.K +
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Wcstinghouse Electric Corporation i nevision s, May 5,1994 AP600 DESIGN CERTIFICA'I i i TADLE B - TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTND 1
,. DESCRIPTION
( 21. Wind Tunrol Test Phase 2 21.1 WCAP 13318,
- Passive Containment Coohng System Wind Tunnel Test Specifcaton, Rev. 0" ,
21.2 WCAP-13412, " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containmen 21.3 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & & 21.4 WCA P-13323, Rev. O, " Phase II Wind Tunnel Testing for the Westinghouse AP600 Reactor" 21.5 WCAP-13J24, Rev,0, " Phase ll Wind Tunnel Testing for the Westinghouse AP600 Reactor" F 22. Wind Tunnel Test - Phase 4A 22.1 WCAP 13318, " Passive Containment Cooling System Wind Tunnel Test Specificaton, Rev. 0" 22 2 WCAP-13757, " Wind Tunnel Phase 4A Test Plan, Investigation of the Hgh Reynolds Number Behavior of the Westinghouse AP600 System," , j 22.3 WCAP-13756," Wind Tunnel Phase 4A Test Plan, investigation of the Hgh Reynolds Number Behavior of the Westinghouse AP600 System,"
- 23. Wind Tunnel Test a Phase 4B 23.1 WCAP-13318, " Passive Containment Coohng System Wind Tunnel Test Specifcation, Rev. 0" l 23 2 WCAP-14005," Wind Tunnel Phase 4B Test Plan, Investigation of the Effects of Siting on the Wir,d Behavior of the Westinghouse AP600 Sysk 23.3 WCAP-14006," Wind Tunnel Phase 4B Test Plan, Investigation of the Effects of Siting on the Wind Behavior of the Westinghouse AP600 Sysd 24, PRHR Heat Exchanger Test - Phase 1 24 1 WCAP 12666,"AP600 Passive Residual Heat Removal Heat Exchanger Test Test Report" l
- 25, PRHR Heat Exchanger Test - Phase 2 25 1 WCAP-13368," Passive RHR Heat Exchanger Test Extension, Rev. 0"
{ 25.2 r WCAP-13369, " Pass've RHR Heat Exchanger Test Extension, Rev. 0" 25.3 WCAP-13573,"AP600 Passive Residual Heat Exchanger Test Final Report" l ""~~ 25.4 WCAP-12980, Rev.1, "AP600 Passive Residual Heat Exchanger Test Final Report" {
- 26. Automatic Depressurtration System Test Phase A (Sparger)-
1 1 i 26.1 WCAP 13343, "AP600 Automatic Depresurization System Test, Rev. 0" i L j i 26 2 WCAP 13342,"AP600 Automatic Depressurization System Test, Rev 0" R l 26.3 Presentation Matenal from the April 20,1993 Meeting on the AP600 ADS Tests at the VAPORE Facility I' 26.4 l Presentation Matenal from the May 4,1993 Meeting to discuss the AP600 ADS Phase A Test Results 26 5 Presentation Matorials from the May 26-27,1993 Meeting on the AP600 ADS Tests T f i
' ION TEST PROGRAM OVERVIEW O NRC) l PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE No ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley
- x$ary Buildir gs' No ET-N RC-92-3726 73192 Murley ixil;ary Buildirgs' Yes ET-N RC-92-3726 73192 Murley Yes ET-N RC-92-3753, NS RA- APSL-92-0198 10292 Murley No ET-N RC-92-3753, NSRA-APSL-92-0198 10292 Murley No ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Murley No ET-N RC-93-3926, NSRA-APSL-93-0250 71593 Borchardt Yes ET-NRC-93-392G, NSRA-APSL-93-0250 71593 Borchardt No ET-NRC-92-3G88, NSRA-APSL-92-0094 43092 Murley m' Yos NTD-N RC-944082, DCP/NRC0020 32194 Borchardt im" No NTD-NRC-944082, DCP/NRC0020 32194 Borchardt Yes NS-NRC-90 3525, NPAP APSL-90-0048 71690 Donatell Yes ET-NRC-92-3730, NS RA- APSL-92-0161 8792 Murley No ET-N RC-92-3730, NSRA-APSL-92-0161 8792 Murley No ET-N RC-92-3779, NSRA-APSL-92-0259 12 15 92 Murley Yes ET-N RC-92-3779, NSRA-APSL-92-0259 12 15 92 Murley No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Murley Yes ET-N RC- 93-3877, NSRA-APSL-93-0159 5393 Borchardt Yes ET-N RC-93 -3879, NSRA APSL-93-0106 5593 Borchardt Yes ET-N RC-93-3881, NSRA-APSL-93-0197 6193 Borchardt
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9405250122~
We:tinghouse Electric Corporation , nevision c, May s,1994 AP600 DESIGN CERTIFICAT i TABLE 8 -TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATER DESCRIPTION
- 27. Automatic Depressurization System Test . Phase B~
27.1 WCAP 13343, "AP600 Autornatic Depresurization System Test, Rev. 0" ] i 1 27.2 WCAP-13342, "AP600 Automatic Depressurization System Test, Rev 0" l 27.3 Presentation Material from the April 20,1993 Meeting on the AP600 ADS Tests at the VAPORE Facility l 27.4 AP600 Automatic Depressurization System Phase B Test Matrix, Revision 1 I 27.5 Preliminary Facility Design Drawings for the AP600 ADS Phase B Tests ] 27.6 Presentation Materials from the May 26 27,1993 Meeting on the AP60 ) ADS Tests j 27.7 AP600 Automatic Depressurization System Phase B Test Matrix, Revisioi 1A , 27.8 Presentation Materiab from the January 25,1994 Meeting on AP600 ADS Design Certification Test Plans f 27.9 Additional Information in Support of Westinghouse Response to RAI 952.64 on the AP600 Design l
- 28. Core Makeup TarA Test j 28.1 WCAP-13345, "AP600 Core Make-Up Tank Test Specification, Rev. 0" i.
28.2 Materialin Support of February 25,1993 Westinghouse /NRC Meeting on CMT Tests for AP600 (Test Matrix, instrument List, Drawings) ; I 28.3 Presentation Matenal from the February 25,1993 Westinghouse /NRC meeting on the AP600 CMT Tests
]
i 28.4 Transmittal of Drawing of Steam Distributer for AP600 Core Makeup Tank Test 28 5 Draft Scaling Analysis for the AP600 Core Makeup Tank Separate Effects Tests 28.6 WCAP-13345, "AP600 Core Makeup Tank Test Specification", Revision 2 28.7 WCAP-13963, " Scaling Logic for the Core Makeup Tank Test," Revision 0 28.8 WCAP-13975, " Scaling Logic for the Core Makeup Tank Test," Revision 0 I 28.9 Responee to Requests for Additional information on the AP600 Core Makeup Tank Tests l { 28,10 1
- Presentation Materials from the March 14,1994 Meeting on AP600 Core Makeup Tank Tests and Analysis ;
- 29. DNBR Tests
! 29.1 WCAP-12488, " Westinghouse Fuel Criteria Evaluation Process" ) 29.2 Test Matrix for AP600 Departure from Nucleate Boiling Tests l l r t t l l l f I I i. r
= %.
ION TEST PROGRAM OVERVIEW NRC) PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE No ET-NRC-92 3688, NS RA- APSL-92-0094 43092 Murley Yes ET-N RC-92-3688 NSRA-APSL-92-00M 43092 Murley Yes ET-N RC-93-3877, NSRA-APSL-93-0159 5393 Borchardt Yes ET-NRC-93 3885, NSRA-APSL-93-0171 51193 Borchardt Yes ET-N RC-93-3893, NSRA-APSL 93-0189 52493 Borchardt Yes ET-N RC-93-3881, NSRA APSL-93-0197 61 93 Borchardt Yes ET-N RC-93-3881, NSRA-APSL-93-0197 6193 Borchardt Yes NTD NRC 94-4050, NSRA- APSL 94-0030 12594 Borchardt Yes NTD-NRC.944109, DCP/NRC0043 42994 Borchardt No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-93-3823, NS RA- APSL-93-0042 21893 Borchardt Yes ET-N RC-93-3829, NSRA /,PSL 93-0053 22593 Borchardt Yes ET-NRC-93 3944, NS RA- APSL-93-0303 81693 Borchardt Yes ET-NRC 93-4031, NS RA- APSL-93-0497 12 20 93 Borchardt No NTD-NRC-M-4068, DCP/NRC0010 22294 Borchardt Yes NTD-N RC-944068, DCP/NRC0010 22294 Borchardt No NTD-NRCM4068, DCP/NRC0010 22294 Borchardt No NTD-NRC-M4076, DCP/NRC0015 3494 Borchardt Yes NTD-NRC-944081 32194 Borchardt Yes NS-NRC-90-3482 4290 Wilson Yes ET-N RC-93 -3984, NSRA-APSL 93-0385 10893 Borchardt j 's
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Westinghouse Electric Corporation Revision 6, May 5,1994 AP600 DESIGN CERTIFICAT p- ____ {, TABLE 8 - TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED T DESCRIPTION
- 30. Low Pressuna 1/4 Height integral Systems Tests 30.1 Scaling Report on Glass Model of the AP600
?;, WCAP 13234,"AP600 Long Term Cooling Test Fpecification, Rev. O
~
v N ; WCAP-13283, "AP600 Long Term Cooling Test Specifmation, Rev. 0" I h , Draft Scaling Analysis for the OSU AP600 Integral Systems Test 30.5 Materialin Support of Westinghouse /NRC Mooting on OSU Test Program for AP600 (Test Schedule, Draft Scahng Report, Tew yecification F Matnx and Facdity Design Drawings) I 30 6 s Presentation Matenal frorn December 9-10,1992 WestinghousaNRC Moetngs on AP600 Test Program
\
30 7 Component and Pping Drawing for the AP600 Long Term Cooling Tests I 30.8 WCAP-13283 Revtsion 1. "Long Terrn Cooling Test," 30.0 WCAP 13234 Revison 1. "Long Terrn Cooling Test," l l i [ 30 10 Response to INEL Requests for information regarding OSU Long Term Cooling Test Facility (Requests dated April 14,1993 and May 12,1993 i 30.11 RELAPS/ MOD 3 input Filo Notebook for OSU/AP600 Components 30.12 Draft Scaling Analysis for the OSU AP600 Integral Syste e and Long Term Cooling Test Facihty f 30.13 Facihty Drawings and Piping and Instrumontation Diagrams for the AP600 Long Term Cooling Test Facility at Oregon State University 30.14 Presentation Matenals from the September 20,195G Meeting on AP600 Low Pressure Integral Systms Tests at Oregon State University 30.15 Information on Test Conditions for AP600 Testing Performed at the SPES-2 and OSU Test Facilities
- 31. Full Pressure Full Height integral Systems Tests 31.1 WCAP-13277," Scaling Design and Venfication of SPES-2, the Italian Experimental Facility Simulator of the AP600 Plant" 31.2 WCAP-13278," Scaling Dosegn and W,nfication of SPES-2, the Italian Experimental Facility Simulator of the AP600 Plant" l 31.3 NRC Request for Additional Infornution Related to SPES-2 Test Faci!rty
} ,
i 31.4 Matenalin Support of Westinghouse /NRC Meeting on SPES Test Program for AP60v (Test Schedule Draft Scaling Report, Draft Test Sp-7 31.5 Preseja Material from December 9-10,1992 WestinghousaNRC Meetings on AP600 Test Program 31.6 Oomponent and Piping Drawings for the SPES-2 Facihty 31.7 P sentation Matenai from the Apnl 22,1993 Meeting on the AP600 Intayal Systems Tests at SPES-2 Facility 31 8 WC AP-13278 Revtsion 1,
- Scaling. Design, and Venfication of SPES-2, The Italian Experimental of the AP600; Scaling Update" 31.9 WCAP-13277 Revision 1, " Scaling. Design, and Verification of SPES-2, The Italian Experimental of the AP600; Scaling Update" 31.10 SPES-1 Pump Characterization, SIET NT/54 31.11 Rmponse to INEL Request for SDES-2 InformatiorvClanficaton MGO-29-93 31.12 SPFS-1 System Desenption, SIET NT/32 31.13 Informaton on Test Condfions for AP600 Testing Pedormed at the SPES-2 and OSU Test Facilities 31.14 WC AP-14053, Revision 0, "AP603 FHFP integral Systems Test Specification" 31.15 WCAP-14056. Revision 0, "AP600 FHFP Integral Systems Test Specification" l
l l l no men
a. [ON TEST PROGRAM OVERVIEW ; 80tCj$ ' PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE No NPAP-APSL-910095 3591 Sheron .{ Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-NRC-92-3715, NSRA-APSL-92-0132 7792 Murley port, Updated instrumentation Ust, Test Yes ET-N RC-92-3775, NSRA-APSL-02-0250 11 24 92 Murley l I Yes ET-N RC-92-3785, NSRA-APSI.-92-0268 12 17 92 - Murley f I Yes ET-N RC-93-3830, NSRA-APSL-93-0062 3393 Borchardt j No ET-NRC-93 3883, NSRA-APSL-93-0169 51193 Borchardt Yes ET-NRC-93 3883, NSRA-APSL-93-0169 51193 Borchardt ! Yes ET-N RC-93-3901, NSRA-APSL-93-206 61093 Borchardt l Yes ET-N RC-93-3932, NSRA-APSL-93-0273 72793 Wilson Yes ET-NRC-93-3933, NSRA-APSL-93-0974 72893 Wilson Yes ET-NRC-93-3969, NSRA-APSL-93-0350 91793 Borchardt Yes ET-NRC-93-3993, NSRA-APSL-93-0401 10 15 93 Borchardt ; Yes NTD-NRC-94-4070 DCP/NRC0012 33194 Borchardt Yes ET-N RC-92-3685, NSRA-APSL-92 0082 4392 Murley No ET-N RC-92-3685, NSRA-APSL-92-0082 4392 Murley ; I Yes ET-N RC-924749, NSRA-APSL-92-0188 91492 Murley ! tion) Yes ET-N RC-92-3776 NSRA-APSL-92-0251 11 24 92 Murley l l Yes A T-NHC-92-3785 NSRA-APSL-92-0268 12 17 92 Murley Yes ~. ' 93d25, NSRA-APSL-93-0046 22393 Borchardt Yes t;r .Nd0-93-3877, NSRA-APSL-93-0159 5393 Borchardt j l __ _._,m.. .. No ET-N RC-93-3883, NSRA-APSL-93-0169 51193 Borchardt j U # Yes ET-N RC-93-3883, NSRA-APSL-93-0169 51193 Borchardt [@ 5 ki i I 3 d D - No ET-N RC-93-3943, NSRA-APSL-93-0300 81293 Borchardt i NN No ET-NRC-93-3943, NSRA-APSL-93-0300 81293 Borchardt e 1 {. . No ET-NRC-93-3943, NS RA-APSL-93-0300 81293 {
?a, Borchardt j
,e o, m u .-.-1-h s
mi A00rtur0 Card Yes NTD-NRC-94 4070 DCP/NRC0012 33194 Borchardt l Yes NTD-NRC-944122 DCP!NRC0055 5494 Borchardt No NTD-NRC-94 4122, DCP/NRC0055 54 94 Borchardt 4 i 9405250122 - i
. - ~
Westinghouse Electric Corporation i nevision 6, May 5,1994 AP600 DESIGN CERTIFICAT TABLE B - TE'.iT PROGRAM REFERENCES (
SUMMARY
OF WESTlHGHOUSE AP600 TEST PROGRAM RELATED MATERIALS THANSMTTTEDY DESCRIPTION
- 32. Other Tests 32.1 WCAP-12668,"AP600 High inertia Rotor Testirg - Phase I, Test Report"
( 32.2 WCAP-13299 "RCP Air Model Test Report, Rev. 0* 32.3 WCAP-12648, "AP600 incore instrumentation System Electromagnetic Interference Test Report, Rev.1" 32 4 WCAP-13352, " Studies of Hydraulic Phenomena in the Reactor Vessel Lower Plenurn Region Test Report, Rev. 0" 32 5 WCAP-13305, Studies of Hydrau!ic Phenomena In Reactor Lower Plenum Region - Test Plan" r 32.6 WCAP 13298, "RCP Air Model Test Report, Rev,0"
>- 32.7 WCAP-13322. "AP600 Incore Instrumentation System Electromagnetic Interference Test Report, Rev. O*
32.8 WCAP-13312. " Journal Beanng Test - Task 2 Test Specifcation"
; 32 9 WCAP-13313, " Journal Bearing Test - Task Plan For the DOE Phase il Hgh inertia Rotor Test Program" 32.10 WCAP-13320 "AP600 Hgh Inertia Rotor Testirg Phase 2 Report, Rev. 0" I
32.11 WCAP-12668,"AP600 Hgh inertia Rotor Testing Phase 1 Test Report, Rev.1"
'i 32.12 WC AP-13319. "AP600 Hgh Inertia P.otor Testing Phase 2 Rnport, Rev. 0" 32,13 WCAP-13288, " Passive Core Cooling System Check Vane Test Specrbcation, Rev. 0" 32.14 WCAP-13284, ' Test Plan For the Passive Core Cooling System Check Valve Test, Rev. 0"
[' 32.15 WCAP-13314. " Journal Bearing Test - Task Plan For the DOE Phase 11 High inertia Rotor Test Program" 32.16 WCAP-13287,"AP600 Passive Core Cooling System Check Valve Test Final Report, Rev. 0"
. 32.17 WCAP-13285 " Test Plan For the Passive Core Cochng System Check Vane Test, Rev. 0" 32.18 WCAP-13321 "AP600 Hgh Inertia Rotor Testmg Phase 1 Report, Rev. 0" 32.19 WCAP 13286, "AP600 Passive Core Cooling System Chock Valve Test Final Report, Rev. 0" l 32 20 WCAP-13289, " Passive Core Cooling System Check Valve Test Specification, Rev. 0" i ]
7 32.21 WCAP-13310, "Joumal Bearing Test - Task 1 Test specification" 3222 WCAP-13351, " Studies of Hydraulic Phenomena in the Reactor Vessel Lower Plenum Region - Test Report, Rev. 0" 32 23 WCAP-13306, " Studies of Hydrauhe Phenomena in Reactor Vessel Lower Plenum Region - Test Plan" 32.24 WCAP-13309, " Journal Bearing Test - Task 1 To:,t Specification" d 32 25 WC AP-13487, Rev. O, "Hgh inertia Rotor Phase 3. Task 1 Test Report" 7 32 26 WCAP-13488, "Hgh inertia Rotor Phase 3, Task i Test Report" , H
! 32.27 WCAP 13560. " Advanced Plant Check Vatve Study" Rev. 0 3228 WCAP-13743," Heavy Water Reactor Faciley Project Phase 1 AP600 Small Scale Passive Containment Cooling System Test ' Dry' Test Resh 91-0021" '
32 29 WCAP-13742," Heavy Water Reactor Facihty Prcsect Phase 1 AP600 Small Scale Passive Containment Coohng System Test ' Dry' Test Resh j 91 0C21" l 32.30 WCAP-13726. " Heavy Water Reactor Facihty (HWRF) Largo Scale Passive Containment Coohng System Basehne Test Data Report HWRF-9 32.31 WCAP-13728, " Heavy Water Reactor Facihty (HWRF) Small Scale Containment Cooli ng System Test Final Report HWRF-RPT-92-003, Revd I 32.32 WCAP-13733, "Hoavy Water Reactor Facihty (HWRF) Srnall Scale Containment Cooling Test Preliminary Series 2 Test Results HWRF-RPT-k f 32.33 WCAP 13725 " Heavy Water Reactor Facility (HWRF) Large Scale Passive Containmeut Coohrg System Basehne Test Data Report HWRF-F,d [ 32 34 WCAP 13727, "Hm ,y Water Reactor Facihty (HWRF) Small Scalc Containment Cooling System Test Final Report HWRF-RPT-92-003 Revisk 4
~ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _
ad.-e.-W- [ON TEST PROGRAM OVERVIEW i NRC) PROPRIETARY TRANSMITTAL LLTTER DATh ADDRESUJ -- Yes NS-N RC-90-3525. NPAP-APSL-90-0048 71690 Donatell No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688 NSRA-APSL-92-0094 43092 Murley Ye, ET-N RC-92-3683 NSRA-APSL-92-0094 43092 Murley Yes ET-NRC-92-367, NSRA-APSL-92 0094 43092 Murley No ET-N RC-92-3688, NS RA- APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-NRC 92 3688, NSRA APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley l Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET NRC-92-3688, NSRA-APSL-92-00M 43092 Murley
/\ *,1 C l ' ;- No ET-N PC-92-3688, NSRA-APSL-92-0094 43092 Murley r- ,
~
Is G l,-[ "f '; i E No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley 3 3 - .
, p , j ', .
No ET-NRC-92-3GS8, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92 0094 43092 Murley
@,0./WNhuiC 011 Yes ET-NRC-92-3688, NSRA-APSL-92 0094 43092 Murley fi,9OiluiO UUllI No ET-NRC-92 3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NS RA-APS: 0094 43092 Murley Yes ET-NRC-92 3688 NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-NRC-92-36S8, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92 -3753, NSRA-APSL-92-0193 10292 Murley No ET-N RC-92-3753, NSRA-APSL-92-0198 10292 Murley No ET-N RC-93-3801, NSRA-APSL 93-0012 12593 Murley A PPli cable to the HWRF Proret NPR RPT- No ET-N RC-93-3903, NS RA-APSL-93 -0208 61493 Borchardt Applicabio to the HWRF Propct NPR RPT- Yes ET-N RC-93-3903, NSRA-APSL 93-0208 61493 Borchardt 604," Rom on 1 No ET NRC-93-3903, NSRA-APSL-93-0208 61493 Borchardt 1 No ET-NRC-93-3903. NSRA-APSL-93-0208 61493 Borchardt XJ1 No ET-N RC-93-3903, NSRA. APSL-93-0208 61493 Borcha-dt 492 004," Revison 1 Yes ET-NRC 93-3903, NSRA-APSL-93-0208 61493 Borchardt i1 Yes ET NRC-93-3903, NSRA-APSL-93 0208 61493 Dorchardt 9405250122 . . ,. ,
1
-i'.n Westinghouse Electric Corporation ,
M Revision 6, May 5,1994 AP600 DESIGN CERTIFICA%
~
, [ TABLE 8 iTEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE ape 00 TEST PROGRAM RELATED MATERIALS TRNNSMITTED ( DESCRIPTION l 32.35 WCAP 13732 " Heavy Water Reactor Facility (HWRF) Small Scale Containment Cooling Test Preliminary Series 2 Test Results HWRF-RPT d 32.30 WCAP-13758,"High Inertia Rotor Test Phase 3 Report," Jane,1993 l
~
32.37 WCAP-13759,"Hgh inertia Rotor Test Phase 3 Report," June,1993 1 32.38 WCAP-13415, "High inertia Rotor Test 3 Task 1, Test Speedicaton," 32.39 WCAP-13413. "RCP Hydraulic Flow Test Prospectus," 32.40 WCAP-13420, "High Inertia Rotor Test Phase 3 Test Plan," P- 32.41 WCAP-13419. "High inertia Rotor Test Phase 3 Test Plan,"
< 32.42 WCAP-13414 "RCP Hydraulic Flow Test Prospectus "
r, 32.43 M. H. Kim,"Modelling of Condensation Heat Transfer in a Reactor Containment," PhD Thesis (1985) j 1
}, 32 44 WCAP-14045,"In Situ Check Valve Test Report (Fall Outage '93)"
3 p.
.o a.
if l i i 1 [- J l t i-1 i i l l l 4 l l 4 I
*** sw aw 1
r ' ION TE-ST PROGRAM OVERVIEW O NRC)~'- PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE [ 2-001 Yes ET-NRC-93-3903. NS RA-APSL-93-0208 61493 Borchardt f l Yes ET-N RC-93-3918, NSRA APSL 93-0238 7793 Borchardt No ET-NRC-93-3918, NS RA-APSL-93-0238 7793 Borchardt No ET-N RC-93-3926, NSRA-APSL-93-0250 71593 Borchardt
- Yes ET-NRC-93 3926 NS RA-APSL-93-0250 71593 Borchardt +
No ET-N RC-93-3926, NSRA-APSL-93-0250 71593 Borchardt , Yes ET-N RC-93-3926, NSRA-APSL 93-0250 71593 Borchardt No ET-N RC-93-3926, NSRA-APSL 93-0250 71593 Borchardt { No ET-N RC-93 0945, NSRA-APSL-93-0304 81693 Borchardt No NTD-NRC-94-4120, DCP/NRC0053 5494 Borchardt ANSTEC APERTURE CARD Also Avanabia on Aperture Card 9405250122~[ _ _
1
, - - --- , 'c-- - - - ~-
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.t-Westinghouse Electric Corporation Revision 6. May 5,1994 AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 9 - Summary of NRC Requests for Additional Information (RAI) Related to AP600 Tests and Analysis RAI No. Description / Issue NRC Ltr. Westinghouse Response West. Response Date Letter No. Letter Date 440.001 SPES test, check valve testing & PRHR testing 09/23S2 ET-NRC-92-3777 11/3092 440.001R01 SPES test, check valve testing & PRIIR testing // //
440.002 ChfT testing 09/2362 ET-NRC-93-3795 01/14/93 440lX)2R01 Ch1T testing 09/23S2 NTD-NRC-94-4087 03/2484 440.003 Ch1T testing 09/23S2 ET-NRC-93-3804 Ol/22S3 440.004 Ch1T testing 09/23 S 2 ET-NRC-92-3777 11/30/92 440.004R01 Ch1T test i ng 09/23S2 NTD-NRC-94-4087 03/24 S 4 440.005 CMT testing 09/23S2 ET-NRC-92-3777 11/30S 2 440.005R01 Ch1T testing 09/23S2 NTD-NRC-94-4087 03/24/94 440.006 Chit testing 09/23 S 2 ET-NRC-92-3777 11/30S 2 440.006R01 CMT testing // NTD-NRC-94-4087 03/24/94 440.007 CMT testing 09/23 S 2 ET-NRC-92-3777 11/30/92 440.008 CMT testing 09/23/92 ET-NRC-92-3777 11/3062 440.009 CMT testing 09/23/92 ET-NRC-92-3777 1Ii30/92 440.010 CMT testing 09/23 S 2 ET-NRC-92-3777 11/30S 2 440.010R01 CMT testing 09/23S2 NTD-NRC-94-4087 03/24/94 440.011 ADS testing 09/23 S 2 ET-NRC-92-3777 11/3032 440.011ROI ADS testing // // 440.012 ADS testing 09/23 S 2 ET-NRC-92-3777 11/30 S 2 440.012R01 ADS testing // // 440.013 ADS testing 09/23S2 ET-NRC-93-3804 01/22S 3 440.013R01 ADS testing // NTD-NRC-94-4059 02/03/94 440.014 ADS testing 09/23/92 ET-NRC-93-3804 01/22S 3 440.014R01 ADS testing - // // 440.015 ADS testing 09/23 S 2 ET-NRC-92-3777 11/30S 2 440.016 ADS testing 09/23 S 2 ET-NRC-93-3795 '01/14S3 440.017 . ADS testing 09/23/92. ET-NRC-93-3804 01/22 S 3 t ursumn .m resyssres nursemurs.sern avvo w w
w
~
M105 teseing ~ 69/23/92 15Y-MRC-92-3777 11/30S 2 440.020 Regulatory treatment of nonsafety systems 09/23S2 ET-NRC-93-3804 01/22 S 3 440.021 Post 72-hour operation 09/23B2 ET-NRC-93-3804 01/22/93 440.022 Fuel design and analysis 09/23/92 ET-NRC-92-3789 12/22/92 440.023 Mid-loop operations 09/23S2 ET-NRC-92-3789 12/22 S 2 440.024 Analytical codes 09/23S2 ET-NRC-93-3804 01/22S 3 440.024R01 A ialytical codes // // 440.024R02 Analytical codes // // 440.025 Appendix K 09/23/92 ET-NRC-93-3804 01/22B3 440.026 ATWS 09/23/92 ET-NRC-93-3804 Ol/22S3 440.026R01 ATWS 09/23B2 NE-NRC-94-4075 03/04/94 1 440.027 Multiple SGTR 09/23/92 ET-NRC-93-3804 Ol/22S3 440.027R01 Multiple SGTR (Revised Response) // // 440.028 Tech Specs for nonsafety systems 09/23/92 ET-NRC-93-3795 01/14/93 440.029 Safe shutdown; PRA evaluation of safe shutdown 09/23/92 ET-NRC-93-3804 01/22S 3 440.030 Interfacing system LOCA 09/23 S 2 ET-NRC-92-3789 12/22/92 440.031 Credit in analysis for nonsafety systems 09/23S 2 ET-NRC-93-3804 01/22S 3 440.032 Emergency response guidelines 01/26/93 ET-NRC-93-3886 05/14B3 440.032R01 Emergency response uidelines // // 440.033 Applicability of 3-tube PRiiR tests 02/18/93 ET-NRC-93-3905 06/17/93 440.034 CMT scaling tests 02/18S 3 ET-NRC-93-3886 05/14/93 l 440.034R01 CMT scaling tests // NTD-NRC-94-4110 04/28/94 l l 440.035 LOFTRAN/NOTRUMP AP600 models 08/05/93 ET-NRC-93-4007 11/04S3 [ 440.035ROI LOFTRAN/NOTRUMP AP600 Models // NTD-NRC-94-4075 03/04/94 440.036 Purpose of valves V007A,-B,-C and -D 11/02/93 NTD-NRC-94-4059 02/03/94 0 440.037 PR11R heat exchanger heat transfer 11/02/93 NTD-NRC-94-4059 02/03/94 A 440.038 Ilydrogen venting from the pressurizer 11/02N3 NTD-NRC-94-4059 02/03 S 4 0 440.039 " failure of a CMT discharge valve" 11/02/93 NTD-NRC-94-4059 02/03/94 C;t 440.040 MSLB analysis, feed How assumptions 11/02/93 NTD-NRC-94-4059 02/03/94 N 440.041 MSLB minimum DNBR- plot 11/02S3 NTD-NRC-94-4059 02/03/94 Cft 440.042 Feedline break PRHR delay rationale 11/02/93 NTD-NRC-94-4059 02/03/94 O 440.043 Locked rotor failed fuel assumptions 11/02/93 NTD-NRC-94-4059 02/03/94 w M Key: M 440 NRR - Reactor Systems Branch I 3 , 480 NRR - Containment Systems Branch b lT A y:: >o py 951 RES (Containment Systems) Ey O m 2" o= y;g g# , 952 RES (Reactor Systems) @g] a;
=
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I i de Westinghouse Electric Corporation Rawlsion 6, May 5.1994 AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 9 - Summary of NRC Requests for Additional Information (RAI) Related to AP600 Tests and Analysis (cont.) RAINo. Description / Issue NRC Ltr. Westinghouse Response West. Response Date Letter No. Letter Date 440.044 Rationale for locked rotor being limiting 11/02S 3 NTD-NRC-94-4059 02/03S 4 440.045 Rod ejection failed fuel assumptions 11/02S 3 NTD-NRC-94-4059 02/03S 4 440.046 Inadvertant 4th stage opening at pressure ll/0L93 NTD-NRC-94-4059 02/03S 4 l 440.047 SGTR-SG overfill analytical results 11/02S 3 NTD-NRC-94-4059 02/03 S 4 440.048 Assumptions on available equipment / boron dilution 11/02/93 NTD-NRC-94-4059 02/03S 4 440.048R01 Assumptions on available equipment / boron dilution // NTD-NRC-94-4105 04/21 S 4 440.049 ADS Phase B test facility configuration 01/1394 NTD-NRC-94-4099 04/14/94 440.050 Impact of ADS design change on OSU & SPES 01/13/94 NTD-NRC-94-4087 03/24S4 440.051 Limiting single failures in light of ADS change Ol/13S4 NTD-NRC-94-4099 04/14 S 4 440.052 CMT Scaling Report 03/07 S 4 // 440.053 Assessment of AP600 vs. NUREG-1449 issues N/15S4 // 440.054 Potential rapid boron dilution scenarios 04/15 S 4 // 440.055 Failure of temporary RCS boundaries N/1564 // 440.056 Instrumentation available during shutdown /midloop 04/1564 // 440.057 EPGs for shutdown and mid-loop operations N/15S4 // 440.058 Tech Spec changes to deal with shutdown operations 04/15S4 // 440.059 Design features for mid-loop 04/15 S 4 // 440.060 . Design features to minimize loss of ac power 04/15/94 // 440.061 Design features to minimize shutdown risk 04/15S4 // 440.062 Design features to reduce passive sysems challenge N/15S4 // 440.063 Analysis of system performance during shutdown 04/15N4 // 440.064 Procedures during reduced inventory operation 04/15N4 // 440.065 Outage and maintenance activities. 04/15 S 4 ' // 440.066 Applicable modes for SSAR safety analyses N/15S4 / /. 440.067 RHR system operation during mid-loop operation N/15S4 // 440.068 Vulnerabilities for shutdown /midloop operation 04/15 S 4 -/ / 440.069 Compliance with GL 87-12 104/15S 4 // .l __li%W& _ IdwrNm:mreemrtrWhvMt/mTwittirnrrrreyt_1fiWMen _ _ _ _ _ _ _ _____AA- I
440.071 - Operating experience for shutdown events 04/15S4 // -) 440.072 Action items from GL 88-17 04/15S4 // l
'440.073 Control Rod Position Monitoring System 04/19/94 //
480.001 Operator actions during 72-hours post-accident 09/23/92 ET-NRC-92-3789 12/2262 480.002 PCS heat transfer correlations 09/23/92 ET-NRC-93-3804 Ol/22S3 480.003 Failure modes for PCS 09/23S2 ET-NRC-92-3789 12/22S 2 480.004 HWRF Test Data 04/13S3 ET-NRC-93-3895 05/2SS3 480.0NR01 HWRF Test Data // // 480.005 Wind tunncI tests 04/2893 ET-NRC-93-3914 07/01S 3 480.006 Safety relief valve pool dynamic loads / temp limits 07/01 S 3 ET-NRC-93-3962 09/03 S 3 480.007 EQ of components inside containmnet 07/01/93 ET-NRC-93-3962 09/03 S 3 480.008 Natural circulation of air in PCCS 07/01S 3
- ET-NRC-93-3962 09/03/93 480.009 Heat transfer & mixing in containment 07/01 S 3 ET-NRC-93-3962 09/03S 3 480.010 Jet discharge 07/01/93 ET-NRC-93-3962 09/03S 3 480.011 1/8-scale fscility instrumentation 07/0193 ET-NRC-93-3962 09/03 S 3 l
480.012 1/8-scale facility test matrix 07/01S 3 ET-NRC-9'4-3962 09/03/93 480.013 Westinghouse scaling approach 07/01/93 ET-NRC-93-3962 09/03 S 3 480.013R01 Westinghouse scaling approach // // 480.014 Mcchanistic correlations in WGOTHIC 07/0lS3 ET-NRC-93-3963 09/1093 480.015 WGOTHIC validation with test data 07/01/93 ET-NRC-93-3962 09/03/93 480.015R01 WGOTHIC validation with test data // // 480.016 WGOTHIC numerics 07/01/93 ET-NRC-93-3962 09/03/93 480.017 External film pattern / water distribution 07/0lS3 ET-NRC-93-3962 09/03/93 480.017R01 External film pattem/ water distribution // // c 480.018 Degree of rain in containment 07/01S 3 ET-NRC-93-3962 09/03S3 4 480.019 Reactor vessel cooling / insulation 07/01S3 ET-NRC-93-3962 09/03S3 o 480.020 Reactor vessel cooling 07/01S3 ET-NRC-93-3962 09/03/93 (n 480.021 Reactor vessel cooling - subcooled water 07/01S 3 ET-NRC-93-3962 09/03/93 g 480.022 High pressure melt ejection 07/01/93 ET-NRC-93-3962 09/03/93 m 480.023 Steam explosions 07/01S3 ET-NRC-93-3962 09/03/93
.o 480.024 Core debris equilibrium height 07/0163 ET-NRC-93-3962 09/03/93 g Key:
'440 NRR - Reactor Systems Branch 480 NRR - Containment Systems Branch y =- 't>
951 RES (Containment Systems) p8 % y, 952 RES (Reactor Systems) ( PE mm OCm
&$:) 30 I-tTl 4
- - __~, __- __
1 j } i t Wesunghouse Electric Corporation Revision 6 May 5,1994 . AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 9 - Summary of NRC Requests for Additional Information (RAI) Related to AP600 Tests and Analysis (cont.) RAI No. Description / Issue NRC Ltr. Westinghouse Response West. Response Date Letter No. Letter Date 480.025 Core debris coolability/ mace 07/01/93 ET-NRC-93-3962 09/03/93 480.026 Containment integrity / liner penetration 07/01S3 ET-NRC-93-3962 09/03 S 3 480.027 Deflagration / detonation of combustible gases 07/0lS3 ET-NRC-93-3980 10/04 S 3 480.028 Hand calculations 07/01/93 ET-NRC-93-3980 10/04 S 3 480.029 Long-term radial ablation 07/01/93 ET-NRC-93-3962 09/03S 3 480.030 Heat removal from core debris 07/01/93 ET-NRC-93-3962 09/03 S 3 480.031 Water ingression into solidified debris 07/01S3 ET-NRC-93-3962 09/03 S 3 480.032 Prediction of hydrogen distribution 07/01/93 ET-NRC-93-3980 10/04S3 480.033 Passive autocatalytic recombiners 07/01S3 ET-NRC-93-3962 09/03 S 3 480.034 Rationale for hydrogen igniter placement 07/01/93 ET-NRC-93-3962 09/03/93 480.035 Localized detonations, DDT mechanisms 07/0lS3 ET-NRC-93-3962 09/03B3 - 480.036 Diffusion flames above IRWST 07/01/93 ET-NRC-93-3980 10/04 S 3 480.036R01 Diffusion flames above IRWST // // 480.037 Mechanisms for uniform hygrogen distributions 07/t>lS3 ET-NRC-93-3980 10/04 S 3 480.038 Igniter placement criteria 11/02S 3 NTD-NRC-94-4059 02/03 S 4 480.039 Igniter coverage of hydrogen source locations 11/02S 3 NTD-NRC-94-4059 02/03 S 4 480.040 Subcompartments without igniters ll/02S3 NTD-NRC-94-4059 02/03S 4 480.041 Criteria on igniter separation 11/02 S 3 NTD-NRC-94-4059 02/03/94 480.042 Igniter electrical power source 11/02S 3 NTD-NRC-94-4059 02/03S 4 480.043 Structural response / detonation calculations 11/02S 3 NTD-NRC-94-4059 02/03 S 4 480.044 Potential for large hydrogen concentration 11/02/93 NTD-NRC-94-4059 02/03 S 4 480.045 Igniter reliability given one per room 11/02 S 3 NTD-NRC-94-4059 02/03B4 480.046 Igniter in Technical Specifications 11/02S 3 NTD NRC-94-4038 01/1264 480.047 Review of hydrogen experimental databases 11/02S 3 NTD-NRC-94-4059 02/03 S 4 480.048 Equipment survivability in " burn zones" 11/02/93 NTD-NRC-94-4059 02/03 S 4 952.001 Piping Diagrams 07/28/93 ET-NRC-93-4003 10/2763 j 952.002 ADS smrger drawings 08/27/93- ET-NRC-93-3980 10/04 S 3 BMGB M*-rrntnn -- reW6DTM r:De M n e a k t0TKe SWi&NML-
rn v -- 952.004 [ Starting conditions fo"r depressurization transicat 08/27B3 ET-NRC-93-3980 ' 1054S3' 952.005 Primary purap shutoff time 08/27/93 ET-NRC-93-4023 - 11/30S3
'952.006 Test conditions 08/27/93 ET-NRC-93-3980 10/NS3 952.007 Collection of fluids leaving the primary 08/27/93 ET-NRC-93-39SO 10/04 S 3 952.008 Pressurizer heater controls 08/27 S 3 ET-NRC-93-3980 10/04 S 3 952.009 Safety valve pressure setting OS/27S3 ET-NRC-93-3980 10/0493 952.010 Steam generator level control 08/27 S 3 ET-NRC-93-4023 11/30/93 952.011 Core power during a transient 08/27/93 ET-NRC-93-3980 10/04S 3 952.012 Addition of flowmeter to ADS Phase B design 11/0293 NTD-NRC-94-4059 02/03S 4 952.013 Effect of non-condensible gases in test program 11/02 S 3 NTD-NRC-94-4059 02/03 S 4 952.014 Applicability of PRHR test to current design 11/02S 3 NTD-NRC-94-4059 02/03 S 4 952.015 ADS Phase B capability to hold constant pressure 11/02 S 3 NTD-NRC-94-4059 02/03/94 952.016 SPES-2 design documents update 11/02S3 NTD-NRC-94-4059 02/03S 4 952.017 Insights from pre-operational SPES-2 tests 11/02/93 NTD-NRC-94-4059 02/03/94 952.017R01 Insights from pre-operational SPES-2 tests // //
952.018 Cold and hot pre-operational data from SPES-2 11/02S 3 TED-NRC-94-4059 02/03 S 4 952.018R01 Cold and hot pre-operational data from SPES-2 // // 952.019 Flow orifices at SPES-2 11/02S 3 NTD-NRC-94-4059 02/03 S 4 952.020 Volume versus elevation for SPES-2 11/02 S 3 NTD-NRC-94-4059 02/03 S 4 952.020R01 Volume versus elevation for SPES-2 // // 952.021 SGTR analysis for hot and cold side breaks 11/02S 3 NTD-NRC-94-4059 02/03S4 952.022 Information gained from ADS Phase A tests 11/02S 3 NTD-NRC-94-4059 02/03S 4 952.023 Effect of PRHR heat exchanger on ADS operation I1/02S3 NTD-NRC-94-4059 02/03/94 952.024 Test procedures for ADS Phase B testing 11/02/93 NTD-NRC-94-4059 02/03/94 952.025 Analyses for ADS Phases A and B 11/02/93 NTD-NRC-94-4059 02/03/94 rp 952.026 Fluid conditions for ADS Phase B tests 11/02S 3 NTD-NRC-94-4059 02/03 S 4 A, 952.027 RCS behavior versus ADS test facility 11/02/93 NTD-NRC-94-4059 02/03S 4 o 952.027R01 RCS behavior versus ADS test facility // / /. 6 952.028 Dynamic reflection wave forces in ADS operation 11/02S 3 NTD-NRC-94-4059 02/03/94
.p 952.029 SPES-2 bend / elbow radii 11/30/93 NTD-NRC-94 4059 02/03/94 m 952.029R01 SPES-2 bend / elbow radii // //
O Key: y ) N M 440 NRR -. Reactor Systems Branch N 'U 3>
$> OmZ t 480 NRR - Containment Systems Branch E$ 3> T C/)
Cjf I -! -i 951 RES (Containment Systems) o :::r gCm
~ R5 952 RES (Reactor Systems) Co 20 g
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g. i Westinghouse Electric Corporation Revision 6, May 5,1994 m APG00 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 9 - Summary of NRC Requests for Additional Information (RAI) Related to AP600 Tests and Analysis (cont.) RAI No. Description / Issue NRC Ltr. Westinghouse Response West. Response Date - Letter No.- Letter Date 952.030 SPES-2 valve types and sizes 11/30/93 NTD-NRC-94-4059 02/03S 4 952.030R01 SPES-2 valve types and sizes !/ // 952.031 SPES-2 schematics and drawings update 11/30/93 NTD-NRC-94-4059 02/03 S 4 952.031R01 SPES-2 schematics and drawings update // // 952.032 SPES-2 operational parameters 11/30/93 NTD-NRC-94-4059 02/03S 4 952.033 SPES-2 component position relationships 11/30B3 NTD-NRC-94-4059 02/03S 4 952.034 SPES-2 test procedures 11/30/93 NTD-NRC-94-4059 02/03 S 4 952.035 SPES-2 facility insulation information 11/30/93 NTD-NRC-94-4059 02/03S 4 952.035R01 SPES-2 facility insulation information // // 952.036 SPES-2 annular downcomer 11/30S 3 NTD-NRC-94-4059 02/03 S 4 952.037 OSU facility orifice plate information 01/1864 !TFD-NPC-94-4105 04/21/94 952.038 OSU valves with sigt ificant flow loss 01/18/94 NTD-NRC-94-4105 04/21S4 L 952.039 OSU MOV opening / closing rates 01/18/94 NTD-NRC-94-4105 04/21/94 952.040 OSU heater rod power profile 01/18/94 NTD-NRC-94-4105 04/21/94 952.041 OSU drawings LKL930104 & LKL930105 01/18S 4 NTD-NRC-94-4105 04/21/94 952.042- Pressurizer Balance Line Piping Diagrams 01/27/94 NTD-NRC-94-4110 04/28/94 952.043 RELAP-5 Thermal Hydraulic Information 01/27/94 NTD-NRC-94-4110 04/28/94 952.044 Reactivity coefficients and check valve info 02/1784 // 952.045 LOCA steady-state and transient asssumptions 02/17/94 // 952.046 WCOBRAfrRAC results 02/17/94 // 952.047 Valve setpoints 02/17B4 // 952.048 Fuel rod temperature profiles 02/1764 // 952.049 SPES-2 test conditions 02/24/94 NTD-NRC-94-4105 04/21S4 952.050 SPES-2, Basis for fuel rod stored energy 03/01/94 NTD-NRC-94-4105 04/21 S 4 952.051 SPES-2, Secondary side mass 03/01/94 NTD-NRC-94-4105 04/21 S 4 952.052 SPES-2, Basis for pressurizer water level 03/01 S 4 NTD-NRC-94-4105 04/2164 952.053 SPES-2, Secondary side conditions 03/0164 NTD-NRC-94-4105 04/21S4 rwsuen m awmcw censurstwrmavw awaarm
"95'2.055 $ PES-2 Delaked neutron simulation- 03/0194 NTD-NRC-94-4105 -04/21S4 952.056 SPES-2, Basis for heat loss compensation 03/0lS4 hTD-NRC-94-4105 04/2194 952.057 SPES-2, Secondary side relief valve closing setpts 03/0164 NTD-NRC-94-4105 04/2194 952.058 SPSE-2, Pump coastdown 03/01B4 STD-NRC-94-4105 N/21S4 952.059 SPES-2, Pressurizer heater rods 03/01 S 4 NTD-NRC-94-4105 04/21B4 952.060 ADS, Nominal valve inlet conditions 03/01S4 //
952.061 ADS, Nominal control valve area 03/0IS4 // 952.062 ADS, Nominal control valve mass flow rate 03/01S 4 // 952.063 ADS Stage 4, valve train piping dimemsions 03/01S4 // 952.064 ADS Stage 4. Valve train geometry 03/01S4 // Key: 440 NRR - Reactor Systems Branch 480 NRR - Containment Systems Branch 951 RES (Containment Systems) 952 RES (Reactor Systems) C c 61 10 CJ1 O w EO to
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CMT CATEGORY 1 MATRIX Start: 2/15/94 (2/15/94 Actual) l TESTS End: 6/22/94 , l i CMT CATEGORY 2 Start: 6/27/94 l MATRIX TESTS End: 8/19/94 ; h SPES-2 CATEGORY 1 MATRIX TESTS E SPES-2 CATEGORY 2 , Start: 9 MATRIX TESTS End: 9 i 4 4 t OSU CATEGORY Start: 7/1/94 1 MATRIX TESTS End: 9/22/94 I OSU CATEGORY 2 M ' TESTS
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