ML20065A473

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AP600 Design Certification Test Program Overview, Rev 5.W/ Ten Oversize Drawings
ML20065A473
Person / Time
Site: 05200003
Issue date: 03/22/1994
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20029C585 List:
References
PROC-940322, NUDOCS 9403310172
Download: ML20065A473 (50)


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n. ANSTEC APEnyugg CARD A o Available on porturo Card TABLE OF CONTENTS Table 1 - Test Program Overview (Part 1) l l Table 2 - Test Program Overe (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 l 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 of Westinghouse AP600 Test Program Related Materials Transmitted to NRC l Table 9 - Summary of NRC Requests for AdditionalInformation (RAI) Related to AP600 Test Programs Chart 1 - Matrix Testing Schedules i i O .. i e [ ( > - r J

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~ Westinghouse Electric Corporation Revision 5, March 22,1994 AP600 DESIGN CERTIFICA'j APG00 TEST PROGRAMS: TABLE 1 - TEST PROGRAM OVERVIEW (PART 1) Item . _ TEST 1N No. TEST DESCRFUON FACILITY LOCATION SCALE C ATEGORY - STATU PASSIVE CotRAINMEt(T COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN k 1 Air Flow Path Detta P Test W Science & Technology Center - Churchill, PA 1:6 linear Basic Research Complete t Water Film Formation Test 2 W Science & Technology Center - Churchill, PA N/A Basic Research Complete 3 Hoated Plate Test W Science & Technology Center - Churchill, PA N/A Basic Research Complete { 4 Bench Wind Tunnel Experiment W Science & Technology Center - Churchill, PA 1:120 linear Basic Research Complete 5 Condonsation Tests - Bare surface upward University of W~sconsin - Madison, WI N/A Basic Research Complete I

   ;                    6  Condensation Tests - Bare surface downward      University of Wisconsin - Madison, WI         N/A            Basic Research Complete 7  Condensaten Tests - Painted surf ace oown       University of Wisconsin - Madison, WI         (4 A           Basic Research Cornplete j                     8  Condensation Tests - Light noncor densibles     University of Wisconsin - Madison, WI         P4 A           Basic Research Complete 1

1 9 Condensation Tests - Stagnation Flow Universrty of Wisconsin - Madison, WI itA Basic Research Complete Cordtjons 10 Condensation Tests - Stagnatiorright Univers:ty of Wisconsin - Madison, WI N/A Basic Research Complete noncondensibles 11 Condensation Tests - 2D condonsation Universtry of Wisconsin - Madison, WI t4A Basic Research in Progre PASSIVE CONTAltfMEtR COOLING SYSTEM TESTS IN SUPPOFTT OF APEOO DESIGN CERTIFICATION 12 Integral (sma!I scale) Tests Phase 1 W Science & Technology Center - Churchill, PA 1:3 height Safety Related Complete I (Feasibility) 1:40 diarmter 13 Intngral(small scale) Tests Phase 2A W Science & Technology Center - Cnurchill, PA 1:3 height Safety Related Complete r (Extension Tests) 1:40 { diameter 4 14 Integral (small scale) Tosts - Phase 28 W Science & Technology Center - Churchill, PA 1:3 height Safety Related Complete f (Cont 5nuaton Tests) 1.40 j diameter 15 1/8th Scaia Hoat Transfer Test Phase 1 W Science & Technology Center - Churchill, PA ~1:8 linear Safety Related Complete e (Baseline)

     .                 16  1/8th Scale Heat Transfer Ted - Phase 2         W Science & Technology Center - Churchill PA
                                                                                                                         ~1:8 linear    Safety Related Complete (Confirmatory) l                   17  Water Distribution System Test - Phase 1 (20ft  W Waltz Mill Site Madison, PA 1:1            Safety Related Complo j                        Diameter) 18  Water Distribution System Test - Phase 2 (1/8th W Waltz Mill Sete - Madison, PA 1:1            Safety Related Complets-g                        Sector) 19   Water Distribution System Test - Phase 3 (1/Sth W Waltz Mill Site - Madison, PA               1:1            Safety Related Complete sector w:th selectnd distribution system)
 $                    20   Wind Tunnel Test - Phase 1                      Univ. of Western Ontario - London, Ontano     ~1:100 liriear Safety Related Complete b
 %.                   21  Wind Tunnel Test Phase 2                         Univ. of Western Ontano - London, Ontano      -1:100 linear Safety Related  Complete
                      '"  Wirrf Tunnel Test Phase 4A                       CNRC Wind Tunnel - Ottawa, Canada             1:30 linear    Safety Related Complete f{                  23  Wind Tunnel Test Phase 4B                        Univ. of Westem Ontano - London, Ontano       1 500 linear   Safety Related Complete
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UON TEST PROGRAM OVERVIEW i l l t  ! ADDITIONAL INCORMATION OBTAINED - . item' - l

                                  . TEST PURPOSE                                                                                                                                                                               (Optional):                            v No.           l

{' t Obtain pressure drop data through the downcomer and annulus 1 l Confirm wettability of coated steel surf ace 2 w 7 41 l Confirm Passue Containment Cooling System heat transfer capability hM y l. C.V 3 Assess effects of wird on shield building design (inlet / outlet location) r,oF M U W 4 1 1 Comparison wrth past separate effects tests (]QO 5 l Cbtain heat transfer coefhcients with downward facing surfaces 6 [ Obtain the effect of AP600 paint on heat transfer performance g Avail &D50 M 7 Obtain the effect of light noncondensibles on heat transfer performance Ap0i1GIO V# 8 Obtain the heat transfer F>erformance under stagnant flow conditions 9 i Obtain the heat transfer pedormance under stagnant fluw cond:tions in 10 l the presence of light noncondensibles j ) Moasure condensation heat transfer coefficient using 2D test model Investgate effect of non-condonsibles on heat transfer coefficient and 11 visualize flow field i b l Determine feasibility of water enhanced containment cooling system investgate external cooling impact from air velocity. air humidity, 12 ternperature and water film flow rates l Demonstrate cperation of Passive Containment Cooling System (PCS) Investigate effect of various annullus widths ard uniforrn steam 13 l t over increased range of operating conditions. Confirm PCS intomal distributions. Obtain data on water film behavior on external sudace and etternal heat transfer capabilities (with 1:1 scale cooling air over long vertical heat transfer surface. annulus at controikd air temperature & humidity) Domonstrate operation of Passive Containment Coohng System with 14 l prototypic steam injection L _ C btain heat transfer data for WGOTHIC computer code validation with 15 minimal intervals Obtain heat transfer data for WGOTHIC computer code validation Investgate ef+ect of non-condensibles on PCS heat removal capability 16 and internai tempo.ots.2 dbtributions investgate performance of passive containment cooling system center Assess containment water coverage at top of dome 17 water dehvery distnbution device j Measure containment water coverage using drstrubution system Obtain film thickness measurements 18 Measure containment water coverage using selected design distnbution Obtain film thickness measurements 19 j [ system investigate wind sensrtivity of shek! building design Asess effects of site structures on wind loading 20 Assess wind loads on containment baffle Compare wind effects w & w/o internal flow path 21 Venty Phase 1 & 2 test results at hgher Reynolds numbers Confirm baffle tomado loads 22 f investgate site topography effects on a:r flow throught PCS annulus investgate effects of large structures on air flow throught PCS 23 annulus i I l f O 1 > j l /

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{ Westinghouse Electric Corporation

  !-             Revision 5, March 22,1994                                                        AP600 DESIGN CERTIFICA' APG00 TEST PROGRAMS: TABLE 1 TEST PROGRAM OVERVIEW (PART 1)

Item . . TEST 2 No. TEST DESCRIPTION FACILITY LOCATION  : SCALE CATEGORY - 1STATt

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PASSIVE CORE COOLING SYSTEM TESTS IN SUPPORT OF APG00 DESIGN CERTIFICATION : 24 PRHR Heat Exchanger Test - Phase 1 W Science & Technology Center - Churchill, PA 1:1 height Safety Related Complet+ 25 PRHR Heat Exchanger Test - Phase 2 W Science & Technology Center - Churchill, PA 1:1 height Safety Related Complet< l 26 Automatic Depressurization System Test - Phase ENEA (VAPORE faciley) Casaccia, Italy 1:1 Safety Related Completi A (sparger) 27 Automatic Depressurization Systems Test - ENEA (VAPORE facility)- Casaccia, haly 1:1 Safety Related Planned PMw B t { 28 Core Makeup Tonk Test ,W Wattz Mill Site - Madison, PA ~1:8 Safety Related in Progr< diameter

                                                                                                              -1:2 height 29   DNBR Ter.ts                                    Columbia University - New Yo*, NY              1:1            Safety Related      Complet.

30 Low Pressure 1/4 Height Integral Systems Oregon State University - Corvallis, OR 1:4 height Safety Related Planned Tests 1:192 volume 31 Full Pressure Full Height integral Systems SIET (SPES-2 Facility) . Piacenza, Italy 1:1 height Safety Related in Progri Tests 1:395 volume l l Y I i e r a m I

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8 ON TEST PROGRAM OVERVIEW l ADDITIONAL INFORMA110N OBTAINED : Item ' TEST PURPOSE (Optional) : No. h Determine thermal performance of the PRHR beat exchanger tubes. Assess water mixing in the IRWST and the effects cd mixing on heat 24 transfer rates and steaming. Expard the range of test conditons to more tully define a PRHR heat Determine the impact of lower instal tank water level on steaming. 25 transfer correlation. Obtain sparger performance data, measure loads impouxi on quench Obtain thermal hydraulic data for computer code validation 26 tank for use in confirming IRWST design s Obt:In vdve performance data; Piping, structure loads / responses Obtain thermal-hydraulic data for computer code validation 27 with both 19 and 24 flow h Obtain thermaLhydraulic data for computer code validation Confirm acbequacy of CMT level instrumentation 28 b l Obtain DNB data at low flow condttions Obtain data on fuel assembly flow mixing grds at design flow 29 ( conditons Obtain thermabbydraulic data for computer code validation investigate long term cooling behavior 30 l l l p Gu.eki'hermal-hydraulic data for computer code validation investigate systems interactions during high pressure transients 31 i _ ANSTEC APF_RTURE CARD l Ab0 AWi {GDIO i 0D Apenure Card l l l l l ~ r 1 [ i [ i i l

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Westinghouse Electric Corporation nevision 5, March 22,1994 AP600 DESIGN CERTIFICA' j AP600 TEST PROGRAMS: TABLE 2 TEST PROGRAM OVERVIEW (PART 2) TEST SCHEDULE item f' No. TEST NAME ' - Start End. '. SCHEDULE i PASSIVE CONTAtHMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN . I 1 Air Flow Path Delta P Test January 1988 February 1988 Completed PWA 2 Water Film Formation Test February 1988 March 1988 Completed N/A 3 Heated Plate Test April 1988 June 1988 Completed MA 4 Bench Wind Tunnel Espenment August 1983 September 1988 Completed N/A 5 Condensation Tests - Bare surface upward September 1988 December 1988 Completed N/A I 6 Condensation Tests - Bare surface downward September 1989 December 1989 Completed N/A e 7 Cordmsatbn Tests - Painted surf ace downward September 1990 December 1990 Completed MA r 8 Condensation Tests - Light noncondensbles September 1991 Decernber 1991 Completed MA , 9 Condensation Tests - Stagnatx>n flow conditions September 1992 March 1993 Completed N/A 10 Condensation Tests - Stagnatiorvlight noncondensbles March 1993 July 1993 Completed N'A 11 Condensation Tests - 2D Condensation January 1994 April 1994 In Progress MA PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF APGOO DESIGN CERTIFICATION - 12 Integral (small scale) Tests - Phase 1 (Feasibility) May 1989 October 1989 Completed N/A 13 Integral (small scale) Tests - Phase 2A (Extension Tests) January 1990 June 1990 Completed MA 14 Integral (small scale) Tests - Phase 2B (Continuation Tests) June 1992 August 1992 Completed MA 15 1/8th Scale Heat Transfer 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 MA 17 Water Distribution System Test - Phase 1 (20ft Diameter) June 1991 August 1991 Completed N'A 18 Water DistributK>n System Test - Phase 2 (1/Sth Sector) September 1991 February 1992 Completed MA 19 Water Distribution System Test Phase 3 September 1993 September 1993 Completed N/A 20 Wind Tunnel Test - Phase 1 June 1991 August 1991 Completed N/A 21 Wind Tunnel Test - Phase 2 February 1992 March 1992 Completed MA l 22 Wind Tunnel Test - Phase 4A June 1993 August 1993 Completed N/A i W Wind Tunnel Test Phase 48 September 1993 September 1993 Completed MA g PASSIVE CORE COOLJNG SYSTEM TESTS IN SUPPORT OF APCOO DESIGN CERTIFICATION I i 24 PRHR Heat Exchanger Test - Phase 1 November 1989 January 1990 Completed N/A 25 PRHR Heat & changer Test Phase 2 July 1990 November 1990 Completed N/A 26 Automatic Depressunration System Test - Phase A (sparger) June 1992 November 1992 Completed N/A 27 Automatic Depressurization Systems Test - Phase B July 1994 October 1994 Chart 1 Table 28 Core Makeup Tank Test February 1994 September 1994 Chart 1 Table @j l 29 DNBR Tests June 1993 February 1994 Completed N/A 30 Low Pressure 1/4 Height integral Systems Tests July 1994 February 1995 Chart 1 Table { 31 Full Pressure Full Height integral Systems Tests February 1994 November 1994 Chart 1 Table Fl 4- 1 L

w.m ON TEST PROGRAM OVERVIEW HRC WITNESS OF KEY TESTS . g kTRIX TEST NAME/fJO. ^ DESCR1Pil0H WEEK OF ' -: No. N/A N/A [dshTkh N/A 1 ( r M'A P4 A

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N/A 2 [ f4'A RA p_(g,{}Q N/A 3 r u [ KA NA N/A 4 NA MA nten Availabla 00 N/A 5 RA N/A A00rtuf 0 CE KA 6 N/A MA RA 7 N/A P4A N/A 8 N/A N/A N/A 9 i N/A RA N/A 10 ( M'A N/A NA 11 I NA f4'A N/A 12 [ NA N/A N/A 13 r N/A WA N/A 14 ( N/A N/A P4A 15 l f4/A NA N/A 16 r i RA NA N/A 17 N'A NA NA 18 MA N/A N/A 19 l NA P4 A N/A 20 MA f4'A NA 21 [ WA N'A N/A 22 N*A t1 A N/A 23 l N/A f4A N/A 24 i N/A N/A N'A 25 l N/A P4 A fl'A 26 210 Satursted water blowdown from 2250 psig, maximum flow 8/18/94 27 ( 403 Hot CMT draindown during depressurization 9/16 S4 28 WA MA N/A W S812 SBLOC A - DEG DVI line break 8/17 S4 30 1 SBLOCA - -lin. Cold Leg Break 4/14 S4 31 11 Steam Generator Tube Rupture 11/2/94 l j q1 o a > l

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,                              Westinghouse Electric Corporation L                              nevision s, March 22,1994                                                      AP600 DESIGN CERTIFICA1 i        AP600 TEST PROGRAMS: TABLE 32 TEST PROGRAM OVERVIEW (PART 3) s s

4

llem V REVIEW ( Test Metrix? Scallng l Test SpecificationI Operating Pt Report '
                 . No. :                    : TEST DESCRIPTION :                 0 MEETINGS 1                                                           >

PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN 3 1 Air Flow Path Delta P Test - N/A N/A N/A WA 2 Water Film Formation Test - N/A N/A N/A N/A 3 Heated Plate Test - N/A WA MA N/A 4 Bench Wind Tunnel Experiment - N/A N/A WA N/A 5 Condensation Tests - Bare surface upward - Reference 5.3 N/A N/A N/A 6 Condensation Tests - Bare surface downward - Reference 6.3 N/A WA N/A 7 Condensation Tests Painted surface - WCAP-13307 WA N/A N/A t downward . 8 Condensat>on Tests - Light noncondensbles - Reference 8.2 WA N/A N/A

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9 Condensation Tests - Stagnaten flow - Reference 9.2 N/A MA N/A conditions a 10 Condensation Tests - Stagnatvan/hght Reference 10.2 N/A N/A N/A noncondensibles I 11 Condensation Tests - 2D condensation - 8/94 WA N/A N/A-

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PASSIVE CONTAINMENT COOUNG SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION 12 Integral (small scale) Tests - Phase 1 - WCAP-12667 N/A NA Completed (Feasbikty) Revi 13 Integral (small scale) Tests - Phase 2A - Presentation N/A WCAP-13315 Completed (Extension Tests) Mat 1 from 3/17/92 meeting [ w/ NRC 14 Integral (small scale) Tests Phase 2B - Presentation MA WCAP-13315 Completed t > (Continuation Tests) Mat 1 from 3/17/92 meeting w/ NRC q_ 15 1/8th Scale Heat Transfer Test - Phase 1 - WCAP-13566 WCAP-13246 WCAP-13267 Completed - (Baseline) 16 1/8th Scale Heat Transfer Test - Phase 2 3/23-24/93 W Letter ET- WCAP-13246 WCAP-132G7 Completed ! (Conhrmatory) 2/23 24/94 N RC-93-3845 17 Water Distnbuten System Test - Phase 1 (20ft - WCAP-13290 N/A WCAP-13290 Completed . ] Diameter) j 18 Water Drstnbution System Test - Phase 2 - WCAP-13290 N/A WCAP-13290 Completed (1/8th Sector) 19 Water Distribution System Test - Phase 3 - WCAP-13816 N/A WCAP-13816 Completed j

p. 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 Tunne! Test - Phase 4 A                             -       WCAP-13756         4/94         WCAP-13318          Completed
      .             23        Wind Tunnel Test Phase 4B                                -

WCAP-14005 5/94 WCAP-13318 Completed g- l I

DN TEST PROGRAM OVERVIEW f TEST DOCUMENrs ures

  • FaclHty Description Report Quick Look Final Test Report Other Relevant information Reports hem No.
                     - FACILITY OPERATING PROCEDURES ARE MAINTAINED IN WESTINGHOUSE FILES AND ARE AVAILABLE FOR REVIEW.

WCAP-13328 f1'A WC AP-13328 WCAP-13330 1 WC AP-13834 N'A WCAP-13884 WCAP-13330 2 WCAP-12665 f4'A WCAP-12665 WCAP-13330, WCAP-13246 3 4/94 PL'A 4/94 WCAP-13330 4 l Referenco 5.3 M'A Rderonce 5.3 WCAP-13246 /iNR Tis C, 5 R.Jorance 6.3 tFA R4hwence 6.3 WCAP-13246 j g {} { p"[] l f} p 6 WCAP 13307 N. A WCAP-13307 WCAP-13246 {' 7 Reforor e 8 2 tL A Rulerence 8.2 ,, 8

                                                                                                                                              *   .0. L. i j        Reterence 9 2                                                     ti'A           Reference 9.2                                                           9 gg .    .

hetererre 10 2 None Reference 10 2 10 l &M None 8/48

  • 11 l

i WCAP-12667, Rev.1 frA WCAP 12667 Rev 1 WCAP-13330 WCAP-13246 12 l 6 94 None S G-1 WCAP-13246 13 l a 94 Nane a St WC AP-13246 14 l l a st None WC AP-13566 WCAP-13725, WCAP-13246 15 l l 6 94 11.93 4 44 a St WC A P-13566 16 u - l WC AP- 13292 Norm WC A P-13353 WC A P-13246 17 i l WCAP-1332 None WCAP 13296 WC A P-13246 18 WC AP- 1332 Nano WC A P-13960 WCAP-13353, WCAP-13296 19 WC AP 13?M Ncne WC A P-13234 WC A P-13246 23 WCAP 13323 Nor'e WC A P-13323 WC AP-13294, WCA P-13246 21 i i

4. N N r. 4 at WCAP-13294, WCAP-13323 22 5 91 5 91 WCAP-13294, WCAP-12323 l None 23 -

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  ' - "" ~ ~ ~ -                Westinghouse Electric Corporation                                                                                                        :

Revision 5, March 22,1994 AP600 DESIGN CERTIFICAj

                                                                                                                            ^

j ~AP600 TEST PROGRAMSi TABLE 3NTEST PROGRAM OVERVIEW'(PART 3h

                                                                                                                        +
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p p; . e < pdj Item _ . . . . . . . . . . . _ , . [ REVIEW Test Matrix 5 Scalinh$ s;..  : Test SMWicettori[ Operating h

                                                                                                                                             ~~                      "
                    ' No!    ,

t TEST DESCRIPTION.:- 3 MEETINGS h 4 , Report ' ' " " PASSIVE SAFETY SYSTEMS TESTS IN SUPPORT OF AP600 DESIGN CERTIRCATION =: - i

  • iFACitJT OPERA 1 24 PRHR Heat Exchanger Test - Phase 1 -

WCAP 12666 - N/A N/A Completed ; 25 PRHR Heat Exchangor Test - Phase 2 ' - WCAP 12980 N/A WCAP-13368 Completed 1 26 Automatic Depressurizaton System Test - 5/26-27/93 WCAP-13342 N/A WCAP-13342 - Completed f- Phase A (Sparger) L 27 Automatic Depressurization Systems Test . S/26-27/93 Table 4 N/A WCAP-13342 5/94 Phase B 2/25/94 To be revised 4/94 l 28 Core Makeup Tank Test 2/25/93 Table 5 WCAP-13963 WCAP-13345, Series 100d i 3/14/94 Revision 2 Series M 29 DNBR Tests - N/A N/A WCAP-12488 Completed I, j" 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 31 Full Pressure Full Height Integral Systems 12/10/92 Table 7 WCAP-13277 W letter ET NRC- 12/93 - 5/94) Tests 92-3776, WCAP to I be issued 4<D4 F,? 1 a. ( !p t. l I a-46 @ An

JON TEST PROGRAM OVERVIEW W-

                      .- TEST DOCUMENTS J h *-        Facility Description' Report Quick Look$      FinalTest Aport                                                      Other Relevant'information Reports .':                                                                          ,
                                                                                                                                                              ~

gg lG PROCEDURES ARE MAINTAINED IN WESTINGHOUSE FILES AND ARE AVAILABLE FOR REVIEW :s [ WCAP-12666 N/A WCAP-12666 24 f WCAP-12980 N/A WCAP 12980 25 l 4/94 N/A 4/94 26 A M O ~7"1" O

            *                          " "*             *'5                                                                                                                                      

L ANNbUkE ) Pl ote 5/94 4/94 10/94 j tfg4 . g

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j ] 1 e Weatinghouse Electric Corporation R2 vision 5, March 22,1994

. AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW t

TABLE 4 - MATRIX TESTS, AUTOMATIC DEPRESSURIZATION SYSTEM TEST, PHASE B i TEST CATEGORY lEST NO. DESCRIPTION , Category 2 Matrix Testa 110 Saturated Steam from top of supply tank, Stage 1 ooon. -2250 to 400 pelg, hirnum flow resistance simulated. Obtas single phase TM data 3 120 Saturated Steam from top of supoly tank, Stages 1 and 2 open, -800 to 100 psig, Maximum tiow resistance simulated. Obtain single phase TM data t 130 Saturated Steam from top of supply tank, Stages 1 and 3 open. -500 to 50 pstg, Maximum flow resistance simulated. Obtain single phase 1M data 140 Saturated Steam from top of supp!y tank Stages 1,2 and 3 open, ~500 to 50 peig, Maximum flow resistance simulated. Obtain single phase T/H data 210 Saturated Water from bottom of supply tank. Stage t open, ~2250 to 400 psig. Maximum flow resistance simulated. 12-inch gate vane positioned to cbtain a range of two-phase TM data. 220 Saturated Water from bottom of supply tank, Stages 1 and 2 open, -1200 to 100 pelg Maximum fiow resistance simulated. 12 inch gate valve positioned to obtain a range of twtphase T/M data. 3 230 Saturated Water from bottom of supply tank, stages 1 and 3 open, ~500 to 50 psig. Maximum flow resstance simulated.124nch gate valve positioned to obtain a range of two-phase TM data. 24 0 Saturated Water from bottom of supply tank. Stages 1,2 and 3 open, ~500 to 50 psig, Maximum flow resistance simulated.12-inch gate valve - positioned to obtain a range of twghase TM detai , 250 Saturated Water from bottom of supply tank, Stage 2 open (inadvedent opening at full power) -2235 psig. Maxirnum flow resistance simulated. ' 12-inch gate valve postiotwd to cbtain a range of twophase TM data. 310 Saturated water from bcttom of suppfy tank, Stages 1,2 and 3 open, -500 to 50 psig, Quench tank water intially at 212"F, Minimum flow resistance simulated. Maximum flow / minimum quality for max loads 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, Mn! mum flow resistance simulated. Maximum flow / minimum quality for max toads on sparger and ouench tank. 330 Saturated water from bottom of suppfy tank, Stages land 2 open, ~1200 to 100 psig. Quench tank water initia!!y at 212"F, Mnimum flow resistance simulated. f&ximum flow / minimum querity for max loads on sparger and quench tank. 340- Saturated water from bottom of supply tank Stage 2 open, ~2235 psig, Quench tank water initia!!y at 212*F, fAnimum flow resistance sirnulatedf Maximum flow / minimum quality for max loads on spanger and quench tank.

                                                         -TABLE 5 - MATRIX TESTS, CORE MAKEUP TANK TEST
                                                 ~                      ~     ~~                                 ~
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Category 1 101 105 CMT wait N: A. CUT d@n rate based on 10/13S6891085/2235, with subsequent CMT Initia0y contains no water, and is evacua*ed (no air). Matdx Teta condensaten wth etsam condensation este and d sin depressuriza$on and without cacaotty 106-108 noncondens:ble 10 CMT initta!!y evacuated and then pressunzed with a:t (or N,) to gases .236,1.13 and 2.13 psia, respectively. 109-111 1035 CMT Icitia:!y evacuated and then pressurized with hebum to 42, 146, and 296 psia respectively. 20t-200 CMT Watt and Water N. A - CMT level faed. Water 10/135/1085'2235, w!!h subsequent CMT rnftisHy 90% and 75% feli. CMT 1evel control used to surface drained from CMT via external path depressurization rna;ntain fixed CMT leve!. Condensa+ ion to mn*ch steam condensation 209 214 10/13S/1085. w.th subsequert CMT inmaily 50*. and 25% fail. CMT tevel comro! used to dapressunzation enaintain imod CMT ievel. 301 312 CMT draindown at 6/11/16 Max 10/135/1995 Low resistance steam supply ime no 2 utuzed. d<ain rare conSt39t pres 6U'e controiled by d'Scharge 1:ne resistance. ^

          .  -_A 313 316                             Flow ra'e controlled t>y steam                  10W2235                                   Low resis!ance steam supply line rio. 2 utized, dram rata l\                                                          soppty line no 1 resistance. (3                                                           controtted by disctwge line resistance.

%' ft/ gem') Category 2 401 402 CMT draindown Discharge I:ne resstance for 6/16 1095 fonowed by depressurt:ation to 20. Low resista,ce steam supoly line no. 2 utitzod; drain rate i MaMx Tests durng gpm contretud by discharoe line resistance depressurization 403-401 Dra!n rate contronad by steam 2235 foHowed by decressunzabon to 20 Dmcharge bne remstance sat to procce 6/16 gom g<avity &ain P

            ]                                                       suppiy hne no 1 resistance                                                                rate at atonspheric pressure 531-502  Natural circulation        Discharga bne resstance set for                1085 fo0cwed by depressurizaton to 20      Steam scpply line no.1 is closed Reservoir water level rt "HF foltowed by                6/16 gom drain rate                                                                       levat Reservoir water tarrparature initsity 545T. Steam draindown und                                                                                                        sopp!y hne no. 7 is opened to initate natural circulation until dopressurization                                                                                                     one-fit h of CMT heated. Reservoir water levelis reduced to inrate draindown The steam supply is isoiated and the water / steam reservoir is vented when the CMT is drarned to 97 inches.

503-$0>1 Repeat with naturaJ circulation until one ha!f of CMT heated. 505 506 Repeat with natural circulation until CMT is cornpieteiy heated. 601 606 CMT actuation wah O?scharge line resistance set for 1835 - constant I' Reservoir water level Nr. Reservoir water ternpemtu<e ini!;a'!y Y both steam unes. 6/16 gom. Steam suppfy line no.1 54 5T. Steam suppiy hne no.1 is open. Both steam supply with and without resistance set to be 3 "jgpm'. line no. 2 and CMT discharge lines opened simultaneously. 607 612 noncondensibfe gas. 1085 - constant Pedormed with steam, and with 146 and 206 psig of He initially j in CMT side of staam mupp;y fina no. ? hao2 b G ,_, ts is) . l f ?0 5$ kW~ og RE O.Cm  % uD lM %a mo rT1 I' . l

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. l l t Wsstinghouse Electric Corporation Rwlsion 5. March 22,1994 AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW TABLE 6 - MATRIX TESTS, LOW PRESSURE 1/4 HEIGHT INTEGRAL SYSTEMS TEST (OSU) TEST CATEGORY TEST NAME DESCRIPTION Cold Preoperational Tes:s C01 Core makeup tank gravity drain CO2 Accumulator tank d a!n C03 in<ontainment refueling water storage tank drain C04 Chemical and Volume Control System pump f ow vs. pressure C05 Normal residual heat removal system pump flow vs. pressure C06 Steam generator feed flow versus pressure C07 ADS 1-3 Une Flow Test C08 ADS 4 Une Flow Test C09 RNS injection Flow Test Hot Pre-Operational Tests HS01 Reactor Coolant Forced Circulation Loop Flow Test HS02 Reactor Coolant Natural Circulation Loop Flow Test HSO3 Reactor Power Caforimetric HSO4 Ambient Heat Losa Determination HS05 PRHR Loss Determination HS06 Steam Generator Performance Test HS07 Reactor Coolant System Heatupcooldown Test Category i #Aitrix Tests SB1 2-inch cold leg break, bottora of pipe, loop A with continuation into long-term cooling mode SB4 2-inch cold leg break, bottom of pipe, loop A SBt0 Double-ended guulotine break of cold leg balance line, vertical loop, loop A with cont!nuation into long term cooling SB12 Doubleended guDlotine break of direct vesselinjection line SB13 2-inch break of direct vesselinjection line S8? 6 Double +nded guillotlne break of pressurizer / core makeup tank balance line, between check valve / core rnakeup tank, loop A, with continuation into long term cooling Category 2 Matrix Teste . LB01 Large CLB, Higher Decay Heat during long term coofing __. - _-. __. _ . . ~

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-1 Westinghouse Electric Corporation Rnvision 5, March 22,1994 APG00 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW TABLE 7 - MATRIX TESTS, FULL PRESSURE FULL HEIGHT INTEGRAL SYSTEMS TEST (SPES-2) f TEST CATEGORY TEST NUMGER DESCRIPTION Cold Shakedown Tests C-01 Single phase flow through the pressurizer surge line 4 flow rates C-02A B Single phase flow through the pressurizer to core makeup tank balance lines,4 flow rates per balance fine 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 makeup tank balance line C-05A.B Core makeup tank gravity draindown using pressurizer to core makeup tank balance line C-06A.B Safety Inlection Accumulator blowdown C-07A.D in-containment rrefuelir:g water storage tank gravity draindown, three water levels C-08 Chernical and Volume Control System, Normal Residual Heat Removal System and Stadup Feedwater System pump flow rate venfration C-09 Operation of primary system with 2 reactor coolant pumps running C-10A,0 Operation of primary system adh 1 reactor coolant pump running C-11 Facility volume measurement Hot shakedown tests H-01 Facility heated and heat at five constant temperatures H-02 Starting from nominal conditions, power w!tt be shut off and steam generators isolated H-03 Facility operated at normal full pressure, temperature and power H-04 Facility transitioned from full power operating conditions to hot shutdowntnatural circulation mode of operation H-05 Core makeup tank draindown using pressurizer to core makeup tank tmtsnce line H-06 Low pressure, safety system actuation esing the automatic depressurization system with care makeup tank dratndown and accumulator delivery H-07 Full power, full pressure, safety system actuation initiated by the opening of the first stage of the automatic dapressurization 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 systems off 4 2-inch cold leg break with non-safety systems on 5 2-inch direct vessel injection line break with non safety systems off _n____.__._____._ - - - - . . _

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Westinghouse Electric Corporation nevision 5, March 22,1994 APG00 DESIGN CERTIFICATD TABLE 8 - TEST PROGRAM REFERENCES (

SUMMARY

OF WESTWGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMffTED TO DESCRIPTION TEST PROGRAM GEHERAL i 0.1 Response to November 14,1991 Request for Informaton Rogarding AP600 Test Program j 0.2 Response to January 15,1992 Request for information Regarding the AP600 Passive Containmont Cooling System Tests O.3 Rosponses to "AP600 Design issues to be Resolved by High-Pressure, Full-Height integral Testing" 04 Presonta6on Matenal from February 25,1992 Westinghouso NRC Monting on AP600 Testirig

  • 0. 5 Responso to November 14,1991 Roquest for Addrtional Information Regarding AP600 Test Program

, 06 Presentation Material from March 3,1992 ACRS Meeting on AP600 Testing

0. 7 Presentabon Matenal from June 1,1992, AP600 Meeting on integral Systems Testing 0.8 Presentabon Matonal from June 23,1992 AP600 ACRS Testing Presentation P

O9 NRC Request for Additionalinformation Regarding the AP600 Testing Program 0.10 AP600 Testing to Support Design Cortrheation 0.11 AP600 Testing Schedule 0 12 Presentabon Matenal from December 14,1992 West nghouse NRC Meeting on AP600 Testiry 0 13 Westinghou .o Response to NRC Request for Additional Information on the AP600 Testing Program dated July 21,1992 0 14 Updated Testing Schedules for the AP600 Testing Program 0.15 Westinghouse Responce to NRC Request for Additional Informaton on the AP600 Testm) Program dated September 1,1992 0 16 Test Schedule for AP6,00 Automatic Deprescurizabon System Test - Phase 8 0.17 Presentat:on Matenal from the March 9-10.1993 Meetirg on the AP600 Testng Program 0 18 Matenal in Support of March 23-24,1993 WestinghouseJNRC Meeting on Containment Tests for AP600 (Test Spec additions. Test Matrix, Schet 0.19 Draft AP600 TestWitness Matnx 0 20 Prosentabon Material from the March 23 24, 1993 Meeting on the AP600 Containment Test Program 0 21 Updated Testtng Schedules for the AP600 Testing Program 0 22 Badground Matenals in Prmaration for the July 22-23 Meeting of ACRS Subcommitten on T/H Phenomena 0 23 Presentation Materials from the June 18,1993 Meeting on the AP600 Testing Program 1 0 24 AP600 Design and Design Certrication Test Program Overview, Revision 2 0.25 General Outhne for Quick look Data Roports on AP600 Tests 0 26 AP600 Design and Desiga Certrhcation Test Program Overview, Revision 3

0 27 Outhne for /sP600 Code Validation Process Steps Incorporating NRC Rmuest for S:ngle Blind Test Prcdctions 1

l 0 28 Presentaban Matonals from the December 10,1993 Meeting on APG00 Test Program Issues ,- t j l 0 29 AP600 Design Geecaban Test Program Overview, Revision 4

1. Air Flow Detta P Test i l 11 I

WCAP-13328. " Tests of Air Flow for Coolnig the AP600 Reactor Containment. Rev O' l

  • i

{ 12 WCAP-13329, " Tests of Air Flow for Ceohng the AP600 Reactor Containment. Rev 0"

           ,      13         WCAP-13330, " Natural Convection Cochng of AP600 Containment, Rm 0" I

14 WCAP-13331,' Natural Convection Cochrg of AP600 Contatnnwnt Rev 0"

w.~.- f TEST PROGRAM OVERVIEW ( PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET NRC-91-3650, NPP-APSL-910286 12 16 91 Mudey [ A y y ,- p Yes ET-N RC-91 -3656, NPP-APSL-924013 12292 Mudey K 15 4 b/ 5 LV

 $ TDW f n
  • Yes ET NRC-92 3663, NSRA APSL-92-0037 21492 Crutchheld wa aaty v3lu pgnn Yes ET-N RC-92-3664, NSRA-APSL-92-0047 22492 Mudoy vn i 4 L./

l No ET-N RC-92-3666 NSRA-APSL-92-0046 22492 Hasselberg ilso Availabie on Yes ET-NRC-92 3671 NSRA-APSL-92-0053 3492 Mudey Aperture Card Yes ET-NRC-92-3713, NSRA-APSL-92-0130 62592 Mudey Yes ET-NRC-92 3716, NSRA APSL-92 0133 63092 Mudey Yes ET-N RC-92-3750, NSRA-APSL-92-0189 91492 Mudey i No ET-NRC-92 3754, NSRA-APSL-92-0200 10592 Ward [ No ET-NRC 92-3768 NSRA-APSL-92-0239 11592 Murley Yes ET-N RC-92-3783, NSRA-APSL-92-0264 12 14 92 Murley f ( No ET-NRC-93-3799, NSRA- APSL-934010 11993 Mudey l No ET-N RC-93-3800, NSRA-APSL-93-0011 11993 Murley l [ No ET-NRC-93 3798, NSRA-APSL-93-0009 11993 Mudey r l No ET-N RC-93-3811, NSRA-APSL-93-0026 2293 Borchardt r No ET-N RC-93-3834, NSRA APSL-93-0065 3993 Borchardt l Yes ET-N PC-93-3841, NSRA-APSL-93-0076 31693 Borchardt No ET-N RC-93-3848, NSRA APSL-93-0093 32393 Borchardt l f l Yes ET-N RC-93-3845, NSRA-APSL-93 0090 32493 Borchardt No ET-N RC-934855, NSRA APSL-93-0109 41393 Borchardt No ET-N RC-93-3911, NS RA- APSL-93-0224 62893 Boehrieri f No ET-N RC-93-3910 NS RA-APSL-93-0223 62893 Borchardt No ET-N RC-93-3919, NSRA-APSL-93-0233 7793 Borchardt No ET-NRC-93 3946, NSRA-APSL-93-0305 81693 Borchardt I No ET-NRC 93 3947, NSRA APSL-93-0306 81893 Borchardt - I No ET-N RC-93-3976. NSRA-APSL-93-0360 92793 Borchardt i 1 l Yes ET-N RC-93 +029. NS RA- APSL-93-0492 12 16 93 Borchardt No NTD-NRo94 4078, DCP/NRC0017 3894 Borchardt Yes ET-N RC-92-3688, NSRA-APSL 92-00M 43092 Murley No ET-NRC-92-3688, NSRA-APSL-92-00M 43092 Murley Yes ET-NRC-92 3688, NSRA APSL-92-00M 43092 f Murley ( No ET-NRC-92 3688, NSRA-APSL-92-0094 43092 Murley ( l .===. , i

    "" ~

Westinghouse Electric Corporation Revision 5, March 22,1994 AP600 DESIGN CERTIFICATI< TABLE D TEST PROGRAM REFERENCES (

SUMMARY

OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO DESCRIPTION

2. Weter Film Fortnation Test 2.1 WCAP-13330. " Natural Convection Coohng of AP600 Contamment, Rev. 0" 2.2 WCAP-13331, " Natural Convoction Coohng of AP600 Containment, Rev. 0" 2.3 WCAP 13884, " Water Film Formation on AP600 Reactor Containment Surface", Revision 0 f 24 WCAP-13885," Water Film Formation on AP600 Reactor Containment Surface", Revision 0
3. Heated Plate Test 3.1 WCAP-12665," Test of Heat Transfer and Water Film Evaporation on a Heated Plate Simulating Cooling of the AP600 Reactor Containment" 7

.f 3.2 WCAP-12665," Tests of Heat Transfer and Water Film Evaporation on a Heated Plate Simulating Cooling of the AP600 Reactor Containment, Re i 3.3 WCAP-13341," Tests of Heat Transfer and Water Film Evaporation on a Heated Plate simulating Cooling of the AP600 Reactor Containment, Ra 3.4 WCAP-13330," Natural Convection Cooling of AP600 Containment, Rev. O' 35 WCAP-13331, " Natural Convection Coohng of AP600 Containment, Rev. 0" 3.6 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nucioar Plant Containments & Auxq 3.7 WCAP 13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxi

4. Bench Wind Tunnel Experiment 4.1 WCAP 13330, " Natural Convection Cooling of AP600 Containment, Rev. 0" 4.2 WCAP-13331," Natural Convection Cooling of AP600 Containment, Rev. 0"
 }           $, Condensation Tests - Bare Surface Upward 51          WCAP 13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydrauhc Transients for Nuclear Plant Containmerta & Auxii t

5.2 WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxili f S3 References for Basic Research Tests on Condensaton Performed in Support of the AP600 Design 5.4 J J. Barry, " Effects of Interfacial Structure on Film Condensation,* PhD Thesis (1987) 6, Condensation Tests - Bare Surface Downward . 61 WCAP-13246,"Westinghou e-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxil I 62 WCAP 13412. "Wwstinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxi

6. 3 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design
     .       7. Condensation Tests - Painted Surface Downward 7.1        WCAP 13307, " Condensation in the Presence Of A Noncondensable Gas - Experimental Investigation" 7.2        WCAP-13308, " Condensation in the Presence Of A Noncondensable Gas - Expenmental investigation"                                                l 7.3        WCAP-13412 " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transierts for Nuclear Plant Containments & Auxd 74         WCAP-13246," Westinghouse-GOTHIC: A Cornputer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxh
8. Condenssilon Tests - Light Noncondensibles 81 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design -

8.2 A. P. Pornsteiner, " Condensation in the Presence of Noncondentble Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thesisj l 83 i K. Huhtiniemi. "Condensaton in the Presence of Noncondensible Gas. The Effect of Surface Onentation," Prelim Thesis (1990) { i 1 84 l l K. Huhtiniorni," Condensation in the Presence of Noncondensble Gas: The Effect of Surface Orietation," Prelim Thests (1990) j l

_ ~ _ _ 1 TEST PROGRAM OVERVIEW l l x 1 ! 3 , , , PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE 0 lkU l l dp' Mii UHE Yes ET-NRC 92-3688 NS RA-APSL-92-0094 43092 Murley No ET-N RC-92-3688. NSRA-APSL.92-0094 43092 Murley l A i g n ^A ' ,^ ,= , , , , , Yes NTD- N RC-94 4056, DCP/NRC0002 2294 Borchardt M;u w; APOff ur() Og No NTD-NRC-94-4056, DCP/NRC0002 2294 Borchardt Yos NS-NRC-90-3525, NPAP-- APSL-90 0048 71690 Donatell Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Murley Yes ET-NRC-92 3G88 NSRA-APSL-92-0094 43092 Murley No ET- N RC-92-3688, NSRA APSL-92 0094 43092 Murley luddirgs" Yes ET-N RC-92-3726 / 31 92 Murley luildirgs" No ET-NRC-92 3726 73192 Murley Yes ET-NRC 92 3688, NS RA- APSL-92-0094 43092 Murley No ET NRC-92 3688, NSRA APSL-92-0094 43092 Murley I Iuildirgs" Yes ET-N RC-92-3726 73192 Murley luildirgs" No ET NRC-92-3726 73192 Murley No ET-NRC-93 3945, NSRA-APSL-93-0304 81693 Borchardt No ET-NRC 93-3945, NSRA APSL-93-0344 81693 Borchardt t iuildirv)s" Yes ET-NRC-92-3726 73192 Murley luildirgs" No ET NRC 92-372G 73192 Murley e No ET-N RC-93-394 5, NSRA APSL 93-0304 81693 Borchardt Yes ET-NRC-92 3688 NS RA- APSL-92-0094 43092 Murley No ET-N RC-92--3688, NSRA-APSL 92-0094 43092 Murley . }uildirgs" No ET-NRC 92-3726 73192 Murley , juildirgs" Yes ET-NRC-92 3726 73192 Murley No ET-N RC-93-3945 NS RA-- APSL 0304 81693 Borchardt No ET NRC-934014 NSRA APSL-93 0448 11 12 93 Borchardt No ET NRC-93-3945. NS RA- APSL 93 0304 81693 Borchardt r Yes ET NRC-93-3945, NSRA-APSL-93 0304 81693 Borchardt

                                             \

j -

l

       . - - ,            Westinghouse Electric Corporation                                                                                                                1 Revision 5, March 22,1994                                                          AP600 DESIGN CERTIFICATI(
                 ~ TADLE 8 -TEST PROGRAM REFT 1ENCES (S1,lMMARY OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMrrTED TO(

DESCRIPTION j

                                                                                                                                                                       ~q
9. Condensation Tests Stagnation Flow Conditions .

9.1 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design I 92 A. P, Pemsteiner, " Condensation in the Presence of Noncondensible Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thesis l . . j

10. Condensation Tests Stagention/ Light Noncondensibles 1

[ 10.1 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design {i 10.2 A. P. Pernsteiner," Condensation in the Presence of Noncondensible Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thesis

  ;               11. Condensation Tests - 2D Condensation'-

( 11.1 References for Basic Research Tests on Condensaton Performed in Support of the AP600 Design

12. Integral (small scale) Tests Phase 1 (Feasit>ility)-

12.1 WCAP.12667," Test of Heat Transfer and Water Film Evaporation From a Simulated Containment To Demonstrate the AP600 Passive Containmo 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-13%to," Tests of Heat Transfer and Water Film Evaporation from a Simulated Containment to Domonstrate the AP600 Passive Containme 12.5 WCAP.12667," Tests of Heat Transfer and Water Film Evaporation from a Simulated Containment to Demonstrate the AP600 Passive Containme 12.6 WCAP-13412,
  • West;nghouse-GOTHIC: A Computer Code For Analysos of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxili
  ,               12.7      WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxili

(

  ;              13. Integral (stnell scale) Tests - Phase 2A (Extension Tests) 13 1      WCAP 13316. " Integral Containnent Cochng Test Extension - Test Specification, Rev. 0" 13.2      WCAP-13315, " Integral Containment Cooling Test Extension - Test Specifcation, Rev. 0" 13.3      WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxil, 13.4      WCAP-13246, "W.:stinghouse-GOTHIC: A Computer Code For Analyses of Thermai Hydraulic Transients for Nuclear Plant Containments & Auxili i
14. Integral (small scale) Tests - Phase 2 (Continuation Tests) l 14.1 WCAP 13315. " Integral Containment Cooling Test Extension - Test Specificaton, Rev. 0*

k- 14.2 WCAP-13316, " Integral Containment Cooling Test Extension - Test Specification, Rev. 0" 14.3 WCAP-13246, " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxiit

  &.             14 4      WCAP 13412, " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermai Hydraulic Transients for Nuclear Plant Containments & Auxil 15.1/8th Scale Heat Transfer Tests - Phase 1 (Baseline) 15 1      WCAP-13267, " Test Specification: Large Scale Passive Containment Coolity Tost, Rev.1" 15.2      WCAP-13268. 7est Specification" Large Scale Passrve Containment Coofing Test, Rev.1" 15.3      WCAP 13244 ' Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nxlear Plant Containments & Auxilc 154       WCAP 13412. " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & AuxiL l             15 5      WCAP-13566. "AP6001/8th Large Scale Passive Containment Coohng Systern Heat Transfer Test Baseline Data Report." Rev. O,
    \*

15 6 WCAP 13567 "AP6001/8th Large Scale Passive Containment Coohng System Heat Transfer Test Baseline Data Report," Rev. O

                                                                                                                                           "%  M
TEST PROGRAM OVERVIEW l

l p= - l I ,, PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE A% ANb TEC

                  .m .- .

CbId)fdh No ET NRC 93 3945, NS RA- APSL-93-03N 81693 Dorchardt 4 No ET-N RC-93-4014, NS RA-APSL-93-0448 11 12 93 Borchardt Alen A t r_;_

                        'mu UT)

Ap0ff UTn (!y No ET-NRC-93 3945, NSRA APSL-93-0304 81093 Borchardt No ET-N RC-934014, NSRA- APSL 0448 11 12 93 Borchardt I-No ET-N RC-93-394 5, NS RA. APSL-93-03N 81693 Borchardt l I s hng Systom" Yes NS-NRC 90-3525, NPAP-APSL-90-0048 71690 Donatell Yes ET- N RC-92-3688. NSRA APSL-92 00N 43092 Murley No ET-N RC-92-3688, NS RA- A PSL-92-0094 43092 Murley bry System, Rev. 0" Nu ET-NRC-92 3688. NSRA-APSL 92-0094 43092 Murley kng Systorn, Rev l' Yos ET NRC-92-3688. NSRA-APSL-92 00N 43092 Murley .. Idirgs" No ET NRC-92-3726 73192 Murley khngs" Yes ET-N RC- 92-3726 73192 Murley No ET NRC 92-3688 NSRA-APSL 92-00N 43092 Murley Yes ET NRC-92-3688, NSRA-APSL-92 00N 43092 Murley kinvjs" Na E T NRC-92-3726 73192 Murley kiirgs" Yes ET-N RC-92-3726 73192 Murley I Yes ET-NRC-92 3688, NSRA.APSL-92-0094 43092 Murley No E.T-NRC 92 3638 NSRA- APSL-92-0094 43092 Murley dirgs" Yes ET-NRC 92 3726 73192 Murley , ding s" No ET-NRC-92 3726 73192 Murley Yes ET-N RC-92-3688, NS RA' APS L 00N 43092 Murley I No ET.NRC-92 3688, NSRA- APSL-92-00N 43092 Murley thrys* Yes ET-N RC-92-3726 73192 Murley i ing s" Na EI-NRC-92 3706 73192 Murley Yes ET-NRC 93 3301, NSRA-APSL-93-0012 12593 Murley No ET NRC43-3801, NSRA APSL 93 0012 12593 Murley I O

                  /

i 1 _ j - ..

    --~ +

Westinghouse Electric Corporation hvision 5, march 22,1994 AP600 DESIGN CERTIFICATI _TADLE 8 - TEST PROGRAM REFERENCES (

SUMMARY

OF WESTINGHOUSE APCOO TEST PROCRAM RELATED MATERIALS TRANSMITTED T DESCRIPTION 16.1/8th Scal. Heat Transfar Test Phase 2 (Confirmatory) 16.1 WCAP-13267, ' Test Specihcation: Large Scale Passive Containment Cooling Test Rov.1" 16.2 WCAP.13268," Test Specification" Largo Scale Passive Containment Coohng Test. Rev 1" 16.3 Phase 2 Large Scale Test Matrix Rationalo; Information in Support of Request for Addtbonal Information on the AP600 Design (RAI 480.12) 16.4 Ouick Look Data R+ port for AP600 PCCS Largo Scalo Phase 2 Tests: Constant Prossure Tests (Tests 202.3 and 203.3) 16.5 Facilrty "as-buitt" Drawings for AP600 PCCS Large Scale Test Facility 16 6 Ouick Look Data Report far AP600 PCCS Largo Scale Phase 2 Tests: Tests 212.1 and 213.1 16.7 Heat Sink Data for AP600 PCCS Large Scalo Phase 2 Test Facihty 16 8 Proposed Initial Conditions Data and Forcing Functions for Large Scale Phase 2 Test 2201 16.9 Ouick Look Data Rnport for AP600 PCCS Large Scale Phase 2 Tasts: Tests 214.1 and 2151 16.10 Quick Look Data Report for APC40 PCCS Large Scale Phase 2 Tests: Tests 217.1 and 218.1 16 11 Test Description Package for AP600 PCCS Large Scalo Phase 2 Test Test 220.1 16.12 Quick Look Data Rrport for AP600 PCCS Large Scalo Phase 2 Tests: Test 216.1 16.13 Quick Look Data Rnport 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 I 16 15 l Presentation Matenals from the February 23-24,1994 Mooting on AP600 PCCS Tests and Analysis _17. Water Distribution System Te.st - Phase 1 (20ft Diameter) 17 1 WCAP 13353, " Passive Containment Coohng System Water Distnbution Phase 1 Test Data Report, Rev. 0" 17 2 WCAP 13354, " Passive Containment Coohng System Water Distnbution Phase 1 Test Data Report, Rev. 0" 17.3 WCAP-13291, "Passrve Containmont Coohng System Water Drctrbution Test, Rev. 0" 17.4 WCAP-13290, " Passive Containment Coohng System Water Distnbution Test, Rev. 0" [ 17.5 WCAP-13293, "ConstructiorvTest Plan For the Passive Containment Cochng System Test Articles, Rev. 0" 17 6 WCAP-13292, " Construction, Test Plan For the Passhe Containment Cochng System Test Articles, Rev. 0" 17.7 WCAP-13412,"WestinghousmGOTHIC: A Computer Code For Analyses of Thermal Hydrauhc Transients for Nuclear Plant Containments & Auo 17.8 WCAP-13246, " Westinghouse-GOTHIC: A Computar Code For Analyses of Therrnal Hydraulic Transients for Nuclear Plant Containments & Auxd

18. Water Distribution System Test Phase 2 (118th Sector) 18.1 WCAP.13291. " Passive Containment Coohng System Water Distnbution Test, Rev. 0" 18.2 WCAP-13297, "PCS Water Detnbution Test Phase ll Test Data Report" 18 3 WCAP 13296, "PCS Water Distribution Test Phase il Test Data Report" i

j 18 4 WCAP 13290, " Passive Containment Coobog System Water Distnbution Test, Rev. 0" 4 18 5 WC AP 13293, " Construct >ortTost Plan For the PassNe Containment Cochng System Test Articles, Rev. 0" f 18 6 j WC AP-13292. "ConstructmTest Plan For the Passive Containment Cochng System Test Articles, Rev. 0" t 18.7 yl WCAP-13246. "Westarghouse-GOTHIC' A Computer Code For Analysos of Thermal Hydraulic Transient i, 18 8 f WCAP-13412. "Westnjhous& GOTHIC A Computer Code For Analyses of Thermal Hydrauhc Transients for Nucle e, .e. um.m.ms A

N TEST PROGRAM OVERVIEW D) r l { PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley ( A f},Q ~)"* [- p No ET-NRC 92-3688, NSRA-APSL-92-0094 43092 Mudey ( APFA-f-UN,r - , i A. Yes ET-N RC-93-3961, NS RA-APSL-93-0334 92393 Borchardt Qj\ , Yes ET-N RC-93-3981, NSRA-APSL-93-0380 to 4 93 Borchardt Yes ET-NRC-93-3983, NSRA-APSL-93-0381 10693 Borchardt ( 0 /Wailable en Yes ET-N RC-93-3991, NSRA-APSL-93-0394 10 15 93 Borchardt

      'WW Gard                y ,3          gy NRC-93-3997, NSRA-APSL-93-0405      10 21 93  Borchardt l                              No           ET NRC-93-3998 NS RA-APSL-93-0406       10 22 93  Borchardt Yes          ET-N RC-93-4006, NSRA-APSL-93-0421      10 29 93  Borchardt I                                                                                                          !

Yes ET-N RC-93-4012, NS RA-APSL-93-0446 11 12 93 Borchardt  ; ( Yes ET-NRC 93-4030, NSRA-APSL-93-0495 12 20 93 Borchardt l Yes ET-NRC-M-4035, NSRA-APSL-94-0002 11894 Borchardt r l Yes NTD-NRC-94-4053, SAL /NRC0037 12894 Borchardt I ( Yes NTD-NRC44-4062, DCP/NRC0004 21194 Borchardt l i [ Yes NTD-NRC-94-4067, DCP/NRC0009 22394 Borchardt { f I l Yes ET-NRC-92-3688, NSRA APSL-92-0094 43092 Muriey i No ET-NRC-92-3688, NSRA-APSL-92 0094 43092 Mudey ( No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley ( No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL 92-0094 43092 Murley %uildings" No ET-N RC-92-3726 73192 Murley $uildings" Yes ET-N RC-92-3726 73192 Murley f No ET-N RC-92-3688, NSRA-APSL-92 0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley f Yes ET-NRC-92-3688 NSRA-APSL-92-0094 43092 Murley f Yes ET-N RC-92-3688 NS RA-APSL-92-0094 43092 Murley No ET NRC-92-3688, NSRA-APSL-92-0094 43092 Murley f Yes ET-N RC-92-3688 NSRA-APSL-92-0094 43092 Murley hu:kfings" Yes ET-N RC-92-3726 73192 Murley p,5- No ET-NRC-92-3726 73192 Muriey

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Westinghouse Electric Corporation nevision s, March 22,1994 APG00 DESIGN CERTIFICATI< TADLE 8 TEST PROGRAM REFERENCES (GUMMARY OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSA4ITTED TO I DESCRIPTION

19. Water Distribution System Test . Phose 3 19.1 WCAP-13292," Construction / Test Plan For the Passive Containment Cooling System Test Arbcles, Rev. 0" 19 2 WCAP 13293. "ConstructiorVTest Plan For the Passive Containment Cooling System Test Artcles, 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 Distibution Test" 19 5 WCAP 13960,"PCS Water Distrbution Phase 3 Test Data Report," Revision 0 19 6 WCAP-13961,"PCS Water Distrbubon Phase 3 Test Data Report," Revision 0
                                                                                                                                                        ..i i         20. Wind Tunrwl Test - Phase 1                                                                                                               g 20.1     WCAP 13294, " Phase 1 Wind Tunnel Testing For the Westinghouse AP600 Reactor" 20 2     WCAP 13295, " Phase I Wind Tunnel Testing For the Wesunghouse AP600 Reactor" 20 3     WCAP-13318," Passive Containment Coding 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 & Auxf 20.5     WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxf l         21. Wind Tunnel Test . Phase 2                                                                                                                  -

21.1 WCAP-13318. " Passive Containment Coding System Wind Tunnel Test Specification, Rev. 0" y 21.2 WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxi 21.3 WCAP-13246,"Westinghoum-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Aux! 21.4 WCAP-13323, Rev. O, " Phase ll Wind Tunnel Testing for the Westinghouse AP600 Roactor" 21 5 WCAP-13324, Rev. O, " Phase 11 Wind Tunnel Testing for the Westinghouse AP600 Reactor"

22. Wind Tunrml Test . Phase 4 A f'

4 22.1 WCAP-13318. " Passive Containment Cooling System Wind Tunnel Test Specihcation, Rev. 0" k 22.2 WCAP-13757,

  • Wind Tunnel Phase 4A Test Plan, investgation of the Hgh Reynokis Number Behavior of the Westnghouse AP600 Systern,"

f 22 3 WCAP-13756," Wind Tunnel Phase 4A Test Plan, investgabon of the High Reynokis Number Behavior of the Westnghouse AP600 Systern," J

23. Wind Tunrwl Test . Phase 48 3
!         23.1     WCAP-13318, " Passive Containment Cooling System Wind Tunnel Test Specihcation, Rev. 0" 23.2     WCAP 14005," Wind Tunnel Phase 4B Test Plan, investgation of the Effects of Sitng on the Wind Behavior of the Weshnghouse AP600 System
,         23 3     WCAP-14006. " Wind Tunnel Phase 4B Test Plan, Investgabon of the Effects of Sibng on the Wind Behavior of the Westinghouse AP600 System k

4 24. PRHR Heat Exchanger Test - Phase 1 24.1 WCAP-12666, "AP600 Passive Resdual Heat Removal Heat Exchanger Test. Test Repoit"

25. PRHR Heat Exchanger Test - Phase 2 51 WCAP-13368. "Passrve RHR Heat Exchanger Test Extension. Rev. 0" f 25 2 WCAP-13369. " Passive RHR Heat Exchanger Test Extension, Rev. 0" n

25 3 WCAP-13573. "AP600 Passive Resdual Heat Exchanger Test Final Report" {' 25 4 WCAP-12980, Rev.1, "APG00 Passive Resdual Hoat Exchanger Test Final Report" l4

    .- ~-

1 3N TEST PROGRAM OVERVIEW JRC) PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE

             /\blS'Tm             Yes           ET-NRC-92 3688 NS RA- APSL-92-00N       43092      Murloy
         /k        @l J.Onr----. No            ET-N RC-92-3688, NSRA-APSL-92-0094      43092      Murley h[p                Yes           ET-NRC 93-3952, NSRA-APSL 93 0318       81993      Borchardt          j No            ET-NRC-93-3952, NSRA-APSL-93-0318       81993      Borchardt
           ' /M l Jab l0 %        Yos           NTD-NRC-94-403, DCP/NRC0002             2294       Borchardt U Y Cold         No            PITD NriC-94-405G, DCP!NRC0002          2294       Borchardt Yes           ET-N RC-92-3688, NSRA-APSL-92-00M       43092      Mu ley No            ET-N RC-92-3685, NSRA-APSL-92-00M       43092      Muriey No            ET NRC-92-3688, NSRA-APSL-92 0094       43092      Murley ary Buildirys'                     No            ET-NRC-92 3726                          73192      Murley ary Buildirgs"                     Yes           ET-N RC-92-3726                       l 7 3192     Murioy No            ET-NRC 92 3688, NSRA-APSL-92-0094       43092      Murley ary Buildirys"                     No            ET-N RC-92-3726                         73192      Murley ary Builduye                       Yes           ET-NRC-92 3726                          73192      Murley Yes           ET-NRC 92 3753, NSRA APSL-92 0198       10292      Murley No            ET-NRC-92 3753 NSRA- APSL-92-0198       10292      Muiley No            ET-N RC-92-3683, NSRA-APSL-92-0094      43092      Murley No            ET-NRC 93 392G, NSRA-APSL-93-0250       71593      Borchardt Yos           ET-NRC 93 3926, NSRA-APSL-93-0250       71593      Borchardt No            ET NRC-92-3688, NSRA-APSL-92-0094       43092      Murley Yes           NTD NRC-94 4082                         32194      Borchardt No            NTD-N RC-M 4082                         32194      Borchardt Yes           N S -N RC-90-3525, NPAP-APSLMOO48       71690      Donatell Yes           ET-NRC 92-3730, NSRA-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   Muriey Yes           ET-NRC-92 3779, NSRA APSL-92-0259       12 15 92   Murley l

I

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v )  ; -

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\ n -. , Westinghotisc Electric Corporation Revision 5, March 22,1994 APG00 DESIGN CERTIFICATTJ { TABLE 8 - TEST PROGRAM REFERENCES (

SUMMARY

OF WESTINGHOUSE AP600 TEST PROGRAM RE!ATED M ATERIALS TR ANSMITTED TO DESCRIPTION 4

26. Automatic Depressurization System Test Phase A (Sparger) 26.1 WCAP-13343, "AP600 Autornatsc Depresunzation System Test, Rev. 0" ,

26.2 WCAP-13342,"AP600 Automat >c Doprossurization System Test, Rov 0" 26 3 Presentation Material from the Apnl 20,1993 Meeting on the AP600 ADS Tests at the VAPORE Facility , f 26 4 Presentation Material from the May 4,1993 Maetirg to de*. cuss tha AP600 ADS Phase A Test Results 26 5 Prosentation Matenals from the May 26-27,1993 Meeting on the AP600 ADS Tosts

27. Automatic Depressurization System Test - Phase B -

27.1 WCAP-13343,"AP600 Automate D+resurization System Te;t Rev. 0" i 27.2 WCAP 13342, *AP600 Automatic Depressunzation System Test, Rev 0" 27.3 Presnritation Matonal from the April 20,1993 Meeting on the AP600 ADS Tests at the VAPORE Facility l 1 27 4 AP600 Automatic Depressunzaton System Phase B Test Matnx, Revision 1 27.5 Preliminary Facihty Oesign Drawings for the AP600 ADS Phase B Tests 27.6 Presentation Materials from the May 26-27,1993 Meeting on the AP600 ADS Tests { 27.7 AP600 Autornatic Deprenunzaton System Phase B Test Matnx, Revision 1 A f 27.8 Prosentation Matonals from the January 25,1994 Meeting on AP600 ADS Design Certihcaton Test Plans

28. Core Makeup Tera Test t 28.1 WCAP-13345, "AP600 Core Make Up Tank Tect Specification, Rev. 0*

28.2 Matenalin Support of February 25,1993 Westinghousa'NRC Meeting on CMT Tests for AP600 (Test Matrix, Instrument List, Drawings) 28.3 Prosentation Material from the February 25,1993 Westinghous4NRC meeting on tho AP600 CMT Tests 28 4 Transmrtial of Drawing of Steam Distnbuter for AP600 Core Makeup Tank Test 28.5 WCAP-13345, "AP600 Core Makeup Tank Test Specihcation", Revision 2 28 6 WCAP 13963, " Scaling Loge for the Core Makeup Tank Test," Revision 0 l f 28.7 WCAP-13975," Scaling Logic for the Core Makeup Tank Test." Revision 0 f ] 28 8 Rosponse to Roquests for Ad%onal information on the AP600 Core Makeup Tank Tests 1 [ 28.9 Presentation Materials from the March 14,1994 Monting on AP600 Coro Makeup Tank Tests and Analysis j

29. DNBR Tests l j

29 1 WCAP 12488, " Westinghouse Fuel Cnteria Evaluation Process" l 29.2 Test Matrix for AP600 Dwarture from Nucleate Boding Tests

                                                                                                                                                           ]

l l

                                                                                                                                                      \     l V

i 1 l l

b TEST PROGRAM OVERVIEW l h r PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE ANSTEC LPERTilRE "o ET-NRC-92 3688 NSRA-APSL-92-0041 43092 Morley l (' A R D Yes ET-NRC-92 3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-93-3877, NSRA-APSL-93-0159 5393 Borchardt 20 Avall3b !O Ofi Yes ET NRC-93-3879, NSRA-APSL-93-0166 5593 Borchardt rnpu< iu s v w w a l Yes ET-NRC-93-3881, NSRA- APSL-93-0197 61 93 Borchardt h No ET-N RC-92-3688, NSRA-APSL-92 0094 43092 Murley [ Yes ET-N RC-92-3688, NSRA APSL-92-0094 43092 Murley Yes ET-NRC-93-3877, NS RA-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-NRC 93-3881, NSRA-APSL-93-0197 6193 Borchardt [ Yes ET-N RC-93-3881, NSRA-APSL-93-0197 6193 Borchardt [ Yes NTD-NRC-94-4050, NSRA-APSL-94-0030 12594 Borchardt L No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-93-3823, NSRA-APSL-93-0042 21893 Borchardt Yes ET-N RC-93-3829, NS RA-APSL-93-0053 22593 Borchardt Yes ET-N RC-93-3944, NS RA-APSL-93-0303 81693 Borchardt No NTD-NRC-94 4068, DCP/NRC0010 22294 Borchardt Yes NTD-NRC-94-4068, DCP/NRC0010 22294 Borchardt No NTD-NRC-94 4068 DCP/NRC0010 22294 Borchardt No NTD-NRC-94-4076 DCP/NRC0015 3444 Borchardt Yes NTD-NRC 94-4081 32194 Borchardt f~ l b - 4 Yes NS NRC-90 3482 4290 Wilson Yes ET-N RC-93-3984, NSRA-APSL-93-0385 10893 Borchardt i t f ( - . Yl ll )

                                                                                                              )

Westinghouse Electric Corporation nevision s, March 22,1994 AP600 DESIGN CERTIFICATE TABLE 8 -TEST PROGRAM REFERENCES (

SUMMARY

OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATER 1ALS TRANSMirTED TO DESCRIPTION

30. Low Pressure 1/4 Height integral Systems Tests 30.1 Scahng Report on Glass Model of the AP600 30.2 WCAP 13234 "AP600 Long Term Cooling Test Spec 4fication, Rev. 0 30.3 WCAP-13283, *AP600 Long Term Cooliry Test Specificabon, Rev,0" 30,4 Draft Scafing Analysis for the OSU AP600 Integral Sptoms Test 30.5 Materialin Support of Westinghous6NRC Meoting on OSU Test Prcgram for AP600 (Test Schodule. Draft Scaling Report, Test Specification Ret Matnx and Facility Design Drawirgs) 30.6 Prosentation Material from December 9-10.1992 WestinghousNNRC Meetings on AP600 Tost Program 30.7 Component and Piping Drawing for the AP600 Long Term Cooling Tests 30.8 WCAP-13283 Rnvision 1. "Long Tarm Cooling Test,"

30.9 WCAP-13234 Revision 1, "Long Torm Cooling Test," 30.10 Response to INEL Roquests for Information regarding OSU Long Term Cooling Test Facility (Requests dated Apn! 14,1993 and May 12,1993) 30.11 RELAP5/ MOD 3 input Filo Notebook for OSU/AP600 Conponents 30 12 Dratt Scaling Analysis for the OSU AP600 Integral System and Long Term Cooling Test Facility I 30.13 Facility Drawings and Piping and Instrumentation Diagrams for the AP600 Lorg Term Cooling Test Facikty at Oregon State University 30.14 Presentation Matenals from the September 20,1993 Meeting on AP600 Low Pressure Intngral Systerns Tests at Oregon State Unrversity 30.15 Draft Scahng Anahsis for the AP600 Core Makeup Tank Separate Effects Tests

31. Full Pressure Full Height Integral Systems Tests 31.1 WCAP-13277. " Scaling Design and Venfication of SPES-2, the Italian Experimental Facihty Simulator of the AP600 Plant" 31.2 WCAP 13278,"Scahry Design and Venficaton of SPES-2, the itahan Expenmental Facihty Simulator of the AP600 Plant" 31.3 NRC Request for AddibonalInformation Related to SPES 2 Test Facihty 31.4 Matenalin Support of Westinghouse,NRC Meeting on SPES Test Program for AP600 (Test Schedule. Draft Scaling Report, Draft Test Specificat) 31.5 Presentation Matenal from Docernber 0-10,1992 Westinghouse /NRC Meetings on AP600 Test Program

( 31.6 Component and Piping Drawings for the SPES-2 Facihty 31.7 Presentation Material from the April 22,1993 Meeting on the AP600 Integral Systems Tests at SPES-2 Facility 31.8 WCAP 13278 Revision 1 " Scaling, Design, and Verst cation of SPES 2 The Itahan Expenmental of the AP600; Scanng Update" 31.9 WCAP 13277 Revision 1, "Scahng Design, and Verification of SPES-2, The Itahan Expenmental of the AP600; Scahng Update" 31.10 SPES-1 Pump Charactenzation SIET NT/54 31.11 Response to INEL Roquest for SPES-2 Information Clanficahon MGO-29-93

                                                                     ~

31.12 SPES-1 System Desenption, SIET NT/32 31.13 Information on Test Coswitions for AP600 Testry Performed at the SPES-2 Test Facihty r s.

IN TEST PROGRAM OVERVIEW lC) [ T PROPRIETARY TRANSN11TAL LETTER DATE ADDRESSEE APEElnigg p No NPAP-APSL-91 -0095 3591 Sheron Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey MI' AVik-W DD No ET-NRC-92 3688, NSRA-APS! 02-0094 43092 Mudoy Yes ET NRC 92-3715, NSRA-APSL-92 0132 7792 Mudey t, Updated trutrurrontabon List Test Yes ET-N RC-92-3775, NSRA-APSL-92-0250 11 24 92 Morley Yes ET-NRC-92-3785, NSRA APSL-92-0268 12 17 92 Mudey Yes ET-NRC 93-3330, NSRA-APSL-93-0062 3393 Borchardt No ET-N RC-93-3883, NSRA- APSL-93-0169 51193 Borchardt Yes ET-NRC-93 3883, NSRA APSL-93-01G9 51193 Borchardt Yes ET-NRC 93-3901, NSRA-APSL-93-206 61093 Borchardt Yes ET-N RC-93-3932, NSRA-APSL 93-0273 72793 Wilson Yes ET-N RC-93-3933, NS RA-APSL-93-0274 72893 Wilson Yes ET-N RC43-3969, NS RA- APSL-93-0350 91793 Borchardt Yos ET NRC-93-3993, NSRA-APSL-93-0401 10 15 93 Boichardt Yos ET-N RC-93 4031, NSRA-APSL 93 0497 12 20 93 Borchardt Yes ET-N RC-92-3685, NSRA-APSL-92 0082 4392 Mu, ay No ET-NRC-92 3685, NS RA- APSL-92-0082 4392 Mudey Yes ET-N RC-92-3749, NSRA-APSL-92-0188 91492 Murtey ) Yes ET-NRC-92 3776, NSRA-APSL-92 0251 11 24 92 Murley Yes ET-N RC-92-3785, NSRA APSL 92-0268 12 17 92 Marley Yes ET-N RC-93-3825, NSRA- APSL-93-0046 22393 Borchardt Yes ET-N RC-93-38 77, NSRA APSL-93-0159 5393 Borchardt No ET-N RC-93-3833, NSRA-APSL-93-0169 R 1193 Borchardt Yes ET NRC-33 3833 NSRA-APSL-93-0169 51193 Borchardt No ET-NRC-93 3943. NSRA APSL-93-0300 81293 Borchardt I No ET-N R C-93-3943, NSRA-APSL-93 0300 81293 Borchardt No ET-N RC43-3943, NSRA-APSL 93-0300 81293 Borchardt Yes NTD-NRC %4070, DCP.NRC0012 , 93 Borchardt O /

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Westinghouse Electric Corporation Revision 5, March 22,1994 AP600 DESIGN CERTIFICATE l [ TADLE 8'-TEST PROGRAM REFERENCES (

SUMMARY

OF WEST 1NGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMrrTED TS DESCRIPTION

32. Other Tosts 32.1 WCAP-12668,"AP600 High Inertia Rotor Testing - Phase I, Test Report" 32.2 WCAP-13299,"RCP Air Model Test Report, Rev. 0*

32.3 WCAP-12648, "AP600 incore Instrumentation System Electromagnetx: Interference Test Report, Rev.1"

    ~

32 4 WCAP-13352, " Studies of Hydraulic Phenomena in the Reactor Vessel Lower Plenum Region - Test Report, Rev. 0" 32.5 WCAP-13305, Studies of Hydraulic Phenomena In Reactor Lower Plenum Region - Test r$lan" 32.6 WCAP-13298,"RCP Air Model Test Report, Rev,0* t 32.7 WCAP-13322, "AP600 incore instrumernation System Electromagnetic Interference Test Report, Rev, 0" 32.8 WCAP 13312,

  • Journal Bearing Test - Task 2 Test Specification" i,

32.9 WCAP-13313, "Joumal Bearing Test - Task Plan For the DOE Phase ll High Inertia Rotor Test Program" 32.10 WCAP 13320,"AP600 Hgh Inertta Rotor Testing Phase 2 Report, Rev. 0" , 32.11 WCAP-12668, "AP600 High inertta Rotor Testing Phase 1 Test Report, Rev,1" ] 32.12 WCAP-13319. "AP600 High Inertia Rotor Testing Phase 2 Roport, Rev. 0" 32.13 WCAP-13288, " Passive Core Cooling System Check Valve Test Specification, Rev. 0" 32.14 WCAP-13284, " Test Plan For the Passive Core Coohng System Check Vatve 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 Vane Test Final Report, Rev. 0" 32 17 WCAP-13285," Test Plan For the Passive Core Cooling System Check Vane Test, Rev. 0" 32 18 WCAP-13321, "AP600 High inertia Rotor Testing Phase 1 Report, Rev. 0" 32.19 WCAP 13286, "AP600 Passive Core Cooling System Check Valve Test Final Report, Rev. 0" 3220 WCAP-13289, " Passive Core Cooling System Check Vane Test Specifration, Rev. 0" 32.21 WCAP-13310. " Journal Bearing Test - Task 1 Test Specification" f 32 22 WCAP-13351,

  • Studies of Hydraulic Phenomena in the Reactor Vessel Lower Plenum Region - Test Report, Rev. 0" k

3223 WCAP-13306, " Studies of Hydraulic Phenomena in Reactor Vessel Lower Plenum Region - Test Plan" 32 24 WCAP-13309, "Joumal Bearing Test - Task 1 Test Specification" b 32.25 WCAP-13487, Rev. O,"Hgh inertia Rotor Phase 3. Task 1 Test Report" 32.26 WCAP 13488, "High Inerba Rotor Phase 3, Task 1 Test Roport" I. g, 32.27 WC AP-13560, " Advanced Plant Check Valve Study", Rev. 0 32.28 WCAP 13743,"He.vy Water Reactor Facihty Project Phase 1 AP600 Small Scale Passive Containment Coohng System Test ' Dry' Test Results 91-0021" "' 3229 WCAP-13742," Heavy Water Reactor Facihty Project Phase i AP600 Small Scale Passrve Containment Coohng System Test ' Dry' Test Results j 91-002'" l 32 30 WCAP-13726, " Heavy Water Reactor Facabty (HWRF) Large Scale Passive Containment Coohng System Baseline Test Data Report HWRF-92d 32 31 WCAP-13728, " Heavy Water Reactor Facihty (HWRF) Small Scale Containment Cooling System Test Final Report HWRF-RPT-92-003, Revisiod 32.32 WCAP-13733," Heavy Water Reactor Facihty (HWRF) Small Scale Containment Coohng Test Prehminary Series 2 Test Results HWRF-RPT 92 f 32.33 WCAP 13725," Heavy Water Reactor Facihty (HWRF) Large Scale Passive Containment Cooling System Baseline Test Data Report HWRF-RPj 32.34 WCAP-13727. "Hoavy Water Reactor Facihty (HWRF) Small Scale Containment Cochng System Test Final Report HWRF-RPT-92-003, Revisiod

          .~ -

1

)N TEST PROGRAM OVERVIEW IRC) PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes NS-N RC-90-3 525, NPAP-APSL-90-0048 71690 Donatell p hIgCp No ET-NRC42-3G88 NSRA-APSL 92-0094 43092 Mudey O, % Q T*j j p ~ - - - Yes ET-N RC-92-3688, NS RA- APSL-92-00M 43092 Mudoy s . J (] A f) p No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey l Yes ET-NRC-92 3688, NS RA-APSL-92-0094 43092 Mudey So AvaHabM Cn Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudoy

 96iiul o ygrd No          ET NRC-92 3688, NS RA- APSL-92-00M    43092 Murley No          ET-N RC-92-3688, NSRA-APSL-92-00M     43092 Mudey Yes         ET-N RC-92-3688, NSRA-APSL 92-00M     43092 Mudey No          ET-N RC-92-3688, NSRA-APSL 92-00M     43092 Murley Yes         ET-N RC-92-3688, NS RA- APSL-92-00%   43092 Mudey Yes         ET-NRC-92 3688, NSRA-APSL-92-00M      43092 Murley Yes         ET NRC-92-3688, NSRA-APSL 92-00M      43092 Murley Yes         ET-N RC-92-3688, NSRA-APSL 92-00M     43092 Murley No          ET-N RC-92-3683, NSRA-APSL-92-0094    43092 Murley No          ET-N RC 3688. NSRA-APSL-92-0094   43092 Murley No          ET-NRC-92 3688, NSRA-APSL-92-00M      43092 Murley r-No          ET NRC-92-3688, NS RA- APSL-92-0094   43092 Mudey Yes         ET-N RC-92-3688. NSRA-APSL-92-00M     43092 Murley No          ET-NRC 92-3688, NSRA-APSL 92-0094     43092 Mudey No          ET-N RC-92-3688, NS RA-APSL-92-00M    43092 Mudey Yes         ET-NRC-92 3688, NSRA-APSL-92-0094     43092 Mudoy No          ET-NRC 92-3688, NSRA-APSL-92-0094     43092 Murley Yes         ET-N RC-92-3688, NS R A-APSL-92-00M   43092 Murley Yes         ET-NRC-92-37S3, NSRA-APSL-92-0198     10292 Mudey No          ET-N RC-92-3753, NS RA- APS L-92-0198 10292 Mudey No          ET-N RC-93-3801, NS RA-APSL-91-0012   12593 Murley

>plcable to the HWRF Project NPR-RPT- No ET-N RC-93-3903, NSRA-APSL-93-0208 61493 Borchardt

plete to the HWRF Project NPR-RPT- Yes ET- N RC-93-3903, NS RA- APSL-93-0200 61493 Borchardt i, Revision 1 No ET-N RC-93-3903. NS RA- APSL-93-0208 61493 Borchardt No ET NRC-93-3903 NSRA APSL-93-0208 61493 Boichardt 1

No ET-N RC43-3903. NSRA APSL-93-0208 61493 Borchardt l2-004,* Revision 1 Yes ET-N RC-93-3903 NSRA-APSL-93-0208 61493 Borchardt Yes ET-NRC 93 3903, NSRA-APSL-93-0208 61493 Borchardt 9 033/o/ a- - -

Westinghouse Electric Corporation nevision s, March 22,1994 APG00 DESIGN CERTIFICATI TADLE 8 TEST PROGRAM REFERENCES (SUMMdLRY OF WESTINGHOUSE APCOO TEST PROGRAM RELATED MATERIALS TRANSMITTED TO DESCRIPTION 32 35 WCAP 13732, " Heavy Water Reactor Facrirty (HWRF) Small Scale Containment Cookng Test Preliminary Series 2 Test Results HWRF RPT 92-f 32 36 WCAP-13758, "Hgh inertia Rotor Test Phase 3 Report," June,1993 32.37 WC AP-13759, "Hgh Inortia Rotor Test Phase 3 Report " June,19<J3 32.38 WCAP-13415, "Hgh Inerta Rotor Test 3 Task 1, Test Specihcation," 32 39 WCAP-13413, "RCP Hydraulo Flow Test Prospectus," 32 40 WCAP-13420, "Hgh inetta Rotor Tect Phase 3 Test Plan," 32.41 WCAP-13419, "Hgh Inertia Rotor Test Phase 3 Test Plan," 32 42 WCAP 13414, "RCP Hydraule Flow Test Prospodus " 32 43 M H Kim. "Modelhng of Condensation Heat Transfer in a Roactor Containrnent," PhD Thesis (1985) e n 1 l 4

)N TEST PROGRAM OVERVIEW camwm=- 22.- -.__ m _ .._- ___ -- 2 - IRC)

,.=mene-,            . . .        .._    ..

PROPRIETARY TRANSMITTAL L.ETTER DATE ADDRESSEE ft Yns ET-N RC-93-3903, NSRA- APSL-93-0200 61493 Borchardt l l ( Yes ET-NRC-93 3918, NSRA-APSL-93 0238 7793 Borchardt f No ET-NRC 93 3918, NSRA-APSL.93 0238 7793 Borchardt No ET-NRC-93 3920 NSRA-APSL-93-0250 71593 Borchardt f Yes ET NRC-93 3926 NSRA APSL 93-0250 71593 Dorchardt f No ET-NRC-93 3326 NSRA-APSL-93 0250 71593 Borchardt f Yes ET NRC 93 3926, NSRA-APSL-93'0250 71593 Borchardt No ET-NRC RL3926, NSRA-APSL-93-0250 f 71593 Borchardt No ET-NRC-93 3945, NCRA-APSL-93-0304 81693 Borchardt

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Wastinghouse Electric Corporation Rsvision $, March 22,1994 AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 9 - Summary of NRC Requests for Additional Information (RAI) Related to AP600 Test Programs RAINo. Description / Issue NRC Ltr Date 440.001 SPES test, check valve testing & PIUIR testing 09/23/92 440.002 - Gir testing 09/23/92 440.003 CMT testing 09/23S 2 440.004 CMT testing 09/23/92 440.005 CMT testing 09/23S 2 440.006 git testing 09/23 S 2 440.007 G1T testin5 09/23S 2 440.008 git testing 09/23S 2 440.009 oft testing 00/2192 440.010 git testing 09/23S2 440.011 ADS testing 09/23/92 440.012 ADS testing 09/2.V92 440.013 ADS testing 09/23S 2 440.014 ADS testing 09/2.V32 440.015 ADS testing 09/2332 440.016 ADS testing 09/2332 440.017 ADS testing 09/2192 440.018 ADS testing 09/23S 2 440.019 ADS testing 09/23S 2 440.033 Applicability of 3-tube PRHR tests 02/18/93 440.034 git scaling tests 02/18/93 440.(49 ADS Phase B test facility configuration 01/13S 4 440.050 Impact of ADS design change on OSU & SPES Ol/13S4 440.052 G1T Scaling Report 03/07/94 480.004 IIWRF Test Data 04/13S 3 480.005 Wind tunnel tests 04/28/93 480.008 - Natural circulation of air in PCCS 07AIS3 480.009 IIcat transfer & reixing in containment 07plS3 480.010 Jet discharge 07N t/93 480.011 I/S-scale fscility instrumentation 07N1/93 480.012 1/5-scale facility test matrix 07bl/93 480.013 Westinghouse scaling approach ' 07NI/93

                                               -480.015             WOOT111C validation with sest data                                      07N1/93 480.017             Extemal film partern/ water distribution                                07MI/93 95 LOO 2          - Tests for condenser behavior                                            07/l493 951.007             Long term cooling scaling for OSU                                       07/1433 952.002             ADS aparger drawings (OSU)                                              08/27S 3 952.003             Insulation / heat-tracing (OSU)                                         08/27/93 952.004             Starting conditions for depres. transient (OSU)                         08/27/93 952.005             Primary pump shutoff time (OSU)                                         08/27/93 952.006             Test conditioris (OSU)                                                  08/27/93 952.007.            Collection of fluids leaving the primary (OSU)                          08/2763 952.008             Pressurizer heater controls (OSU)                                      08/27/93

952.011 Core power during o transient (OSU) OG/27B3 952.012 Addition of flowmeter to ADS Phase B design Il#2S3 l 952.013 Effect of non<ondensible gases in test program liN2S3 952.014 Applicability of PRIER test to current design iIN2S3 952.015 ADS Phase B capabihty to hok! constant pressure iIS2S3 952.016 SPES-2 design documents update  !!M233

                            ~
                              )l             952.017                       Insights from pre-operational SPES-2 tests                                                                            IIM193 952.018                       Cold and hot pre-operational data from SPES-2                                                                         IIM2S3 q                        952.019                       1%w orifices at SPES-2                                                                                                IIM233
                      .                      952.020                       Volume versus elevation for SPES-2                                                                                    11M2S3 k                      952.022                       Information gained from ADS Phase A tests                                                                             llM193 952.023                       Effect of PRIIR heat exchanger on ADS operanon                                                                        iIM2S3 952 024                       Test procedures for ADS Phase B testing                                                                               (192/93 952.025                       Analyses for ADS Phanes A and B                                                                                       iIS2S3 952.026                       I%id conditions for ADS Phase B tests                                                                                 IIS233 952.027                       RCS behavior versus ADS test facility                                                                                 Il#2S3 952.029                       SPES-2 bend /clbow radii                                                                                              i1/3083 f.
  • 952.030 SPES-2 volve types and sizes ll/3(V93 952.031 SPES-2 schematics and drawings update 1I/30/M 952.032 SPES-2 operational parameters 11/30/93 j- 952.033 SPES-2 component position relatiomhips  ! I/30S3 I 952.034 SPES-2 rest pmcedures i I/W)3 952.035 SPES-2 facility insulation infonnation iI/30S3 952.036 SPES-2 annular downcomer 11/3083 952.037 OSU facihty orifice plate infonnation 01/18S 4 952.038 OSU valves with significant flow loss 01/1884 952.039 OSU MOV opening / closing rates 01/1884

[ 952.040 OSU hester rod power profile 01/88/94 952.04I OSU drawings LKL930104 & LKL930105 01/1BS4 i 952.489 SPESL2 test condidom 02/2434 952.050 SPES-2, Basis for fuel rod stored energy 03NIS4 952.051 SPES-2. Secondary side mass 03NI/94 952.052 SPES-2. Basis for pressurizer water level 03MI/94 952.053 SPES-2, Secondary side conditions 03 MIS 4 952.054 SPES-2. Scaling rationale 03MIB4 l I 952.055 SPES-2. Delayed neutron simulation 03 MIS 4 952.056 SPES-2. Basis for heat loss compermation 03#1B4 952.057 SPES-2, Secondary side relief valve closing setpts 03SI/94 952.058 SPSE-2, Pump coastdown 03MISd 952.059 SPES-2, Pressurizer heater rods 03 MIS 4 i

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Westinghouse Electric Corporation Revision 5, March 22,1994 I CHART 1

    ,                                                                   AP600 DESIGN CERTIFICATIO I                                                                   1994 -

l I

                                   'JAN.
                                         'FEB  MAR   ~APR   MAY  JUN.    ~ JLY' . LAUG :: 'GEP  OCTi     NOV!-   DEC: , JAW:  ,

f 1 CMT CATEGORY 1 Start: 2/15/94 (2/1S/94 Actual) r MATRIX TESTS End: 5/30/94 CMT CATEGORY 2 Start: 6/2/94 MATRIX TESTS End: 9/16/94

                                                                                                                          ^"0 h         SPES-2 CATEGORY 1 MATHlX TESTS                        g      4 SPES-2 CATEGORY 2                              Start: 10/10t MATHlX TESTS                                End:    11/22t OSU CATEGORY           Start: 7/1/94 1 MATRIX TESTS         End:    9/22/94 i

OSU CATEGORY 2 MATRIX TESTS 9 TT ADS PHASE B bt C ATEGORY 2 MATRIX

                                                                                                                  /0 l /94 E

TESTS i .. 7 i ,e9. 1 L

Md4Vw . i-l TEST SCHEDULE I 1 sM!nidb:s *@# -

                                               $1995 M ' &                  '
                                                                                  * / TRW 45 fLCAN             $APgj $ MAN             ,$JUN E          (Jt.Yj fAUGs ji3EP3      ;I(OCTs (NOVjji          (DEC}

[, . . 4 I i j, 6 f g 8 4 9 l . .: I 4 ( A

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4 Start: 10/3'94 End: 2/8/95 I t i k

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