ML20072E793
| ML20072E793 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 08/15/1994 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20072E797 | List: |
| References | |
| PROC-940815, NUDOCS 9408230090 | |
| Download: ML20072E793 (25) | |
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AP600 DESIGN CERTIFICATION E-"[gjs.J "5
TEST PROGRAM OVERVIEW
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i TABLE OF CONTENTS Table 1 Test Program Overview (Part 1)
Table 2 Test Program Overview (Part 2)
Table 3 Test Matrix, Automatic Depressurization System Test, Phase B r
Table 4 Test Matrix, Core Makeup Tank Test Table 5 Test Matrix, Low Pressure 1/4 IIeight Integral Systems Test (OSU)
Table 6 Test Matrix, Full Pressure Full IIeight Integral Systems Test (SPES-2)
Table 7 Summary of Westinghouse AP600 Test Program Related Materials Transmitted to NRC
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Table 8 Summary of NRC Requests for Additional Information (RAI) Related to l
AP600 Tests and Analyses Matrix Testing Schedules Chart 1 94 0 8 23 0 0 9 0 -b
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Revision 7, August 15,1994 APG00 DESIGN CERTIFICATI AP600 TEST PROGRAMS: TABLE 1 TEST PROGRAM OVERVIFW (PART 1)
Item TESTIN(
No.
TEST DESCRIPTION FACILITY LOCATION SCALE CATEGORY STATUS PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN 1
Air Flow Path Delta P Test
,W Science & Technology Center - Churchill, P A 1:6 linear Basic Research Completed 2
Water Film Forrnation Test W Science & Technology Center - Churchill, PA N/A Basic Research Completn 3
Heated Plate Test W Science & Technoicgy Center - Churchill, PA N/A 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 N/A Basic Research Completc 6
Condensation Tests - Bare surface downward University of Wisconsin Madison, WI N/A Basic Research Completec 7
Condensation Tests - Painted sudace down University of Wisconsin - Madison, WI N/A Basic Research Completec 8
Condensation Tests - Light noncondensibles University of Wisconsin - Madison, WI N/A Basic Research Completr 9
Condensation Tests - Stagnaten Flow University of Wisconsin - Madison, WI N/A Basic Research Completec 10 Condensation Tests - Stagnation / light noncond.
University of Wisconsin - Madison, WI N/A Basic Research Completr 11 Condensation Tests - 2D condensation University of Wisconsin - Madison, WI N/A Basic Research Completec PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION 1
12 Integral (small scale) Tests - Phase 1 W Science & Technology Center - Churchiti, PA 1:3 h 1.40 dia.
Safety Related Completec 13 Integral (small scale) Tests - Phase 2A W Science & Technology Center - Churchill, PA 1:3 h 1:40 dia.
Safety Related Completec 14 Integral (small scale) Tests - Phase 28 W Science & Technology Center - Churchill, PA 1:3 h 1:40 dia.
Safety Rotated Completec 15 1/8th Scale Heat Transfer Test - Phase 1 W Science & Technology Center - Churchill, PA
~1:8 linear Safety Related Completec 16 1/8th Scale Heat Transfer Test - Phase 2 W Science & Technology Center - Churchill, PA
~1:8 linear Safety Related Completec 17 Water Dist. System Test - Phase 1 (20ft Dia.)
W Waltz Mill Site - Madison, PA 1:1 Safety Related Completed 18 Water Dist. System Test - Phase 2 (1/8th sector)
W Waltz Mill Site - Madison, PA 1:1 Safety Rotated Completec 19 Water Dost System Test - Phase 3 (1/8th sector)
W Waltz Mill Site - Madison, PA 1:1 Safety Related Completeo 20 Wind Tunnel Test - Phase 1 Univ. of Western Ontario - London, Ontario
-1:100 linear Safety Related Completec 21 Wind Tunnel Test - Phase 2 Univ. of Western Ontario - London, Ontario
~1:100 linear Safety Related Completec 22 Wind Tunnel Test - Phase 4 A CNRC Wind Tunnel - Ottawa, Canada 1:30 linear Safety Related Completed 23 Wind Tunnel Test Phase 4B Univ. of Western Orftano - London, Ontario 1:500 linear Safety Related Completed PASSIVE CORE COOLING SYSTEM TESTS IN SUPPORT OF AP600 DEstGN CERTIFICATION 24 PRHR Heat Exchanger Test - Phase 1 W Science & Technology Center - Churchill, PA 1:1 height safety Related Completoe 25 PRHR Heat Exchanger Test - Phase 2 W Science & Technology Center - Churchill, PA 1:1 height Safety Related Completai 26 Automatx: Depressurization Sys. Test - Phase A ENEA (VAPORE facil,ty) - Casaccia, Italy 1:1 Safety Related Completr 27 Automatr Depressurization Sys. Test-Phase B ENEA (VAPORE facihty) - Casaccia, Italy 1:1 Safety Related in Progres 28 Core M Aoup Tank Test W Waltz Mill Site - Madison, PA
~1:8 dia. -1:2 h Safety Related in Progres 29 DWR Tests Columbia University New York, NY 1:1 Safety Related Completec 30 Low Pressure 1/4 Height Integral Systems Tests Oregon State University - Corvallis, OR 1:4 h 1:192 v.
Safety Related Completa 31 Full Pressure Full Height intogral Systems Tests SIET (SPES-2 Facility) Piacenza, Italy 1:1 h 1:395 v Safety Related in Progres
1
)N TEST PROGRAM OVERVIEW ADDITIONAL ffJFORMATION OBTAINED item TEST PURPOSE (Optional)
No.
' ~
I' 1
Obtain pressure drop data through the downcomer and annulus T
Confirm wettability of coated steel surface 2
Ccafirm PCS heat transfer capability 3
Effecta of wind on shield building design (inlet' outlet location) 4 Comparison with past separato e'fects tests d
5 Obtain heat transfer coefficients wth downward facing surfaces 6
l Obtain the effect of AP600 paint on heat transfer performance 7
Obtain the effect of light noncond. on heat transfer performance 8
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Obtain the HT performance under stagnant flow conditions 9
Heat transfer under stagnant flow condrtions w/ light noncond.
10 r
Measure condensation heat transfer coefficient using 2D test model Effect of non-cond. on heat transfer coefficient and visualize flow feld 11 Feasibility of water onhanced containment cooling system External cooling impact from air vel., hum, temp. and film flow rates 12 Operation of PCS over increased rango of operating conddions.
Investigate effect of various annullus widths and uniform steam 13 Confirm PCS internal and external heat transfer capabiltties (with distributions. Obtain data on water film behavior on external surf ace 1:1 scale cooling air annulus at control lod air temp. & humidity) over long vertical heat transfer surf ace Demonstrate operation of PCCS with prototypic steam injection 14 Obtain heat transfer data for WGOTHIC validation 15 Obtain heat transfer data for WGOTHIC computer code validation Effect of non-cond. on PCS heat removal and intemal ternp. dist.
16 invest @ ate performance of PCCS water delivery / distribution device Assess containment water coverage at top cf dome 17 Measure containment water coverage using distrubution system Obtain film thickness measurements 18 Measure cont. water coverage using selected design dist. system Obtain film thickness measurements 19
.m investigato wind sensitivity of shield building design Asess effects of site structures on wind loading 20 Assess wind loads on containment baffle Compare wind effecta w & w/o internal flow path 21 Verrfy Phase 1 & 2 test results at higher Reynolds numbers Confirrn baffle tomado loads 22 Invest @ ate site topography effects on air flow through PCS annulus Investigate effects of large structures on air flow through PCS annulus 23 Thermal performance of the PRHR heat exchanger tubes.
Assess IRWST mixing and effects nn heat transfer and steaming.
24 Expartd the range of conditions to extend PRHR HT correlation.
Determine the impact of lower initial tank water level on steaming.
25 Obtain sparger performance data, measure loads on quench tank Obtain thermal hydraulic data for computer code validation 26 for r 79 in confirming IRWST design Obtain thermal-hydraulic data for computer code validation oiping, structure loads / responses with both 1$ and 29 flow 27 Obtain thermakhydraulic data for computer code validation Confirm adequacy of CMT levelinstrumentation 28 Obtain DNB data at low flow conditions Data on fuel assembly flow mixing grids at design flow conddions 29
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Obtain thermabhydraulic data for computer code validation Investigate long term cooling behavior 30 Obtain thermal-hydraulic data for comouter code validation investigate systems interactions during high pressure transients 31 9408230090-
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Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT T
AP600 TEST PROGRAMS: TABLE 2 TEST PROGRAM OVEfWlEW (PART 2) L L.
? TEST SCHEDULE.
Item iREVIEWO Start' Erd '
Status '.
Test Matrix No.'
-.. TEST DESCRIPTION --
MEETINGS :
PASSIVE CONTAINMENT COOLING SYSTEM TESTS tN SUPPORT OF AP600 DESIGN L g
1 Air Flow Path Detta P Test 1/88 - 2/88 Completed RA 2
Water Film Formation Test 2/88 - 3/88 Completed KA
/
3 Heated Plate Test 4'88 - 6/88 Completed N/A 4
Bench Wind Tunnel Experiment 8/88 W88 Completed N/A 5
Condensation Tests - Bare surface upward 9/88 -12/88 Completed Reference 5.3 r
6 Condensation Tests - Bare surface downward W89 12/89 Completed Reference 6.3 7
Condensation Tests - Painted surface downward 9/90 - 12/90 Completed WCAP-13307 V
8 Condensation Tests - Light noncondensbles 9/91 - 12/91 Completed Reference 8.2 9
Condensation Tests - Stagw tion flow conditions 9/92 - 3/93 Completed Reference 9.2 p
10 Condensation Tests Stagnation / light noncondensibles 3/93 - 7/93 Completed Reference 10.2 11 Condensation Tests - 2D condensation 1/94 - 6/94 Completed 8/94 PASSIVE CONTAINMENT COOLING SYSTEM TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION 12 Int, at (small scale) Tests - Phase 1 (Feasibility) 5'89 -10/89 Completed WCAP-12667, Rev 1 13 Integral (smaR scale) Tests - Phase 2A (Extension Tests) 1/90 - 6/90 Completed WCAP-14134 (Rev. 0 8'94)
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14 Integral (smat scale) Tests - Phase 29 (Continuation Tests) 6/92 - 8/92 Completed WCAP 14134 (Rev. 0 &94) 1 15 1/8th Scale Heat Transfer Test - Phase 1 (Baseline) 2/92 - 6/92 Completed WCAP-13566 16 1/8th Scale Heat Transfer Test - Phase 2 (Confirmatory) 3/23/93, 2/23/94 6/93 - 9/93 Completed WCAP-14135 17 Water Distribution System Test Phase 1 (20ft Diameter) 6/91 - 8/91 Completed WCAP-13290 18 Water Distribution System Test Phaso 2 (1/8th Sector) 9/91 2/92 Completed WCAP-13290 19 Water Distribution System Test - Phase 3 W93 - 9/93 Completed WCAP-13816 j
20 Wind Tunnel Test - Phase 1 6/91 - 8/91 Completed WCAP-13294 i
21 Wind Tunnel Test Phase 2 2/92 - 3/92 Completed WCAP-13323 22 Wind Tunnel Test - Phase 4 A 6/93 - 8/93 Completed WCAP 13756 23 Wind Tunnel Test Phase 4B 9/93 - 9/93 Completed WCAP 14005 PASSIVE SAFETY SYSTEMS TESTS IN SUPPORT OF AP600 DESIGN CERTIFICATION 24 PRHR Heat Exchanger Test Phase 1 11/89 - 1/90 Completed WCAP-12666 25 PRHR Heat Exchanger Test - Phase 2 7/90 - 11/90 Completed WCAP-12980 26 Automatic Depressurization System Test - Phase A 5'26 27/93 6/92 - 11/92 Completed WCAP-13342
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27 Automatx: Depressurization Systems Test - Phase B 5/26-27/93, 2/25/94 7/94 - 11/94 in Progress Table 3
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28 Core Makeup Tank Test 2/25/93, 3/14/94 2/94 - 9/94 In Progress Table 4 29 DNBR Tests 6/93 - 2/94 Completed N/A 30 Low Pressure 1/4 Height Integral Systems Tests 12/W92, 9/20-21/93 5/94 - 8/94 Completed Table 5 31 Full Pressure FuD Height Integral Systems Tests 12/10/92 2/94 - 10/94 in Progress Table 6 m.
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ON TEST PROGRAM OVERVIEW TEST DOCUMENTS (See Tables 3 through 7 for additional relevant information)
F>caling R; port Test Specification Operating Faciltty Description Report Outck Look Final Test Report item Procedures
- Reports
. No.
- - FACILfrY OPERATING PROCEDURES ARE MAINTA!NED IN WESTINGHOUSE FILES AND ARE AVAILABLE FOR REVIEW.
pA M'A M'A WCAP-13328 N/A WCAP-13328 1
hA M'A M'A WCAP-13884 N'A WCAP-13884 2
4'A M'A N/A WCAP 12665 N/A WCAP-12665 3
k'A M'A N/A WCAP-14048 N/A WC AP-14048 4
4'A M'A N/A Reference 5 3 N/A Reference 5.3 5
4'A 4'A N'A Reference 6.3 N/A Reference 6.3 6
4'A N/A N/A WCAP-13307 N/A WCAP-13307 7
WA N/A NA Reference 8.2 M'A Reference 8 2 8
h'A N/A N'A Reference 9.2 M'A Reference 9.2 9
'A N/A N'A Reference 10.2 None Reference 10.2 10 hA N/A N/A
&'N None 8M 11 k'A N/A Completed WCAP-12667 Rev.1 N'A WCAP-12667. Rev 1 12
'A WCAP-13315 Completed WCAP 14134 (Rev. 0 8/94)
None WCAP-14134 (Rev. 0 8'94) 13 f4'A WCAP 13315 Completed WCAP-14134 (Rev. 0 &94)
None WCAP-14134 (Rev. 0 8'94) 14 hCAP-13246 WCAP 13267 Completed WC A P-1413 5 None WCAP-13566 15 VCAP 13246 WC A P-13267 Completed WCAP 14135 Completed WCAP 14135 16 yA WCAP 13290 Completed WCAP-13292 None WCAP-13353 17 hA WCAP-13290 Completed WCAP-13292 None WCAP 13296 18 l'A WC AP-13816 Completed WCAP-13292 None WCAP-13%0 19 NCAP-13294 WCAP 13318 Completed WCAP-13294 None WC AP-13294 20 hCAP-13323 WCAP-13318 Completed WCAP-13323 None WCAP-13323 21 VCAP-13294 VC A P-14068 WCAP 13318 Completed WCAP-14068 None WCAP-14068 22 yCAP-14091 WCAP-13318 Completed WCAP-14091 None WC AP-14091 23 k'A N/A Completed WCAP-12666 N, A WCAP 12666 24
'A WCAP-13368 Complated WC AP-12980 N'A WCAP-12980 25
'A WC AP-13342 Completed 8 94 M'A WCAP-13891 26
'A WCAP-14112 Completed 12/94 None 3/95 27 hCAP-13963 RO WCAP 13345. R3 9/94 WCAP-14132 C/9410/94 11/94 28
)
Rev. I 12/94)
(Rev.4 &'94)
LA WC AP 12488 Completod RXS-T2R-003 Completed 1/95 29
,94 WCAP-13234 R0 Completed WCAP-14124 7/94 'E94 3/95 30 (Rev.18/94)
VCAP-13277 WC A P-14053 (1 94 WCAP 14073 7/N-10/94 3.'95 31 9408230090-
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I Revision 7, August 15,1994 APG00 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 3 - MATRIX TESTS, AUTOMATIC DEPRESSURIZATION SYSTEM TEST, PHASE B TEST DESCRIPTICiN SCHEDULED ACTUAL PROJECTED NRC Witness Facility Turncver Tests 7/15/94 7/14/94 312 ADS Stages 1,2 & 3 open. Saturated water blowdown. No orifices 7/19/94 7/26/94 in spool pi3ces. Quench tank at subcooled temp. Low supply tank pressure (pressure setting #2). Vaive setting #2.
311 As Test 312 except: Intermediate supply tank pressure (pressure 7/21/94 7/26/94 setting #3). Valve setting #3.
310 As Test 312 except: High supply tank pressure (pressure setting #6).
7/23/94 7/28/94 Valve setting #4.
331 As Test 312 except: ADS Stages 1 & 2 open. Intermediate supply 7/26/94 7/27/94 tank pressure (pressure setting #3). Valve setting #1.
330 As Test 312 except: ADS Stages 1 & 2 open. High supply tank 7/28/94 7/27/94 pressure (pressure setting #5). Valve setting #2.
340 As Test 312 except: ADS Stage 2 open. High supply tank pressure 7/30/94 7/29/94 (pressure setting #6). Valve setting #1.
Plant Cooldown, Maintenance and Setup for next set of tests.
8/1/94 -
8/1/94-Characterization tests for Atwood and Morrill valve.
9/3/94 9/3/94 212 ADS Stage 1 open. Saturated blowdown from bottom of supply tank, 9/7/94 9/7/94 orifices installed in spool pieces. Low initial supply tank pressure (pressure setting #1). Valve setting #5.
211 As Test 212 except: Low supply tank pressure (pressure setting #2).
9/8/94 9/8/94 Valve setting #5.
210 As Test 212 except: Intermediate supply tank pressure (pressure 9/9/94 9/9/94 setting #3). Valve setting #6.
250 As Test 212 except: ADS Stage 2 open. Intermediate supply tank 9/13/94 9/13/94 pressure (pressure setting #3). Valve setting #3.
221 As Test 212 except: ADS Stages 1 & 2 open. High supply tank 9/16/94 9/16/94 procenro (nrosenra enmnn em V,'"n en+- ec 1 --
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As hest 212 except: ADS Stages 1 & 2 open. Intermediate supply 220 9/20/94 9/20/94 tank pressure (pressure seiting #3). Valve setting #5.
231 As Test 212 except: ADS Stages 1 & 3 open. High supply tank 9/23/94 9/23/94 pressure (pressure setting #6). Valve setting 5.
241 As Test 212 except: ADS Stages 1,2 & 3 open. Low supply tank 9/27/94 9/27/94 pressure (pressure setting #2). Valve setting #5.
242 As Test 212 except: ADS Stages 1,2 & 3 open. Low initial supply 9/28/94 9/28/94 tank pressure (pressure setting #2). Valve setting #3.
240 As Test 212 except: ADS Stages 1,2 & 3 open. Intermediate supply 10/1/94 10/1/94 tank pressure (pressure setting #3). Valve setting #5.
Plant Cooldown, Maintenance and Setup for next set of tests 10/2/94 -
10/2/94 -
10/9/94 10/9/94 110 ADS Stage 1 open. Saturated steam blowdown from top of supply 10/13/94 10/13/94 tank. Orifices installed in spool pieces. High supply tank pressure (pressure setting #7).
130 As Test 110 except: ADS Stages 1 & 3 open. Intermediate supply 10/14/94 10/14/94 tank pressure (pressure setting #3).
120 As Test 110 except: ADS Stages 1 & 2 open. High supply tank 10/18/94 10/18/94 pressure (pressure setting #4).
140 As Test 110 except: ADS Stages 1,2 & 3 open. High supply tank 10/20/94 10/20/94 pressure (pressure setting #4).
322 As Tesi 312 except: Saturated quench tank.
11/9/94 11/9/94 321 As Test 311 except: Saturated quench tank.
11/11/94 11/11/94 320 As Test 310 except: Saturated quench tank.
11/16/94 11/16/94 350 As Test 330 except: Saturated quench tank.
11/18/94 11/18/94 351 As Test 331 except: Saturated quench tank.
11/22/94 11/22/94 Y
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li AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW e
it Table 4 - MATRIX TESTS, CORE MAKEUP TANK TEST Tcst Test type CMT drain rate Steam supply Comments Scheduled Actual Projected NRC Test j
pressure (s),
witness I
101 CMT wall CMT drain rate 10 CMT initia!!y contains no 3/22/94 8/1/94 101 condensation based on steam water, and is evacuated.
102 135 w/ and w/o condensation rate 3/24/94 7/25/94 102 103 noncond.
and drain capability 685 3/29/94 7/26/94 103 104 gases 1085 3/31/94 7/27/94 104 105 2235 2/15/94 2/21/94 105 106 10 CMT press, w/ air (or N ) to 4/5/94 7/29/94 106 2
107
.236,1.13 and 2.13 psia, 4/6/94 7/30/94 107 resp.
j 108 4/7/94 7/31/94 108 301 CMT 6
10 low resistance steam 5/20/94 7/12/94 301 dr nd wn at supply line no. 2 utilized;-
302 6
135 5/23/94 7/11/94 302 constant drain rate controlled by j
303 pressure 6
1085 discharge line resistance.
5/25/94 7/13/94 303 304 11 10 5/27/94 5/27/94 304 305 11 135 5/30/94 5/31/94 305 306 11 1085 6/1/94 6/1/94 Levin 306 307 16 10 6/3/94 6/3/94 307 i
l 308 16 135 6/13/94 7/7/94 308 309 16 1085 6/15/94 7/15/94 303 310 max 10 6/17/94 6/30/94 310 1
311 max 135 6/20/94 7/1/94 311 312 max 1085 6/22/94 on hold 312 j
317 6
45 New 8/5/94 317 318 11 45 New 8/8/94 318 319 16 45 New 8/9/94 319 i
320 6
685 New 8/10/94 320 321 11 685 New 8/12/94 321 3H2 9(lL 685 3aw M*
--323 max 685 1--
fNew 8/16/94 h323 401 CMT 6/16 gpm 1085, depress.
Steam line no. 2 used.
6/27/94 8/22/94 401 402 6/30/94 8/24/94 402 dunng 403 depress.
Rate controlled by 2235, depress.
Resistance set for 6/16 8/5/94 9/12/94 403 supply line 1 resist.
to 20 gpm drain rate.
404 8/9/94 9/14/94 404 501 Natural Discharge line 1085, depress.
Nat. circ. until 1/5th of CMT 7/8/94 8/26/94 501 circulation resistance set for to 20 heated.
502 7/11/94 8/29/94 502 followed by 6/16 gpm drain rate 503 draindown and Nat. circ. until 1/2 of CMT 7/13/94 8/31/94 503 depress.
heated.
504 7/15/94 9/2/94 504 505 Nat. circ. until CMT fully 7/18/94 9/6/94 505 506 heated.
7/20/94 9/9/94 506 507 Drain rate to be 1835, depress.
1/5 CMT heated 8/12/94 9/16/94 Yes 607 508 1/2 CMT heated 8/16/94 9/19/94 Yes 508 os tes s 5Ob 509 506 CMT fully heated 9/19/94 901/94 Yes 509 fD k
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AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 5 - MATRIX TESTS, LOW PRESSURE 1/4 HEIGHT INTEGRAL SYSTEMS TEST (OSU)
Test Description Scheduled Actual NRC Witness hot 5/10/94-6/30/94 5/26/94 pre-ops SB1 2-Inch CL break, bottom of pipe, loop A with continuat!on into long-7/1/94 5/31/94 INEL,Ortiz term cooling, fall 1/2 lines in 1 ADS 4 train SB4 2-inch cold leg break, bottom of pipe, loop A, with non-safety 7/18/94 (6/3/94)
INEL systems on, single failure as SB1 gj28/94 SB13 2-inch break of direct vessel Injection line, continuation into long-9/1/94 6/7/94 term coollng mode, single falture as SB1 SB12 DEG break of DVIIIne, continuation into LTC, loss of one train 8/17/94 (6/9/94)
- Bessette, ADS 1 and ADS 3 7/21/94 Dimartzo SB10 DEG break of cold leg balance line, horizontal loop, loop A with 8/2/94 (6/14/94)
Scott,Roth continuation into LTC, single failure as SB1 6/24/94 SB3 2-Inch cold leg break, top of pipe, loop A, single fa!!ure as SB1 10/18/94 6/16/94 SB5 1-inch cold leg break, bottom of pipe, loop A, with continuation into 11/2/94 6/21/94 INEL LTC, single failure as SB1 SB7 2-inch cold leg break, bottom of pipe, loop A, fall train of ADS 1-4 11/17/94 6/23/94 INEL SB9 2-inch break on CL balance line, horizontal loop, loop A, single 12/2/94 6/29/94
- Archizel, (Blind) failure as SB1 INEL SB11 DEG break of DVI line with continuation into LTC, single failure as 12/19/94 7/28/94 SB1 SB14 Inadvertent ADS-1, with continuation into LTC, single failure as SB1 1/3/95 7/7/94 SB15 2-inch HL break, bottom of pipe, loop a, single failure as SB1 1/18/95 7/12/94 SB19 Same as SB1 with simulated containment back pressure 2/2/95 7/14/94 Levin LB01 Large CLB, higher decay heat, continuation into LTC, single failure 10/3/94 8/3/94 HasselbergNinh (LTC21) as SB1
-. _. _ _ _ _ _.. _ _. _ _ _ _. _. _.. _.. _ _. ~. _. _ _. -.
Tcbla 6 - MATRIX TESTS, FULL PRESSURE FULL HEIGHT INTEGRAL SYSTEMS TEST (SPES-2)
Test Description Scheduled Actual Projected NRC Witness 3
2-inch cold leg break with non-safety systems off 2/25/94 4/30/94 Levin (1st run) 1 1-inch cold leg break with non-safety systems off 4/14/94 5/6/94 ANPA 4
2-inch cold leg break with non-safety systems on 3/22/94 5/18/94 ANPA 5
2-inch direct vessel injection line break with non-5/16/94 5/27/94 ANPA safety systems off 6
Double-ended guillotine break of the direct vessel 6/15/94 6/10/94 McPherson injection line with non-safety systems off 7
2-inch break of cold leg to core makeup tank 7/15/94 7/7/94 ANPA balance line with non-safety systems off 4
8 (blind)
Double-ended guillotine break of cold leg to core 8/16/94 6/23/94 ANPA makeup tank balance line with non-safety systems j
off 9
Design basis steam generator tube rupture with 9/15/94 9/8/94 ANPA non-safety systems on and operator action to isolate steam generator i c3 10 Design basis steam generator tube rupture with 10/10/94 7/14/94
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!A non-safety systems on and no operator action Carlson o
oo 11 (blind)
Design basis steam generator tube rupture with 11/2/94 9/22/94 McPherson, to manual ads actuation Kelly CO l o 12 (blind)
Large steamline break 11/16/94 10/6/94
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Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT I
~ TABLE 7. TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO f DESCRIPTION t
7 TEST PROGRAM GENERAL' O.1 Response to November 14,1991 Request for Information Regarding AP600 Test Program 0.2 Response to January 15,1992 Request for Information Regarding the AP600 Passive Containment Cooling System Tests 2
(
0.3 Responses to "AP600 Design issues to be Resolved by High Pressure, Full-Height integral Testing" O.4 Presentation Material from February 25,1992 Westinghouse NRC Meeting on AP600 Testing i
I 0.5 Ra_ponse to November 14,1991 Request for AdditionalInformation Regarding AP600 Test Program 0.6 Presorsation Material from March 3,1992 ACRS Meeting on AP600 Testing 0.7 Presentation Material from June 1,1992, AP600 Meeting on Integral Systems Testing 0.8 Presentation Material from June 23,1992 AP600 ACRS Testing Presentation 0.9 NRC Request for AdditionalInforrnation Rogarding the AP600 Testing Program f
0,10 AP600 Testing to Support Design Certification 0.11 AP600 Testing Schedule 0.12 Presentation Material from December 14,1992 Westinghouse NRC Meeting on AP600 Testing O.13 Westinghouse 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 j
0.15 Westinghouse Response to NRC Request for Additional Information on the AP600 Testing Program dated September 1,1992 0.16 Test Schedule for AP600 Automatic Depressurization System Test - Phase B
]
J 4
0.17 Presentation Material from the March 9-10,1993 Meeting on the AP600 Testing Program 0.18 Materialin Support of March 23 24,1993 Westinghouse'NRC Meeting on Containment Tests for AP600 (Test Spec additions, Test Matrix, Sched 0.19 Draft AP600 Test /WRness Matrix 0.20 Presentation Material from the March 23-24,1993 Meeting on the AP600 Containtnent Test Program J
0.21 Updated Testing Schedules for the AP600 Testing Program 1
0.22 Background Materials in Preparation for the July 22-23 Meeting of ACRS Subcommittee on T/H Phenomena l
1 0.23 Presentation Materials from the June 18,1993 Meeting on the AP600 Testing Program 1
O.24 AP600 Design and Design Certification Test Program Overview, Revision 2
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0.25 General Outline for Quick Look Data Reports on AP600 Tests 0 26 AP600 Design and Design Certification Test Program Overview, Revision 3 4
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0.27 Outline for AP600 Code Validation Process Steps incorporating NRC Request for Single Blind Test Predictions 0.28 Presentation Materials from the December 10,1993 Meeting on AP600 Test Program issues
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O.29 AP600 Design Certification Test Program Overview, Revision 4 l
0.30 AP600 Design Certification Program Schedule and Revision 5 of the AP600 Design Certification Test Program Overview 0.31 Additional Information in Support of Westinghouse Response to RAI 952.48 on the AP600 Design 0.32 Additonal Information in Support of Westinghouse Response to RAI 952.43 on the AP600 Design 0.33 Additional Information in Support of Westinghouse Response to RAI 952.44 952.46 on the AP600 Design
! !L.
0.34 Closure of AP600 Testing Program issues 0.35 AP600 Design Certification Test Program Overviaw, Revision 6 1
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PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-N RC-91 -3650, N P P-APSL-91-0286 12 16 91 Murley Yes ET-N RC-91 -3656, NPP APSL-92-0013 122 92k h N Mur}ey Yes ET-N RC-92-3663, NSRA-APSL-92-0037 214 9d ' '
1 Crutchfield Yes ET-N RC-92-3664, NSRA-APSL-92 0047 22492
' Murley No ET-N RC-92-3666 NSRA-APSL 92-0046 22492
.Hasselberg Yes ET-N AC-92-3671, NSRA APSL 92-0053 3 4 92,'. t. rig
' Murley; Yes ET-N RC-92-3713, NSRA-APSL-92-0130 62592 Murley Yes ET NRC-92 3716, NSRA-APSL 92-0133 63092 Murlay Yes ET-N RC-92-3750, NS RA-APSL-92-0169 91492 Murley No ET-N RC-92-3754, NSRA-APSL-92-0200 10592 Ward No ET-NRC-92 3768, NSRA APSL-92-0239 11592 Muriey Yes ET-N RC-92-3783. NSRA-APSL-92-0264 12 14 92 Muriey No ET-NRC-93 3799, NSRA APSL-93-0010 11993 Murley No ET-NRC 93-3800, NSRA-APSL-93-0011 11993 Murley 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 Yes ET NRC-93-3841, NSRA-APSL-93-0076 31693 Borchardt No ET-NRC-93-3848, NSRA-APSL-93-0093 32393 Borchardt Yes ET-N RC-93-3845, NSRA-APSL 93-0000 32493 Borchardt l
No ET-NRC 93-3855, NSRA-APSL-93-0109 41393 Boichardt 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-N RC-93 -3919, NSRA-APSL-93-0233 7793 Borchardt No ET-N RC-93-3946, NSRA-APSL 93-0305 81693 Borchardt No ET-N RC-93-3947, NSRA APSL-93 0306 81893 Borchardt No ET-N RC43 -3976, NSRA-APSL-93 0360 92793 Borchardt Yes ET-N RC-93 -4029, NSRA-APSL-93-0492 12 16 93 Dorchardt No NTD-NRC-94-4078, DCP/NRC0017 3894 Borchardt No NTD-NRC 94-4084, DCP/NRC0026 32894 Borchardt Yes NTD-NRC-94-4106, DCP/NRC0040 42594 Borchardt Yes NTD NRC 94-4108, DCP/NRC0042 42994 Borchardt Yes NTD-NRC-94 4114, DCP/NRC0048 51794 Borchardt No NTD-NRC-944117, DCP/NRC0051 5394 Crutchfield No NTD-NRC-94-4138, DCP/NRC0065 51794 Borchardt 9408230090- O
I.
Westinghouse Electric Corporation Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT f
.. TABLE 7 - TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERI ALS TRANSMITTED TO l DESCRIPTION t
0.36 AP600 Design Change Description Report 0.37 AP600 LOCA Analysis Sensitivity to Containment Pressure, Action item from May 10,1994 Senior Management Meet;ng
- 1. Air Flow Delta P Test 1.1 WCAP-13328," Tests of Air Flow for Cooling the AP600 Reactor Containment, Rev. 0" bbO^D<
1.2 WCAP-13329," Tests of Air Flow for Cooling the AP600 Reactor Containment, Rev. 0" NI 0 - 4
L 1.3 WCAP-13330, " Natural Convection Cooling of AP600 Containment, Rev. 0*
i bdU*
1.4 WCAP-13331," Natural Convection Cooling of AP600 Containment, Rev 0" ypn
- 2. Water Film Formation Test AD0dN9 CMd 2.1 WCAP-13330 " Natural Convection Cooling of AP600 Containment, Rev. 0" 2.2 WCAP-13331 " Natural Convection Cooling of AP600 Containment, Rev. 0*
2.3 WCAP-13884," Water Film Formation on AP600 Reactor Containment Surface" Revision 0 2.4 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" 3.2 WCAP-12665," Tests of Heat Transfer and Water Film Evaporation on a Heated Plate Simulating Cooling of the AP600 Reactor Containment, Rei 3.3 WCAP-13341,' Tests of Heat Transfer and Water Film Evaporation on a Heated Plate Simulat:ng Cooling of the AP600 Reactor Containment, Rei 3.4 WCAP-13330," Natural Convection Cooling of AP600 Containment, Rev. 0" 3.5 WCAP-13331, " Natural Convection Cooling of AP600 Containment, Rev. 0" 3.6 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxity 3.7 WCAP-13412. " Westinghouse-GOTHIC: A Computer Code For Analyser of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxilq 4, Bench Wind Tunnel Experiment '
4.1 WCAP-13330," Natural Convection Cooling of AP600 Containment, Rev. 0" J
4.2 WCAP 13331, " Natural Convection Cooling of AP600 Containment, Rev. 0" 4.3 WCAP-14048," Passive Containment Cooling System Bench Scale Wind Tunnel Test"
{
- 5. Condensation Tests Bare Surface Upward 1i S.1 WCAP 13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxili 5.2 WCAP 13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxily References for Basic Research Tests on Condensation Performed in Support of the AP600 Design j
5.3 5.4 J.J. Barry, " Effects of Interfacial Structure on Film Condensation," PhD Thesis (1987)
- 6. Condensation Tests - Bare Surface Downward L
6.1 WCAP 13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxits f'
6.2 WCAP-13412. " Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & AuxilS, be 6.3 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design 1
.~
o
>N TEST PROGRAM OVERVIEW
)
t PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes NTD-NRCM4175, DCP/NRC0112 63094 Borchardt No NTD-NRC 94-4239, OCP/NRC0164 72694 Yes ET-NRC-92-3688, NS RA-APSL-92-0094 43092 Murley No ET-NRC-92-3688, NS RA-APSL-92-00M 43092 Murley Yes ET-N RC-92-3688 NSRA-APSL-92-00M 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Murley No ET-NRC-92-3688, NS R A-APSL-92-0094 43092 Murley Yes NTD-NRC-94 4056, OCP/NRC0002 2294 Borchardt No NT D-N RC-944056, DCP/NRC0002 2294 Borchardt Yas N S -N RC-90-3 525, NPAP APSL-90-0048 71690 Donatell Yes ET-NRC-92 3688, NS RA-APSL-92-00M 43092 Murley No ET-NRC-92 3608, NSRA-APSL 92 0094 43092 Murley Yes ET-N RC-92-3688, NS RA-APSL-92-00N 43092 Murley f
No ET NRC-92-3688, NSRA-APSL-92-0004 43092 Murley Iluildirtgs" Yes ET-NRC-92-3726 73192 Murley I
Duildirgs" No ET-N RC-92-3726 73192 Murley i
Yos ET-NRC-92 3688 NS R A-APSL-92-0094 43092 Murley No ET-NRC-92-3688, NSRA-APSL-92-00M 43092 Murley
(
No NTD-NRC-M4116, DCPiNRC0050 42994 Borchardt
[
I l
uilding s" Yes ET-N RC-92-3726 73192 Murley luildings" No ET-NRC-92 3726 73192 Murley No ET-N RC-93-3945, NS RA-APSL-93-0304 81693 Borchardt No ET-N RC-93-394 5, NS RA-APSL-93-0304 81693 Borchardt Buildirgs" Yes ET-NRC 92-3726 73192 Murley luildirgs" No ET-NRC-92-3726 73192 Murley l
l No ET-N RC-93-3945 NSRA-APSL-93 0304 81693 Borchardt 9408230090 -
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i Westinghouse Electric Corporation
- - - ~
i Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT:
TABLE 7 - TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO F DESCRIPTION
- 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 - Experimental Investigation" 7.3 WCAP-13412. " Westinghouse-GOTHIC: A Computer Code For Analyses of Therrnal Hydraulic Transients for Nuc' ear Plant Containments & Auxili 7.4 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Themial Hydraulic Transients for Nuclear Plant Containments & Auxiii.
- 8. Condensation Tests - Light Noncondensibles 8.1 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design 8.2 A. P. Pernsteiner, " Condensation in the Presence of Noncondensble Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thesis 8.3
- 1. K. Huhtiniemi, " Condensation in the Presence of Noncondensible Gas: The Effect of Surface Orientation," Prelim Thesis (1990)
- 8. 4
- 1. K. Huhtiniemi, " Condensation in the Presence of Noncondensible Gas: The Effect of Surface Orietation," Prelim Thesis (1990)
- 9. Condensation Tests Stagnation Flow Conditions 9.1 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design 9.2 A. P. Pernsteiner, " Condensation in the Presence of Noncondensble Gas: Effect of Helium Concentration," 1993, University of Wisconsin Thesis
- 10. Conderisation Tests. Stagr ation/ Light Noncondensfbles 10.1 References for Base 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 Thesis
- 11. Condensation Tests - 2D Condensation 11.1 References for Basic Research Tests on Condensation Performed in Support of the AP600 Design
- 12. Integrn! (small scale) Tests - Phase 1 (Feasibility) 12.1 WCAP 12667," Test of Heat Transfer and Water Film Evaporation From a Simulated Containment To Demonstrate the AP600 Passive Containm$
N 12.2 WCAP-13330, " Natural Convection Cooling of AP600 Containment, Rev. 0" 12.3 WCAP-13331, " Natural Convection Cooling of AP600 Containment, Rev. 0" 1
12 4 WCAP-13340," Tests of Heat Transfer and Water Film Evaporation from a Simulated Containment to Demonstrate the AP600 Passive Containmed 12.5 WCAP-12667," Tests of Heat Transfer and Water Film Evaporation from a simulated Containment to Demonstrate the AP600 Passive Containmed 12 6 WCAP 13412,
- Westinghouse-GOTHIC: A Corrputer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxilis 12.7 WC AP 13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxilid
- 13. Integral (small scale) Tests Phase 2A (Ex%nsion Tests) 13.1 WC AP 13316," Integral Containment Cooling Test Extension - Test Specification, Rev. 0" 13 2 WCAP 13315,"Ir:tegral Containment Cooling Test Extension Test Specification, Rev. 0" 13.3 WCAP 13412," Westinghouse GOTHIC: A Computor Code For Analyses of Thermal Hydrauite Transients for Nuclear Plant Containments & Auxilid 13.4 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thormal Hydraulic Transients for Nuclear Plant Containments & Auxili!
- 14. Integral (small scale) Tests - Phase 2 (Continuation Tests) 14.1 WCAP-13315 " Integral Containment Cooling Test Extension Test Specification, Rev. 0" 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 & Auxilid 14.4 WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxilid
. - ~ _
)N TEST PROGRAM OVERVIEW 9
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-N RC-92-3688, NSRA-APSL 92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL 92-0034 43092 Modey f
[Buildigs" No ET-N RC-92-3726 73192 Mhy E3uildigs' Yes ET-NRC-92 3726 73192 Mudey No ET-N RC-93-394 5, NSRA-APSL-93-0304 81693 Borchardt No ET-N RC-93-4014, NS RA-APSL-93-0448 11 12 93 Borchardt No ET-NRC-93 3945, NSRA-APSL-93-0304 81693 Borchardt Yes ET-N RC-93-394 5, NSRA APSL-93-0304 81693 Borchardt x
No ET-N RC-93-394 5, NSRA-APSL-93-0304 81693 Borchardt No ET-N RC-934014, NSRA-APSL-93-0448
'11 12 93 Borchardt
%..>J No ET-NRC-93 3945, NSRA-APSL-93-0304 816 93
- c. -
Borchardt 7
2 No ET-NRC-93 4014, NS RA-APSL-93-0448
'11 12 93 Borchardt No ET-N RC-93 -3945, NSRA-APSL-93-0304 81693 Borchardt
- soling System" Yes NS-NRC 90-3525, NPAP-APSL-90-0048 71690 Donatell Yes ET-N RC-92-3688, NSRA-APSL 92-0094 43092 Mudey No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey polig System, Rev. 0" No ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Murley hlig System, Rev.1" Yes ET-N RC-92-3688, NSRA-APSL 92-0094 43092 Mudey uiMqs" No ET-N RC-92-3726 73192 Murley huildigs*
Yes ET-N RC-92-3726 73192 Mudey No ET-NRC-92 3688, NSRA-APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey 3uildigs" No ET-N RC-92-3726 73192 Murley Buildigs*
Yes ET-N RC-92-3726 73192 Mudey Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA APSL-92-0094 43092 Murley 3uildigs" Yes ET-NRC 92-3726 73192 Mudey Buildigs" No ET-N RC-92-3726 73192 Murley 9408230090 -
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Westinghouse Electric Corporation
" " ~ ~ *
!L Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT$
i U
f~
R J TABLE 7 - TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINCHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO NI DESCRIPTION
_15.1/8th Scale Heat Transfer Tests Phase 1 (Basehne) 15.1 WCAP 13267," Test Specification: Large Scale Passive Containment Cooling Test, Rev.1*
152 WCAP-13268, " Test Specification
- Large Scale Passive Containment Cooling Test, Rev.1*
WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containment 15.3 WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containment l
15.4 i
15.5 WCAP 13566, *AP6001/8th Large Scale Passive Containment Cooling System Heat Transfer Test Baseline Data Report," Rev. O, R
15.6 WCAP 13567, *AP6001/8th Large Scale Passive Containment Cooling System Heat Transfer Test Baseline Data Report," Rev. 0 16.1/8th Scale Heat Transfer Test - Phase 2 (Confirmatory) -
16.1 WCAP 13267," Test Specification: Large Scale Passive Containment Cooling Test, Rev.1*
16.2 WCAP-13268," Test Specification
- Large Scale Penive Containment Cooling Test, Rev.1*
16.3 Phase 2 Large Scale Test Matrix Rationale; information in Support of Request for Additional Information on the AP600 Design (RAl 480.12) 16.4 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Constant Pressure Tests (Tests 202.3 and 203.3) 16.5 Facihty *as-built
- Drawings for AP600 PCCS Large Scale Test Facility 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 Facility 16.8 Proposed initial Conditions Data and Forcing Functions for Large Scale Phase 2 Test 220.1 16.9 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Tests 214.1 and 215.1 16.10 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Tests 217.1 and 218.1 1
16.11 Test Description Package for AP600 PCCS Large Scale Phase 2 Test: Test 220.1 16.12 Quick look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 216.1 16.13 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 219.1 16.14 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 221.1 16.15 Presentation Materials from the February 23 24,1994 Meeting on AP600 PCCS Tests and Analysis 16.16 Presentation Materials from the March 17,1994 Meeting on AP600 Passive Containment Cooling System Design Basis Analyses 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" 16.19 Westinghouse AP600 Letter Report, " Liquid Film Model Validation *
'(
1620 Quick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Tests 222.2, 222.3, 222.4 16.21 Presentation Materials from the May 25,1994 Meeting on AP600 Passive Containment Cooling System Analyses
)
1622 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Test 223.1 1623 Ouick Look Data Report for AP600 PCCS Large Scale Phase 2 Tests: Tests: 224.1,224.2 16.24 Westinghouse AP600 Letter Report, "AP600 Containment Plume investigation" 1625 AP600 PCCS Design Basis Analysis Models and Margins Assessment Roport 1626 Presentation Materials from the July 26-28,1994 Meetings on AP600 Passive Containment Cooling System Analyses 16.27 Westinghouse AP600 Letter Report
- Method for Determining Film Flow Coverage for the AP600 Passive Containment Cooling System
- 16 28 AP600 Passive Containment Cooling System Preliminary Scaling Report w
+-,,.
-.-e
.---m--mmm,e-~r,. - - +.w.
] TEST PROGRAM OVERVIEW
(
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE i
l Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey j
No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey hrgs" Yes ET-N RC-92-3726 73192 Mudey hrgs" No ET-NRC-92 3726 73192 Murley I
Yes ET-NRC-93 3801, NSRA APSL-93-0012 12593 Mudey f.
No ET-N RC-93-3801, NSRA-APSL-93-0012 12593 Mudey l
l l
Yes ET-N RC-92-3688, NSRA-APSL-92-0094
,4 30 S2 Mudey l
l No ET-N RC-92-3688, NSRA APSL-92-0094 I
.[30 92, Mudey
[
Yes ET-N RC-93-3961, NSRA-APSL-93-0334 ^'N'.. IIN3 b3" Borchardt
^'
Yes ET-N RC-93-3981, NSRA-APSL-93-0380 L
1d 4 93 Borchardt Yes ET-N RC-93-3983, NSRA APSL-93-0381 A b o Abni 110 6 93 i Borchardt Yes ET-N RC-93-3991, NSRA-APSL-93-03M
'10 kh93 Borchardt Yes ET-NRC-93 3997, NSRA-APSL-93-0405 10 21 93 Borchardt l
No ET-NRC-93 3998, NSRA-APSL-93-0406 10 22 93 Borchardt
(
Yes ET-NRC-S3-4006, NSRA APSL-93-0421 10 29 93 Borchardt l
Yes ET-N RC-93-4012, NSRA-APSL-93-0446 11 12 93 Borchardt Yes ET-NRC-93 4030, NSRA-APSL-93-0495 12 20 93 Borchardt i
Yes ET-N RC-94-4035, NSRA-APSL 94-0002 11894 Borchardt
[
Yes NTD-NRC-944053, SAUN RC0037 12894 Borchardt Yes NTD-NRC-94-4062, DCP/NRC0004 21194 Borchardt Yes NTD-NRC-944067, DCP/NRC0009 22394 Borehardt
(
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-944100, DCP/NRC0035 41894 Borchardt l
Yes NTD-NRC-94-4121, DCP/NRC0054 5494 Borchardt No NTD-NRC 94-4152 DCP/NRC0076 53194 Borchardt f
Yes NTD-NRC-94 4150, DCP/NRC0077 53194 Borchardt Yes NTD-NRC-94-4159, DCP/NRC0100 6794 Borchardt Yes NTD-NRC-944166, DCP/NRC0105 61094 Borchardt f
No NTD-NRC-94-4174, DCP/NRC0111 63094 Borchardt f
Yes NTD NRC-94-4241, DCP/NRC0166 72994 Borchardt l
Yes NTD-NRC-94-4247, DCP/NRC0172 72894 Borchardt I
Yes NTD-NRC-944246, DCP/NRC0171 72894 Borchardt 9 4 0 8 23 0 0 9 0
/'g
i Westinghouse Electric Corporation i
Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT TABLE 7 TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINCHOUSE AP600 TEST PROGRAM RELATED MATERIAL!i TR MfTTED TO f DESCRIPTION
/
)
16.29 WCAP-14135, " Final Test Report for PCS Large Scale Phase 2 and Phase 3 Tests
- 1 16.30 WCAP-14138, " Final Test Report for PCS Large Scale Phase 2 and Phase 3 Tests" 16.31 EPRI Report TR-103053-V1," GOTHIC Containment Analysis Package *, Version 3.4e, Volume 1: Technical Manual
?
16.32 EPRI Report TR 103053.V2, " GOTHIC Containment Analysis Package", Version 3.4e, Volume 2: User's Manual 16.33 EPRI Report TR-103053-V3, " GOTHIC Containment Analysis Package", Version 3.48, Volume 3: Qualification Report
- 17. Water Distribution System Test Phase 1 (20f1 Diameter) 17.1 WCAP-13353, " Passive Containment Cooling System Water Distnbution 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 Distributon Test, Rev. 0" 17.4 WCAP-13290, " Passive Containment Cooling System Water Distrbution Test, Rev. 0" 17.5 WCAP-13293," Construction / Test 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 & Auxili 17.8 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxili
- 18. Water Distribution Systern Test Phase 2 (1/8th Sector) 18.1 WCAP-13291, " Passive Containment Cooling System Water Distribution Test. Rev. 0" 18.2 WCAP-13297,"PCS Water Distrbution Test Phase 11 Test Data Report" 18 3 WCAP 13296,"PCS Water Distribution Test Phase il Test Data Report" 18.4 WCAP-13290, " Passive Containment Cooling System Water Distribution Test, Rev. 0" 18.5 WCAP-13293,"ConstructiorVTest Plan For the Passive Containment Cooling System Test Articles, Rev. 0" 18.6 WCAP-13292, "ConstructiorVTest Plan For the Passive Containment Cooling System Test Articles, Rev. 0" j
18.7 WCAP-13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & AuxilK 18 8 WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxil 19, Water Distribution System Test - Phase 3 i
19 1 WCAP-13292,"ConstructiorVTest Plan For the Passive Containment Cooling System Test Articles, Rev 0*
19 2 WCAP 13293," Construction / Test Plan For the Passive Containment Cooling System Test Articles, Rev. 0" l
19.3 WCAP-13816," Phase 3 Passive Containment Cochng System Water Distribution Test" 19 4 WCAP-13817," Phase 3 Passive Containment Coo;ing System Water Distribution Test" 19 5 WCAP-13960,"PCS Water Distribution Phase 3 Test Data Report," Revision 0 19.6 WCAP-13961,"PCS Water Distnbution Phase 3 Test Data Report," Revision 0 20, Wind Tunnel Test Phase 1 20.1 WCAP-13294," Phase I Wind Tunnel Testing For the Westinghouse AP600 Reactor" g
20.2 WCAP-13295, " Phase I Wind Tunnel Testing For the Westinghouse AP600 Reactor" 20.3 WCAP 13318, " Passive Containment Cooling System Wind Tunnel Test Specsfication, Rev. 0" WCAP-13412," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxilih 20.4 20 5 WCAP-13246," Westinghouse-GOTHlC: A Computer Codo For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxiliq
DN TEST PROGRAM OVERVIEW CL)
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes NTD-NRC N-4243, DCP/NRC0168 72994 Borchardt No NTD-N RC-944243, DCPiNRC0168 72994 Borchardt No NTD-N RC-94-4260, DCP/NRC0183 8 t o 94 Borchardt Yes (EPRI)
NTD-NRC-N-4260, DCPiNRC0183 81094 Borchardt Yes (EPRI)
NTD-NRC-N-4260, DCP/NRC0183 81094 Borchardt Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA APSL-92-0094 53092 Murley No ET-NRC-92 3688, NSRA APSL-92-0094 43092' Muriey
' ~#
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-92-3688, NSRA-APSL-92-00W
'It d 30 9i!
Murley
' Buildirtgs" No ET-NRC-92 3726 73192 Murley Guildirgs" Yes ET-NRC-92 3726 73192 Murley No ET-NRC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA APSL-92-00W 43092 Murley Yes ET-N RC-92-3688 NSRA APSL 92-0094 43092 Murley Yes ET-NRC 92-3688, NSRA-APSL-92-0094 43092 Murley No ET-NRC 92 3688 NSRA-APSL-92-00N 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92-00M 43092 Murley i
Buildirtgs" Yes ET-N RC-92-3726 73192 Murley Buildings" No ET-N RC-92-3726 73192 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 3952, NSRA APSL-93-0318 81993 Borchardt No ET-N RC-93-3952, NSRA APSL-93-0318 81993 Borchardt Yes NTD-NRC 94,4056, DCP/NRC0002 2294 Borchardt No NTD-N RC-944056, DCP/NRC0002 2294 Borchardt Yes ET-N RC-92-3688, NSRA APSL-92-00M 43092 Murley No ET NRC-92-3688, NSRA-APSL-92-00N 43092 Murfey No ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Murley Buildirtgs" No ET-NRC-92 3726 73192 Murley Buildir:gs" Yes ET NRC-92 3726 73192 Murley 9408230090-
Westinghouse Electric Corporation
'T '. Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT t
-l~
'L TABLE 7. TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO l 4
DESCRIPTION r*
, 'y
- 21. Wind Tuntwl Test Phase 2 21.1 WCAP-13318,
- Passive Containment Conling System Wind Tunnel Test Specification, Rev. 0*
I 21.2 WCAP-13412," Westinghouse-GOTH!C: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxil I
21.3 WCAP 13246," Westinghouse-GOTHIC: A Computer Code For Analyses of Thermal Hydraulic Transients for Nuclear Plant Containments & Auxil F
21.4 WCAP 13323, Rev. O, " Phase il Wind Tunnel Testing for the Westinghouse AP600 Reactor
- 21.5 WCAP-13324, Rev. O, *Phasa il Wind Tunnel Testing for the Westinghouse AP600 Reactor
- I,-
22, Wind Tunnel Test Phase 4A
(
22.1 WCAP 13318,
- Passive Containment Cooling System Wind Tunnel Test Specification, Rev. 0*
22.2 WCAP-13757," Wind Tunnel Phase 4A Test Plan, investigation of the High Reynolds Number Behavior of the Westinghouse AP600 System,"
22.3 WCAP-13756, " Wind Tunnel Phase 4A Test Plan, investigation of the High Reynolds Number Behavior of the Westinghouse AP600 System."
WCAP-14068, Revision 0, " Phase IVA Wind Tunnel Testing for the Westinghouse AP600 Reactor" 22.4 i
t 22.5 WCAP 14084, Revision 0, " Phase IVA Wind Tunnel Testing for tho Westinghouse AP600 Reactor"
' 23. Whd Tunnel Test Phase 48 f
23.1 WCAP-13318,
- Passive Containment Cooling System Wind Tunnel Test Specification, Rev. 0*
l 23 2 WCAP 14005, " Wind Tunnel Phase 48 Test Plan, investigafon of the Effects of Siting on the Wind Behavior of the Westinghouse AP600 System' 23.3 WCAP-14006,
- Wind Tunnel Phase 48 Test Plan, investigation of the Effects of Siting on the Wind Behavior of the Westinghouse AP600 System" 23.4 WCAP 14091, Revision 0, " Phase IVB Wind Tunnel Testing for the Westinghouse AP600 Reactor" 23.5 WCAP 14092, Revision 0,
- Phase IVB Wind Tunnel Testing for the Westinghouse AP600 Reactor *
- l
- 24. PRHR Heat Exchanger Test - Phase 1 24.1 WCAP-12666,'AP600 Passive Resklual Heat Removal Heat Exchanger Test, Test Report
- 25 PRHR Heat Exchanger Test - Phase 2.
25.1 WCAP 13368, " Passive RHR Heat Exchangor Test Extension, Rev. 0*
25.2 WCAP 13369,
- Passive RHR Heat Exchanger Test Extension, Rev. 0*
25.3 WCAP 13573,"AP600 Passive Residual Heat Exchanger Test Final Report" 25.4 WCAP 12980, Rov.1,"AP600 Passive Residual Heat Exchanger Test Final Report"
~
- 26. Automatic Depresswization System Test. Phase A (Sperger) 26.1 WCAP 13343,'AP600 Automatic Depresurization System Test, Rev,0*
(
26.2 WCAP 13342,'AP600 Automatic Depressurization System Test, Rev 0*
1 i
26.3 Presentation Material from the April 20,1993 Meeting on the AP600 ADS Tests at the VAPORE Facildy q
26.4 Presentation Material from the May 4,1993 Meeting to discuss the AP600 ADS Phase A Test Results j
l 26.5 Presentation Materials from the May 26-27,1993 Meeting on the APG00 ADS Tests 26 6 WCAP-13891, Revision 0,"AP600 Automatic Depressurization System Phase A Test Data Report
- i 26.7 WCAP 14095, Revision 0,"AP600 Automatic Depressurization System Phase A Test Data Report
- j i
> --,----;-,., -, = -., _ - - -.. ~
- -, -... -.. - ~.. - - - - - - - - -..
-m ON TEST PROGIULM OVERVIEW 1C)
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE No ET NRC-92-3688, NSRA-APSL-92-0094 43092 Mudey y Buildirgs*
No ET-NRC-92 3726 73192 Murley y Bddirgs" Yes ET-NRC-92 3726 73192 Mudey Yes ET-NRC-92 3753, NSRA APSL-92 0198 10292 Mudey No ET-N RC-92-3753, NSRA APSL 92 0198 10292 Mudey I*'
4 50 2 Mudey No ET-N RC-92-3688 NSRA-APSL 92-0094 No ET-NRC-%3926, NSRA APSL 93-0250 7j 5 93' ~
Borchardt Yes ET-N RC-93-3926, NSRA-APSL 93-0250 7IS93 Borchardt Yes NTD-N RC-94-4156, DCP/NRC0096
,6694i eq Borchardt No NTD-NRC-94-4156, DCP,NRC0096 0
6'8 94 '
Borchardt
~
No ET-N RC-92-3688, NS RA-APSL-92-00M 43092 Murley Yes NTD-NRC 94 4082, DCP/NRC0020 32194 Borchardt No NTD-NRCM4082, DCP/NRC0020 32194 Borchardt Yes NTD-N RC-94 -4205, DCP/NRC0132 71994 Borchardt No NTD-NRC-94-4205, DCP/NRC0132 7 19 S4 Borchardt Yes NS NRC-90-3525, NPAP APSL 90-0048 71690 Donatell i
l Yes ET-NRC-92 3730, NSRA APSL-92-0161 8792 M eley No ET-N RC-92-3730, NSRA APSL 92-0161 8792 Mudey No ET-N RC-92-3779, NSRA-APSL 92-0259 12 15 92 Mudey 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 NRC-92-3688 NSRA-APSL 92-00M 43092 Murley Yes ET-NRC-%3877 NSRA-APSL-93 0159 53G3 Borchardt Yes ET-NRC-%3879, NSRA-APSL 93-0166 55 93 Borchardt Yes ET-N RC-%3881, NSRA-APSL-93-0197 61 93 Borchardt Yes NTD-NRC-94 4176, OCP/NRC0114 62094 Borchardt No NTD-NRC-94 4176 DCP/NRC0114 62094 Borchardt 9408230090-
- f Westinghouse Electric Corporation Revision 7, August 15,1994 AP600 DESIGN CERTIFICAT i
l
' TABLE 7. TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO I DESCRIPTION
- 27. Automalle Depressurization System Test Phase B 27.1 WCAP 13343,"AP600 Automatic Depresurization System Test, Rev. 0*
i 27.2 WCAP 13342, *AP600 Automatic Depressurization System Test, Rev 0" 27.3 Presentation Material from the April 20,1993 Meeting on the AP600 ADS Tests at the VAPORE Facility 1
27.4 APG00 Automatic Depressurization System Phase B Test Matrix, Revision 1
\\
4 27.5 Preliminary Facility Design Drawirxp for the AF600 ADS Phase B Tests e
27.6 Presentation Materials from the May 2627,1993 Meeting on the AP600 ADS Tests 27.7 AP600 Automatic Depressurization System Phase B Test Matrix, Revision 1 A i
27.8 Presentation Materials from the January 25,1994 Meeting on AP600 ADS Design Certification Test Pians
/
27.9 Additional information in Support of Westinghouse Response to RAI 952.64 on the AP600 Design 27.10 WCAP 14112, Revision 0,'AP600 Automatic Depressurization System - Test Specification (Phase B1)"
27.11 WCAP 14113, Revision 0,"AP600 Automatic Depressurization System - Test Specification (Phase B1)"
27.12 Additionalinformation in Support of Westinghouse Response to RAI 952.27
- 28. Core Makeup Tonk Test 28.1 WCAP-13345, 'AP600 Core Make-Up Tank Test Specifcation, Rev. 0*
28.2 Materialin Support of February 25,1993 Westinghouse /NRC Meeting on CMT Tests for AP600 (Test Matrix, Instrumont List, Drawings)
I 28.3 Presentation Material from the February 25,1993 Westinghouse /NRC meeting on the AP600 CMT Tests l
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, *Scafing Logic for the Core Makeup Tank Test," Revision 0 28.8 WCAP-13975, " Scaling Logic for the Core Makeup Tank Test," Revision 0 J
1 28 9 Response to Roquests for Additional Information on the AP600 Core Makeup Tank Tests 28.10 Presentation Materials from the March 14,1994 Meeting on AP600 Core Makeup Tank Tests and Analysis 28.11 WCAP 13345, 'AP600 Core Make-Up Tank Test Specifcatior, Revision 3*
28.12 Ouick Look Data Report for AP600 Core Makeup Tank Soparate Effects Tests: Hot Prooperational Tests j
28.13 Ouick Look Data Report for AP600 Core Makeup Tank Separate Effects Tests: Cold Prooperational Tests i
(
28.14 WCAP 14132, 'AP600 CMT Program - Facility Description Report
- 28.15 WCAP-14133, *AP600 CMT Program - Facility Description Report
- f i
- 29. DNBR Tests 29.1 WCAP 12488," Westinghouse Fuel Criteria Evaluation Process
- 29.2 Test Matrix for AP600 Departure from Nucleate Boiling Tests 29.3 Quick Look Data Report for AP600 Cntical Heat Flux (CHF) Tests i
._._m
.m m..
. ~,, -
_y-,
[ON TEST PROGRAM OVERVIEW IRC)i PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE 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-NRC-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-@3881, NSRA-APSL-93-0197 61 93 Borchardt Yes ET-NRC-@3881, NSRA APSL-93-0197 61 93 Borchardt Yes NTD-NRC 944050, NSRA-APSL-94-0030 12594 Borchardt Yes NTD-NRC-944109, DCP/NRC0043 42994 Borchardt Yes NTD-NRC-94-4178, DCP/NRC0115 7694 Borchardt No NTD NRC-N 4178, DCP/NRC0115 7694 Borchardt Yes NTD-NRC 944240, DCP/NRC0165 72694 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-NRC-@3829, NSRA APSL-93-0053 22593 Borchardt Yes ET NRC-@3944, NSRA-APSL-93-0303 81693 Borchardt bbD5 T12.20 93 Borchardt Yes ET-N RC-934031,NSRA-APSL-93-0497 No NTD-NRC-94-4068, DCP/NRC0010
- N I 'NUI S 2'2'94 Borchardt Yes NTD-NRC-94-4068, DCP/NRC0010 k-b'b'M h 22 94 Borchardt No NTD-NRC-N 4068, DCP/NRC0010 4 p,., a,,
.22294 Borchardt No NTD-NRC-94 4076, DCP/NRC0015 s APUdOTO I
- 3 4?94 Borchardt Yes NTD-NRC-944081 32194 Borchardt No NTD NRC-94 4133, DCP/NRC0062 51394 Borchardt Yes NTD-NRC-944229, DCP/NRC0155 72994 Borchardt Yes NTD-NRC-944231, DCP/NRC0158 72994 Borchardt Yes NTD-NRC-944244, DCP/NRC0169 72994 Borchardt No NTD-NRC-94-4244, DCP/NRC0169 72994 Borchardt Yes NS-NRC-90-3482 4290 Wilson Yes ET-N RC-93-3984 NSRA APSL-93-0385 10893 Borchardt Yes NTD-NRC-94-4250, DCP/NRC0174 8294 Borchardt 9408230090- [
c.
y
(
Westinghouse Electric Corporation Revision 7, August 15,1994 AP600 DESIGN CERTIFICA'I t
f TABLE 7. TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO DESCRIPTION
- 30. Low Pressure 1/4 Height Integral Systems Tests 30.1 Scaling Report on Glass Model of the AP600 302 WCAP-13234, *AP600 Long Term Cooling Tast Specification, Rev. 0 30.3 WCAP 13283,"AP600 Long Term Cooling Test Specification, Rev. 0"
[
30 4 Draft Scaling Analysis for the OSU AP600 Integral Systems Test
\\
t, 30.5 Matenalin Support of Westinghouse /NRC Meeting on OSU Test Program for AP600 (Test Schedule, Draft Scaling Report, Test Specification Rei Test Matrix and Facility Design Drawings) 30.6 Presentation Material from December 9-10,1992 Westinghouse /NRC Meetings on AP600 Test Program 30.7 Component and Pping Drawing for the AP600 Long Term Cooling Tests 30.8 WCAP-13283 Revision 1,"Long Term Cooling Test,"
30.9 WCAP-13234 Revision 1,"Long Term Cooling Test,"
30.10 Response to INEL Requests for information regarding OSU Long Term Cooling Test Facility (Requests dated April 14,1993 and May 12,1993) 30.11 RELAPS/ MOD 3 input File Notebook for OSU/AP600 Components 30.12 Draft Scaling Analysis for the OSU AP600 Intngral System and Long Term Cooling Test Facility 30.13 Facility Drawings and Piping and Instrumentation Diagrams for the AP600 Long Term Cooling Test Facility at Oregon State University 30.14 Presentation Materials from the September 20,1993 Meeting on AP600 Low Pressure Integral Systems Tests at Oregon State University 30.15 Informatx>n on Test Conditions for AP600 Testing Performed at the SPES-2 and OSU Test Facilities 30.16 WCAP-14124,"AP600 Low Pressure 1/4 Height Integral Systems Tests - Facility Description Report" 30.17 WCAP-14136,"AP600 Low Pressure 1/4 Height integral Systems Tests - Facility Description Report
- 30.18 Ouick Look Data Report for AP600 Long Term Cooling Tests at Oregon State University: OSU Component Volume Determinations 30.19 Ouick Look Data Report for AP600 Long Term Cooling Tests at Oregon State University: OSU Flow Test /Line Resistance Determination 3020 Quick Look Data Report for AP600 Long Term Cooling Tests at Oregon State University: Hot Preoperadonal Test HS01 30.21 Quick Look Data Report for AP600 Long Term Cooling Tests at Oregon State University: Hot Preoperational Test HS02 3022 Ouick Look Data Report for AP600 Long Term Coohng Tests at Oregon State University: Hot Preoperational Test HS03 3023 Ouick Look Data Report for AP600 Long Term Cooling Tests at Oregon State University: Matrix Test SB01 3024 Ouick Look Data Report for AP600 Long Term Cooling Tests at Oregon State University. Matrix Test SB04 3025 Ouick Look Data Report for AP600 Long Term Cooling Tests at Oregon State Unwwsity: Matrix Test SB13 3026 Ouick Lock Data Report for AP600 Long Term Cooling Tests at Oregon State University. Matrix Test SB10 L
i i
arm m**
4-
N TEST PROGRAM OVERVIEW
~-
IC))
l PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE f.
No NPAP-APSL-91-0095 3591 Sheron Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley f
No ET NRC-92-3688, NSRA-APSL-92 0094 43092 MAiey f
Yes ET NRC-92 3715, NSRA-APSL-92-0132 7792 Murley
, Updated Instrumentation Ust, Yes ET-NRC-92 3775, NSRA-APSL-92-0250 11 24 92 Murley l
Yes ET-N RC-92-3785, NSRA APSL-92-0268 12 17 92 Murley l
Yes ET-NRC-93 3830 NSRA-APSL-93-0062 3393 Borchardt l
No ET-NRC 93-3883, NSRA APSL-93-0169 51193 Borchardt l
Yes ET-N RC-93-3883, NSRA-APSL-93-0169 51193 Borchardt Yes ET-N RC-93-3901, NSRA APSL-93-206 61093 Borth vdt
(
Yes ET-NRC-93 3932, NSRA-APSL-93-0273 72793 Wilson f
Yes ET NRC-93-3933, NSRA-APSL-93-0274 72893 Wilson Yes ET-NRC-93-3969, NSRA APSL-93-0350 91793 Borch,udt f
Yes ET-N RC-93-3993, NS RA. APSL-93-0401 10 15 93 Borchardt f
Yes NTD-NRC-94-4070, DCP/NRC0012 41294 Borchardt l
Yes NTD-NRC-944245, DCP/NRC0170 72994 Borchardt
(
No NTD-NRC-N-4245, DCP/NRC0170 72994 Borchardt Yes NTD-NRC-94-4219 DCP/NRC0146 72994 Borchardt f
Yes NTD-NRC-N-4220, DCP/NRC0147 72994 Borchardt Yes NTD-NRC-944221, DCP/NRC0148 72994 Borchardt f
Yes NTD-NRC-94-4222, DCP/NRC0149 72994 Borchardt j
l Yes NTD-NRC-94 4223, DCP/NRC0150 72994 Borchardt Yes NTD-NRC-94-4224, DCP/NRC0151 72994 Borchardt
[
Yes NTD-NRC-94-4225, DCP/NRC0152 72994 Borchardt f
Yes NTD-NRC-944226, DCP/NRC0153 72994 Borchardt f
Yes NTD-NRC-944221, DCP/NRC0154 72994 Borchardt ANSTEC MIN $YObb f A D R w u em l
blw AvaiiaHe on A;wnon Caru 9408230090 -
'{'
Westinghouse Electric Corporation
(
Revision 7, August 15,1994 AP600 DESIGN CERTIFICATl f
. TABLE 7-YEST PROGRAM RENERENCES (
SUMMARY
dF WESTINGHOUSE AP600 TEST PROGRAM RELATED DESCRIPTION
- 31. Full Pressure Full Height Integral Systems Tests 31.1 WCAP 13277," Scaling Design and Venheation of SPES-2, the Italian Experimental Facility Simulator of the AP600 Plant" 31.2 WCAP-13278," Scaling Design and Verification of SPES-2, the Italian Experimental Facility Simulator of the AP600 Plant" i {
31.3 NRC Request for Additional Information Related to SPES-2 Test Facility
/
31.4 Materialin Support of Westinghouse /NRC Meeting on SPES Test Program for AP600 (Test Schedule, Draft Scaling Report Draft Test Specificatic 31.5 Presentation Material from December 9-10,1992 WestinghouseNRC 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, "Scahng Design, and Verification of SPES 2, The Italian Experimental of the AP600; Scaling Updato" 31.9 WCAP-13277 Revision 1, " Scaling Design, and Venfication of SPES-2, The Italian Experimental of the AP600; Scaling Update
- 31.10 SPES-1 Pump Characterization, SIET NT/54 31 11 Response to INEL Request for SPES-2 InformatiorVClarification MGO-29-93 31.12 SPES-1 System Description, SIET NTt32 31.13 Information on Test Conditions for AP600 Testing Performed at the SPES-2 and OSU Test Facilities 31.14 WCAP-14053. Revision 0, "AP600 FHFP Integral Systems Test Specification" 31.15 WCAP-14056, Revision 0, "AP600 FHFP Integral Systems Test Specification" 31.16 Initial Condition Data for AP600 SPES-2 Matrix Test 4 31.17 WCAP-14073, Revision 0, "SPES-2 Facility Description
- 31.18 WCAP-14074, Revision 0, "SPES-2 Facihty Description" 31.19 Ouick Look Data Report for AP600 SPES 2 Integral Systems Tests: Cold Prooperational Test Results 31.20 Quick Look Data Report for AP600 SPES 2 Test S00303 (Matrix Test 3) 31.21 Quick Look Data Report for AP600 SPES-2 Test S00504 (Matrix Test 4) 1 31.22 Quick Look Data Report for AP600 SPES 2 Test S00605 (Matrix Test 5) e 31.23 Quick Look Data Report for AP600 SPES-2 Test S00706 (Matrix Test 6) 31.24 Test Description for AP600 SPES-2 Test S00908 (Matrix Test 8 Blind) 31.25 Ouick Look Data Report for AP600 SPES-2 Test S01007 (Matrix Test 7) j 1
31.26 Quick Look Data Report for AP600 SPES-2 Test S01110 (Matrix Test 10)
Ouick Look Data Report for AP600 SPES-2 Tests. Hot Prooperational Tests 31.27 31.28 WCAP-14124 "AP600 Low Pressure 1/4 Height Integral Systems Tests - Facihty Description Report" 31.29 WCAP 14136, *AP600 Low Pressure 1/4 Height integral Systems Tests - Facility Description Report" 31.30 Quick Look Data Report for AP600 SPES-2 Test S00401 (Matrix Test 1) s m e., m m
DN TEST PROGRAM OVERVIEW l
C)
PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-N RC-92-3685, NS RA-APSL-92-0082 4392 Murley No ET-N RC-92-3685, NSRA-APSL-92-0082 4392 Muriey Yes ET-N RC-92-3749, NSRA-APSL-92-0188 91492 Murley
)
Yes ET-N RC-92-3776, NSRA-APSL-92-0251 11 24 92 Murley Yes ET-NRC 92-3785, NS RA-APSL-92-0268 12 17 92 Murley Yes ET-N RC-93-3825, NSRA-APSL-93-0046 22393 Borchardt Yes ET-NRC-93 3877, NSRA-APSL-93-0159 5393 Borchardt No ET-N RC-93 -3883, NSRA-APSL-93-0169 51193 Borchardt Yes ET-N RC-93-3883 NSRA-APSL-93-0169 51193 Borchardt No ET-N RC-93-3943, NSRA-APSL-93-0300 81293 Borchardt No ET-NRC 93 3943, NSRA-APSL-93 0300 81293 Borchardt No ET-NRC-93 3943, NS RA-APSL-93-0300 81293 Borchardt Yes NTD-NRCM4070, DCP/NRC0012 41294 Borchardt Yes NTD-NRC-944122, DCP/NRC0055 5494 Borchardt No NTD-NRC-94-4122, DCP/NRC0055 5494 Borchardt Yes NTD-NRC-94 4164, DCP/NRC0104 61594 Borchardt Yes NTD-NRC-N-4178, DCP/NRC0115 7694 Borchardt No NTD-NRC 944178, DCP/NRC0115 76M Borchardt Yes NTD-NRC-M4193, DCP/NRC0126 76M Borchardt Yes NTD-N RC-94-4206, DCP/NRC0133 72294 Bo chardt Yes NTD-NRC-M-4212, DCP/NRC0139 72994 Borchardt Yes NTD-NRC-M4213, DCP/NRC0140 72994 Borchardt Yes NTD-NRC-M-4214, DCP/NRC0141 72994 Borchardt Yes NTD-NRC 94-4215, DCP/NRC0142 72994 Borchardt Yes NTD-NRC-94-4216, DCP/NRC0143 72994 Borchardt Yes NTD-NRC44217, DCP/NRC0144 72994 Borchardt Yes NTD-NRC-94-4218, DCP/NRC0145 72994 Borchardt Yes NTD-N RC-94 -4245, DCP/NRC0170 72994 Borchardt No NTD-NRC-M 4245, DCP/NRC0170 72994 Borchardt Yes NT D-N RC-94-4211, DCP/NRC0138 72994 Borchardt
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L-Revision 7, August 15,1994 APG00 DESIGN CERTIFICA$
I
. TABLE 7. TEST PROGRAM REFERENCES (
SUMMARY
OF WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO..
i..,
DESCRIPTION
- 32. Other Tests 32.1 WCAP-12668, "AP600 High inertia Rotor Testing - Phase I, Test Report"
)
32.2 WCAP-13299, "RCP Air Model Tost Report, Rev. 0" 32.3 WCAP-12648,"AP600 incore instrumentation System Electromagnetic interference Test Report, Rev.1*
i 32.4 WCAP-13352, " Studies of Hydraulic Phenomena in the Reactor Vessel Lower Plenum Region - Test Report, Rev. 0*
l i
32.5 WCAP-13305, Studies of Hydraulic Phenomena In Reactor Lower Plenum Region - Test Plan
- 32.6 WCAP-13298, "RCP Air Model Test Report, Rev. 0*
1 32.7 WCAP-13322, "AP600 Incore Instrumentation System Electromagnetic Interforence Test Report, Rev. 0*
32.8 WCAP-13312. "Joumal Bearing Test - Task 2 Test specification
- 32.9 WCAP-13313, "Jourr,al Bearing Test - Task Plan For the DOE Phase il High inertia Rotor Test Program" 32.10 WCAP-13320,"AP600 High Inertia Rotor Testing Phase 2 Report, Rev. 0*
32.11 WCAP-12668, "AP600 High inertia Rotor Testing Phase 1 Test Report, Rev.1" 32.12 WCAP-13319, *AP600 High inertia Rotor Testing Phase 2 Report, Rev. O' 32.13 WCAP 13288, " Passive Core Cooling System Check Vafve Test Specification, Rev. 0*
32.14 WCAP-13284," Test Plan For the Passive Core Cooling System Check Valve Test, Rev. O' 32.15 WCAP 13314, " Journal Gearing 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. O'
{
32.17 WCAP-13285," Test Plan For the Passive Core Cooling System Check Valve 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" 32.20 WCAP 13289. " Passive Core Cooling System Check Valve Test Specification, Rev. 0" 32.21 WCAP 13310. "Joumal Bearing Test - Task 1 Test Specification" 32,22 WCAP 13351,
- Studies of Hydraulic Phenomena in the Reactor Vessel Lower Plenum Region - Test Report, Rev,0*
32.23 WCAP-13306," Studies of Hydraulic Phenomena In Reactor Vessel Lower Plenum Region Test Plan
- r 32.24 WCAP 13309, "Joumal Bearing Test - Task 1 Test Specification" 32.25 WCAP-13487, Rev. O,"High inertia Rotor Phase 3 Task 1 Test Report" s
32.26 WCAP-13488,"High inertia Rotor Phase 3 Task 1 Test Report"
(
32.27 WCAP 13560, " Advanced Plant Check Valve Study *, Rev. 0 32.28 WCAP-13743," Heavy Water Reactor Facility Project Phase 1 AP600 Small Scale Passive Containment Cooling System Test 'Ory* Test Results Ai
[
RPT-91 -0021" 32.29 WCAP 13742, " Heavy Water Reactor Facihty Project Phase 1 AP600 Small Scale Passive Containment Cooling System Test ' Dry' Test Results Aj RPT-91 -0021" r
32.30 WCAP-13726, " Heavy Water Reactor Facihty (HWRF) Large Scale Passive Containment Cooling System Baseline Test Data Report HWRF-92-00 32.31 WCAP 13728, " Heavy Water Reactor Facility (HWRF) Small Scale Containment Cooling System Test Final Report HWRF-RPT-92-003, Revision 1 32.32
[
WCAP-13733," Heavy Water Reactor Facihty (HWRF) Small Scale Containment Cooling Test Preliminary Series 2 Test Results HWRF RPT-92-0C 32.33 WCAP 13725 " Heavy Water Reactor Facihty (HWRF) Large Scale Passive Containment Cooling System Baseline Test Data Report HWRF RPTs 32.34 WCAP-13727, " Heavy Water Reactor Facihty (HWRF) Small Scale Containment Cooling System Test Final Report HWRF-RPT-92-003, Revision 1 L
[ON TEST PROGRAM OVERVIEW IRC)
PROPRIETARY THANSMITTAL LETTER DATE ADDRESSEE Yes NS-NRC-90-3525, NPAP-APSL-90-0048 71690 Donatell No ET NRC-92 3688, NSRA-APSL-92-0094 42092 Mudey Yes 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-924688, NSRA-APSL-92-00M 43092 Murley Yes ET NRC 92-3688, NSRA-APSL-92-00M 43092 Mudey No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-N RC-92-3688, NS RA-APSL-92-0094 43092 Mudey 5
Yes ET-N RC-92-3688, NSRA-APSL-92 0094 ISO 92 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092-Mudey
~
Yes ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey Yes ET-NRC-92 3688, NSRA-APSL-92-0094
- 43092, Murley Yes ET NRC 92-3688, NSRA-APSL 92-0094 4 80'92 Murley Yes ET NRC-92-3688, NSRA-APSL-92-0094 43092 Mudey No ET-N RC-92-3688, NSRA APSL-92-0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL-92-0094 43092 Mudey No ET-NRC-92 3688, NSRA-APSL-92-0094 43092 Mudey No ET NRC-924688, NSRA APSL-92-00M 43092 Mudey Yes ET NRC-92-3688, NSRA-APSL-92-0094 43092 Murioy No ET NRC-92-3688, NSRA-APSL-92-0094 43092 Murley No ET-NRC-92-3688, i 3RA APSL-92-0094 43092 Murley Yes ET-N RC-92-3688, NSRA-APSL-92 0094 43092 Murley No ET-N RC-92-3688, NSRA-APSL 92-00M 43092 Murioy Yes ET-NRC 92-3688 NSRA-APSL-92-00N 43092 Murley Yes ET-N RC-92-3753, NSRA-APSL-92-0198 to 2 92 Mudey No ET-N RC-92-3753, NSRA-APSL-92 0198 10292 Mudey No ET-N RC-93-3801, NSRA APSL-93-0012 12593 Mudey Acab'a to ths HWRF Project NPR-No ET-N RC-93-3903, NSRA-APSL-93-0208 61493 Borchardt alicable to the HWRF Project NPR.
Yes ET-N RC-93-3903, NSRA-APSL-93-0203 61493 Borchardt
" R; vision 1 No ET NRC-93 3903, NSRA-APSL-93 0208 61493 Borchardt No ET-NRC-93-3903, NSRA-APSL 93-0208 61493 Borchardt No ET NRC-93-3903, NSRA-APSL-93-0208 61493 Borchardt l-004," Revisbn 1 Yes ET-N RC-93-3903, NSRA-APSL-93-0208 61493 Borchardt Yes ET-NRC 93-3903, NSRA-APSL-93-0208 61493 Borchardt 9408230090 - g
4-j Westinghouse Electric Corporation i
Itevision 7, August 15,1994 AP600 DESIGN CERTIFICNI I
I
~
TABLE 7. TEST PROGRAM REFERENCES (
SUMMARY
0F WESTINGHOUSE AP600 TEST PROGRAM RELATED MATERIALS TRANSMITTED TO DESCRIPTION 32.35 WCAP 13732, " Heavy Water Reactor Facikty (HWRF) Small Scale Containtnent Cooling Test Preliminary Series 2 Test Results HWRF-RPT 92-(
32.36 WCAP-13758, "High Inertia Rotor Test Phase 3 Report," June,1993
}
32.37 WCAP-13759, "High inertia Rotor Test Phase 3 Report," June,1993 1
32.38 WCAP-13415, "High Inertia Rotor Test 3 Task 1. Test Specification,"
[
32.39 WCAP-13413, *RCP Hydraulic Flow Test Prospectus."
32.40 WCAP-13420,"High Inertia Rotor Test Phase 3 Test Plan,"
32.41 WCAP-13419, "High inertia Rotor Test Phase 3 Test Plan,"
32.42 WCAP-13414,."RCP Hydraulic Flow Test Prospectus,"
s 32.43 M. H. Kim, %delling of Condensation Heat Transfer in a Reactor Containment." PhD Thesis (1985) 32.44 WCAP-14045, "In Situ Check Valve Test Report (Fall Outage '93)*
32.45 APWR-0452-P "AP600 Vortex Mdigator Developrnent Test for RCS Mid Loop Operation"
(
32.46 APWR4452-NP,"AP600 Vortex Mitigator Development Test for RCS Mid Loop Operation
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PROPRIETARY TRANSMITTAL LETTER DATE ADDRESSEE Yes ET-NRC-93 3903, NSRA-APSL 93-0208 61493 Borchardt Yes ET-NRC-93-3918, NSRA APSL 93-0238 7793 Borchardt No ET-NRC-93 3918, NSRA APSL-93-0238 7793 Borchardt No ET-NRC-93-392G, NSRA APSL-93-0250 71593 Borchardt Yes ET-N RC-93-3926 NSRA APSL-93-0250 71593 Borchardt No ET NRC-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 NRC-93-3945, NSRA-APSL-93-0304 81693 Borchardt No NTD-NRC 94-4120, DCP/NRC0053 5494 Borchardt Yes NTD-NRC-94-4191, DCP/NRC0124 7694 Borchardt No NTD-N RC-94-4191, DCP/NRC0124 7694 Borchardt p, 4. e.... -_ s
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AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 8 - Summary of NRC Requests for additional Information (RAI) related to AP600 Tests and Analysis RAI No.
Description / Issue NRC Ltr. Date Westinghouse Response West. Response letter Letter No.
Date 440.001 SPES test, check valve testing & PRHR testing 09/23S2 ET-NRC-92-3777 11/30/92 440.001R01 SPES test, check valve testing & PRHR testing 09/23 S 2 NTD-NRC-94-4236 07/25/94 440.001R02 SPES test, check valve testing & PRHR testing I
440.002 CMT testing 09/23S2 ET-NRC-93-3795 01/14 S 3 440.002R01 CMT testing 09/23 S 2 NTD-NRC-94-4087 03/24/94 440.002R02 CMT testing 440.003 CMT testing 09/23S2 ET-NRC-93-3804 01/22/93 440.004 CMT testing 09/23B2 ET-NRC-92-3777 11/30/92 440.004R01 CMT testing 09/23/92 NTD-NRC-94-4087 03/24 S 4 440.005 CMT testing 09/23S2 ET-NRC-92-3777 11/30S 2 440.005R01 CMT testing 09/23S2 NTD-NRC-94-4087 03/24 S 4 440.006 CMT testing 09/23S2 ET-NRC-92-3777 11/30/92 440.006R01 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 09/23S 2 ET-NRC-92-3777 11/30/92 440.009 CMT testing 09/23/92 ET-NRC-92-3777 11/30/92 440.010 CMT testing 09/23/92 ET NRC-92-3777 11/30S 2 440.010R01 CMT testing 09/23/92 NTD-NRC-94-4087 03/24 S 4 440.011 ADS testing -
09/23 S 2 ET-NRC-92-3777 11/30/92 440.011R01 ADS testing 09/23 S 2 NTD-NRC-94-4236 07/25B4 440.012 ADS testing 09/23/92 ET-NRC-92-3777 11/30/92 440.012R01 ADS testing 440.013 ADS testing 09/23S2.
ET-NRC-93-3804 01/22 S 3 440.013R01 ADS testing NTD-NRC-94-4059 02/03/94 440.014 ADS testing 09/23 S 2 ET-NRC-93-3804 01/22 S 3 440.014R01 ADS testing 09/23 S 2 NTD-NRC-94-4259 08/10/94 440.015 ADS testing 09/23/92 ET-NRC-92-3777 11/30/92 440.016 ADS testing.
09/23 S 2 ET-NRC-93-3795 Ol/14S3 440.017 ADS testing 09/23/92-ET-NRC-93-3804 31/22/93 440.018 ADS testing 09/23 S 2 ET-NRC-93-3804 41/22S 3
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Wrt$S2 LalPtMLCMP41@J W/2?2H3 440.021 Post 72-hour operation 09/23S2 ET-NRC-93-3304 01/2293 440.022 Fuel design and analysis 09/23S2 ET-NRC-92-3789 12/22 S 2 440.023 Mid-loop operations 09/2392 ET-NRC-92-3789 12/22B2 440.024 Analytical codes 09/23/92 ET-NRC-93-3804 Ol/22S3 440.024R01 Analytical codes 440.025 Appendix K 09/23/92 ET-NRC-93-3804 01/22B3 440.026 ATWS 09/23S2 ET-NRC-93-3804 01/22S3 440.026R01 ATWS 09/23/92 NTD-NRC-94-4075 03/04 S 4 440.027 Multiple SGTR 09/23S2 ET-NRC-93-3804 Ol/22S3 440.027R01 Multiple SGTR (Revised Response) 440.028 Tech Specs for nonsafety systems 09/23S2 ET-NRC-93-3795 01/14S3 440.029 Safe shutdown; PRA evaluation of safe shutdown 09/23S2 ET-NRC-93-3804 01/22/93 440.030 Interfacing system LOCA 09/23S 2 ET-NRC-92-3789 12/22 S 2 440.031 Credit in analysis for nonsafety systems 09/23/92 ET-NRC-93-3804 Ol/22S3 440.032 Emergency response guidelines 01/26S 3 ET-NRC-93-3886 05/14S3 440.032R01 Emergency response guidelines 440.033 Applicability of 3-tube PRHR tests 02/18/93 ET-NRC-93-3905 06/17 S 3 440.034 CMT scaling tests 02/18/93 ET-NRC-93-3886 05/14 S 3 440.034R01 CMT scaling tests NTD-NRC-94-4110 G4/28S4 440.035 LOFTRAN/NOTRUMP AP600 models 08/05 S 3 ET-NRC-93-4007 II/04S3 440.035R01 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 S 4 440.037 PRHR heat exchanger heat transfer 11/02/93 NTD-NRC-94-4059 02/03S 4 440.038 Hydrogen venting from the pressurizer 11/02S 3 NTD-NRC-94-4059 02/03S4 440.039
" failure of a CMT discharge valve" 11/02S 3 NTD-NRC-94-4059 02/03/94 440.040 MSLB analysis, feed flow assumptions 11/02/93 NTD-NRC-94-4059 02/03/94 440.041 MSLB minimum DNBR plot 11/02/93 NTD-NRC-94-4059 02/03/94 440.042 Feedline break PRHR delay rationale 11/02S 3 NTD-NRC-94-4059 02/03S 4 440.043 Locked rotor failed fuel assumptions 11/02S 3 NTD-NRC-94-4059 02/03 S 4 440.044 Rationale for locked rotor being limiting 11/02/93 NTD-NRC-94-4059 02/03/94 440.045 Rod ejection failed fuel assumptions 11/02S 3 NTD-NRC-94-4059 02/03/94 440.046 Inadvertant 4th stage opening at pressure 11/02S 3 NTD-NRC-94-4059 02/03 S 4 j
440.047 SGTR-SG overfill analytical results 11/02S3 NTD-NRC-94-4059 02/03 S 4 Key:
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440.079 Tests for NRHRS relief valves 04/29 S 4 NTD-NRC-94-4202 07/15B4 440.080 Operator ections for low temperature operation 04/29/94 NTD-NRC-94-4254 08/03/94 440.081 TS LCO 3.4.13, LTOP system 04/29B4 NTD-NRC-94-4184 06/30/94 440.082 TS LCO 3.4.13, increasing RCS temperature 04/29/94 NTD-NRC-94-4181 06/27S 4 440.083 Required MSSV relief capacity 04/29S4 NTD-NRC-94-4254 08/03 S 4 440.084 Quality group classification for LTOP system 04/29 S 4 NTD-NRC-94-4181 06/27/94 440.085 Emergency core makeup & boration 05/02/94 NTD-NRC-94-4184 06/30S 4 440.086 Availability of PXS during refueling conditions 05/02/94 NTD-NRC-94-4181 06/27 S 4 440.087 Boration capability to restore shutdown margin 05/02B4 NTD-NRC-94-4184 06/30/94 440.088 PXS nonsafety-related design requirements 05/02B4 NTD-NRC-94-4184 06/30/94 440.089 ADS actuation frequency 05/02B4 NTD-NRC-94-4181 06/27S 4 440.090 PXS component parameters 05/02/94 NTD-NRC-94-4257 08/08/94 440.091 Break in PRHR heat excharger common lines 05/02/94 NTD-NRC-94-4181 06/27/94 440.092 PXS/PCS safe shutdown capability 05/02S 4 NTD-NRC-94-4184 06/30S 4 440.093 PRHR heat exchanger design transients 05/02S 4 NTD-NRC-94-4234 07/22S 4 440.094 SG channel head injection nozzle thermal stress 05/02S 4 NTD-NRC-94-4234 07/22S 4 440.095 Systematic search for ASIS 05/02S 4 440.096 Refueling cavity flooding 05/02B4 NTD-NRC-94-4234 07/22/94 440.097 IRWST spill flow during DVI line break 05/02B4 NTD-NRC-94-4194 07/08S 4 440.098 Thermal / vibration effects of direct vessel inj.
05/02/94 NTD-NRC-94-4254 08/03B4 440.099 SSAR Table 6.3-1, sheet 1 05/02S 4 NTD-NRC-94-4181 06/27/94 440.100 PXS valve failure states 05/02/94 NTD-NRC-94-4184 06/30/94 440.101 PXS features and compliance with GDC 4 05/02/94 NTD-NRC-94-4234 07/22 S 4 440.102 Accumulator P&ID 05/02S 4 NTD-NRC-94-4181 06/27 S 4 440.103 PRHR operation beyond 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 05/02 S 4 NTD-NRC-94-4184 06/30S 4 440.104 CMT check valve arrangement 05/02S 4 NTD-NRC-94-4184 06/30S4 440.105 PXS single passive failure NTD-NRC-94-4234 07/22/94 440.106 CMT inlet & outlet valve stroke times 05/02S 4 NTD-NRC-94-4254 08/03 S 4 440.107 SSAR Section 6.3.3.1.1 05/02B4 NTD-NRC-94-4181 06/27/94 440.108 Steam generator overfill protection 05/02S 4 NTD-NRC-94-4234 07/22S 4 440.109 SSAR Section 6.3.1.1 05/02S 4 NTD-NRC-94-4234 07/22/94 440.110 Steam generator safety valve failure to close 05/02S 4 NTD-NRC-94-4234 07/22S 4 440.111 Justification for small break LOCA size 05/02/94 NTD-NRC-94-4237 07/27/94 Key:
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Table 8 - Summary of NRC Requests for additional Information (RAI) related to AP600 Tests and Analysis RAI No.
Description / Issue NRC Ltr. Date Westinghouse Response West. Response Letter Letter No.
Date 440.112 Extended operation by PRHR heat exchangers 05/02/94 NTD-NRC-94-4184 06/30S 4 440.113 Operator actions during mid-loop operation 05/02S 4 NTD-NRC-94-4184 06/30/94 440.114 Loss of NRHRS during refueling 05/02S 4 NTD-NRC-94J 181 06/27 S 4 440.115 ADS actuation after extended loss of ac power 05/02/94 NTD-NRC-94-4181 06/27B4 440.116 TS LCO 3.5.3 05/02S4 NTD-NRC-94-4234 07/22/94 440.117 TS LCOs 3.4.12, 3.5.2, 3.5.3 & 3.5.4 05/02/94 NTD-NRC-94-4234 07/22 S 4 440.118 Technical specification TBDs 05/02S 4 NTD-NRC-94-4234 07/22/94 440.119 ADS valves 05/02/94 NTD-NRC-94-4234 07/22/94 440.120 Boron dilution 05/02/94 440.121 Emergency procedures for feed & bleed operation 05/02S 4 NTD-NRC-94-4257 08/0SS4 440.122 DWS makeup isolation actuation logic 05/16/94 NTD-NRC-94-4249 07/29/94 440.123 Commercial service record of canned motor pumps 05/11/94 NTD-NRC-94-4184 06/30/94 440.124 RCP performance characteristics 05/11/94 NTD-NRC-94-4184 06/30/94 440.125 Credit taken for CVCS 05/11/94 NTD-NRC-94-4171 06/16/94 440.126 PRHRS capabilities w/o pressurizen heater control 05/11/94 NTD-NRC-94-4234 07/22B4 440.127 RNS safety classification 05/11/94 NTD-NRC-94-4181 06/27/94 440.128 RNS capabilities with single failure 05/11/94 NTD-NRC-94-4249/
07/29 S 4 440.129 RNS cooling with IRWST 05/1164 NTD-NRC-94-4181 06/27/94 440.130 RNS functions during shutdown operations 05/IIS4 NTD-NRC-94-4184 06/30/94 440.131 RNS design requirements under RTNSS 05/11/94 NTD-NRC-94-4249 07/29 S 4 440.132 RCS pathways to outside containment 05/1IS4 NTD-NRC-94-4234 07/22/94 440.133 RNS pump suction 05/11 S 4 NTD-NRC-94-4236 07/25/94 440.134 RNS isolation valves 05/11/94 NTD-NRC-94-4184 06/30/94 440.135 Pathway from IRWST to refueling cavity via RNS 05/11/94 NTD-NRC-94-4181 06/27/94 440.136 PXS performance upon RNS operation 05/11/94 NTD-NRC-94-4249 07/29S4 440.137 Conformance to RG 1.68 05/11/94 NTD-NRC-94-4184 06/30/94 440.138 RNS interlocks 05/11/94 NTD-NRC-94-4184 06/30S4 440.139 Inadvertent closure of RNS suction isolation valve 05/11/94 NTD-NRC-94-4181 06/27/94 440.140 GDC compliance for RNS 05/11/94 NTD-NRC-94-4184 06/30/94 440.141 RV head vent system 05/11/94 NTD-NRC-94-4184 06/30/94
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440.144 Venting from steam generator U-tubes 05/11S 4 ITTD-NRC-94-4184 06/30S4 440.145
_ WCOBRAfrRAC 05/05S 4 NTD-NRC-94-4259 08/10S 4 440.146 WCOBRAfrRAC 05/05/94 NTD-NRC-94-4257 OS/08S4 440.147 WCOBRAfTRAC-05/05/94 NTD-NRC-94-4257 08/08S 4 440.148 WCOBRAfrRAC 05/05S 4 NTD-NRC-94-4259 08/10S 4 440.149 WCOBRA/ TRAC 05/05/94 NTD-NRC-94-4257 08/08B4 440.150 WCOBRAfrRAC 05/05 S 4 NTD-NRC-94-4257 08/08/94 440.151 WCOBRAfrRAC 05/05S 4 NTD-NRC-94-4257 08/08S 4 440.152 WCOBRAfrRAC 05/05/94 NTD-NRC-94-4257 08/08S 4 440.153 WCOBRAfrRAC 05/05S4 NTD-NRC-94-4257 08/08S 4 440.154 WCOBRAfrRAC
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05/05S 4 NTD-NRC-94-4259 08/10/94 440.155 WCOBRAfrRAC 05/05/94 NTD-NRC-94-4259 08/10/94 440.156 WCOBRAfrRAC 05/05 S 4 NTD-NRC-94-4257 08/08/94 440.157 Controls on isolation of unborated water sources 05/16/94 NTD-NRC-94-4181 06/27/94 440.158 CVCS design pressures 05/16/94 NTD-NRC-94 4234 07/22S 4 440.159 Design of pressurizer safety valves 05/16/94 NTD-NRC-94-4181 06/27 S 4 440.160 Relief & safety valve power sources & QA 05/16/94 NTD-NRC-94-4234 07/22/94 440.161 Remote venting of PRHR heat exchangers 05/16/94 NTD-NRC-94-4181 06/27S 4 440.162 RVLIS 05/16/94 NTD-NRC-94-4264 08/12/94 440.163 Conformance to TMI action items 05/16/94 NTD-NRC-94-4234 07/22/94 440.164 Loose parts monitoring system 05/16/94 NTD-NRC-94-4171 06/16S4 440.165 Startup feedwater isolation valves 05/16S4 NTD-NRC-94-4237 07/27 S 4 440.166 GSI-129 & GSI-137 05/16/94 NTD-NRC-94-4234 07/22S 4 440.167 Main steamline break analysis assumptions 05/26S 4 NTD-NRC-94-4254 08/03/94 440.168 Shutdown operations 05f26/94 NTD-NRC-94-4254 08/03S 4 440.169 CMT, accumulator, IRWST boron conc. adjustment 06/01/94 NTD-NRC-94-4234 07/22/94 440.170 Multiple SGTR analysis 06/01/94 440.171 HF analysis inclusion of high point vent operation 06/01S 4 NTD-NRC-94-4236 07/25/94 440.172 Operation of high point vents 06/01/94 NTD-NRC-94-4234 07/22/94 440.173 PRA quantitative reliability / availability missions 06/08/94 440.174 Regulatory significance of CVS 06/08/94 440.175 Credit of beyond design basis performance 06/08/94 440.176 Methods to identify adverse systems interactions 06/08/94 NTD-NRC-94-4257 08/08/94 Key:
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Table 8 - Summary of NRC Requests for additional Information (RAI) related to AP600 Tests and Analysis RAI No Description / Issue NRC Ltr. Date Westinghouse Response West. Response Letter Letter No.
Date 440.177 Correspondence of code runs & success criteria 06/08/94 NTD-NRC-94-4254 08/03/94 440.178 ADS success criteria 06/08/94 440.179 Localized pressure effects on ADS performance 06/08/94 440.180 ADS success criteria for medium LOCA 06/08/94 440.181 Time available for manual actuation of ADS 06/08/94 NTD-NRC-94-4249 07/29/94 440.182 ADS success criteria for small break LOCA 06/08 S 4 440.183 Success criteria ATWS event 06/08/94 NTD-NRC-94-4254 08/03/94 440.184 ADS success criteria for SGTR 06/08B4 440.185 CMT/ Accumulator success / failure configuration 06/08B4 NTD-NRC-94-4254 08/03/94 440.186 CMT success criteria for SGTR 06/08/94 NTD-NRC-94-4254 08/03 S 4 440.187 CMT success criteria for steamline break 06/08/94 NTD-NRC-94-4254 08/03S 4 l
440.188 PRHRS success criteria for SGTR 06/08/94 NTD-NRC-94-4254 08/03/94 440.189 PRHRS success criteria for small breaks / transients 06/08/94 j
440.190 Effects of design changes on PRA success criteria 06/08/94 NTD-NRC-94-4249 07/29/94 440.191 IE frequency increase in focused PRA 06/08/94 l
440.192 RCP trip following loss of CCW 06/08/94 440.193 Loss of instrument air on PRHR throttling 06/08/94 NTD-NRC-94-4254 08/03/94 440.194 Recovery factors for LOOP 06/08/94 1
440.195 SGTR probcbility for MSLB or open sec. relief valv 06/08/94 440.196 Success paths for MSLB upstream of MSIV 06/08/94 NTD-NRC-94-4249 07/29/94 440.197 Secondary side condensation effect on boron cone.
06/08S 4 440.198 Credit for PRHR control in RTNSS evaluation 06/08S 4 NTD-NRC-94-4249 07/29/94 440.199 Recirculation in tree SIS 06/08/94 NTD-NRC-94-4249 07/29/94 440.200 ADS actuation frequency 06/08/94 NTD-NRC-94-4254 08/03/94 440.201 Non-coherence in very small break LOCA event tree 06/08/94 440.202 Credit for break isolation in PRHR break tree 06/08/94 NTD-NRC-94-4257 08/08/94 1
440.203 Makeup water needed for extended PRHRS operation 06/08/94 NTD-NRC-94-4257 08/08/94 440.204 Mission times used in event tree analyses 06/08/94 440.205 Sequence 24 of LOOP event tree 06/08/94 440.206 Success paths which allow cladding damage 06/08/94 440,207.
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~ 440.209 Seismic event at shutdown 06/08S 4 440.210 lE analyzed at hot & cold shutdown 06/08S 4 440.211 Quantification of event trees for shutdown 06/08S 4 440.212 Maintenance unavailability during shutdown 06/08S 4 NTD-NRC-94-4254 08/0394 440.213 Reflux cooling in event trees for midloop op.
06/08S 4 NTD-NRC-94-4254 08/03S 4 440.214 Use of freeze seals; PRA accountability 06/08/94 440.215 ADS actuation following CMT failure 06/08/94 440.216 ADS 4 pressure interlock value; squib valve act.
06/08S 4 440.217 ADS MOV failure repairs at power 06/08/94 440.218 Minimum RCS inventory needed for PRHRs operation 06/08S 4 440.219 RCS makeup in steamline break event tree 06/08/94 NTD-NRC-94-4264 08/12B4 440.220 Verification of PRHRs HX tube integrity 06/08S 4 440.221 Radiolytic gas impact on PRHRS operation 06/08S4 NTD-NRC-94-4257 08/08/94 440.222 Sequence 6 of S2 event tree 06/08S4 440.223 Sequence 1 of SGTR event tree 06/08/94 NTD-NRC-94-4254 08/03/94 440.224 Sequences 23 & 29 of ATWS event tree 06/08/94 440.225 Sequences of LOOP event tree with PRHRS success 06/08S 4 NTD-NRC-94-4264 08/12S 4 440.226 Effect of noncondensibles on PRHRS operation 06/08/94 440.227 Effect of PRHRS on plant behavior during SB LOCA 06/08/94 440.228 Effect of pzr safety valve flow on CMT operation 06/08/94 NTD-NRC-94-4264 08/12/94 440.229 Modeling of SG PORVs & SG safety valves 06/08/94 440.230 Capacity of deaerated storage tank 06/08/94 440.231 Deboration during startup; LOOP during deboration 06/08/94 NTD-NRC-94-4264 08/12/94 440.232 Definition of small break LOCA 06/08/94 440.233 Medium break LOCA frequency 06/08/94 440.234 Ruptures in regenerative HX; letdown HX; demins 06/08/94 440.235 Maintenance of components inside containment 06/08/94 NTD-NRC-94-4234 07/22B4 440.236 Letdown orifice bypass valve during RNS operation 06/08/94 NTD-NRC-94-4234 07/22/94 440.237 Dependancy on CCW system in PRA 06/08/94 440.238 CCW success criteria in shutdown modes 06/08/94 NTD-NRC-94-4254 08/03/94 440.239 Wide range level instrumentation 06/08/94 NTD-NRC-94-4264 08/12/94 440.240 Time available to restore offsite power 06/08S 4 NTD-NRC-94-4264 08/12 S 4 l
440.241 RCS conditions 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after loss of RNS 06/08S 4 NTD-NRC-94-4264 08/12/94 w
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[ 480.024 Core debris equilibrium height 07/C1/93 ET-NRC-93-3962 0 03B3 480.025 Core debris coolability/ mace 07/01/93 ET-NRC-93-3962 09/03ST 480.026 Containment integrity / liner penetration 07/01/93 ET-NRC-93-3962 09/03B3 480.027 Deflagration /dctonation of combustible gases 07/01B3 ET NRC-93-3980 10/04S 3 480.028 Hand calculations 07/01S 3 ET-NRC-93-3980 10/04S 3 480.029 Long-term radial ablation 07/0lS3 ET NRC-93-3962 09/03B3 480.030 Heat removal from core debris 07/01/93 ET-NRC-93-3962 09/03S 3 480.031 Water ingression into solidified debris 07/01/93 ET-NRC-93-3962 09/03/93 480.032 Prediction of hydrogen distribution 07/01S 3 ET-NRC-93-3980 10/04/93 480.033 Passive autocatalytic recombiners 07/01/93 ET-NRC-93-3962 09/03S 3 480.034 Rationale for hydrogen igniter placement 07/01/93 ET-NRC-93-3962 09/03B3 480.035 Localized detonations, DDT mechanisms 07/0lS3 ET-NRC-93-3962 09/03/93 480.036 Diffusion flames above IRWST 07/01/93 ET-NRC-93-3980 10/04B3 480.036R01 Diffusion flames above IRWST 480.037 Mechanisms for uniform hygrogen distributions 07/01/93 ET-NRC-93-3980 10/04/93 480.038 Igniter placement criteria 11/02S 3 NTD-NRC-94-4059 02/03/94 480.039 Igniter coverage of hydrogen source locations 11/02/93 NTD-NRC-94-4059 02/03/94 480.040 Subcompartments without igniters 11/02B3 NTD-NRC-94-4059 02/03/94 480.041 Criteria on ;gniter separation 11/02S 3 NTD-NRC-94-4059 02/03S 4 480.042 Igniter electrical power source 11/02/93 NTD-NRC-94-4059 02/03/94 480.043 Structural response / detonation calculations 11/02/93 NTD-NRC-94-4059 02/03/94 480.044 Potential for large hydrogen concentration 11/02/93 NTD-NRC-94-4059 02/03/94 480.045 Igniter reliability given one per room 11/02S 3 NTD-NRC-94-4059 02/03/94 480.046 Igniter in Technical Specifications 11/02 S 3 NTD-NRC-94-4038 01/12/94 480.047 Review of hydrogen experimental databases 11/02/93 NTD-NRC-94-4059 02/03/94 480.048 Equipment survivability in " burn zones" 11/02/93 NTD-NRC-94-4059 02/03/94 480.049 Provisions for Type C testing, Table 6.2.3-1 04/29/94 NTD-NRC-94-4236 07/25B4 480.050 Type C testing of service air 04/29/94 NTD-NRC-94-4236 07/25/94 480.051 Component cooling system isolation signals 04/29S 4 NTD-NRC-94-4171 06/16S 4 480.052 SSAR Tabic 6.2 3-1 & Figure 9.2.4-1 04/29 S 4 NTD-NRC-94-4236 07/25/94 480.053 Cont pressure instrument line penetration RG 1.11 04/29/94 NTD-NRC-94-4194 07/08/94 480.054 Type C testing of RHR suction isolation valves 04/29/94 NTD-NRC-94-4194 07/08S 4 480.055 Inidentified NRHR penetrations 04/29/94 NTD-NRC-94-4249 07/29/94 Key: ? >F 1> 440 NRR - Reactor Systems Branch _j[u e 480 NRR - Containment Systems Branch f N f;, 951 RES (Containment Systems) Ni1 ?.o rn v. 952 RES (Reactor Systems) k$ hf O [, = m I' 9408230090---2 )
~ =~~-- a I Westinghouse Electric Corporation 4 Revision 7 August 15,1994 { AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 8 - Summary of NRC Requests for additional Information (RAI) related to AP600 Tests and Analysis RAI No. Description / issue NRC Ltr. Date Westinghouse Response West. Response Letter Letter No. Date 480.056 Relief valves as containment isolation barriers 04/29/94 NTD-NRC-94-4236 07/25 S 4 480.056R01 Relief valves as containment isolation barriers NTD-NRC-94-4259 08/10/94 480.057 LTC signal 04/29/94 NTD-NRC-94-4189 07/01/94 480.058 Airlock seal testing as reduced pressure 04/29S 4 NTD-NRC-94-4237 07/27/94 480.059 Method of testing spare penetrations 04/29/94 NTD-NRC-94-4189 07/01/94 480.060 manual vs remote manual 04/29S 4 NTD-NRC-94-4236 07/25/94 480.061 Chilled water return isolation valve size 04/29/94 NTD-NRC-94-4237 07/27 S 4 480.062 Steam generator isolation valve closure time 04/29 S 4 NTD-NRC-94-4181 06/27B4 480.063 Nonsafety power supply for hydrogen recombiners 04/29 S 4 NTD-NRC-94-4189 07/0164 480.064 Rate of hydrogen generation due to radiolysis 04/29S 4 NTD-NRC-94-4254 08/03S 4 480.065 Potential for drain clogging from coatings 04/29S 4 NTD-NRC-94-4194 07/08/94 480.066 Margin between max calculated & design cont press 04/29S 4 NTD-NRC-94-4236 07/25 S 4 480.067 HT coefficient sensitivity to node size near wall 04/29S 4 NTD-NRC-94-4234 07/22S 4 l 480.068 Postulated break size for subcompartment analyses 04/29S 4 NTD-NRC-94-4236 07/25 S 4 480.069 Use of TMD code for M&E releases 04/29 S 4 NTD-NRC-94-4236 07/25 S 4 480.070 Containment pressure analyses for ECCS performance 04/29S4 NTD-NRC-94-4237 07/27/94 480.071 Testing of containment heat transfer 04/29/94 NTD-NRC-94-4189 07/01/94 480.072 Credit taken for secondary containment during DBA 04/29 S 4 NTD-NRC-94-4181 06/27/94 i 480.073 Closure time for containment isolation valves 04/29S 4 NTD-NRC-94-419407/08S4 480.074 Recombiner power supply; post-LOCA cont purging 04/29/94 NTD-NRC-94-4234 07/22S 4 l 480.075 Containment leakage testing 04/29 S 4 NTD-NRC-94-4202 07/15/94 480.076 Containment penetrations beyond " state of art" 04/29S 4 NTD-NRC-94-4249 07/29/94 480.077 Isolation valves >10 ft from cont wall 04/29/94 480.078 Max cont P,T for severe accident conditions 04/29S 4 NTD-NRC-94-4184 06/30/94 480.079 Fuel-coolant interaction parameters 06/16/94 951.001 Calculation of condensate collection 07/14/93 ET-NRC-93-3980 10/04S 3 951.002 Tests for condenser behavior 07/14/93 ET-NRC-93-3962 09/03/93 951.003 Affect of condensate uncertainty on LOCA 07/14S3 ET-NRC-93-3963 09/10 S 3 951.004 Dead volumes for condensate 07/14/93 ET-NRC-93-3980 10/04/93 951.005 Description of sump 07/14/93 ET-NRC-93-3962 09/03/93 T@mM M. A55CJWCa%WML - K!1Riw
951.007 Long term cooling scaling for OSU 07/1493 ET-NRC-93-3980 10/04 S 3 952.001 Piping Diagrams 07/2893 ET-NRC-93-4003 10/2793 952.002 ADS sparger drawings 08/2793 ET-NRC-93-3980 10/04S3 952.003 Insuhtion/ heat-tracing 08/2763 ET-NRC-93-3980 10/04S 3 952.004 Starting conditions for depressurization transient 08/27/93 ET-NRC-93-3980 10/04/93 952.005 Primary pump shutoff time 08/27B3 ET-NRC-93-4023 11/30S 3 952.006 Test conditions 08/27S 3 ET-NRC-93-3980 10/04 S 3 952.007 Collection of fluids leaving the primary 08/27/93 ET-NRC-93-3980 10/04B3 952.008 Pressurizer heater controls 08/27 S 3 ET-NRC-93-3980 10/04/93 952.009 Safety valve pressure setting 08/27/93 ET-NRC-93-3980 10/04/93 952.010 Steam generator level control 08/27S 3 ET-NRC-93-4023 11/30S 3 952.011 Core pcwer during a transient 08/2763 ET-NRC-93-3980 10/04/93 952.012 Addition of flowmeter to ADS Phase B design 11/02S 3 NTD-NRC-94-4059 02/03S 4 952.013 Effect of non-condensible gases in test program 11/02/93 NTD-NRC-94-4059 02/03 S 4 952.014 Applicability of PRHR test to current design 11/02S 3 NTD-NRC-94-4059 02/03/94 952.015 ADS Phase B capability to hold constant pressure ll/02S3 NTD-NRC-94-4059 02/03B4 952.016 SPES-2 design documents update 11/02S 3 NTD-NRC-94-4059 02/03S 4 952.017 Insights from pre-operational SPES-2 tests 11/02S 3 NTD-NRC-94-4059 02/03S4 952.017R01 Insights from pre-operational SPES-2 tests NTD-NRC-94-4234 07/22/94 952.018 Cold and hot pre-operational data from SPES-2 11/02/93 NTD-NRC-94-4059 02/03/94 952.018R01 Cold and hot pre-operational data from SPES-2 NTD-NRC-94-4234 07/22/94 952.019 Flow orifices at SPES-2 11/02/93 NTD-NRC-94-4059 02/03/94 952.020 Volume versus elevation for SPES-2 11/02S 3 NTD-NRC-94-4059 02/03/94 952.020R01 Volume ver ms elevation for SPES-2 NTD-NRC-94-4234 07/22S 4 952.021 SGTR analysis for hot and cold side breaks 11/02S 3 NTD-NRC-94-4059 02/03/94 952.022 hiformation gained from ADS Phase A tests 11/02/93 NTD-NRC-94-4059 02/03S 4 952.023 Effect of PRHR heat exchanger on ADS operation 11/02S 3 NTD-NRC-94-4059 02/03/94 952.024 Test procedures for ADS Phase B testing 11/02S 3 NTD-NRC-94-4059 02/03S 4 952.025 Analyses for ADS Phases A and B 11/02/93 NTD-NRC-94-4059 02/03/94 952.026 Fluid conditions for ADS Phase B tests 11/02/93 NTD-NRC-94-4059 02/03/94 952.027 RCS behavior versus ADS test facility 11/02S 3 NTD-NRC-94-4059 02/03/94 932.027R01 RCS behavior versus ADS test facility NTD-NRC-94-4257 08/08/94 952.028 Dynamic reflection wave forces in ADS operation 11/02S 3 NTD-NRC-94-4059 02/03/94 952.029 SPES-2 bend / elbow radii 11/30/93 NTD-NRC-94-4059 02/03/94 Key: k[ 440 NRR - Reactor Systems Branch A 480 NRR - Containment Systems Branch { ~ s-951 RES (Containment Systems) n: ( I 952 RES (Reactor Systems) 1 '9408230000 - ] -, v n)
r A c-i f Westinghouse Electric Corporation hevision 7. August 15,1994 .j AP600 DESIGN AND DESIGN CERTIFICATION TEST PROGRAM OVERVIEW Table 8 - Summary of NRC Requests for additional Information (RAI) related to AP600 Tests and Analysis RAI No. Description / Issue NRC Ltr. Date Westinghouse Response West. Response Letter Letter No. Date l 952.029R01 SPES-2 'oend/ elbow radii NTD-NRC-94-4234 07/22/94 952.030 SPES-2 valve types and sizes 11/30/93 NTD-NRC-94-4059 02/03 S 4 952.030R01 .SPES-2 valve types and sizes NTD-NRC-94-4234 07/22S 4 952.031 SPES-2 schemadcs and drawings update 11/30/93 NTD-NRC-94-4059 02/03/94 952.031R01 SPES.2 schematics and drawings update NTD-NRC-94-4234 07/22/94 952.032 SPES-2 operational parameters 11/30/93 NTD-NRC-94-4059 02/03B4 952.033 SPES-2 component position relationships 11/30S 3 NTD-NRC-94-4059 02/03 S 4 952.034 SPES-2 test procedures 11/3083 NTD-NRC-94-4059 02/03/94 952.035 SPES-2 facility insulation information 11/30/93 NTD-NRC-94-4059 02/03B4 952.035R01 SPES-2 facility insulation information NTD-NRC-94-4234 07/22B4 952.036 SPES-2 annular downcomer 11/30/93 NTD-NRC-94-4059 02/03B4 952.037 OSU facility orifice plate information 01/18S 4 NTD-NRC-94-4105 04/21 S 4 952.038 OSU valves with significant flow loss 01/18/94 NTD-NRC-94-4105 04/21S4 952.039 OSU MOV opening / closing rates 01/18/94 NTD-NRC-94-4105 04/21S4 932.040 OSU heater rod power profile 01/18S 4 NTD-NRC-94-4105 04/21S4 952.041 OSU drawings LKL930104 & LKL930105 01/18/94 NTD-NRC-94-4105 04/21/94 952.042 Pressurizer Balance Line Piping Diagrams 01/27 S 4 NTD-NRC-94-4110 04/28 S 4 952.043 RELAP-5 Thermal Ilydraulic Information 01/27/94 NTD-NRC-94-4110 04/28 S 4 952.044 Reactivity coefficients and check valve info 02/17/94 NTD-NRC-94-4136 05/1764 952.045 LOCA steady-state and transient asssumptions 02/17S 4 NTD-NRC-94-4136 05/17/94 952.046 WCOBRAfrRAC results 02/17/94 NTD-NRC-94-4136 05/17S4 952.047 Valve setpoints 02/17 S 4 NTD-NRC-94-4136 05/17 S 4 952.048 Fuel rod temperature profiles 02/17/94 NTD-NRC-94-4136 05/17S 4 952.049 SPES-2 test conditions 02/24/94 NTD-NRC-94-4105 04/21/94 952.050 SPES-2, Basis for fuel rod stored energy 03/01/94 NTD-NRC-94-4105 04/2164 952.051 SPES-2, Secondary side mass 03/01S4 NTD-NRC-94-4105 04/21S4 952.052 SPES-2, Basis for pressurizer water level 03/01/94 NTD-NRC-94-4105 04/21S4 952.053 SPES-2, Secondary side conditions 03/01/94 NTD-NRC-94-4105 04/21S4 952.054 SPES-2, Scaling rationale 03/01S 4 NTD-NRC-94-4105 04/21 S 4 952.055 SPES-2, Delayed neutron simulation 03/01/94 NTD-NRC-94-4105 04/21 S 4 RUN - 19T&13MthtJhwubwre6mrewrMm JMVICE% M4PdIMWLAKE E@Nhl
.058-_ 952 SPSE-2, Pump coastdown 03/0lS4 NTD-NRC-94-4105 04/21$4 952.059 SPES-2, Pressurizer heater rods 03/0l$4 NTD-NRC-94-4105 04/2194 952.060 ' ADS, Nominal valve inlet conditions 03/0l$4 NTD-NRC-94-4154 06/02$4 952.061 ADS, Nominal control valve area 03/01/94 NTD-NRC-94-4154 06/02/94 l' 952.062 ADS, Nominal control valve mass flow rate 03/01S4 NTD-NRC-94-4154 06/02/94 952.063 ~ ADS Stage 4, valve train piping dimemsions 03/01/94 NTD-NRC-94-4154 06/02B4 952.064 ADS Stage 4, Valve train geometry 03/0164 NTD-NRC-94-4154 06/02S 4 952.065 ADS phase B, measurement of liguid flow rate 05/26B4 NTD-NRC-94-4259 08/10S 4 952.066 SPES-2 test facility break location details 05/26S 4 NTD-NRC-94-4234 07/22/94 952.067 SPES-2 break location, size & geometry 05/26S 4 NTD-NRC-94-4234 07/22B4 952.068 Basis for SPES-2 setpoints 05/26 S 4 NTD-NRC-94-4234 07/22S 4 952.069 SPES-2 pressurizer heater power 05/26/94 NTD-NRC-94-4234 07/22/94 952.070 SPES-2 CMT level setpoint 05/26S 4 NTD-NRC-94-4234 07/22 S 4 952.071 SPES-2 PRHR operation 05/26/94 NTD-NRC-94-4234 07/22S 4 952.072 SPES-2 hot & cold shakedown data 05/26/94 NTD-NRC-94-4234 07/22B4 952.073 SPES-2 pump coastdown data 05/26 S 4 NTD-NRC-94-4234 07/22/94 952.074 SPES-2 leakage power 05/26S 4 NTD-NRC-94-4184 06/30S 4 952.075 SPES-2 SG recirculation ratios 05/26S 4 NTD-NRC-94-4257 08/08B4 952.076 SPES-2 ADS stage 4 L/d values 05/26S 4 NTD-NRC-94-4234 07/22/94 952.077 SPES-2 Chfr outer tank temp. & pressure 05/26S 4 NTD-NRC-94-4234 07/22S 4 952.078 SPES-2 lower plenum conditions 05/26S 4 NTD-NRC-94-4181 06/2764 952.079 SPES-2 initial uppper head temperature 05/26B4 NTD-NRC-94-4259 08/10/94 952.080 SPES-2 orifice sizes, locations & flows 05/26/94 NTD-NRC-94-4234 07/22/94 952.081 SPES-2 facility drawings 05/26B4 NTD-NRC-94-4234 07/22B4 l 952.082 SPES-2 pipe schedule changes 05/26/94 NTD-NRC-94-4236 07/25 S 4 _. 952.083 SPES-2 piping system bend / elbow radii 05/26S 4 NTD-NRC-94-4181 06/27S 4 952.084 SPES-2 valve type & sizes 05/26/94 NTD-NRC-94-4234 07/22B4 952.085 SPES-2 pressure vessel connections 05/26S 4 NTD-NRC-94-4181 06/27B4 952.086 SPES-2 insulation characteristics 05/26S 4 NTD-NRC-94-4234 07/22S 4 952.087 SPES-2 upper plenum & annular downcomer 05/26S4 NTD-NRC-94-4181 06/2764 952.088 SPES-2 pressurizer 05/26/94 NTD-NRC-94-4234 07/22S 4 952.089 CMT test matrix 06/0lS4 952.090 PRHR test data 06/16S 4 b m Key: d; kj $> 70 QMZ 440 NRR - Reactor Systems Branch jg .,gg 480 NRR - Containment Systems Branch k I o ir F"1 % M 951 RES (Containment Systems) R6 2O Di 952 RES (Reactor Systems) 9408230090 - ]
r Westinghouse Electric Corporation i Revision 7, August 15,1994 CHART AP600 DESIGN CERTIFICAT i ^
- 1994; sp
-LJANT i FEB: ': M AR j 3 APR ![ IMAN j?JUN d f:JI.Y. 5AUG: ESEP:t (OCTf S HOV lii :DEC:1 !!?JAN (Scheduled)- Start: P115/94 End: 8/19/94 Start: 2/15/94 (Actual) (Actual / Pro}ected) End: 9/21/94 (Projected Start: 2/25 (Scheduled) ' End: 11/1 (Actual / Pro}ected) Start: 2/5/94 (Actual) End: 10/6/94 (Projecte (Scheduled) SM 5/31/94 (A&al) (Actual) End: 8/3/94 (Actual) 8 (Scheduled) Eg b. 8# (Actual / Projected) End: 11 3 ~ ~ - -. -, ~ - g-- /- j $$4 ;~~ ' .j v. b-> f I l 4.. I e eru me a y 1
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(AUG?
- SEP s :;!OCTj 'NOV?
c DEC:- 1 I CMT MATRIX TESTS ./94 394 SPES-2 MATRIX TESTS d) 1 J Start: 7/1/94 Erd 2/2/94 OSU MATRIX ~ TESTS trt: 7/19/94 1: 11/22/94 ADS PHASE B 26/94 (Actual) MATRIX TESTS /22/94 (Projected) I l Sat _.. .\\tuesse i' 1;l i1995.': 9408230090 - J _ _ _ _}}