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2 to Updated Final Safety Analysis Report, Chapter 6, Appendix 6A, Tables
ML20309A726
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/08/2020
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Duke Energy Carolinas
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Office of Nuclear Reactor Regulation
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RA-19-0424
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McGuire Nuclear Station UFSAR Appendix 6A. Tables Appendix 6A. Tables

McGuire Nuclear Station UFSAR Table 6-1 (Page 1 of 2)

Table 6-1. Containment Subcompartment Pressures Compartment Maximum Press Time(Sec) Element 1 0.1585E+02 0.3940 C.L. 1 2 0.1401E+02 1.0060 C.L. 2 3 0.1324E+02 1.0960 C.L. 3 4 0.1333E+02 1.0960 C.L. 4 5 0.1388E+02 1.0060 C.L. 5 6 0.1522E+02 0.3760 C.L. 6 7 0.8070E+01 0.2320 H.L. 5 8 0.6940E+01 0.6820 C.L. 4 9 0.6760E+01 2.9680 C.L. 1 10 0.7840E+01 0.2500 H.L. 6 11 0.6780E+01 2.9680 C.L. 1 12 0.6770E+01 2.9680 C.L. 1 13 0.6960E+01 0.1980 H.L. 6 14 0.6770E+01 2.9680 C.L. 1 15 0.6770E+01 2.9680 C.L. 1 16 0.6890E+01 0.1980 H.L. 1 17 0.6770E+01 2.9680 C.L. 1 18 0.6770E+01 2.9680 C.L. 1 19 0.7770E+01 0.2500 H.L. 1 20 0.6770E+01 2.9680 C.L. 1 21 0.6770E+01 2.9680 C.L. 1 22 0.7930E+01 0.2320 H.L. 2 23 0.6780E+01 0.6280 C.L. 3 24 0.6770E+01 2.9680 C.L. 1 25 0.6770E+01 2.9680 C.L. 1 26 0.1286E+02 1.6540 C.L. 1 27 0.1318E+02 1.2580 C.L. 1 28 0.1288E+02 1.6540 C.L. 1 29 0.1225E+02 2.2120 C.L. 1 30 0.1283E+02 1.6000 C.L. 1 31 0.1317E+02 1.2580 C.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-1 (Page 2 of 2)

Compartment Maximum Press Time(Sec) Element 32 0.1279E+02 1.6360 C.L. 6 33 0.1321E+02 1.0420 C.L. 2 34 0.1289E+02 1.6540 C.L. 1 35 0.1290E+02 1.6540 C.L. 1 36 0.1287E+02 1.6000 C.L. 1 37 0.1283E+02 1.6360 C.L. 6 38 0.6770E+01 2.9680 C.L. 1 39 0.6770E+01 2.9680 C.L. 1 40 0.1067E+02 0.4660 C.L. 1 41 0.9570E+01 1.0060 C.L. 1 42 0.8940E+01 1.1140 C.L. 2 43 0.9030E+01 1.0420 C.L. 5 44 0.9410E+01 1.0600 C.L. 6 45 0.1030E+02 0.4480 C.L. 6 46 0.6770E+01 2.9680 C.L. 1 47 0.6770E+01 2.9680 C.L. 1 48 0.6770E+01 2.9680 C.L. 1 49 0.6770E+01 2.9680 C.L. 1 50 0.1284E+02 1.6000 C.L. 1 51 0.1366E+02 0.7000 C.L. 3 52 0.1286E+02 1.6360 C.L. 1 53 0.1280E+02 1.6360 C.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 1 of 7)

Table 6-2. Containment Subcompartment Differential Pressures. (Table 6-2 and Table 6-3 were originally one table)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 1 2 0.8100E+01 0.0270 H.L. 1 -0.6020E+01 0.0180 H.L. 2 1 6 0.1156E+02 0.0360 H.L. 1 -0.1181E+02 0.0360 H.L. 6 1 7 0.1636E+02 0.2860 C.L. 1 -0.2200E+00 0.0360 C.L. 6 1 8 0.1580E+02 0.3040 C.L. 1 -0.2200E+00 0.0360 C.L. 6 1 9 0.1539E+02 0.3840 C.L. 1 -0.2200E+00 0.0360 C.L. 6 1 25 0.1413E+02 0.2320 C.L. 1 -0.2200E+00 0.0360 C.L. 6 1 26 0.1390E+02 0.2320 C.L. 1 -0.4800E+00 2.5180 C.L. 6 1 27 0.1135E+02 0.0360 H.L. 1 -0.2300E+00 0.0360 C.L. 6 1 28 0.1396E+02 0.2320 C.L. 1 -0.5000E+00 2.3380 C.L. 6 1 33 0.1167E+02 0.0450 H.L. 1 -0.2240E+01 0.0900 H.L. 5 1 34 0.1296E+02 0.2140 C.L. 1 -0.4200E+00 2.5180 C.L. 6 1 38 0.1462E+02 0.2860 C.L. 1 -0.2200E+00 0.0360 C.L. 6 1 40 0.1115E+02 0.0360 H.L. 1 -0.2200E+00 0.0360 C.L. 6 1 51 0.1236E+02 0.1080 H.L. 1 -0.1550E+01 0.5380 H.L. 3 2 1 0.6020E+01 0.0180 H.L. 2 -0.8100E+01 0.0270 H.L. 1 2 3 0.7620E+01 0.0630 H.L. 1 -0.5940E+01 0.0270 H.L. 3 2 10 0.1203E+02 0.3040 C.L. 2 0.0 0.0090 C.L. 6 2 11 0.1163E+02 0.2860 C.L. 2 0.0 0.0090 C.L. 6 2 12 0.1105E+02 0.3220 C.L. 2 0.0 0.0090 C.L. 6 2 25 0.1135E+02 0.1260 H.L. 2 0.0 0.0090 C.L. 6 2 27 0.8720E+01 0.0720 H.L. 1 -0.1500E+00 2.4820 C.L. 6 2 28 0.1096E+02 0.1170 H.L. 2 -0.4900E+00 2.4100 C.L. 6 2 33 0.8880E+01 0.0630 H.L. 1 -0.1420E+01 0.0810 H.L. 5 2 39 0.1076E+02 0.2320 C.L. 2 0.0 0.0090 C.L. 6 2 41 0.9350E+01 0.0630 H.L. 1 0.0 0.0090 C.L. 6 2 51 0.1036E+02 0.1170 H.L. 2 -0.1530E+01 0.5380 H.L. 3 3 2 0.5940E+01 0.0270 H.L. 3 -0.7620E+01 0.0630 H.L. 1 3 4 0.5980E+01 0.0270 H.L. 3 -0.7340E+01 0.0270 H.L. 4 3 13 0.9920E+01 0.3040 C.L. 3 0.0 0.0180 C.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 2 of 7)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 3 14 0.9710E+01 0.3040 C.L. 3 0.0 0.0180 C.L. 6 3 15 0.9410E+01 0.3580 C.L. 3 0.0 0.0180 C.L. 6 3 25 0.9190E+01 0.2140 H.L. 4 0.0 0.0180 C.L. 6 3 27 0.7420E+01 0.0450 H.L. 3 -0.4300E+00 2.5720 C.L. 1 3 28 0.8790E+01 0.2140 H.L. 3 -0.4700E+00 2.4100 C.L. 6 3 29 0.1022E+02 0.4840 C.L. 3 -0.5500E+00 2.4640 C.L. 6 3 30 0.8780E+01 0.2140 H.L. 4 -0.4600E+00 2.4640 C.L. 6 3 33 0.6930E+01 0.0360 H.L. 3 -0.1150E+01 0.1440 H.L. 4 3 35 0.9100E+01 0.2140 H.L. 4 -0.4900E+00 2.3560 C.L. 6 3 42 0.7300E+01 0.1080 H.L. 1 0.0 0.0180 C.L. 6 3 46 0.9520E+01 0.2140 H.L. 4 0.0 0.0180 C.L. 6 3 50 0.8870E+01 0.2140 H.L. 4 -0.4600E+00 2.5180 C.L. 6 3 51 0.7820E+01 0.1170 H.L. 1 -0.1560E+01 0.5560 H.L. 1 4 5 0.6460E+01 0.0270 H.L. 4 -0.6680E+01 0.0540 H.L. 4 4 16 0.1074E+02 0.3840 C.L. 4 0.0 0.0090 C.L. 6 4 17 0.1017E+02 0.3040 C.L. 4 0.0 0.0090 C.L. 6 4 18 0.9520E+01 0.3400 C.L. 4 0.0 0.0090 C.L. 6 4 25 0.9530E+01 0.1080 H.L. 6 0.0 0.0090 C.L. 6 4 29 0.1021E+02 0.4480 C.L. 4 -0.5600E+00 2.4640 C.L. 1 4 30 0.9190E+01 0.1080 H.L. 6 -0.4700E+00 2.5540 C.L. 1 4 31 0.8090E+01 0.0360 H.L. 4 -0.3800E+00 2.5900 C.L. 6 4 33 0.7830E+01 0.0360 H.L. 4 -0.1110E+01 0.2140 C.L. 1 4 36 0.9370E+01 0.1080 H.L. 6 -0.4800E+00 2.4640 C.L. 1 4 43 0.8240E+01 0.0900 H.L. 6 0.0 0.0090 C.L. 6 4 47 0.9740E+01 0.2500 H.L. 1 0.0 0.0090 C.L. 6 4 51 0.9180E+01 0.0990 H.L. 6 -0.1720E+01 0.5560 H.L. 1 5 4 0.6680E+01 0.0540 H.L. 6 -0.6460E+01 0.0270 H.L. 4 5 6 0.5940E+01 0.0180 H.L. 5 -0.8280E+01 0.0270 H.L. 6 5 19 0.1159E+02 0.2860 C.L. 5 0.0 0.0 C.L. 6 5 20 0.1116E+02 0.2860 C.L. 5 0.0 0.0 C.L. 6 5 21 0.1060E+02 0.3220 C.L. 5 0.0 0.0 C.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 3 of 7)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 5 25 0.1125E+02 0.1170 H.L. 5 0.0 0.0 C.L. 6 5 30 0.1080E+02 0.1170 H.L. 5 -0.5000E+00 2.5540 C.L. 1 5 31 0.8280E+01 0.0630 H.L. 6 -0.1600E+00 2.4640 C.L. 1 5 32 0.1065E+02 0.1170 H.L. 5 -0.5000E+00 2.5540 C.L. 1 5 33 0.8650E+01 0.0630 H.L. 6 -0.1480E+01 0.0900 H.L. 2 5 44 0.9160E+01 0.0630 H.L. 6 0.0 0.0 C.L. 6 5 48 0.1063E+02 0.1080 H.L. 5 0.0 0.0 C.L. 6 5 51 0.1044E+02 0.1080 H.L. 5 -0.1750E+01 0.5560 H.L. 1 6 5 0.8280E+01 0.0270 H.L. 6 -0.5940E+01 0.0180 H.L. 5 6 22 0.1581E+02 0.2860 C.L. 6 -0.2100E+00 0.0360 C.L. 1 6 23 0.1521E+02 0.3040 C.L. 6 -0.2100E+00 0.0360 C.L. 1 6 24 0.1482E+02 0.3040 C.L. 6 -0.2100E+00 0.0360 C.L. 1 6 25 0.1357E+02 0.2320 C.L. 6 -0.2100E+00 0.0360 C.L. 1 6 30 0.1332E+02 0.2140 C.L. 6 -0.5000E+00 2.5900 C.L. 1 6 31 0.1156E+02 0.0360 H.L. 6 -0.2200E+00 0.0360 C.L. 1 6 32 0.1320E+02 0.2140 C.L. 6 -0.5000E+00 2.5900 C.L. 1 6 33 0.1185E+02 0.0450 H.L. 6 -0.2280E+01 0.0900 H.L. 2 6 37 0.1238E+02 0.1170 H.L. 6 -0.4400E+00 2.5900 C.L. 1 6 45 0.1136E+02 0.0360 H.L. 6 -0.2100E+00 0.0360 C.L. 1 6 49 0.1403E+02 0.2860 C.L. 6 -0.2100E+00 0.0360 C.L. 1 6 51 0.1253E+02 0.1080 H.L. 6 -0.1760E+01 0.5560 H.L. 1 7 1 0.2200E+00 0.0360 C.L. 6 -0.1636E+02 0.2860 C.L. 1 7 2 0.0 0.0090 C.L. 6 -0.1090E+02 0.2860 C.L. 1 7 8 0.3480E+01 0.1080 H.L. 2 -0.1020E+01 0.2500 H.L. 1 7 10 0.5200E+01 0.2860 H.L. 2 -0.3490E+01 0.2320 H.L. 1 7 25 0.7540E+01 0.1260 H.L. 2 -0.2550E+01 0.2680 H.L. 1 7 40 0.0 0.0990 C.L. 6 -0.1082E+02 0.2860 C.L. 1 8 1 0.2200E+00 0.0360 C.L. 6 -0.1580E+02 0.3040 C.L. 1 8 7 0.1020E+01 0.2500 H.L. 1 -0.3480E+01 0.1080 H.L. 2 8 9 0.3000E+01 0.1440 H.L. 2 -0.9100E+00 0.2320 H.L. 1 8 11 0.4290E+01 0.2680 H.L. 2 -0.2770E+01 0.2140 H.L. 1 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 4 of 7)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 8 25 0.6440E+01 0.1440 H.L. 2 -0.2210E+01 0.2860 H.L. 1 9 1 0.2200E+00 0.0360 C.L. 6 -0.1539E+02 0.3040 C.L. 1 9 8 0.9100E+00 0.2320 H.L. 1 -0.3000E+01 0.1440 H.L. 2 9 12 0.3350E+01 0.2500 H.L. 2 -0.2230E+01 0.2680 H.L. 1 9 25 0.4730E+01 0.1710 H.L. 2 -0.1730E+01 0.2860 H.L. 1 9 38 0.4910E+01 0.1710 H.L. 2 -0.1200E+01 0.2860 H.L. 1 10 2 0.0 0.0890 C.L. 6 -0.1203E+02 0.3040 C.L. 2 10 7 0.3490E+01 0.2320 H.L. 1 -0.5200E+01 0.2860 H.L. 2 10 11 0.2990E+01 0.1080 H.L. 1 -0.7500E+00 0.2860 H.L. 2 10 13 0.5540E+01 0.1170 H.L. 1 -0.3820E+01 0.2680 H.L. 2 10 25 0.6770E+01 0.1260 H.L. 1 -0.2270E+01 0.2860 H.L. 2 10 41 0.1000E-01 0.0360 C.L. 2 -0.7530E+01 0.2860 C.L. 2 11 2 0.0 0.0090 C.L. 6 -0.1163E+02 0.2860 C.L. 2 11 8 0.2770E+01 0.2140 H.L. 1 -0.4290E+01 0.2680 H.L. 2 11 10 0.7500E+00 0.2860 H.L. 2 -0.2990E+01 0.1080 H.L. 1 11 12 0.2720E+01 0.1440 H.L. 1 -0.9500E+00 0.2860 C.L. 2 11 14 0.4510E+01 0.1350 H.L. 1 -0.2890E+01 0.2500 H.L. 2 11 25 0.5770E+02 0.1440 H.L. 1 -0.1530E+01 0.3040 H.L. 2 12 2 0.0 0.0090 C.L. 6 -0.1105E+02 0.3220 C.L. 2 12 9 0.2230E+01 0.2680 H.L. 1 -0.3350E+01 0.2500 H.L. 2 12 11 0.9500E+00 0.2860 C.L. 2 -0.2720E+01 0.1440 H.L. 1 12 15 0.2530E+01 0.1350 H.L. 1 -0.2510E+01 0.3220 H.L. 1 12 25 0.4090E+01 0.2500 H.L. 5 -0.1220E+01 0.3040 H.L. 2 12 39 0.4700E+01 0.2500 H.L. 5 -0.9900E+00 0.2680 C.L. 2 13 3 0.0 0.0180 C.L. 6 -0.9920E+01 0.3040 C.L. 3 13 10 0.3820E+01 0.2680 H.L. 2 -0.5540E+01 0.1170 H.L. 1 13 14 0.2730E+01 0.1800 H.L. 6 -0.4500E+00 0.3760 H.L. 3 13 16 0.4440E+01 0.2500 H.L. 4 -0.4770E+01 0.1440 H.L. 6 13 25 0.6300E+01 0.1710 H.L. 1 -0.1230E+01 0.3040 H.L. 3 13 42 0.0 0.0900 C.L. 6 -0.5820E+01 0.3040 C.L. 3 13 50 0.5970E+01 0.1710 H.L. 1 -0.6850E+01 1.5820 C.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 5 of 7)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 14 3 0.0 0.0180 C.L. 6 -0.9710E+01 0.3040 C.L. 3 14 11 0.2890E+01 0.2500 H.L. 2 -0.4510E+01 0.1350 H.L. 1 14 13 0.4500E+00 0.3760 H.L. 3 -0.2730E+01 0.1800 H.L. 6 14 15 0.2490E+01 0.1800 H.L. 1 -0.8600E+00 0.2860 H.L. 3 14 17 0.3610E+01 0.2680 H.L. 4 -0.3850E+01 0.1620 H.L. 6 14 25 0.5210E+01 0.1890 H.L. 1 -0.1000E+01 0.3040 C.L. 3 14 50 0.4800E+01 0.1890 H.L. 1 -0.6870E+01 1.6000 C.L. 5 15 3 0.0 0.0180 C.L. 6 -0.9410E+01 0.3580 C.L. 3 15 12 0.2510E+01 0.3220 H.L. 1 -0.2530E+01 0.1350 H.L. 1 15 14 0.8600E+00 0.2860 H.L. 3 -0.2490E+01 0.1800 H.L. 1 15 18 0.2710E+01 0.3400 H.L. 5 -0.2230E+01 0.1620 H.L. 6 15 25 0.3720E+01 0.2140 H.L. 1 -0.8500E+00 0.3220 H.L. 3 15 46 0.4140E+01 0.2140 H.L. 1 -0.8000E+00 0.2680 H.L. 3 15 50 0.3320E+01 0.2320 H.L. 6 -0.6850E+01 1.6180 C.L. 5 16 4 0.0 0.0090 C.L. 6 -0.1074E+02 0.3040 C.L. 4 16 13 0.4770E+01 0.1440 H.L. 6 -0.4440E+01 0.2500 H.L. 4 16 17 0.2630E+01 0.1800 H.L. 1 -0.8600E+00 0.3040 H.L. 4 16 19 0.3110E+01 0.2500 H.L. 5 -0.4390E+01 0.1170 H.L. 6 16 25 0.6230E+01 0.1980 H.L. 1 -0.2240E+01 0.2860 H.L. 4 16 43 0.1000E-01 0.0360 C.L. 4 -0.6680E+01 0.2860 H.L. 4 17 4 0.0 0.0090 C.L. 6 -0.1017E+02 0.3040 C.L. 4 17 14 0.3850E+01 0.1620 H.L. 6 -0.3610E+01 0.2680 H.L. 4 17 16 0.8600E+00 0.3040 H.L. 4 -0.2630E+01 0.1800 H.L. 1 17 18 0.2380E+01 0.1710 H.L. 6 -0.1070E+01 0.2860 H.L. 4 17 20 0.2430E+01 0.2500 H.L. 5 -0.3490E+01 0.1260 H.L. 6 17 25 0.5100E+01 0.1710 H.L. 6 -0.1480E+01 0.2860 H.L. 4 18 4 0.0 0.0090 C.L. 6 -0.9520E+01 0.3400 C.L. 4 18 15 0.2230E+01 0.1620 H.L. 6 -0.2710E+01 0.3400 H.L. 5 18 17 0.1070E+01 0.2860 H.L. 4 -0.2380E+01 0.1710 H.L. 6 18 21 0.2010E+01 0.3040 H.L. 6 -0.2240E+01 0.3760 C.L. 3 18 25 0.3500E+01 0.1980 H.L. 6 -0.1030E+01 0.3220 H.L. 4 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 6 of 7)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 18 47 0.4130E+01 0.2500 H.L. 1 -0.1150E+01 0.2680 H.L. 4 19 5 0.0 0.0 C.L. 6 -0.1159E+02 0.2860 C.L. 5 19 16 0.4390E+01 0.1170 H.L. 6 -0.3110E+01 0.2500 H.L. 5 19 20 0.2890E+01 0.1080 H.L. 6 -0.7800E+00 0.2860 H.L. 5 19 22 0.3370E+01 0.2320 H.L. 6 -0.4880E+01 0.2860 H.L. 5 19 25 0.6610E+01 0.2140 H.L. 2 -0.2330E+01 0.2860 H.L. 5 19 44 0.1000E-01 0.0360 C.L. 5 -0.7190E+01 0.2860 C.L. 5 20 5 0.0 0.0 C.L. 6 -0.1116E+02 0.2860 C.L. 5 20 17 0.3490E+01 0.1260 H.L. 6 -0.2430E+01 0.2500 H.L. 5 20 19 0.7800E+00 0.2860 H.L. 5 -0.2890E+01 0.1080 H.L. 6 20 21 0.2650E+01 0.1440 H.L. 6 -0.9600E+00 0.2860 C.L. 5 20 23 0.2650E+01 0.2140 H.L. 6 -0.4040E+01 0.2680 H.L. 5 20 25 0.5640E+01 0.1440 H.L. 6 -0.1550E+01 0.2860 H.L. 5 21 5 0.0 0.0 C.L. 6 -0.1060E+02 0.3220 C.L. 5 21 18 0.2240E+01 0.3760 C.L. 3 -0.2010E+01 0.3040 H.L. 6 21 20 0.9600E+00 0.2860 C.L. 5 -0.2650E+01 0.1440 H.L. 6 21 24 0.2110E+01 0.2680 H.L. 6 -0.3170E+01 0.2500 H.L. 5 21 25 0.4090E+01 0.2500 H.L. 2 -0.1270E+01 0.3040 H.L. 5 21 48 0.4700E+01 0.2500 H.L. 2 -0.1020E+01 0.2680 C.L. 5 22 6 0.2100E+00 0.0360 C.L. 1 -0.1581E+02 0.2860 C.L. 6 22 19 0.4880E+01 0.2860 H.L. 5 -0.3370E+01 0.2320 H.L. 6 22 23 0.3450E+01 0.1080 H.L. 5 -0.1050E+01 0.2500 H.L. 6 22 25 0.7510E+01 0.1260 H.L. 5 -0.2570E+01 0.2500 H.L. 6 22 45 0.0 0.0270 C.L. 6 -0.1057E+02 0.2860 C.L. 6 23 6 0.2100E+00 0.0360 C.L. 1 -0.1521E+02 0.3040 C.L. 6 23 20 0.4040E+01 0.2680 H.L. 5 -0.2650E+01 0.2140 H.L. 6 23 22 0.1050E+01 0.2500 H.L. 6 -0.3450E+01 0.1080 H.L. 5 23 24 0.3010E+01 0.1440 H.L. 5 -0.9300E+00 0.2320 H.L. 6 23 25 0.6420E+01 0.1440 H.L. 5 -0.2180E+01 0.2860 H.L. 6 24 6 0.2100E+00 0.0360 C.L. 1 -0.1482E+02 0.3040 C.L. 6 24 21 0.3170E+01 0.2500 H.L. 5 -0.2110E+01 0.2680 H.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-2 (Page 7 of 7)

Maximum Between Diff Time Minimum Time Comp And Comp Pressure (Sec) Element Diff Pressure (Sec) Element 24 23 0.9300E+00 0.2320 H.L. 6 -0.3010E+01 0.1440 H.L. 5 24 25 0.4670E+01 0.1710 H.L. 5 -0.1750E+01 0.2860 H.L. 6 24 49 0.4850E+01 0.1800 H.L. 5 -0.1220E+01 0.2860 H.L. 6 25 25 0.0 2.9680 C.L. 6 0.0 2.9680 C.L. 6 26 1 0.4800E+00 2.5180 C.L. 6 -0.1390E+02 0.2320 C.L. 1 26 2 0.4800E+00 2.4820 C.L. 6 -0.1085E+02 0.1170 H.L. 2 26 27 0.3300E+00 2.4460 C.L. 6 -0.6610E+01 0.2320 H.L. 1 26 28 0.1500E+00 0.2860 C.L. 1 -0.1000E+00 0.6460 C.L. 5 26 32 0.5900E+00 0.4480 C.L. 2 -0.5600E+00 0.2320 H.L. 1 26 34 0.7000E-01 2.3920 C.L. 6 -0.1060E+01 0.2320 H.L. 1 26 52 0.3800E+00 0.5920 C.L. 5 -0.2500E+00 0.2320 H.L. 1 27 1 0.2300E+00 0.0360 C.L. 6 -0.1135E+02 0.0360 H.L. 1 27 2 0.1500E+00 2.4820 C.L. 6 -0.8720E+01 0.0720 H.L. 1 27 3 0.4300E+00 2.5720 C.L. 1 -0.7420E+01 0.0450 H.L. 3 27 26 0.6610E+01 0.2320 H.L. 1 -0.3300E+00 2.4460 C.L. 6 27 28 0.6670E+01 0.2320 H.L. 1 -0.3500E+00 2.3200 C.L. 6 27 34 0.5740E+01 0.4120 C.L. 1 -0.2700E+00 2.5900 C.L. 6 27 35 0.7360E+01 0.4120 C.L. 1 -0.3700E+00 2.3560 C.L. 6 27 40 0.4480E+01 1.5280 C.L. 4 -0.5670E+01 0.0900 H.L. 1 27 41 0.4600E+01 1.3660 C.L. 4 -0.3920E+01 0.1170 H.L. 2 27 42 0.4520E+01 1.7260 C.L. 1 -0.4020E+01 0.1800 H.L. 6 27 52 0.6690E+01 0.4660 C.L. 1 -0.3400E+00 2.5720 C.L. 6 28 1 0.5000E+00 2.3380 C.L. 6 -0.1396E+02 0.2320 C.L. 1 28 2 0.4900E+00 2.4100 C.L. 6 -0.1096E+02 0.1170 H.L. 2 28 3 0.4700E+00 2.4100 C.L. 6 -0.8790E+01 0.2140 H.L. 3 28 26 0.1000E+00 0.6460 C.L. 5 -0.1500E+00 0.2860 C.L. 1 28 27 0.3500E+00 2.3200 C.L. 6 -0.6670E+01 0.2320 H.L. 1 28 29 0.5550E+01 1.0960 C.L. 2 -0.1100E+00 2.5540 C.L. 5 28 30 0.5800E+00 0.4120 C.L. 3 -0.5800E+00 0.4660 C.L. 5 28 35 0.1470E+01 0.7540 C.L. 1 -0.6000E-01 1.6180 C.L. 6 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 1 of 9)

Table 6-3. Containment Subcompartment Differential Pressures. (Table 6-2 and Table 6-3 were originally one table.)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 29 3 0.5500E+00 2.4640 C.L. 6 -0.1022E+02 0.484 C.L. 3 0

29 4 0.5600E+00 2.4640 C.L. 1 -0.1021E+02 0.448 C.L. 4 0

29 28 0.1100E+00 2.5540 C.L. 5 -0.5550E+01 1.096 C.L. 2 0

29 30 0.1400E+00 2.2660 C.L. 4 -0.5570E+01 1.078 C.L. 2 0

29 35 0.1100E+00 2.4460 C.L. 5 -0.5160E+01 1.078 C.L. 1 0

29 36 0.1400E+00 2.2660 C.L. 2 -0.5200E+01 1.096 C.L. 2 0

29 42 0.4000E+01 2.2660 C.L. 6 -0.6790E+01 0.180 H.L. 6 0

29 43 0.4020E+01 2.2120 C.L. 1 -0.7150E+01 0.268 H.L. 1 0

30 4 0.4700E+00 2.5540 C.L. 1 -0.9190E+01 0.108 H.L. 4 0

30 5 0.5000E+00 2.5540 C.L. 1 -0.1080E+02 0.117 H.L. 5 0

30 28 0.5800E+00 0.4660 C.L. 5 -0.5800E+00 0.412 C.L. 3 0

30 29 0.5570E+01 1.0780 C.L. 2 -0.1400E+00 2.266 C.L. 4 0

30 31 0.3500E+00 2.5540 C.L. 1 -0.6500E+01 0.232 H.L. 6 0

30 32 0.1200E+00 0.7540 H.L. 2 -0.2800E+00 0.538 C.L. 2 0

30 36 0.1390E+01 0.7540 C.L. 6 -0.4000E-01 1.636 C.L. 3 0

31 4 0.3800E+00 2.5900 C.L. 6 -0.8090E+01 0.036 H.L. 4 0

31 5 0.1600E+00 2.4640 C.L. 1 -0.8280E+01 0.063 H.L. 6 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 2 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 31 6 0.2200E+00 0.0360 C.L. 1 -0.1156E+02 0.036 H.L. 6 0

31 30 0.6500E+01 0.2320 H.L. 6 -0.3500E+00 2.554 C.L. 1 0

31 32 0.6340E+01 0.4660 C.L. 6 -0.3500E+00 2.554 C.L. 1 0

31 36 0.7170E+01 0.4300 C.L. 6 -0.3500E+00 2.698 C.L. 1 0

31 37 0.5550E+01 0.4660 C.L. 6 -0.2900E+00 2.626 C.L. 1 0

31 43 0.4440E+01 1.7260 C.L. 6 -0.3970E+01 0.180 H.L. 1 0

31 44 0.4550E+01 1.4020 C.L. 3 -0.3870E+01 0.189 H.L. 2 0

31 45 0.4510E+01 1.4380 C.L. 3 -0.5510E+01 0.081 H.L. 6 0

31 53 0.6780E+01 0.4660 C.L. 6 -0.3600E+00 2.554 C.L. 1 0

32 4 0.4700E+00 2.5540 C.L. 1 -0.9050E+01 0.108 H.L. 6 0

32 6 0.5000E+00 2.5900 C.L. 1 -0.1320E+02 0.214 C.L. 6 0

32 26 0.5600E+00 0.2320 H.L. 1 -0.5900E+00 0.448 C.L. 2 0

32 30 0.2800E+00 0.5380 C.L. 2 -0.1200E+00 0.754 H.L. 2 0

32 31 0.3500E+00 2.5540 C.L. 1 -0.6340E+01 0.466 C.L. 6 0

32 37 0.6000E-01 2.9680 C.L. 1 -0.1050E+01 0.214 H.L. 6 0

33 1 0.2240E+01 0.0900 H.L. 5 -0.1167E+02 0.045 H.L. 1 0

33 2 0.1420E+01 0.0810 H.L. 5 -0.8880E+01 0.063 H.L. 1 0

33 3 0.1150E+01 0.1440 H.L. 4 -0.6930E+01 0.036 H.L. 3 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 3 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 33 4 0.1110E+01 0.2140 C.L. 1 -0.7830E+01 0.036 H.L. 4 0

33 5 0.1480E+01 0.0900 H.L. 2 -0.8650E+01 0.063 H.L. 6 0

33 6 0.2280E+01 0.0900 H.L. 2 -0.1185E+02 0.045 H.L. 6 0

33 25 0.8840E+01 0.1980 H.L. 1 -0.2000E-01 0.036 C.L. 4 0

33 51 0.6550E+01 0.1800 H.L. 5 -0.1560E+01 0.556 H.L. 1 0

34 1 0.4200E+00 2.5180 C.L. 6 -0.1296E+02 0.214 C.L. 1 0

34 25 0.6840E+01 1.5460 C.L. 5 0.0 0.063 C.L. 6 0

34 26 0.1060E+01 0.2320 H.L. 1 -0.7000E-01 2.392 C.L. 6 0

34 27 0.2700E+00 2.5900 C.L. 6 -0.5740E+01 0.412 C.L. 1 0

34 40 0.4490E+01 1.6540 C.L. 4 -0.8120E+01 0.117 H.L. 1 0

34 52 0.1010E+01 0.4840 C.L. 1 -0.7000E-01 2.572 C.L. 6 0

35 3 0.4900E+00 2.3560 C.L. 6 -0.9100E+01 0.214 H.L. 4 0

35 27 0.3700E+00 2.3560 C.L. 6 -0.7360E+01 0.412 C.L. 1 0

35 28 0.6000E-01 1.6180 C.L. 6 -0.1470E+01 0.754 C.L. 1 0

35 29 0.5160E+01 1.0780 C.L. 1 -0.1100E+00 2.446 C.L. 5 0

35 42 0.4480E+01 1.6360 C.L. 6 -0.6520E+01 0.180 H.L. 6 0

36 4 0.4800E+00 2.4640 C.L. 1 -0.9370E+01 0.108 H.L. 6 0

36 29 0.5200E+01 1.0860 C.L. 2 -0.1400E+00 2.266 C.L. 2 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 4 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 36 30 0.4000E-01 1.6360 C.L. 3 -0.1390E+01 0.754 C.L. 6 0

36 31 0.3500E+00 2.6980 C.L. 1 -0.7170E+01 0.430 C.L. 6 0

36 43 0.4460E+01 1.6180 C.L. 1 -0.6400E+01 0.250 H.L. 1 0

37 6 0.4400E+00 2.5900 C.L. 1 -0.1238E+02 0.117 H.L. 6 0

37 25 0.6850E+01 1.5640 C.L. 5 0.0 0.018 C.L. 6 0

37 31 0.2900E+00 2.6260 C.L. 1 -0.5550E+01 0.466 C.L. 6 0

37 32 0.1050E+01 0.2140 H.L. 6 -0.6000E-01 2.968 C.L. 1 0

37 45 0.4470E+01 1.6180 C.L. 3 -0.7970E+01 0.099 H.L. 6 0

37 53 0.1250E+01 0.4840 C.L. 6 -0.9000E-01 1.798 C.L. 1 0

38 1 0.2200E+00 0.0360 C.L. 6 -0.1462E+02 0.286 C.L. 1 0

38 9 0.1200E+01 0.2860 H.L. 1 -0.4910E+01 0.171 H.L. 2 0

38 25 0.1850E+01 0.1530 H.L. 2 -0.7300E+00 0.268 H.L. 1 0

38 39 0.1930E+01 0.1530 H.L. 2 -0.2150E+01 0.153 H.L. 1 0

39 2 0.0 0.0090 C.L. 6 -0.1076E+02 0.232 C.L. 2 0

39 12 0.9900E+00 0.2680 C.L. 2 -0.4700E+01 0.250 H.L. 5 0

39 25 0.1580E+01 0.1530 H.L. 1 -0.7000E+00 0.268 C.L. 5 0

39 38 0.2150E+01 0.1530 H.L. 1 -0.1930E+01 0.153 H.L. 2 0

39 46 0.1870E+01 0.2320 H.L. 5 -0.1880E+01 0.189 H.L. 1 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 5 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 40 1 0.2200E+00 0.0360 C.L. 6 -0.1115E+02 0.036 H.L. 1 0

40 7 0.1082E+02 0.2860 C.L. 1 0.0 0.099 C.L. 6 0

40 25 0.8710E+01 0.1170 H.L. 1 0.0 0.099 C.L. 6 0

40 27 0.5670E+01 0.0900 H.L. 1 -0.4480E+01 1.528 C.L. 4 0

40 34 0.8120E+01 0.1170 H.L. 1 -0.4490E+01 1.654 C.L. 4 0

40 41 0.5090E+01 0.0720 H.L. 1 -0.2190E+01 0.063 H.L. 2 0

40 52 0.8420E+01 0.1170 H.L. 1 -0.4520E+01 1.654 C.L. 4 0

41 2 0.0 0.0090 C.L. 6 -0.9350E+02 0.063 H.L. 1 0

41 10 0.7530E+01 0.2860 C.L. 2 -0.1000E-01 0.036 C.L. 2 0

41 25 0.7690E+01 0.2320 H.L. 6 -0.1000E-01 0.036 C.L. 2 0

41 27 0.3920E+01 0.1170 H.L. 2 -0.4600E+01 1.366 C.L. 4 0

41 40 0.2190E+01 0.0630 H.L. 2 -0.5090E+01 0.072 H.L. 1 0

41 42 0.6090E+01 0.1080 H.L. 1 -0.3100E+01 0.081 H.L. 3 0

42 3 0.0 0.0180 C.L. 6 -0.7300E+01 0.108 H.L. 1 0

42 13 0.5820E+01 0.3040 C.L. 3 0.0 0.090 C.L. 6 0

42 25 0.6730E+01 0.1620 H.L. 1 0.0 0.090 C.L. 6 0

42 27 0.4020E+01 0.1800 H.L. 6 -0.4520E+01 1.726 C.L. 1 0

42 29 0.6790E+01 0.1800 H.L. 6 -0.4000E+01 2.266 C.L. 6 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 6 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 42 35 0.6520E+01 0.1800 H.L. 6 -0.4480E+01 1.636 C.L. 6 0

42 41 0.3100E+01 0.0810 H.L. 3 -0.6090E+01 0.108 H.L. 1 0

42 43 0.4190E+01 0.1440 H.L. 1 -0.5140E+01 0.135 H.L. 6 0

42 50 0.6480E+01 0.1530 H.L. 1 -0.4530E+01 1.690 C.L. 6 0

43 4 0.0 0.0090 C.L. 6 -0.8240E+01 0.090 C.L. 6 0

43 16 0.6680E+01 0.2860 H.L. 4 -0.1000E-01 0.036 H.L. 4 0

43 25 0.6610E+01 0.1890 H.L. 1 -0.1000E-01 0.036 C.L. 4 0

43 29 0.7150E+01 0.2680 H.L. 1 -0.4020E+01 2.212 C.L. 1 0

43 31 0.3970E+01 0.1800 H.L. 1 -0.4440E+01 1.726 C.L. 6 0

43 36 0.6400E+01 0.2500 H.L. 1 -0.4460E+01 1.618 C.L. 1 0

43 42 0.5140E+01 0.1350 H.L. 6 -0.4190E+01 0.144 H.L. 1 0

43 44 0.2620E+01 0.0720 H.L. 4 -0.4970E+01 0.099 H.L. 6 0

44 5 0.0 0.0 C.L. 6 -0.9160E+01 0.063 H.L. 6 0

44 19 0.7190E+01 0.2860 C.L. 5 -0.1000E-01 0.036 C.L. 5 0

44 25 0.7690E+01 0.2320 H.L. 1 -0.1000E-01 0.036 C.L. 5 0

44 31 0.3870E+01 0.1890 H.L. 2 -0.4550E+01 1.402 C.L. 3 0

44 43 0.4970E+01 0.0990 H.L. 6 -0.2620E+01 0.072 H.L. 4 0

44 45 0.2300E+01 0.0990 H.L. 4 -0.5260E+01 0.072 H.L. 6 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 7 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 45 6 0.2100E+00 0.0360 C.L. 1 -0.1136E+02 0.036 H.L. 6 0

45 22 0.1057E+02 0.2860 C.L. 6 0.0 0.027 C.L. 6 0

45 25 0.8620E+01 0.1170 H.L. 6 0.0 0.027 C.L. 6 0

45 31 0.5510E+01 0.0810 H.L. 6 -0.4510E+01 1.438 C.L. 3 0

45 37 0.7930E+01 0.0990 H.L. 6 -0.4470E+01 1.618 C.L. 3 0

45 44 0.5260E+01 0.0720 H.L. 6 -0.2300E+01 0.099 H.L. 4 0

45 53 0.8280E+01 0.1080 H.L. 6 -0.4490E+01 1.618 C.L. 2 0

46 3 0.0 0.0180 C.L. 6 -0.9520E+01 0.214 H.L. 4 0

46 15 0.8000E+00 0.2680 H.L. 3 -0.4140E+01 0.214 H.L. 1 0

46 25 0.1590E+01 0.2140 H.L. 6 -0.7400E+00 0.250 H.L. 6 0

46 46 0.0 2.9680 C.L. 6 0.0 2.968 C.L. 6 0

46 48 0.1590E+01 0.2140 H.L. 6 -0.1920E+01 0.232 C.L. 1 0

46 50 0.1270E+01 0.2140 H.L. 6 -0.6840E+01 1.600 C.L. 5 0

47 4 0.0 0.0890 C.L. 6 -0.9740E+01 0.250 H.L. 1 0

47 18 0.1150E+01 0.2680 H.L. 4 -0.4130E+01 0.250 H.L. 1 0

47 25 0.1580E+01 0.2140 H.L. 1 -0.7400E+00 0.250 H.L. 1 0

47 46 0.2000E+01 0.2140 H.L. 1 -0.2150E+01 0.214 H.L. 6 0

47 48 0.2050E+01 0.1800 H.L. 6 -0.1880E+01 0.162 H.L. 4 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 8 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 48 5 0.0 0.0 C.L. 6 -0.1063E+02 0.108 H.L. 5 0

48 21 0.1020E+01 0.2680 C.L. 5 -0.4700E+01 0.250 H.L. 2 0

48 25 0.15800+01 0.1530 H.L. 6 -0.7000E+00 0.268 C.L. 2 0

48 47 0.1880E+01 0.1620 H.L. 4 -0.2050E+01 0.180 H.L. 6 0

48 49 0.2170E+01 0.1530 H.L. 6 -0.1900E+01 0.153 H.L. 5 0

49 6 0.2100E+00 0.0360 C.L. 1 -0.1403E+02 0.286 C.L. 6 0

49 24 0.1220E+01 0.2860 H.L. 6 -0.4850E+01 0.180 H.L. 5 0

49 25 0.1830E+01 0.1530 H.L. 5 -0.7600E+00 0.250 C.L. 3 0

49 48 0.1900E+01 0.1530 H.L. 5 -0.2170E+01 0.153 H.L. 6 0

50 3 0.4600E+00 2.5180 C.L. 6 -0.8870E+01 0.214 H.L. 4 0

50 13 0.6850E+01 1.5820 C.L. 6 -0.5970E+01 0.171 H.L. 1 0

50 14 0.6870E+01 1.6000 C.L. 5 -0.4800E+01 0.189 H.L. 1 0

50 15 0.6850E+01 1.6180 C.L. 5 -0.3320E+01 0.232 H.L. 6 0

50 42 0.4530E+01 1.6900 C.L. 6 -0.6480E+01 0.153 H.L. 1 0

50 46 0.6840E+01 1.6000 C.L. 5 -0.1270E+01 0.214 H.L. 6 0

51 1 0.1550E+01 0.5380 H.L. 3 -0.1236E+02 0.108 H.L. 1 0

51 2 0.1530E+01 0.5380 H.L. 3 -0.1036E+02 0.117 H.L. 2 0

51 3 0.1560E+01 0.5560 H.L. 1 -0.7820E+01 0.117 H.L. 1 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-3 (Page 9 of 9)

Between Maximum Minimum And Diff Time Diff Time Comp Comp Pressure (Sec) Element Pressure (Sec) Element 51 4 0.1720E+01 0.5560 H.L. 1 -0.9180E+01 0.099 H.L. 6 0

51 5 0.1750E+01 0.5560 H.L. 1 -0.1044E+02 0.108 H.L. 5 0

51 6 0.1760E+01 0.5560 H.L. 1 -0.1253E+02 0.108 H.L. 6 0

51 33 0.1560E+01 0.5560 H.L. 1 -0.6550E+01 0.180 H.L. 5 0

52 2 0.4800E+00 2.4820 C.L. 6 -0.1102E+02 0.117 H.L. 2 0

52 6 0.5100E+00 2.5900 C.L. 1 -0.1299E+02 0.232 C.L. 6 0

52 27 0.3400E+00 2.5720 C.L. 6 -0.6690E+01 0.466 C.L. 1 0

52 34 0.7000E-01 2.5720 C.L. 6 -0.1010E+01 0.484 C.L. 1 0

52 40 0.4520E+01 1.6540 C.L. 4 -0.8420E+01 0.117 H.L. 1 0

53 31 0.3600E+00 2.5540 C.L. 1 -0.6780E+01 0.466 C.L. 6 0

53 32 0.2500E+00 0.2860 C.L. 5 -0.4600E+00 0.484 C.L. 6 0

53 37 0.9000E+01 1.7980 C.L. 1 -0.1250E+01 0.484 C.L. 6 0

53 45 0.4490E+01 1.6180 C.L. 2 -0.8280E+01 0.108 H.L. 6 0

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-4 (Page 1 of 2)

Table 6-4. TMD Element Input Data Ice Ice Heat Initial Air Initial Element Volume Mass Transfer Initial Steam Pressure Temperature Number (ft3) (lbm) Area (ft2) Pressure (psia) (psia) (°F) 1 30091. 0 0 .3 14.7 120.

2 36965. 0 0 .3 14.7 120.

3 52737. 0 0 .3 14.7 120.

4 36012. 0 0 .3 14.7 120.

5 36965 0 0 .3 14.7 120.

6 28512 0 0 .3 14.7 120.

7 3295. 93576. 11290. 0.07 14.93 30.0 8 3295. 93576. 11290. 0.07 14.93 30.0 9 3295. 46788. 5645 0.07 14.93 30.0 10 3895. 110595. 13342. 0.07 14.93 30.0 11 3895. 110595. 13342. 0.07 14.93 30.0 12 3895. 55295. 6671 0.07 14.93 30.0 13 7789. 221180. 26685. 0.07 14.93 30.0 14 7789. 221180. 26685. 0.07 14.93 30.0 15 7789. 110590. 13343. 0.07 14.93 30.0 16 5393. 153125. 18474. 0.07 14.93 30.0 17 5393. 153125 18474. 0.07 14.93 30.0 18 5393. 76562. 9237. 0.07 14.93 30.0 19 4194. 119097. 14369. 0.07 14.93 30.0 20 4194. 119097. 14369. 0.07 14.93 30.0 21 4194. 59549. 7185. 0.07 14.93 30.0 22 4194. 119097. 14369. 0.07 14.93 30.0 23 4194. 119097. 14369. 0.07 14.93 30.0 24 4194. 59549 7185. 0.07 14.93 30.0 25 670101. 0 0 .3 14.7 120.

26 11706. 0 0 .3 14.7 120.

27 14953. 0 0 .3 14.7 120.

28 11207. 0 0 .3 14.7 120.

29 11835. 0 0 .3 14.7 120.

30 11099. 0 0 .3 14.7 120.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-4 (Page 2 of 2)

Ice Ice Heat Initial Air Initial Element Volume Mass Transfer Initial Steam Pressure Temperature Number (ft3) (lbm) Area (ft2) Pressure (psia) (psia) (°F) 31 14955. 0 0 .3 14.7 120.

32 9762. 0 0 .3 14.7 120.

33 16129. 0 0 .3 14.7 120.

34 4301. 0 0 .3 14.7 120.

35 4140. 0 0 .3 14.7 120.

36 4140. 0 0 .3 14.7 120.

37 3662. 0 0 .3 14.7 120.

38 5385. 0 0 0.07 14.93 30.0 39 6365. 0 0 0.07 14.93 30.0 40 2778. 46788. 5645. 0.07 14.93 30.0 41 3283. 55295. 6671. 0.07 14.93 30.0 42 6565. 110590. 13343. 0.07 14.93 30.0 43 4545. 76562 9237 0.07 14.93 30.0 44 3535. 59549. 7185. 0.07 14.93 30.0 45 3535. 45549. 7185. 0.07 14.93 30.0 46 12729. 0 0 0.07 14.93 30.0 47 8813. 0 0 0.07 14.93 30.0 48 6854. 0 0 0.07 14.93 30.0 49 6854. 0 0 0.07 14.93 30.0 50 1078. 0 0 .3 14.7 120.

51 15349. 0 0 .3 14.7 120.

52 7657. 0 0 .3 14.7 120.

53 5058. 0. 0 .3 14.7 120.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-5 (Page 1 of 3)

Table 6-5. TMD Flow Path Input Data - Ventilation Duct Intact Flow Resistance Flow Path Element to Flow Path Flow Area Loss L Contraction f

Element Length (ft) (ft2) Coefficient K D a/A 1 to 2 15.0 681. 0.150 0.035 0.54 2 to 3 21.3 681. 0.150 0.050 0.54 3 to 4 23.2 679. 0.076 0.050 0.54 4 to 5 17.4 681. 0.120 0.044 0.54 5 to 6 15.0 681. 0.150 0.035 0.54 6 to 1 29.0 100. 1.58 0 0.080 26 to 32 29.0 26.3 1.59 0.007 0.18 27 to 1 8.87 46.0 2.40 0 0.13 28 to 26 80.0 146 0 0.21 1.0 29 to 28 2.45 9.0 2.22 0 .027 30 to 28 59.4 90.0 1.1 0.081 0.62 31 to 4 8.77 46.0 2.40 0. 0.13 32 to 30 80.0 146. 0 0.21 1.0 2 to 33 5.81 38.3 2.15 0 0.030 34 to 27 4.63 16.00 2.60 0.001 0.076 37 to 31 4.64 16.0 2.60 0.001 0.083 40 to 1 10.46 121.9 1.16 0 1.0 41 to 2 10.36 144.0 1.16 0 1.0 42 to 3 10.36 288.0 1.16 0 1.0 43 to 4 10.36 199.4 1.16 0 1.0 44 to 5 10.36 155.1 1.16 0 1.0 45 to 6 10.36 155.1 1.16 0 1.0 1 to 33 11.5 20.0 2.15 0 0.016 3 to 33 6.60 72.0 2.15 0 0.035 4 to 33 6.24 52.0 2.15 0. 0.041 6 to 33 5.90 18.0 2.15 0. 0.041 7 to 8 12.278 112.80 0. .5165 .239 8 to 9 12.278 112.80 0. .5165 .359 9 to 38 8.8558 112.80 .812 .2582 .359 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-5 (Page 2 of 3)

Flow Resistance Flow Path Element to Flow Path Flow Area Loss L Contraction f

Element Length (ft) (ft2) Coefficient K D a/A 10 to 11 12.278 131.31 0. .5165 .239 11 to 12 12.278 131.31 0. .5165 .359 12 to 39 8.8558 131.31 .812 .2582 .359 13 to 14 12.278 266.63 0. .5165 .239 14 to 15 12.278 266.63 0. .5165 .359 15 to 46 8.8558 266.63 .812 .2582 .359 16 to 17 12.278 184.59 0. .5165 .239 17 to 18 12.278 184.59 0. .5165 .359 18 to 47 8.8558 184.59 .812 .2582 .359 19 to 20 12.278 143.57 0. .5165 .239 20 to 21 12.278 143.57 0. .5165 .359 21 to 48 8.8558 143.57 .812 .2582 .359 22 to 23 12.278 143.57 0. .5165 .239 23 to 24 12.278 143.57 0. .5165 .359 24 to 49 8.8558 143.57 .812 .2582 .359 26 to 27 6.86 17.5 2.69 0.002 0.12 27 to 3 8.70 46.0 2.40 0. 0.13 28 to 27 6.86 17.5 2.69 0.002 0.12 30 to 31 6.86 17.5 2.69 0.002 0.12 31 to 6 9.08 46.0 2.40 0. 0.13 32 to 31 6.03 17.5 2.69 0.002 0.12 5 to 33 5.81 38.3 2.15 0. 0.03 34 to 26 2.86 12.0 2.39 0. 0.057 35 to 28 3.48 12.0 2.38 0. 0.036 36 to 30 3.48 12.0 2.38 0. 0.036 37 to 32 2.91 12.0 2.40 0. 0.062 38 to 25 2.80 233.80 1.45 0. .269 39 to 25 2.80 267.60 1.43 0. .269 40 to 7 8.222 106.7 0.227 .1419 .230 40 to 10 8.222 126.1 0.227 .1419 .230 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-5 (Page 3 of 3)

Flow Resistance Flow Path Element to Flow Path Flow Area Loss L Contraction f

Element Length (ft) (ft2) Coefficient K D a/A 42 to 13 8.222 252.6 0.227 .1419 .230 43 to 16 8.222 174.6 0.227 .1419 .230 44 to 19 8.222 135.8 .227 .1419 .230 45 to 22 8.222 135.8 .227 .1419 .230 46 to 25 2.80 539.5 1.43 0. .269 47 to 25 2.80 376.5 1.41 0. .269 48 to 25 2.80 289.4 1.44 0. .269 49 to 25 2.80 296.3 1.43 0. .269 30 to 50 2.55 5.0 2.20 0. 0.034 34 to 52 4.06 16.0 2.57 0. 0.076 52 to 53 25.19 40.25 1.58 0. 0.22 53 to 37 3.34 16.0 2.58 0. 0.079 53 to 32 2.87 7.5 2.20 0. 0.037 52 to 26 13.45 35.0 2.72 0. 0.187 51 to 3 32.89 45.0 1.62 0. 0.117 40 to 41 13.8 24.7 7.5 0. .075 41 to 42 22.4 24.7 12.5 0. .046 42 to 43 25.3 24.7 12.5 0. .041 43 to 44 18.4 24.7 10.0 0. 0.56 44 to 45 16.1 24.7 10.0 0. 0.64 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-6 (Page 1 of 1)

Table 6-6. TMD Flow Path Input Data - Ventilation Duct Intact Flow Resistance Flow Path Element to Flow Path Flow Area Loss L Contraction f

Element Length (ft) (ft2) Coefficient K D a/A 3 to 33 6.13 56.6 2.15 --- 0.026 4 to 33 5.78 39.8 2.15 --- 0.031 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-7 (Page 1 of 2)

Table 6-7. Mass And Energy Release Rates For Peak Reverse Differential Pressure Steam Mass Steam Energy Spill Mass Spill Energy Time (sec) (lbm/sec) (Btu/sec) (lbm/sec) (Btu/sec)

0. 0. 0. 0. 0.
1. 71,304. 39,106,924. 1,247. 74072.
2. 52,769. 29,384,776. 1,200. 71268.
3. 45,106. 26,213,749. 1,159. 68845.
4. 41,675. 24,112,360. 1,122. 66647.
5. 38,687. 23,089,906. 1,088. 64627.
6. 33,982. 20,897,219. 1,057. 62815.
7. 31,240. 19,440,588. 1,030. 61182.
8. 25,628. 16,783,231. 1,004. 59638.
9. 19,552. 14,038,088. 980. 58236.
10. 15,183. 12,003,759. 958. 56935.
12. 11,403. 9,291,704. 919. 54589.
14. 8,957. 6,897,938. 884. 52510.
16. 4,748. 3,569,112. 853. 50668.
18. 5,302. 3,719,017. 825. 49005.
20. 4,500. 2,185,549. 800. 47520.
22. 3,518. 1,684,524. 778. 46213.
24. 3,125. 1,405,670. 757. 44966.
26. 3,335. 1,379,978. 737. 43778.
28. 3,518. 1,439,306. 719. 42709.
30. 3,551. 1,457,023. 703. 41758.
35. 5,696. 1,699,314. 666. 39560.
40. 2,059. 497,881. 634. 37660.
45. 0. 0. 607. 36056.
50. 0. 0. 582. 34571.
55. 0. 0. 561. 33323.
60. 0. 0. 541. 32135.
65. 0. 0. 523. 31066.
70. 3,900. 863,783. 507. 30116.
75. 4,657. 1,066,886. 492. 29225.
80. 4,079. 1,028,210. 479. 28453.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-7 (Page 2 of 2)

Steam Mass Steam Energy Spill Mass Spill Energy Time (sec) (lbm/sec) (Btu/sec) (lbm/sec) (Btu/sec)

85. 4,922. 1,257,468. 466. 27680.
90. 5,287. 1,377,635. 454. 26968.

93.51 ----- --------- 447. 26552.

95. 5,445. 1,378,187. --- -----
99. 5,344. 1,378,742. --- -----

100.2 0. 0. 211. 3789.

110. 0. 0. 211. 3789.

124. 15. 19,681. 211. 3789.

136. 12. 14,953. 211. 3789.

153. 11. 13,930. 211. 3789.

177. 17. 21,240. 211. 3789.

213. 25. 32,142. 211. 3789.

260. 444. 112,347. 211. 3789.

333. 460. 108,733. 211. 3789.

Note:

1. Broken loop accumulator spill ends at 93.5 sec
2. Beginning of reflood release (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-8 (Page 1 of 1)

Table 6-8. Compartment Volume and Initial Condition Data For Peak Reverse Differential Pressure I. Containment Volume (ft3)

Upper Compartment 720,000 Lower Compartment 250,100 Ice Condenser 122,400 Dead Ended Compartments (includes 125,400 all accumulator rooms, both fan compartments, instrument room and pipe tunnel) 1,217,900 II. Initial Conditions

1. Highest Containment Pressure 15.0 psia
2. Lowest Operational Containment Temperature for
a. Upper Compartment 75°F
b. Lower Compartment 100°F
c. Dead Ended Compartments 100°F
3. Highest Refueling Water Storage 100°F Tank Temperature
4. Lowest Temperature Outside 10°F Containment
5. Highest Initial Spray Temperature 100°F (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-9 (Page 1 of 1)

Table 6-9. Active Heat Sink Data For Peak Reverse Differential Pressure I. Containment Spray System Parameters

1. Runout flow for one pump 4800 gpm
2. Number of pumps operating with no diesel failure 2
3. Number of pumps operating with one diesel failure 1
4. Fastest post-LOCA initiation of spray system (assuming offsite 25 sec power loss at start of LOCA)

II. Containment Air Return Fan System Parameters

1. Conservatively high flow rate (per fan) 40,000 cfm
2. Fastest post-LOCA initiation 25 sec III. Hydrogen Skimmer Fan System Parameters
1. Conservatively low flow rate (per fan) 3000 cfm (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-10 (Page 1 of 1)

Table 6-10. Upper Compartment Passive Heat Sink Data For Peak Reverse Differential Pressure Thermal Volumetric Heat Heat Transfer Thickness and Conductivity Capacity (Btu/ft3-Structure Area (ft2) Material (Btu/ft-hr-°F) °F)

Structural Walls, 28686 1.34 ft. Concrete 1.05 31.95 Doghouses Containment Dome 25473 0.58 in. Carbon Steel 32.0 58.8 and Shell Miscellaneous 34364 0.02 ft. Carbon Steel 32.0 58.8 Equipment, Crane Platforms, Electrical Equipment Reactor Vessel Head 1218 0.028 ft. Stainless Steel 9.4 55.11 Stand, Internals Storage Stand Refueling Canal 6531 0.016 ft. Stainless Steel 9.4 55.11 1.5 ft. Concrete 1.05 31.95 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-11 (Page 1 of 1)

Table 6-11. Lower and Dead Ended Compartments Passive Heat Sink Data For Peak Reverse Differential Pressure Thermal Volmetric Heat Transfer Conductivity Heat Capacity Structure Area (ft2) Thickness and Material (Btu/ft-hr-°F) (Btu/ft3-°F)

Structural Concrete 71873 1.5 ft. Concrete 1.05 31.95 (operating deck, walls, doghouses, refueling canal)

Structural Steel (SG 23147 0.072 ft. Carbon Steel 32.0 58.8 supports, platforms, steel columns)

Containment Shell 19037 0.063 ft. Carbon Steel 32.0 58.8 Refueling Canal 2615 0.016 ft. Stainless Steel 9.4 1.5 ft. Concrete 1.05 31.95 Mechanical 1785 0.003 ft. Stainless Steel 9.4 55.11 Equipment Cooling Coils 71400 0.004 ft. Copper 224.0 51.4 Steam Generator 5964 0.063 ft. Carbon Steel 32.0 58.8 Doghouse Floors and Slabs 8789 2.04 ft. Concrete 1.05 31.95 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-12 (Page 1 of 2)

Table 6-12. Sensitivity Studies For D.C. Cook Plant Change In Change Made Change In Peak Pressure From Base Operating Against the Parameter Value Deck P Shell Blowdown + 10% + 11% + 12%

Blowdown - 10% - 10% - 12%

Blowdown - 20% - 20% - 23%

Blowdown - 50% - 50% - 53%

Break Compartment Inertia Length + 10% + 4% + 1%

Break Compartment Inertia Length - 10% - 4% - 1%

Break Compartment Volume + 10% - 2% - 1%

Break Compartment Volume - 10% + 2% + 1%

Break Compartment Vent Areas + 10% - 6% - 5%

Break Compartment Vent Areas - 10% + 8% + 5%

Door Port Failure in Break Compartment one door port +1 - 1%

fails to open Ice Mass + 10% 0 0 Ice Mass - 10% 0 0 Door Inertia + 10% + 1% 0 Door Inertia - 10% - 1% 0 All Inertia Lengths + 10% + 5% + 4%

All Inertia Lengths - 10% - 5% - 3%

Ice Bed Loss Coefficients + 10% 0 0 Ice Bed Loss Coefficients - 10% 0 0 Entrainment Level 0% Ent - 27% - 11%

Entrainment Level 30% Ent - 19% - 15%

Entrainment Level 50% Ent - 13% - 12%

Entrainment Level 75% Ent - 6% - 6%

Lower Compartment Loss Coefficients + 10% 0 0 Lower Compartment Loss Coefficients - 10% 0 0 Cross Flow Lower Plenum in low estimate of 0 - 7%

resistance Cross Flow Lower Plenum in high estimate 0 - 3%

of resistance (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-12 (Page 2 of 2)

Change In Change Made Change In Peak Pressure From Base Operating Against the Parameter Value Deck P Shell Ice Condenser Flow Area + 10% 0 - 3%

Ice Condenser Flow Area - 10% 0 + 4%

Ice Condenser Flow Area + 20% 0 - 6%

Ice Condenser Flow Area - 20% 0 + 8%

Initial Pressure in Containment + 0.3 psi + 2% + 2%

Initial Pressure in Containment -0.3 psi - 2% - 2%

Initial Ice Bed Temperature + 15°F 0 0 Initial Ice Bed Temperature - 15°F 0 + 1%

Notes:

1. All valves shown are to the nearest percent.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-13 (Page 1 of 1)

Table 6-13. McGuire Ice Condenser Design Parameters Reactor Containment Volume (Net free volume, ft3)

Upper Compartment 670,101 Upper Plenum 47,000 Ice Condenser 86,300 Lower Plenum 24,200 Lower Compartment (Active) 237,411 Lower Compartment (Dead Ended) 130,899 Total Containment Volume 1,195,911 Note:

1. Reactor Power, MWt 3,479 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-14 (Page 1 of 1)

Table 6-14. Deleted Per 1998 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-15 (Page 1 of 1)

Table 6-15. Containment Sump Volume Vs. Time Peak Containment Pressure Transient Time (sec) Total Volume (ft3) 45 11593 60 17541 75 19018 90 19496 160 21097 230 22822 300 24015 450 26316 600 28813 750 31258 1200 38391 1800 47481 2400 55550 3000 63597 3600 70763 4200 72147 4800 74657 5400 76237 6000 77512 6600 77981 8200 77961 10600 77915 (30 NOV 2012)

McGuire Nuclear Station UFSAR Table 6-16 (Page 1 of 1)

Table 6-16. Containment Sump Volume Vs. Elevation(1)

Accumulated Active Volume(2)

Building Elevation (ft) (ft3) 726 7226 727 14600 728 21893 729 29046 730 35798 731 42844 732 50050 733 57352 734 64154 735 71386 736 78596 737 83722 738 88065 739 112398 740 119884 Note:

1. Volumes are determined by calculating the total volume and subtracting the volumes of all obstructions such as interior structures, equipment, piping, cable, etc. The volumes are considered to be accurate within +/- 5%.
2. Assumes incore instrumentation area floods at elevation 738'-6".

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-17 (Page 1 of 2)

Table 6-17. ECCS Flow Rates1 Non-Spilled Spilled Auxiliary ECCS Spilled Spray ECCS ECCS Spray Spray Time from Flow from Flow from Flow from Flow from Flow from Flow from Flow from Beginning of CLR RWST RWST RWST Sump Sump Sump Sump (seconds) (gpm) (gpm) (gpm) (gpm) (gpm) (gpm) (gpm)

ECCS Flow Rate During Cold Leg Recirculation (CLR) - with Spilling Simulation 0.0 to 95.0 3280 1805 0 0 0 0 0 95.01 to 555.02 680 255 0 1465 1490 0 0 2

555.01 to tLO-LO 0.0 0 0 1465 1490 3325 0 tLO-LO2 to end 0 0 0 2190 1750 3325 0 ECCS Flow Rate During Cold Leg Recirculation (CLR) - with No Spilling Simulation Auxiliary ECCS Spray ECCS Spray Spray Time fromBeginning Flow from Flow from Flow from Flow from Flow from of CLR RWST RWST Sump Sump Sump (seconds) (gpm) (gpm) (gpm) (gpm) (gpm) 0.0 to 95.00 4580 05 0 0 0 95.01 to 555.0 2 880 0 2950 0 0 555.01 to tLO-LO 2 0.0 0 2950 3325 0 tLO-LO2 to end 0.0 0 3916 3325 0 (30 NOV 2012)

McGuire Nuclear Station UFSAR Table 6-17 (Page 2 of 2)

Notes:

1. The flow values used in the containment analyses have been reduced by approximately 2% to account for the frequency variation of +/-2% allowed by the Technical Specifications.
2. TLO-LO may occur prior to tCLR+555, in which case spray flow alignment is delayed until after tLO-LO.

(30 NOV 2012)

McGuire Nuclear Station UFSAR Table 6-18 (Page 1 of 3)

Table 6-18. Structural Heat Sink Data A. Upper Containment Area (sq. ft) Thickness (ft) Material

1. Containment Vessel Dome 20,773.8 0.00059 Paint 0.0573 Carbon Steel
2. Containment Shell 3,139 0.00059 Paint 0.0625 Carbon Steel
3. Crane Wall, CRDM Gate, S/G 11,319 0.001167 Paint Doghouse 1.5 Concrete
4. Ice Condenser End Wall, Operating 7,016 0.001167 Paint Floor, Pressurizer Doghouse, S/G 1.0 Concrete Doghouse, S/G Dome Slab
5. CRDM Missile Shield, Walls 734 0.001167 Paint 3.0 Concrete
6. CRDM Missile Shield, Structures 753 0.00059 Paint 0.042 Carbon Steel
7. S/G Shell, S/G Dome, RX vessel Head 5,611 0.00059 Paint Stand, Internals Storage Stands 0.03125 Carbon Steel
8. Refueling Canal, Refueling Canal 7,234 0.01563 Stainless Steel Floor Slab
9. RX Vessel Hand Stand, Internals 1,179 0.04165 Stainless Steel Storage Stands
10. Polar Crane 6,000 0.00059 Paint 0.04917 Carbon Steel
11. Platforms 9,000 0.00059 Paint 0.00917 Carbon Steel
12. Equipment Hatch Guide 310 0.00059 Paint 190 0.02417 Carbon Steel
13. Dead-Ended Compartments 3,941.4 0.001167 Paint 2.0 Concrete
14. Dead-Ended Compartments 649 0.001167 Paint 2.5 Concrete B. LOWER CONTAINMENT Area (sq ft) Thickness (ft) Material
1. Operating Deck Floor 1,709.9 0.001167 Paint 1.25 Concrete
2. Crane Wall 10,979.1 0.001167 Paint 1.5 Concrete
3. Refueling Canal Wall 411.4 0.001167 Paint 8.0 Concrete
4. Refueling Canal Wall 6,316.1 0.001167 Paint 3.0 Concrete (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-18 (Page 2 of 3)

5. Refueling Canal Floor 4,110.4 0.001167 Paint 2.0 Concrete
6. Lower S/G Support 1,700 0.00059 Paint 0.101 Carbon Steel
7. Upper S/G Support 3,972 0.00059 Paint 0.066 Carbon Steel
8. RCP Support Columns 768.8 0.00059 Paint 0.0833 Carbon Steel
9. Platforms 3,000 0.00059 Paint 8.7E-3 Carbon Steel
10. S/G Enclosure Walls, Dome Slab, 4,038 0.001167 Paint Pressurizer Doghouse 1.0 Concrete
11. S/G Enclosure Walls, Dome Slab 2,262 0.001167 Paint 1.384 Concrete
12. S/G Dome, Shell 3,878 0.00059 Paint 0.031 Carbon Steel
13. Lower SM Line Restraints 627 0.00059 Paint 0.0108 Carbon Steel
14. Upper SM Line Restraints 2,399 0.00059 Paint 0.116 Carbon Steel
15. RX Vessel Support 284 0.00059 Paint 0.166 Carbon Steel
16. Lower PRZ Support 1,220 0.00059 Paint 0.038 Carbon Steel
17. Dead-Ended Compartments Slabs 39,715 0.001167 Paint 12,272.4 1.0 Concrete 1,196 1.25 Concrete 11,092 1.5 Concrete 8,671.6 2.0 Concrete 4,165.2 2.5 Concrete 2,317.8 3.0 Concrete
18. Dead-Ended Compartments Slabs 17,913.7 0.00059 Paint 14,161.7 0.0625 Carbon Steel 2,454.9 0.0417 Carbon Steel 1,297.1 0.0352 Carbon Steel C. ICE CONDENSER Area (sq. ft) Thickness (ft) Material
1. Ice Baskets 180,628 0.00663 Carbon Steel
2. Lattice Frames 76,650 0.0217 Carbon Steel
3. Lower Support Structure 28,670 0.0267 Carbon Steel (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-18 (Page 3 of 3)

Note:

1. Ice condenser walls are not considered in the GOTHIC model due to the insulation present. Since these structures would condense additional steam and remove energy from the containment, their omission is conservative.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-19 (Page 1 of 1)

Table 6-19. Comparison of Design Parameters - McGuire and D. C. Cook McGuire Cook Reactor Containment Values (Net free volume)

Upper Compartment, ft3 670,101 695,390 Ice Condenser (Upper Plenum), ft3 47,000 47,000 Ice Condenser (Ice Bed Region), ft3 86,300 86,300 3

Ice Condenser (Lower Plenum), ft 24,200 24,200 Lower Compartment (Active), ft3 237,411 235,481 Lower Compartment (Dead Ended), ft3 130,899 111,571 Total Containment Volume, ft3 1,195,911 1,199,942 Reactor Power, MWt 3,479 3,394 Weight of Ice in Condenser Used for Safety Analysis, lbs 1.89 x 106 2.45 x 106 Normal Spray Flow Rate To Upper Compartment (gpm/pump) 3,4002 2,000 Normal Spray Flow Rate To Lower Compartment (gpm/pump) 0 900 Auxiliary Spray Flow Rate To Upper Compartment (gpm/pump) 2,3501,2 2,000 Auxiliary Spray Flow Rate To Lower Compartment (gpm/pump) ------ ------

Note:

1. Flow is available at approximately 50 minutes after reactor trip
2. Note the flow values used in the containment analyses have been reduced by approximately 2% to account for the frequency variation of +/-2% allowed by the Technical Specifications.

(11 NOV 2006)

McGuire Nuclear Station UFSAR Table 6-20 (Page 1 of 1)

Table 6-20. Allowable Leakage Area For Various Reactor Coolant System Break Sizes 5 ft Deck Leak Air Resultant Peak Compression Peak Deck Leakage Area Containment Break Size (psig) (ft) Pressure (psig)

Double-ended 7.7 50 11.9 0.6 Double-ended 6.6 50 12.5 3 ft 6.25 50 12.2 0.5 ft 5.75 50 14.5 0.5 ft1 5.75 50 11.81 8 inch diameter 5.5 40 14.9 8 inch diameter1 5.5 50 12.01 6 inch diameter 5.0 40 14.7 2 1/2 inch diameter 4.0 50 13.4 1/2 inch diameter 3.0 >50 3.0 Note:

1. This case assumes upper compartment structural heat sink steam condensation of 6 lb/sec and 30 percent of deck leakage is air.

Deleted Per 2011 Update.

(05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-21 (Page 1 of 1)

Table 6-21. Summary Of Heat Transfer Correlations Used To Calculate Steam Generator Heat Flow In The SATAN Code Primary to Secondary Heat Flow Primary Secondary (Tube Side) (Shell Side)

Dittus-Boelter Jens-Lottes Secondary to Primary Heat Flow Primary Secondary Jens-Lottes Dougall-Rohsenow McAdams McEligot (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-22 (Page 1 of 1)

Table 6-22. Deleted Per 2009 Update.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-23 (Page 1 of 1)

Table 6-23. Deleted Per 2009 Update.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-24 (Page 1 of 1)

Table 6-24. Deleted Per 2009 Update.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-25 (Page 1 of 1)

Table 6-25. Deleted Per 2009 Update.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-26 (Page 1 of 1)

Table 6-26. Deleted Per 2009 Update.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-27 (Page 1 of 1)

Table 6-27. Deleted Per 2009 Update.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6 6-41 (Page 1 of 1)

Table 6-28. Deleted Per 1998 Update Table 6-29. Deleted Per 1998 Update Table 6-30. Deleted Per 1998 Update Table 6-31. Deleted Per 1998 Update Table 6-32. Deleted Per 1998 Update Table 6-33. Deleted Per 1998 Update Table 6-34. Deleted Per 1998 Update Table 6-35. Deleted Per 1998 Update Table 6-36. Deleted Per 1998 Update Table 6-37. Deleted Per 1998 Update Table 6-38. Deleted Per 1998 Update Table 6-39. Deleted Per 1998 Udpate Table 6-40. Deleted Per 1998 Update Table 6-41. Deleted Per 1998 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-42 (Page 1 of 1)

Table 6-42. TMD Input Data - 2 Node Steam Generator Enclosure Element Volume 1 5298 ft3 2 6370 ft3 L Inertia Length Flow Area Contraction f

Flow Path K D (ft) (ft2) a/A 1 to 2 0.12 20.14 217.7 0.765 2 to Lower 1.48 0.044 12.43 188.0 0.864 Compartment 2 to Adjacent 2.09 30.45 168.0 1.0 S.G. Volume 2 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-43 (Page 1 of 2)

Table 6-43. TMD Input Data - 9 Node Steam Generator Enclosure Element Volume (ft3) 1 5298 2 788 3 329 4 251 5 996 6 1331 7 567 8 433 9 1673 Flow Path Inertia Flow (Element to L Length Area Contraction f

Element) K D (ft) (ft2) at/Au

1. Steam Generator 1-2 0.372 ---- 7.39 72.9 0.257 1-3 0.448 ---- 6.17 29.9 0.105 1-4 0.460 ---- 5.97 22.8 0.081 1-5 0.338 ---- 7.93 92.0 0.325 2-6 ----- 0.025 13.83 72.9 1.0 3-7 ----- 0.044 13.83 29.9 1.0 4-8 ----- 0.049 13.83 22.8 1.0 5-9 ----- 0.022 13.83 92.0 1.0 6-10 1.06 ---- 8.48 72.60 0.997 7-10 1.85 ---- 5.45 14.7 0.492 8-10 1.49 ---- 6.95 16.9 0.741 9-10 1.43 ---- 7.87 82.4 0.896 2-3 0.286 ---- 10.45 27.4 0.556 3-4 0.108 ---- 10.50 25.1 0.916 4-5 0.393 ---- 8.64 25.1 .429 5-2 0.286 ---- 15.14 49.25 0.841 6-7 0.313 ---- 10.49 46.67 0.561 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-43 (Page 2 of 2)

Flow Path Inertia Flow (Element to L Length Area Contraction f

Element) K D (ft) (ft2) at/Au 7-8 0.129 ---- 10.57 43.3 0.928 8-9 0.407 ---- 8.74 43.3 .440 9-6 0.169 ---- 15.19 83.19 0.845 2-Adjacent 2 0.366 ---- 9.0 112.0 0.75 6-Adjacent 6 0.99 ---- 6.76 112.0 0.471 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-44 (Page 1 of 1)

Table 6-44. Peak Differential Pressures - 2 Node Steam Generator Enclosure Nodes Differential Pressure (psi) Time (sec)

Across Enclosure Walls 1 to Upper Conpartment 13.75 3.38 2 to Upper Compartment 13.0 3.39 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-45 (Page 1 of 1)

Table 6-45. Peak Differential Pressure - Steam Generator Enclosure - 9 Node Nodes Differential Pressure (PSI) Time (sec)

Across Enclosure Walls

1. Upper Compartment 12.5 3.08
2. Upper Compartment 7.5 .028
3. Upper Compartment 9.3 .026
4. Upper Compartment 9.8 .026
5. Upper Compartment 9.8 .027
6. Upper Compartment 6.7 3.34
7. Upper Compartment 7.6 .045
8. Upper Compartment 8.4 .045
9. Upper Compartment 8.3 .045 Across Steam Generator Vessel 4-2 2.4 .023 5-3 0.59 .03 8-6 2.7 .042 9-7 0.8 .051 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-46 (Page 1 of 1)

Table 6-46. TMD Input Data - 2 Node Pressurizer Enclosure Element Volume 1 1763 ft3 2 2251 ft3 L Inertial Length f

Flow Path K D (ft) Flow Area (ft2) Contraction a/A 1 to 2 0.17 17.22 88.64 0.657 2 to Lower 1.7 0.075 10.07 69.0 0.778 Compartment (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-47 (Page 1 of 1)

Table 6-47. TMD Input Data - 4 Node Pressurizer Enclosure Element Volume(ft3) 1 1763 2 886 3 477 4 906 Inertial Flow Path L Length Flow Area Contraction f

(Element to Element) K D (ft) (ft2) at/Au 1-2 0.384 ---- 14.3 34.5 0.233 1-3 0.439 ---- 13.55 18.2 0.123 1-4 0.381 ---- 14.3 35.25 0.239 2-5 1.59 ---- 11.0 29.5 0.855 3-5 1.66 ---- 6.16 8.2 0.451 4-5 1.58 ---- 11.04 30.25 0.858 2-3 0.416 ---- 9.68 29.8 0.336 3-4 0.534 ---- 9.64 29.8 1.0 4-2 0.531 ---- 7.51 61.7 0.681 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-48 (Page 1 of 1)

Table 6-48. Mass and Energy Releases into Steam Generator Enclosure Time (Sec) Mass Flow (103 lbs/sec) Energy Flow (106 BTU/Sec) 0 7.015 8.34 2.453999 7.015 8.34 2.454 20.530 12.69 2.8164999 20.530 12.69 2.8165 23.180 13.54 10.0 23.180 13.54 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-49 (Page 1 of 1)

Table 6-49. Mass and Energy Release Rates Into Pressurizer Enclosure Time (sec) Mass Flow X 10-3 (lbm/sec) Energy x 10-5 (Btu/sec) 0.0 0.0 0.0 0.00251 5.0473 3.0977 0.00502 5.2333 3.2013 0.01002 5.1051 3.1226 0.01251 5.0746 3.1029 0.01755 5.3833 3.2753 0.02505 5.5402 3.3601 0.03259 5.8746 3.5479 0.04002 5.9221 3.5716 0.05005 5.6865 3.4332 0.07250 5.7877 3.4868 0.09001 5.4917 3.3157 0.11253 5.9404 3.5710 0.13756 5.5454 3.3445 0.15755 5.6392 3.3979 0.17760 5.4721 3.3026 0.19254 5.5189 3.3291 0.21254 5.4725 3.3025 0.23508 5.5465 3.3446 0.27752 5.5345 3.3378 0.35027 5.3649 3.2411 0.38001 5.2985 3.2031 0.41515 5.3825 3.2507 0.45006 5.2660 3.1842 0.57002 5.2492 3.1738 0.77015 5.1816 3.1336 1.00005 5.1562 3.1169 2.00015 5.0326 3.0400 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-50 (Page 1 of 2)

Table 6-50. Reactor Cavity Analysis Volumes - Cold Leg Break FT3

1. Break Location 109.6
2. Lower Reactor Cavity 15,830.0
3. Reactor Vessel Annulus 16.09
4. Reactor Vessel Annulus 2.29
5. Reactor Vessel Annulus 6.99
6. Reactor Vessel Annulus 6.99
7. Reactor Vessel Annulus 9.12
8. Reactor Vessel Annulus 13.98
9. Reactor Vessel Annulus 9.12
10. Reactor Vessel Annulus 3.54
11. Reactor Vessel Annulus 8.86
12. Reactor Vessel Annulus 3.54
13. Reactor Vessel Annulus 8.86
14. Reactor Vessel Annulus 3.54
15. Reactor Vessel Annulus 9.12
16. Reactor Vessel Annulus 3.54
17. Reactor Vessel Annulus 9.12
18. Reactor Vessel Annulus 13.98
19. Reactor Vessel Annulus 8.86
20. Reactor Vessel Annulus 13.98
21. Lower Containment 42,250.0
22. Lower Containment 42,250.0
23. Lower Containment 42,250.0
24. Lower Containment 42,250.0
25. Pipe Annulus 38.10
26. Pipe Annulus 38.10
27. Pipe Annulus 42.42
28. Pipe Annulus 42.42
29. Pipe Annulus 38.10
30. Pipe Annulus 38.10
31. Pipe Annulus 79.55 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-50 (Page 2 of 2)

FT3

32. Upper Containment 670,100.
33. Reactor Vessel Annulus 0.721
34. Reactor Vessel Annulus 0.721
35. Reactor Vessel Annulus 2.29
36. Reactor Vessel Annulus 6.99
37. Reactor Vessel Annulus 6.99
38. Reactor Vessel Annulus 13.98
39. Reactor Vessel Annulus 13.98
40. Reactor Vessel Annulus 13.98
41. Reactor Vessel Annulus 13.98
42. Reactor Vessel Annulus 13.98
43. Reactor Vessel Annulus 13.98
44. Reactor Vessel Annulus 13.98
45. Reactor Vessel Annulus 0.721
46. Reactor Vessel Annulus 0.721
47. Upper Reactor Cavity 16,270.
48. Ice Condenser 24,240.0
49. Ice Condenser 28,760.0
50. Ice Condenser 28,760.0
51. Ice Condenser 28,760.0
52. Ice Condenser 47,000.0
53. Inspection Port Above the Break 30.63
54. Broken Loop Pipe Annulus 50.32 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-51 (Page 1 of 6)

Table 6-51. Reactor Cavity Analysis Flow Paths - Cold Leg Break Flow Flow Path Between Inertia Length Minimum Flow Area Ratio (For 'y' Compartments K fl/d (ft) Area (ft2) factor) 1 3 0.73 0.0 1.61 7.42 0.267 2 22 1.62 0.0 15.85 45.0 0.111 3 34 1.2 0.0 3.39 0.834 0.112 4 35 0.0 0.23 3.33 0.687 1.0 4 45 0.33 0.0 2.74 0.625 1.0 4 47 1.0 0.13 1.86 0.625 1.0 5 36 0.0 0.23 3.33 2.11 1.0 5 47 2.15 0.0 18.2 0.175 0.000339 5 46 0.33 0.0 7.14 0.552 1.0 6 37 0.0 0.23 3.33 2.11 1.0 6 2 1.0 0.0 6.37 0.552 1.0 6 5 0.0 0.91 12.67 0.552 1.0 7 9 0.33 0.45 6.67 0.95 1.0 7 38 1.24 0.0 6.58 0.266 0.213 7 47 1.0 0.37 5.21 1.25 1.0 8 10 0.75 0.45 4.18 0.534 0.253 8 2 1.0 0.0 6.41 1.103 1.0 9 11 0.33 0.45 6.67 0.950 1.0 9 39 1.24 0.0 6.58 0.266 0.213 9 47 1.0 0.37 5.21 1.25 1.0 10 12 0.0 0.45 6.66 0.534 1.0 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-51 (Page 2 of 6)

Flow Path Between Inertia Length Minimum Flow Area Ratio (For 'y' Compartments K fl/d (ft) Area (ft2) factor) 10 2 1.0 0.0 1.65 1.103 1.0 11 13 0.33 0.45 6.67 0.950 1.0 11 40 1.24 0.0 6.58 0.266 0.213 11 47 1.0 0.37 5.21 1.25 1.0 12 14 0.0 0.45 6.66 0.534 1.0 12 2 1.0 0.0 1.65 1.103 1.0 13 15 0.33 0.45 6.67 0.950 1.0 13 41 1.24 0.0 6.58 0.266 0.213 13 47 1.0 0.37 5.21 1.25 1.0 14 16 0.0 0.45 6.66 0.534 1.0 14 2 1.0 0.0 1.65 1.103 1.0 15 17 0.33 0.45 6.67 0.950 1.0 15 42 1.24 0.0 6.58 0.266 0.213 15 47 1.0 0.37 5.21 1.25 1.0 16 18 0.75 0.45 4.18 0.534 0.253 16 2 1.0 0.0 1.65 1.103 1.0 17 19 0.33 0.45 6.67 0.950 1.0 17 43 1.24 0.0 6.58 0.266 0.213 17 47 1.0 0.37 5.21 1.25 1.0 18 20 0.0 0.45 6.66 2.11 1.0 18 2 1.0 0.0 6.41 1.103 1.0 19 4 0.65 0.35 4.08 0.687 0.72 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-51 (Page 3 of 6)

Flow Path Between Inertia Length Minimum Flow Area Ratio (For 'y' Compartments K fl/d (ft) Area (ft2) factor) 19 44 1.24 0.0 6.58 0.266 0.213 19 47 1.0 0.37 5.21 1.25 1.0 20 6 0.0 0.35 5.0 2.11 1.0 20 2 1.0 0.0 6.41 1.103 1.0 21 22 0.30 0.09 38.4 852.7 0.84 21 25 1.14 0.0 4.05 4.76 0.0023 21 48 0.7837 0.0 10.36 265.875 0.096 22 23 0.30 0.09 40.2 739.0 0.73 22 26 1.14 0.0 4.05 4.76 0.0023 22 48 0.7837 0.0 10.36 265.875 0.096 23 24 0.30 0.09 38.4 852.7 0.84 23 28 1.14 0.0 4.05 5.30 0.0026 23 48 0.7837 0.0 10.36 265.875 0.096 24 21 1.58 0.0 31.1 100.0 0.099 24 47 2.15 0.0 5.43 52.75 0.072 24 48 0.7837 0.0 10.36 265.875 0.096 25 7 1.2 0.0 5.16 1.06 0.22 25 47 1.43 0.0 2.81 2.60 0.54 26 9 1.2 0.0 5.16 1.06 0.22 26 47 1.43 0.0 2.81 1.60 0.54 27 11 1.2 0.0 4.98 1.06 0.20 27 47 1.43 0.0 5.07 5.30 1.0 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-51 (Page 4 of 6)

Flow Path Between Inertia Length Minimum Flow Area Ratio (For 'y' Compartments K fl/d (ft) Area (ft2) factor) 27 22 1.14 0.0 4.05 5.30 0.00259 28 13 1.2 0.0 4.98 1.06 0.20 28 47 1.43 0.0 5.07 5.30 1.0 29 15 1.2 0.0 5.16 1.06 0.22 29 47 1.43 0.0 2.81 2.60 0.54 29 23 1.14 0.0 4.05 4.76 0.00232 30 17 1.2 0.0 5.16 1.06 0.22 30 47 1.43 0.0 2.81 2.60 0.54 30 24 1.14 0.0 4.05 4.76 0.00232 31 19 1.2 0.0 5.68 1.06 0.20 31 47 1.43 0.0 7.07 5.30 1.0 31 24 1.14 0.0 7.55 5.30 0.00259 33 3 1.2 0.0 3.393 0.834 0.112 33 46 0.0 0.45 6.6 0.0545 1.0 33 19 0.68 0.33 3.45 0.950 0.76 34 7 0.68 0.33 3.45 0.950 0.76 34 46 0.0 0.45 6.6 0.0545 1.0 35 7 0.65 0.35 4.08 0.687 0.725 35 47 1.0 0.13 1.86 0.625 1.0 35 45 0.33 0.0 2.74 0.625 1.0 36 37 0.0 0.91 12.67 0.552 1.0 36 47 2.15 0.0 18.2 0.175 0.00034 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-51 (Page 5 of 6)

Flow Path Between Inertia Length Minimum Flow Area Ratio (For 'y' Compartments K fl/d (ft) Area (ft2) factor) 36 46 0.33 0.0 7.14 0.552 1.0 36 38 0.0 0.35 5.0 2.11 1.0 37 8 0.0 0.35 5.0 2.11 1.0 37 2 1.0 0.0 6.37 0.552 1.0 38 39 0.0 0.45 6.66 2.11 1.0 38 8 0.0 0.91 12.66 1.10 1.0 38 47 2.15 0.0 18.2 0.350 0.000678 39 40 0.0 0.45 6.66 2.11 1.0 39 10 0.0 0.57 7.94 1.10 1.0 39 47 2.15 0.0 18.2 0.350 0.000678 40 41 0.0 0.45 6.66 2.11 1.0 40 12 0.0 0.57 7.94 1.10 1.0 40 47 2.15 0.0 18.2 0.350 0.000678 41 42 0.0 0.45 6.66 2.11 1.0 41 14 0.0 0.57 7.94 1.10 1.0 41 47 2.15 0.0 18.2 0.350 0.000678 42 43 0.0 0.45 6.66 2.11 1.0 42 16 0.0 0.57 7.94 1.10 1.0 42 47 2.15 0.0 18.2 0.350 0.000678 43 44 0.0 0.45 6.66 2.11 1.0 43 18 0.0 0.57 12.66 1.10 1.0 43 47 2.15 0.0 18.2 0.350 0.000678 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-51 (Page 6 of 6)

Flow Path Between Inertia Length Minimum Flow Area Ratio (For 'y' Compartments K fl/d (ft) Area (ft2) factor) 44 5 0.0 0.35 5.0 2.11 1.0 44 20 0.0 0.91 12.66 1.10 1.0 44 47 2.15 0.0 18.2 0.350 0.000678 45 3 1.2 0.0 3.393 0.834 0.112 45 33 0.0 0.45 6.6 0.0545 1.0 45 34 0.0 0.45 6.6 0.0545 1.0 46 3 1.2 0.0 3.393 0.834 0.123 47 21 2.15 0.0 5.43 52.75 0.072 47 22 2.15 0.0 5.43 52.75 0.072 47 23 2.15 0.0 5.43 52.75 0.072 48 49 0.0 0.987 8.733 989.01 0.23 49 50 0.0 1.108 12.278 982.47 0.239 50 51 0.0 1.108 12.278 982.47 0.359 51 52 0.87979 1.169 8.8558 982.47 0.359 52 32 1.43 0.0 2.80 2003.1 0.269 53 1 0.72 0.0 3.29 7.5 0.309 53 47 0.97 0.0 2.32 7.5 1.0 54 1 0.83 0.0 5.13 5.3 0.19 54 21 1.14 0.0 4.80 5.3 1.0 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 1 of 10)

Table 6-52. Mass and Energy Release Rates Into Reactor Cavity Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.00000 0. 0. 0.00

.00251 9.9265719E+03 5.5810926E+06 562.24

.00501 1.1996164E+04 6.7475607E+06 562.48

.00752 1.3233810E+04 7.4455849E+06 562.62

.01002 1.4091650E+04 7.9264327E+06 562.49

.01251 1.4409537E+04 8.1005473E+06 562.17

.01502 1.4142837E+04 7.9419806E+06 561.55

.01754 1.5556178E+04 8.7440378E+06 562.09

.02002 1.5479448E+04 8.6925244E+06 561.55

.02257 1.4945158E+04 8.3812365E+06 560.80

.02502 1.4754991E+04 8.2686786E+06 560.40

.02756 1.4995451E+04 8.4018550E+06 560.29

.03009 1.5105915E+04 8.4611159E+06 560.12

.03256 1.5327930E+04 8.5847750E+06 560.07

.03500 1.5534006E+04 8.6996402E+06 560.04

.03753 1.5755386E+04 8.8234720E+06 560.03

.04005 1.5932306E+04 8.9220306E+06 560.00

.04256 1.6007855E+04 8.9624880E+06 559.88

.04507 1.5937503E+04 8.9194894E+06 559.65

.04756 1.5791651E+04 8.8334786E+06 559.38

.05013 1.5682074E+04 8.7686914E+06 559.15

.05266 1.5627088E+04 8.7355483E+06 559.00

.05512 1.5619501E+04 8.7298691E+06 558.91

.05758 1.5614221E+04 8.7255869E+06 558.82

.06011 1.5544992E+04 8.6847656E+06 558.69

.06251 1.5389808E+04 8.5950588E+06 558.49

.06513 1.5177310E+04 8.4728420E+06 558.26

.06759 1.5052222E+04 8.4009295E+06 558.12

.07002 1.5081665E+04 8.4173614E+06 558.12

.07258 1.5236779E+04 8.5055382E+06 558.22

.07511 1.5383879E+04 8.5890617E+06 558.32 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 2 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.07759 1.5432242E+04 8.6160899E+06 558.32

.08007 1.5361472E+04 8.5750865E+06 558.22

.08259 1.5190944E+04 8.4771985E+06 558.04

.08511 1.4960042E+04 8.3452565E+06 557.84

.08750 1.4715283E+04 8.2056107E+06 557.63

.09010 1.4486184E+04 8.0750512E+06 557.43

.09266 1.4319134E+04 7.9800178E+06 557.30

.09503 1.4235376E+04 7.9323669E+06 557.23

.09765 1.4231012E+04 7.9293979E+06 557.23

.10006 1.4282532E+04 7.9594587E+06 557.29

.10251 1.4359900E+04 8.0082867E+06 557.36

.10501 1.4426338E+04 8.0414862E+06 557.41

.10762 1.4476293E+04 8.0699480E+06 557.46

.11010 1.4519938E+04 8.0948219E+06 557.50

.11251 1.4579716E+04 8.1288788E+06 557.55

.11514 1.4669909E+04 8.1802678E+06 557.62

.11756 1.4757387E+04 8.2300978E+06 557.69

.12012 1.4819932E+04 8.2656890E+06 557.74

.12266 1.4833146E+04 8.2780465E+06 557.74

.12506 1.4798966E+04 8.2588166E+06 557.70

.12762 1.4730734E+04 8.2142001E+06 557.62

.13019 1.4653788E+04 8.1702015E+06 557.55

.13261 1.4575724E+04 8.1256136E+06 557.48

.13503 1.4490726E+04 8.0771046E+06 557.40

.13761 1.4381127E+04 8.0146862E+06 557.30

.14013 1.4252918E+04 7.9617471E+06 557.20

.14259 1.4109847E+04 7.8604785E+06 557.09

.14508 1.3979587E+04 7.7865863E+06 556.99

.14769 1.3872871E+04 7.7260891E+06 556.92

.15007 1.3803656E+04 7.6868199E+06 556.87

.15256 1.3755215E+04 7.6594169E+06 556.84 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 3 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.15501 1.3717337E+04 7.6380874E+06 556.82

.15754 1.3677591E+04 7.6156883E+06 556.80

.16008 1.3636039E+04 7.5921894E+06 556.77

.16259 1.3585770E+04 7.5694620E+06 556.75

.16511 1.3562338E+04 7.5506910E+06 556.74

.16751 1.3542948E+04 7.5398045E+06 556.73

.17012 1.3535876E+04 7.5359680E+06 556.74

.17260 1.3540160E+04 7.5385622E+06 556.76

.17502 1.3549904E+04 7.5442238E+06 556.77

.17758 1.3561441E+04 7.5508714E+06 556.78

.18008 1.3571935E+04 7.5569200E+06 556.80

.18259 1.3580840E+04 7.5620472E+06 556.82

.18508 1.3589190E+04 7.5668517E+06 556.83

.18757 1.3597466E+04 7.5716113E+06 556.84

.19013 1.3605632E+04 7.5763052E+06 556.85

.19255 1.3611081E+04 7.5794446E+06 556.86

.19509 1.3610029E+04 7.5788894E+06 556.86

.19751 1.3597787E+04 7.5719753E+06 556.85

.20006 1.3569176E+04 7.5557697E+06 556.83

.20255 1.3524785E+04 7.5306058E+06 556.80

.20512 1.3461390E+04 7.4946504E+06 556.75

.20758 1.3389894E+04 7.4541126E+06 556.70

.21007 1.3313788E+04 7.4110186E+06 556.64

.21262 1.3237469E+04 7.3677920E+06 556.59

.21507 1.3173072E+04 7.3313852E+06 556.54

.21760 1.3117533E+04 7.2999754E+06 556.51

.22017 1.3075166E+04 7.2760872E+06 556.48

.22261 1.3045530E+04 7.2594105E+06 556.47

.22507 1.3024000E+04 7.2473247E+06 556.46

.22761 1.3004926E+04 7.2366416E+06 556.45

.23011 1.2985724E+04 7.2258736E+06 556.45 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 4 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.23259 1.2967820E+04 7.2158372E+06 556.44

.23500 1.2955953E+04 7.2092296E+06 556.44

.23757 1.2956229E+04 7.2095013E+06 556.45

.24004 1.2966409E+04 7.2153668E+06 556.47

.24259 1.2979069E+04 7.2226275E+06 556.48

.24522 1.2989317E+04 7.2285040E+06 556.50

.24752 1.2997306E+04 7.2330964E+06 556.51

.25010 1.3003499E+04 7.2366512E+06 556.52

.25258 1.3005511E+04 7.2378307E+06 556.52

.25500 1.3006371E+04 7.2383506E+06 556.52

.25750 1.3014605E+04 7.2430532E+06 556.53

.26002 1.3037028E+04 7.2557898E+06 556.55

.26251 1.3076561E+04 7.2782069E+06 556.58

.26503 1.3131110E+04 7.3091468E+06 556.63

.26752 1.3192863E+04 7.3441626E+06 556.68

.27008 1.3260912E+04 7.3827354E+06 556.73

.27250 1.3318805E+04 7.4155405E+06 556.77

.27514 1.3369619E+04 7.4443079E+06 556.81

.27762 1.3399130E+04 7.4609742E+06 556.83

.28004 1.3405746E+04 7.4646462E+06 556.82

.28256 1.3388945E+04 7.4550256E+06 556.80

.28510 1.3351130E+04 7.4334882E+06 556.77

.28752 1.3299072E+04 7.4039010E+06 556.72

.29013 1.3233614E+04 7.3667271E+06 556.67

.29267 1.3169566E+04 7.3303843E+06 556.62

.29504 1.3112882E+04 7.2982537E+06 556.57

.29753 1.3065961E+04 7.2716760E+06 556.54

.30005 1.3031336E+04 7.2520869E+06 556.51

.30259 1.3011966E+04 7.2411505E+06 556.50

.30504 1.3006657E+04 7.2381848E+06 556.50

.30756 1.3012753E+04 7.2416825E+06 556.51 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 5 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.31007 1.3027687E+04 7.2501695E+06 556.52

.31256 1.3050914E+04 7.2633548E+06 556.54

.31505 1.3077352E+04 7.2783456E+06 556.56

.31755 1.3107524E+04 7.2954552E+06 556.59

.32006 1.3137286E+04 7.3123225E+06 556.61

.32263 1.3163790E+04 7.3273358E+06 556.63

.32511 1.3182603E+04 7.3379691E+06 556.64

.32750 1.3191145E+04 7.3427834E+06 556.64

.33001 1.3188970E+04 7.3415128E+06 556.64

.33254 1.3175263E+04 7.3337032E+06 556.63

.33510 1.3151590E+04 7.3202530E+06 556.61

.33761 1.3122216E+04 7.3035726E+06 556.58

.34013 1.3092526E+04 7.2867370E+06 556.56

.34251 1.3067030E+04 7.2722834E+06 556.54

.34505 1.3046299E+04 7.2605431E+06 556.52

.34757 1.3033479E+04 7.2532973E+06 556.51

.35005 1.3028586E+04 7.2505390E+06 556.51

.35253 1.3030386E+04 7.2515714E+06 556.51

.35512 1.3037739E+04 7.2557484E+06 556.52

.35751 1.3047622E+04 7.2613515E+06 556.53

.36009 1.3061122E+04 7.2690005E+06 556.54

.36252 1.3073795E+04 7.2761725E+06 556.55

.36509 1.3088888E+04 7.2847073E+06 556.56

.36758 1.3102772E+04 7.2925486E+06 556.57

.37002 1.3121311E+04 7.3030318E+06 556.58

.37257 1.3145933E+04 7.3169613E+06 556.60

.37512 1.3179982E+04 7.3362342E+06 556.62

.37753 1.3219502E+04 7.3586179E+06 556.65

.38013 1.3263486E+04 7.3835022E+06 556.68

.38255 1.3304048E+04 7.4064474E+06 556.71

.38506 1.3334162E+04 7.4234597E+06 556.72 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 6 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.38754 1.3355980E+04 7.4357614E+06 556.74

.39001 1.3363145E+04 7.4397421E+06 556.74

.39252 1.3356871E+04 7.4361067E+06 556.73

.39501 1.3339691E+04 7.4262822E+06 556.71

.39756 1.3313468E+04 7.4113522E+06 556.68

.40003 1.3279755E+04 7.3921732E+06 556.65

.40260 1.3240302E+04 7.3697503E+06 556.61

.40519 1.3196109E+04 7.3446702E+06 556.58

.40754 1.3151988E+04 7.3196351E+06 556.54

.41011 1.3106422E+04 7.2938052E+06 556.51

.41266 1.3065819E+04 7.2708073E+06 556.48

.41501 1.3036883E+04 7.2544335E+06 556.45

.41751 1.3018344E+04 7.2439630E+06 556.44

.42003 1.3014608E+04 7.2418838E+06 556.44

.42258 1.3025218E+04 7.2479293E+06 556.45

.42503 1.3047845E+04 7.2607762E+06 556.47

.42759 1.3080286E+04 7.2791833E+06 556.50

.43014 1.3117193E+04 7.3000986E+06 556.53

.43251 1.3155457E+04 7.3217883E+06 556.56

.43506 1.3191987E+04 7.3424708E+06 556.69

.43755 1.3224867E+04 7.3610879E+06 556.61

.44010 1.3250482E+04 7.3755613E+06 556.63

.44262 1.3264813E+04 7.3836279E+06 556.63

.44511 1.3269304E+04 7.3861164E+06 556.63

.44760 1.3264219E+04 7.3831822E+06 556.62

.45009 1.3251389E+04 7.3758547E+06 556.61

.45262 1.3234123E+04 7.3660352E+06 556.59

.45507 1.3213626E+04 7.3543821E+06 556.58

.45759 1.3193226E+04 7.3427924E+06 556.56

.46001 1.3173256E+04 7.3314588E+06 556.54

.46261 1.3154015E+04 7.3205435E+06 556.53 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 7 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.46506 1.3134486E+04 7.3094675E+06 556.51

.46758 1.3116041E+04 7.2990155E+06 556.50

.47006 1.3098461E+04 7.2890550E+06 556.48

.47253 1.3083494E+04 7.2805790E+06 556.47

.47504 1.3071598E+04 7.2738479E+06 556.46

.47756 1.3064785E+04 7.2700011E+06 556.46

.48006 1.3064114E+04 7.2696348E+06 556.46

.48261 1.3070026E+04 7.2729994E+06 556.46

.48513 1.3081483E+04 7.2795042E+06 556.47

.48764 1.3097708E+04 7.2887069E+06 556.49

.49003 1.3115613E+04 7.2989594E+06 556.50

.49273 1.3136190E+04 7.3105130E+06 556.52

.49502 1.3154001E+04 7.3206055E+06 556.53

.49762 1.3170745E+04 7.3300750E+06 556.54

.50008 1.3183757E+04 7.3374291E+06 556.55

.51005 1.3226674E+04 7.3616658E+06 556.58

.52010 1.3233878E+04 7.3656266E+06 556.57

.53007 1.3217416E+04 7.3562190E+06 556.56

.54003 1.3198213E+04 7.3452957E+06 556.54

.55004 1.3182668E+04 7.3364868E+06 556.53

.56009 1.3168598E+04 7.3285223E+06 556.51

.57007 1.3168051E+04 7.3282356E+06 556.52

.58001 1.3180356E+04 7.3352264E+06 556.53

.59010 1.3193314E+04 7.3425795E+06 556.54

.60005 1.3195553E+04 7.3438478E+06 556.54

.61011 1.3172129E+04 7.3305811E+06 556.52

.62006 1.3144174E+04 7.3147858E+06 556.50

.63008 1.3141082E+04 7.3131040E+06 556.51

.64004 1.3165075E+04 7.3267526E+06 556.53

.65016 1.3197334E+04 7.3450531E+06 556.56

.66000 1.3224737E+04 7.3605803E+06 556.58 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 8 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.67016 1.3237563E+04 7.3678351E+06 556.59

.68023 1.3235448E+04 7.3666327E+06 556.58

.69014 1.3231651E+04 7.3644964E+06 556.58

.70001 1.3236967E+04 7.3675383E+06 556.59

.71006 1.3253690E+04 7.3770420E+06 556.60

.72003 1.3269938E+04 7.3862620E+06 556.62

.73012 1.3268935E+04 7.3856990E+06 556.62

.74005 1.3251762E+04 7.3759850E+06 556.60

.75012 1.3235463E+04 7.3667942E+06 556.60

.76014 1.3229606E+04 7.3635323E+06 556.59

.77001 1.3231916E+04 7.3648971E+06 556.60

.78005 1.3239365E+04 7.3691663E+06 556.61

.79007 1.3249703E+04 7.3790611E+06 556.62

.80001 1.3261283E+04 7.3816490E+06 556.63

.81001 1.3269949E+04 7.3865782E+06 556.64

.82003 1.3274774E+04 7.3893292E+06 556.64

.83003 1.3279948E+04 7.3922798E+06 556.65

.84000 1.3289797E+04 7.3978749E+06 556.66

.85009 1.3302617E+04 7.4051571E+06 556.67

.86007 1.3310739E+04 7.4097668E+06 556.68

.87012 1.3311205E+04 7.4100371E+06 556.68

.88011 1.3305550E+04 7.4068440E+06 556.67

.89013 1.3298692E+04 7.4029805E+06 556.67

.90017 1.3295550E+04 7.4012311E+06 556.67

.91002 1.3297412E+04 7.4023198E+06 556.67

.92004 1.3302328E+04 7.4051354E+06 556.68

.93005 1.3307600E+04 7.4081473E+06 556.69

.94008 1.3311662E+04 7.4104688E+06 556.69

.95005 1.3314827E+04 7.4122815E+06 556.69

.96008 1.3317484E+04 7.4138059E+06 556.70

.97009 1.3320822E+04 7.4157167E+06 556.70 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 9 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm)

.98018 1.3326430E+04 7.4189146E+06 556.71

.99009 1.3334734E+04 7.4236377E+06 556.71 1.00006 1.3340908E+04 7.4271479E+06 556.72 1.05007 1.3343822E+04 7.4288927E+06 556.73 1.10001 1.3350103E+04 7.4325496E+06 556.74 1.15002 1.3367946E+04 7.4427634E+06 556.76 1.20006 1.3367315E+04 7.4425294E+06 556.77 1.25015 1.3383433E+04 7.4517960E+06 556.79 1.30019 1.3376401E+04 7.4479560E+06 556.80 1.35012 1.3384968E+04 7.4530020E+06 556.82 1.40017 1.3380523E+04 7.4506854E+06 556.83 1.45005 1.3380580E+04 7.4509864E+06 556.85 1.50011 1.3376567E+04 7.4490034E+06 556.87 1.55004 1.3371069E+04 7.4462331E+06 556.89 1.60005 1.3363161E+04 7.4421416E+06 556.91 1.65012 1.3356066E+04 7.4385612E+06 556.94 1.70002 1.3354740E+04 7.4382710E+06 556.98 1.75005 1.3345130E+04 7.4333487E+06 557.01 1.80009 1.3347552E+04 7.4352553E+06 557.05 1.85010 1.3346323E+04 7.4351216E+06 557.09 1.90015 1.3344521E+04 7.4346886E+06 557.13 1.95011 1.3341966E+04 7.4338614E+06 557.18 2.00004 1.3341645E+04 7.4343247E+06 557.23 2.05000 1.3332756E+04 7.4299736E+06 557.27 2.10012 1.3324666E+04 7.4261107E+06 557.32 2.15023 1.3314938E+04 7.4213497E+06 557.37 2.20010 1.3303028E+04 7.4153657E+06 557.42 2.25007 1.3293004E+04 7.4104684E+06 557.47 2.30014 1.3282276E+04 7.4061657E+06 557.52 2.35004 1.3273646E+04 7.4010396E+06 557.57 2.40002 1.3263256E+04 7.3959085E+06 557.62 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-52 (Page 10 of 10)

Time Average Enthalpy (Seconds) Mass Flow (lbm/sec) Energy Flow (BTU/sec) (BTU/lbm) 2.45003 1.3253098E+04 7.3909159E+06 557.67 2.50011 1.3241323E+04 7.3850205E+06 557.73 2.55008 1.3227662E+04 7.3780849E+06 557.78 2.60015 1.3213094E+04 7.3706674E+06 557.83 2.65006 1.3197609E+04 7.3627673E+06 557.89 2.70004 1.3181293E+04 7.3544163E+06 557.94 2.75008 1.3165287E+04 7.3462591E+06 558.00 2.80003 1.3148613E+04 7.3377212E+06 558.06 2.85013 1.3131770E+04 7.3290894E+06 558.12 2.90009 1.3114320E+04 7.3201075E+06 558.18 2.95006 1.3095600E+04 7.3104162E+06 558.23 3.00010 1.3076081E+04 7.3002988E+06 558.29 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-53 (Page 1 of 1)

Table 6-53. Reactor Cavity Design Pressures Calculated Peak Design Pressure Pressure(2)

Volume (psig) (psig)

Upper Reactor Cavity (Element 47) 10.6 5.3 Lower Reactor Cavity (Element 2) 32 3.2 Reactor Annulus (Elements 5 thru 20 and 36 thru 44) 140 55.8 Reactor Pipe Sleeve (Element 54) 1120 221.2 Inspection Shaft (Element 53) 400(1) 226.1 (1)

Inspection Cavity (Element 1) 400 256.7 Note:

1. Based on ultimate strength design method.
2. Based on inspection port covers being removed in modes 1-4. There is an insignificant effect on calculated peak pressures if covers remain (unrestrained) in modes 1-4. (Reference 88)

(05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-54 (Page 1 of 3)

Table 6-54. Mass and Energy Release Rates for Steam Line Rupture. 2.4 ft2 Double Ended Break at 3479 MWt (rated thermal power plus measurement uncertainty)

Time Break Flow Rate Break Enthalpy (sec) (lbm/sec) (Btu/lbm) 0 0 1191.99 0.1 4654.93 1162.62 0.2 4595.92 1168.41 0.3 4925.25 1178.21 0.4 5194.74 1183.08 0.5 5051.86 1180.23 0.6 4897.54 1177.93 0.7 4901.68 1179.53 0.8 4941.07 1181.27 0.9 4950.07 1182.00 1 4927.24 1181.74 1.1 4921.82 1181.65 1.2 4925.84 1181.60 1.3 4919.42 1181.22 1.4 4906.32 1180.71 1.5 4892.6 1180.26 1.6 4876.82 1179.87 1.7 4859.24 1179.58 1.8 4843.2 1179.45 1.9 4829.9 1179.46 2 4818.34 1179.55 2.2 4796.32 1179.76 2.4 4772.63 1179.91 2.6 4749.96 1180.09 2.8 4728.61 1180.30 3 4706.03 1180.51 3.2 4683.36 1180.75 3.4 4662.69 1181.07 3.6 4642.56 1181.40 3.8 4645.81 1182.27 (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-54 (Page 2 of 3)

Time Break Flow Rate Break Enthalpy (sec) (lbm/sec) (Btu/lbm) 4 4782.57 1184.70 4.2 4774.29 1183.38 4.4 4771.05 1182.31 4.6 4756.2 1181.32 4.8 4755.39 1181.13 5 4772.23 1181.61 5.2 4792.85 1182.07 5.4 4786.19 1181.87 5.6 4703.02 1180.69 5.8 4610.08 1180.58 6 4464.01 1181.17 6.2 4173.67 1180.78 6.4 3669.66 1178.76 6.6 3309.93 1181.93 6.8 3071.46 1185.88 7 2909.6 1188.84 7.2 2803.86 1191.49 7.4 2727.74 1193.97 7.6 2668.97 1195.99 7.8 2624.36 1197.62 8 2591.14 1198.91 9 2484.23 1201.76 10 2408.57 1202.72 15 2109.47 1205.45 20 1859.16 1207.45 25 1702.26 1208.93 30 1605.91 1209.46 35 1525.97 1209.91 40 1486.94 1210.16 45 1438.79 1210.17 50 1405.6 1210.43 55 1364.39 1210.66 (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-54 (Page 3 of 3)

Time Break Flow Rate Break Enthalpy (sec) (lbm/sec) (Btu/lbm) 60 1315.26 1210.59 65 1220.07 1210.04 66 1162.28 1267.88 67 1106.62 1267.76 68 1051.28 1270.87 69 1004.89 1271.31 70 1005.14 1266.03 72 1168.9 1265.38 73 1176.51 1267.00 75 1051.74 1265.43 76 1046.54 1265.71 77 999.04 1270.40 78 997.47 1266.06 80 897.43 1270.26 85 631.86 1277.39 91 460.21 1279.05 93 411.09 1290.25 95 351.93 1290.51 100 235.98 1293.83 105 176.39 1296.54 110 137.36 1299.18 125 142.47 1299.87 150 164.73 1300.25 175 163.55 1300.26 200 163.41 1299.77 250 163.53 1298.40 300 163.59 1296.70 350 163.6 1295.00 400 163.5 1293.82 450 163.66 1293.36 495 163.59 1294.15 600 163.59 1294.15 (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6 6-61 (Page 1 of 1)

Table 6-55. Deleted Per 1998 Update Table 6-56. Deleted Per 1998 Update Table 6-57. Deleted Per 1998 Update Table 6-58. Deleted Per 1998 Update Table 5-59. Deleted Per 1998 Update Table 6-60. Deleted Per 1998 Update Table 6-61. Deleted Per 1998 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-62 (Page 1 of 2)

Table 6-62. Mass and Energy Release Rates for Minimum Post-LOCA Containment Pressure Time Mass Flowrate Energy Flowrate (sec) (lbm/sec) (BTU/sec) 0.00 59790.0 31729000.

1.00 62690.0 33611000.

2.00 55960.0 30359000.

3.00 43930.0 24289500.

4.00 37140.0 21232000.

5.00 32570.0 19212500.

6.00 30120.0 17969500.

7.00 28530.0 17070000.

8.00 26810.0 16071000.

9.00 24840.0 14890000.

10.00 22380.0 13533000.

12.00 16520.0 10548000.

14.00 13190.0 8020000.

16.00 11510.0 5791000.

18.00 9000.0 3657000.

20.00 6540.0 2272000.

22.00 5640.0 1771000.

24.00 4750.0 1135500.

26.00 3660.0 776300.

28.00 5320.0 1013000.

30.00 4580.0 793050.

32.00 2580.0 418050.

34.00 1800.0 279150.

36.00 2797.3 414300.

40.00 3104.3 456530.

46.00 2920.3 571680.

52.00 1780.3 627880.

58.00 1540.3 558380.

64.00 1210.3 429430.

72.00 790.3 314930.

80.00 710.3 281850.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-62 (Page 2 of 2)

Time Mass Flowrate Energy Flowrate (sec) (lbm/sec) (BTU/sec) 90.00 750.3 295300.

100.00 880.3 325400.

120.00 1090.3 360250.

140.00 1160.3 366380.

160.00 1090.3 325550.

180.00 820.3 247400.

200.00 480.3 156400.

220.00 370.3 107780.

260.00 360.3 111750.

350.00 360.3 111750.

Note:

1. Includes Broken Loop Accumulator Flow (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-63 (Page 1 of 1)

Table 6-63. Deleted Per 1998 Update.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-64 (Page 1 of 1)

Table 6-64. Volume and Temperature Data For Minimum Post-LOCA Containment Pressure McGuire and Catawba I. Containment NET FREE Volume (ft3)

Upper Compartment (ft3) 676,255 As part of the standard Westinghouse LOTIC2 modeling, this upper containment volume is increased by 59,000. This 59,000 is reassigned from the ice condenser volume and represents ice bed upper plenum volume (47,000) and ice bed cooling duct volume (12,000).

Lower Compartment (ft3) 201,700 Ice Condenser (ft3) 182,813 As part of the standard Westinghouse LOTIC2 modeling, this ice containment volume is decreased by 59,000. This 59,000 is reassigned to the upper containment volume and represents ice bed upper plenum volume (47,000) and ice bed cooling duct volume (12,000).

Dead Ended Compartments (ft3) 148,573 II. Initial Conditions Containment Pressure(psia) 14.7 Upper Containment Temperature (°F) 105 Lower containment Temperature (°F) 125 Dead-Ended Compartment Temperature (°F) 125 Ice Condenser Temperature (°F) 27 Refueling Water Storage Tank Temperature (°F)

Catawba 63.9(1)

McGuire 65.0 Service Water Temperature (°F) 32 Initial Spray Temperature (°F) 70 Lowest Temperature Outside Containment (°F) NA(2)

(1)

Analysis used 65.0 °F since the effect of lower ice mass for McGuire (more free volume) offset the effect of slightly lower RWST water temperature for Catawba (2)

Temperature outside containment not modeled (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-65 (Page 1 of 1)

Table 6-65. Active Heat Sink Data For Minimum Post-LOCA Containment Pressure I. Containment Spray System Parameters

1. Maximum spray system flow, total 9600 gpm
2. Maximum number of spray pumps operating 2
3. Fastest post-LOCA initiation of spray system (assuming 25 sec off-site power loss at start of LOCA)

II. Containment Air Return Fan Parameters

1. Maximum fan flow, total 80,000 cfm
2. Maximum number of fans operating 2
3. Fastest post-LOCA initiation 480 sec (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-66 (Page 1 of 3)

Table 6-66. Structural Heat Sink Data For Minimum Post-LOCA Containment Pressure Thickness Structure Area (ft2) (feet) Material

1. Upper Compartment
a. Operating Floor, Crane Wall, Refueling Canal, Miscellaneous Concrete Slab 1 21,142 0.000833 Coating 2 1.34 Concrete Slab 2 5,017 0.0156 Stainless Steel 1.5 Concrete
b. Containment Vessel Dome, Containment Shell, Polar Crane, Miscellaneous Steel Slab 3 24,391 0.00059 Coating 1 0.058 Carbon Steel Slab 4 31,035 0.00059 Coating 1 0.0290 Carbon Steel Slab 5 801 0.0625 Stainless Steel
2. Lower and Dead Ended Compartments
a. Operating Floor, Crane Wall, Refueling Canal, Miscellaneous Concrete Slab 1 57,387 0.000833 Coating 2 1.97 Concrete Slab 2 9,019 0.00133 Coating 3 2.04 Concrete Slab 3 3,541 0.00133 Coating 3 2.50 Concrete Slab 4 2,361 0.0156 Stainless Steel 1.50 Concrete Slab 5 768 0.00059 Coating 1 0.04207 Carbon Steel 1.50 Concrete
b. Containment Shell, Reactor Coolant Pumps, Supports, and Miscellaneous Steel Slab 6 56,551 0.00059 Coating 1 0.0565 Carbon Steel (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-66 (Page 2 of 3)

Thickness 2

Structure Area (ft ) (feet) Material Slab 7 14,445 0.00059 Coating 1 0.0625 Carbon Steel Slab 8 9,040 0.00059 Coating 1 0.0625 Carbon Steel Slab 9 32,640 0.0026 Stainless Steel

c. Cooling Coils Slab 10 51,000 0.00042 Copper
3. Ice Condenser
a. Ice Baskets Slab 1 180,628 0.00663 Steel
b. Lattice Frames Slab 2 76,650 0.0217 Steel
c. Lower Support Structure Slab 3 28,670 0.0267 Steel
d. Ice Condenser Floor Slab 4 3,336 0.000833 Coating 0.333 Concrete
e. Containment Wall Panels and Containment Shell Slab 5 19,100 1.0 Steel and Insulation 0.0625 Steel Shell
f. Crane Wall Panels and Crane Wall Slab 6 13,055 1.0 Steel and Insulation 1.0 Concrete (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-66 (Page 3 of 3)

Thickness 2

Structure Area (ft ) (feet) Material Note: Coatings (Btu/ft hr °F)

1. 2 mils organic, 5 mils inorganic - 0.6
2. 10 mils organic - 0.29
3. 16 mils organic - 0.29 Volumetric Heat Capacity (BTU/ft3 - F)

Concrete 31.95 Carbon Steel 58.8 Stainless Steel 55.11 Inorganic Coating 28.8 Organic Coating 18.2 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-67 (Page 1 of 1)

Table 6-67. Deleted Per 1998 Update.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-68 (Page 1 of 1)

Table 6-68. Air Return Fans and Hydrogen Skimmer Fans Failure Analysis Component Malfunction Comments and Consequences Air Return Fan Fan fails to start or stops Redundant, full capacity fan is running and cannot be restarted. provided.

Air Return Fan Inadvertent actuation during Containment Pressure Control normal operation System precludes inadvertent actuation of fan Air Return Fan Isolation Damper fails to open Redundant, full capacity fan and Damper isolation damper are provided.

Hydrogen Skimmer Fan Fan fails to start or stops Redundant, full percent capacity running and cannot be restarted fan is provided Hydrogen Skimmer Fan Inadvertent actuation during Containment Pressure Control normal operation System precludes inadvertent actuation of fan.

Hydrogen Skimmer Fan Valve fails to open Redundant, full capacity fan and Isolation Valve isolation valve are provided (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-69 (Page 1 of 2)

Table 6-69. Wall Panel Design Loads1

1. Service Loads Weight of Panels on Containment and End Wall (58 ft length) 100 lbs/linear ft Weight of Panels on Crane Wall (48 ft length) 60 lbs/linear ft Pressure (Wall panel internal) 0 to 0.5 psig
2. 1/2 SSE Lattice Frame Column Loads2 (Maximum at 45 ft elevation)

Radial at 90° (acting alone) +/- 7920 lbs Tangential at 0° (acting alone) +/- 9600 lbs Combined Load at 45° Radial +/- 6190 lbs Tangential +/- 6190 lbs

3. SSE Lattice Frame Column Loads2 (Maximum at 45 ft elevation)

Radial at 90° (acting alone) +/- 8800 lbs Tangential at 0° (acting alone) +/- 11200 lbs Combined Load at 45° Radial +/- 7070 lbs/ea Tangential +/- 7070 lbs/ea

4. DBA2 (Maximum at 15 ft elevation)

Lattice Frame Column Load Radial +/- 6210 lbs Tangential +/- 8259 lbs Pressure (D.L.F. = 1.5; M = 1.4)3 18.9 psig

5. SSE plus DBA2 15 ft Elevation Lattice Frame Column Load @ 0° Radial +/- 6211 lbs Tangential +/- 13260 lbs Lattice Frame Column Load @ 45° Radial +/- 10701 lbs Tangential +/- 12750 lbs (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-69 (Page 2 of 2)

Lattice Frame Column Load @ 90° Radial +/- 13911 lbs Tangential +/- 8260 lbs Pressure (D.L.F. = 1.5; Margin = 1.4)3 18.9 psig 33 ft Elevation Lattice Frame Column Load @ 0° Radial 0 Tangential +/- 14920 lbs Lattice Frame Column Load @ 45° Radial +/- 6916 lbs Tangential +/- 13336 lbs Lattice Frame Column Load @ 90° Radial +/- 11060 lbs Tangential +/- 6420 lbs 3

Pressure (D.L.F. = 1.5; Margin = 1.4) 18.9 psig Note:

1. Design pressure loads, as stated, are applied uniformly to the wall panel transverse beams. Radial and Tangential loads are applied at lattice frame column to wall panel attachment. These are maximum load combinations.
2. Vertical seismic loads (0.35 and 0.55 times dead load for 1/2 SSE and SSE, respectively) and vertical Design Basis Accident loads are neglected in the analyses because they are small in comparison to the radial and tangential loads.
3. DLF = Dynamic Load Factor M = Margin (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-70 (Page 1 of 1)

Table 6-70. Lattice Frame Loads Horizontial 1/2 Safe Shutdown Earthquake2 1/2 SSE at 0° and 90° from Reference Direction of Excitation (kips) 1/2 SSE 45°1 0° 90° of Excitation (kips)

Elevation above Floor Slab, ft Tang Radial Tang Radial Tang Radial 15 4.0 0 0 5.5 3.36 3.36 21 4.96 0 0 6.3 3.98 3.98 27 6.0 0 0 7.1 4.63 4.63 33 6.8 0 0 7.9 5.20 5.20 39 6.96 0 0 7.6 5.15 5.15 45 7.04 0 0 8.0 5.32 5.32 51 6.56 0 0 7.7 5.04 5.04 57 6.4 0 0 7.4 4.88 4.88 Note:

Tang + Radial

1. Cos 45° 2
2. Refer to Figure 6-120 for direction of excitation.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-71 (Page 1 of 1)

Table 6-71. Local Seismic Loads on Lattice Frames Due to Single Ice Basket Ice Basket Load, lbs Elevation above Floor Slab, ft 1/2 SSE SSE 15 550 770 21 630 882 27 750 1050 33 850 1190 39 870 1218 45 880 1232 51 820 1148 57 800 1120 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-72 (Page 1 of 1)

Table 6-72. Ice Condenser Lattice Frame Loads1 Blowdown Pressure Loads for Design Basis Earthquake (SSE) And Design Basis Accident (DBA)

SEISMIC Lattice TOTAL LOADS (LBS) Ice Column Frame2 Lattice SSE + DBA (LBS)

Elevation Horizontal- Ice Column Horizontal- Frame2 Above Floor SSE Tangential Horizontal- Tangential Horizontal-Slab, ft Tangential SSE Radial lbs/ft Radial lbs/ft lbs Radial lbs Tangential Radial 15 5000 7,700 23.8 17.9 8259 6211 13,260 13,911 21 6200 8,820 22.5 8.95 7808 3106 14,008 11,926 27 7500 9,940 19.8 0 6871 0 14,371 9,940 33 8500 11,060 18.5 0 6420 0 14,920 11,060 39 8700 10,640 16.8 0 5830 0 14,530 10,640 45 8800 11,200 14.0 0 4858 0 13,563 11,200 51 8200 10,780 11.8 0 4095 0 12,295 10,780 57 8000 10,360 10.8 0 3748 0 11,745 10,360 Note:

1. A design margin (M) of 40% and a dynamic load factor (DLF) of 1.53 are used where applicable.
2. (lb/ft) x (DLF) x (M) x (6) x (27) -- There are 27 baskets per lattice frame, and blowdown pressure loads are applied over 6 ft of each basket.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-73 (Page 1 of 1)

Table 6-73. Vertical DBA Loads On Lattice Frames Vertical Load lbs/column Elevation above Floor Vertical Blowdown Drag Slab, ft Forces, lbs, lattice frame Crane Side Cont. Side 15 7572 3030 4543 21 7572 3030 4543 27 3726 1490 2236 33 1754 1490 2236 39 1754 702 1052 45 1619 648 970 51 1619 648 970 57 1792 716 1075 TOTALS: 27,408 10,966 16,443 Note:

1. A design margin of 40% and a dynamic load factor of 1.10 should be used with the above values.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-74 (Page 1 of 1)

Table 6-74. Vertical Friction Loads On Lattice Frames (From Table 6-

73) Horiz. Tang. Vert. Friction Vertical Friction Vertical Friction El Above Floor DBA lbs/lattice Load µ = .5 lbs/crane col. lbs/contain col.

Slab frame lbs/lattice frame (40%) (60%)

15 8259 4129 1652 2477 21 7808 3904 1562 2342 27 6871 3435 1374 2061 33 6420 3210 1284 1926 39 5830 2915 1166 1749 45 4858 2429 972 1457 51 4095 2047 819 1228 57 3748 1874 750 1124 TOTALS: 47,889 23,945 9,578 14,367 Note:

A design margin of 40% and a dynamic load factor of 1.53 is used in the above values.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-75 (Page 1 of 1)

Table 6-75. Lattice Frames Summary of Maximum Stresses Criteria D + 1/2 SSE D + DBA D + SSE D + DBA + SSE Bending Allowable Stress1 (psi) 37,500 49,875 49,875 61,875 Max Calculated Stress (psi)

Member No./stress 71/33,360 71/25,640 71/36,850 71/49,330 63/30,590 72/22,900 63/33,770 63/43,720 79/28,360 80/22,300 79/31,320 72/42,870 72/28,160 63/22,040 72/31,110 79/42,160 78/27,780 79/22,030 78/30,690 75/41,600 Interaction Factor Calculated Member No./value 71/.92 71/.81 71/1.02 78/1.46 Allowable 1.0 1.332 1.332 1.652 Note: Bending stress about strong axes, shear and axial are insignificant and are not summarized in this table.

1. Based upon ASTM A-441 steel not normalized. Y.S. = 50,000 psi.
2. The interaction factor considers the combined effect of vertical and horizontal stresses. It is the product of the increase in allowable stresses and the limit for S, per AISC-69.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-76 (Page 1 of 1)

Table 6-76. Summary of Fatigue Analysis1 For Lattice Frames Member Number/ Joint Calculated Stress Range, psi Number (in welded location) Allowable Stress Range2, psi 127/67 2000 22,500 128/68 2300 22,500 130/130 2000 22,500 131/72 2200 22,500 133/92 2200 22,500 134/73 2300 22,500 Note:

1. Based on 400 1/2 SSE cycles.
2. AISC-69 specification, Appendix B.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-77 (Page 1 of 1)

Table 6-77. Ice Basket Load Summary - Minimum Test Loads Case I Case II Case III Case IV D + 1/2 SSE D + DBA D + SSE D + SSE + DBA Elevation1 (ft.) H V H V H V H V 0 463 4933 429 -2283 496 4330 841 -3473 6 1131 4316 423 -1998 1211 3789 1486 -3039 12 1296 3698 414 -1713 1387 3248 1638 -2605 18 1543 3083 357 -1427 1652 2707 1826 -2171 24 1748 2466 333 -1142 1872 2164 2005 -1736 30 1790 1849 303 -856 1916 1623 2017 -1301 36 1810 1232 252 -531 1938 1082 1991 -831 42 1687 617 213 -285 1806 541 1835 -434 48 823 0 192 0 881 0 976 0 Note:

1. Above lower support structure (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-78 (Page 1 of 1)

Table 6-78. Ice Basket Load Summary - Basic Design Loads D 1/2 SSE SSE DBA Elevation 1 (ft.) H V H V H V H V 0 0 1776 225 622 315 977 143 -2536 6 0 1554 550 544 770 855 141 -2219 12 0 1332 630 466 882 733 138 -1902 18 0 1110 750 389 1050 611 119 -1585 24 0 888 850 311 1190 488 111 -1268 30 0 666 870 233 1218 366 101 -951 36 0 444 880 155 1232 244 84 -614 42 0 222 820 78 1148 122 71 -317 48 0 0 400 0 560 0 64 0 Note:

1. Above lower support structure (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-79 (Page 1 of 1)

Table 6-79. Summary of Stresses in Basket Due to Design Loads Elevation from Design Load, lb1 Lower Support Maximum Stress, Allowable Structure, ft. H V psi Stresses, psi 0 304(3) 3029 11,508 25,5362 12 650(3) 2271 17,100 25,5362 24 761(3) 1514 17,976 25,5362 36 835(3) 378 17,435 25,5362 12 1017(4) -2003 23,988 31,1045 Note:

1. With 10% margin
2. Allowable stress = 0.6 x Sy x 1.33 per Section 6.2.2.16
3. Design load, D + SSE
4. Design load, D + SSE + DBA, 10% margin on weight, 40% margin on pressure and 1.5 dynamic load factor.
5. Allowable stress = 0.6 x Sy x 1.65 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-80 (Page 1 of 1)

Table 6-80. Ice Basket Material Minimum Yield Stress Item Material Minimum Yield Stress (KSI)

Clevis Pin and U-Bolts SAE-J 429 Grade 8 130 Basket End Coupling and Stiffener ASTM A-622 32 Nut AISI-431 125 (Min. Shear)

Mounting Bracket Assembly ASTM A-588 Grade A 50 Plate ASTM A-36 36 Grid Bars ASTM A-570 Grade 13 Wire Mesh ASTM A-641 40 Perforated Basket ASTM A-569 32 C-1022 Heat Treated to C52 (Couple Screw) 130 Swivel Bracket ASTM A-747 Type CB7CU-2 75 Swivel Assy Clevis Pin & Cap Screws ASTM A-193 Grade B8 60 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-81 (Page 1 of 1)

Table 6-81. Allowable Stress Limits (D + 1/2 SSE) For Ice Basket Materials ALLOWABLE LIMITS Specified Tension Shear Bearing Bending Minimum Ft = .6Fy Fv = .4Fy Fp = .9Fy Fb = .66Fy Material Yield KSI (KSI) (KSI) (KSI) (KSI)

Carbon Steel 130 KSI Minimum 130 78 52 117 85.8 Yield ASTM-A588 50 30 20 45 33 ASTM-A570 30 18 12 27 19.8 ASTM-A622 32 19.2 12.8 28.8 21.1 ASTM-A36 36 21.6 14.4 32.4 23.8 ASTM-A641 40 24 16 36 26.4 ASTM-A569 32 19.2 12.8 28.8 21.1 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-82 (Page 1 of 1)

Table 6-82. Allowable Stress Limits (D + SSE), (D + DBA) For Ice Basket Materials ALLOWABLE LIMITS Specified Tension Shear Bearing Bending Minimum St = 1.33Ft Sv = 1.33Fv Sp = 1.33Fp Sb = 1.33Fb Material Yield KSI (KSI) (KSI) (KSI) (KSI)

Carbon Steel 130 KSI Minimum 130 103.7 69.2 155.6 114.1 ASTM-A588 50 39.9 26.6 59.8 43.9 ASTM-A570 30 23.9 16.0 35.9 26.3 Grade B ASTM-A622 32 25.5 17.0 38.3 28.1 ASTM-A36 36 28.7 19.1 43.0 31.6 ASTM-A641 40 31.9 21.3 47.9 35.1 ASTM-A569 32 25.5 17.0 38.3 28.1 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-83 (Page 1 of 1)

Table 6-83. Allowable Stress Limits (D + SSE + DBA) For Ice Basket Materials ALLOWABLE LIMITS Tension Shear Bearing Bending Specified S = 1.65 Ft S = 1.65 Fv S = 1.65 Fp S = 1.65 Fb Minimum t v p b Material Yield KSI (KSI) (KSI) (KSI) (KSI)

Carbon Steel 130 KSI Minimum 130 128.7 85.8 193.1 141.6 ASTM-A588 50 49.5 33.0 74.2 54.4 ASTM-A570 30 29.7 19.8 44.6 32.7 Grade B ASTM-A622 32 31.7 21.1 47.5 34.8 ASTM-A36 36 35.6 23.8 53.5 39.2 ASTM-A641 40 39.6 26.4 59.4 43.6 ASTM-A569 32 31.7 21.1 47.5 34.8 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-84 (Page 1 of 1)

Table 6-84. Ice Basket Clevis Pin Stress Summary Pin-Lug Pin Bending Pin Shear Bearing Load Case Horiz. Load Vert. Load V Stress fb (103 Stress fv (103 Stress fp (103 No. H (LBF) (LBF) psi) psi) psi)

I 251 2638 67.3 13.5 10.6 1

(97.5) (52) (45.0)

II 300 -1596 41.2 8.3 6.5 (129.7) (69.2) (59.8)

III 251 3028 77.1 15.5 12.1 (129.7) (69.2) (59.8)

IV 551 -2671 69.3 13.9 10.9 (160.9) (85.8) (74.2)

Note:

1. Parenthetical values are stress allowables.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-85 (Page 1 of 1)

Table 6-85. Ice Basket Mounting Bracket Assembly Stress Summary Point 1 Interaction Washer Shear Tear Weld Shear Horiz. Load H Vert. Load V Load Case Formula Bearing Stress Out Stress fv Stress fv (psi x Load Case No. (LBF) (LBF) Factor N Value1 X fp (psi x 103) (psi x 103) 103)

I 251 2638 1.0 0.90 34.6 - 7.8 2

(45.0) (20.0) (20.0)

II 300 -1596 1.33 0.57 36.6 5.3 5.4 (59.8) (26.6) (26.6)

III 251 3028 1.33 1.02 34.6 - 8.7 (59.8) (26.6) (26.6)

IV 551 -2671 1.65 0.96 53.0 8.9 9.2 (74.2) (33.0) (33.0)

Note:

1. X N indicates safe condition.
2. Parenthetical values are stress allowables.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-86 (Page 1 of 1)

Table 6-86. Ice Basket Plate Stress Summary Point 1 Point 2 Interaction Interaction Load Case Horiz. Load Vert. Load V Load Case Formula Formula No. H (LBF) (LBF) Factor N Value1 X Value1 X I 251 2638 1.0 0.25 0.27 II 300 -1596 1.33 0.23 0.29 III 251 3028 1.33 0.28 0.27 IV 551 -2671 1.65 0.42 0.53 Note:

1. X N indicates safe condition.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-87 (Page 1 of 1)

Table 6-87. Ice Basket U-Bolt Stress Summary Tensile Stress Fb (103 Load Case No. Horiz. Load H LBF Vert. Load V LBF psi)

I 251 2638 42.8 (78.0)1 II 300 -1596 55.1 (103.7)

III 251 3028 42.8 (103.7)

IV 551 -2671 65.6 (128.7)

Note:

1. Parenthetical Values are Stress Allowables (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-88 (Page 1 of 1)

Table 6-88. Ice Basket - Basket End Stress Summary Point 1 Point 2 Interaction Interaction Load Case Horiz. Load Vert. Load H Load Case Formula Formula No. H (LBF) (LBF) Factor N Value X1 Value X1 I 251 2638 1.0 0.74 0.97 II 300 -1596 1.33 0.85 0.63 III 251 3028 1.33 0.76 1.10 IV 551 2671 1.65 1.56 1.08 Note:

1. X N indicates safe condition.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-89 (Page 1 of 1)

Table 6-89. Ice Bucket Coupling Screw Stress Summary 3 Inch Elevation1 Screw Screw Basket Basket Horiz. Bending Shear Bearing Tear-Out Load Case Load H Vert. Load Stress fb Stress fv Stress fp Stress fvt No. (lbs.) V (lbs.) (ksi) (ksi) (ksi) (ksi)

I 251 2638 65.8 12.0 16.8 4.3 2

(85.8) (52.0) (28.8) (12.8)

II 300 -1596 43.1 7.8 11.0 2.8 (114.1) (69.2) (38.3) (17.0)

III 251 3028 74.7 13.6 19.1 4.8 (114.1) (69.2) (38.3) (17.0)

IV 551 -2671 73.1 13.3 18.7 4.7 (141.6) (85.8) (47.5) (21.1)

Note:

1. Above top of lower support structure.
2. Parenthetical values are stress allowables.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-90 (Page 1 of 1)

Table 6-90. Ice Bucket Coupling Screw Stress Summary 12 Foot Elevation1 Screw Screw Basket Basket Horiz. Bending Shear Bearing Tear-Out Load Case Load H Vert. Load Stress fb Stress fv Stress fp Stress fvt No. (lbs.) V (lbs.) (ksi) (ksi) (ksi) (ksi)

I 818 1977 81.8 14.9 20.9 5.3 2

(85.8) (52.0) (28.8) (12.8)

II 289 -1198 40.2 7.3 10.3 2.6 (114.1) (64.2) (38.3) (17.0)

III 818 2271 88.5 16.1 22.6 5.7 (114.1) (64.2) (38.3) (17.0)

IV 1108 -2004 95.3 17.4 24.4 6.2 (141.6) (85.8) (47.5) (21.1)

Note:

1. Above top of lower support structure.
2. Parenthetical values are stress allowables.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-91 (Page 1 of 1)

Table 6-91. Ice Bucket Coupling Screw Stress Summary 24 Foot Elevation1 Screw Screw Basket Basket Horiz. Bending Shear Bearing Tear-Out Load Case Load H Vert. Load Stress fb Stress fv Stress fp Stress fvt No. (lbs.) V (lbs.) (ksi) (ksi) (ksi) (ksi)

I 1122 1319 82.1 15.0 21.0 5.3 2

(85.8) (52.0) (28.8) (12.8)

II 233 -799 29.0 5.3 7.4 1.9 (114.1) (64.2) (38.3) (17.0)

III 1122 1513 86.5 15.8 22.1 5.6 (114.1) (69.2) (38.3) (17.0)

IV 1355 -1335 93.2 17.0 23.9 6.0 (141.6) (85.8) (47.5) (21.1)

Note:

1. Above top of lower support structure.
2. Parenthetical values are stress allowables.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-92 (Page 1 of 1)

Table 6-92. Ice Bucket Coupling Screw Stress Summary 36 Foot Elevation1 Screw Screw Basket Basket Horiz. Bending Shear Bearing Tear-Out Load Case Load H Vert. Load Stress fb Stress fv Stress fp Stress fvt No. (lbs.) V (lbs.) (ksi) (ksi) (ksi) (ksi)

I 1161 658 66.9 12.2 17.1 4.32 2

(85.8) (52.0) (28.8) (12.8)

II 176 -371 16.4 3.0 4.2 1.1 (114.1) (64.2) (38.3) (17.0)

III 1161 757 69.1 12.6 17.7 4.5 (114.1) (69.2) (38.3) (17.0)

IV 1338 -639 74.4 13.6 19.0 4.8 (141.6) (85.8) (47.5) (21.1)

Note:

1. Above top of lower support structure.
2. Parenthetical values are stress allowables.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-93 (Page 1 of 1)

Table 6-93. Crane and Rail Assembly Design Loads

1. Normal Operation
a. Crane Weight (excluding rails) 7200 lbs
b. Maximum Capacity During Plant Erection 6000 lbs (each of two cranes)
c. Maximum Capacity 6000 lbs (one crane)
d. Maximum Load Expected 2400 lbs (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-94 (Page 1 of 3)

Table 6-94. Refrigeration System Parameters

1. General - per twin Containment station
a. Cooling Water Temperature, maximum (A through H) 85°F design (I and J) 95°F
b. Number of ice condenser units 2
2. Refrigeration - per twin Containment station
a. Glycol Chilling Machines - 4 dual packages and 2 stand-alone (25 ton each) installed Refrigeration capacity per chiller (half 25 tons1 pkg), nominal Total plant capacity, nominal, 10 x 25 250 tons1 Glycol design flow per evaporator, ~127 gpm normal Glycol flow per evaporator at max. P 200 gpm Glycol pressure, maximum design 180 psig Pressure drop through evaporator, 16 feet normal Maximum allowable P through 40 feet evaporator Glycol entering temperature, estimated ~2°F Glycol exit temperature minus 5°F Cooling water flow per condenser, ~88 gpm1 normal Total cooling water flow, 5 x 2 x 88 ~880 gpm1 Cooling water pressure, maximum 150 psig design Pressure drop through condenser 3.6 feet Approximate refrigerant charge per (A through H) 90 lbs chiller (I and J) 150 lbs.

Refrigerant R-502

b. Glycol Circulation Pumps - 6 installed; 4 required Design flow per pump 240 gpm Total design flow to containment (2 480 gpm pump operation), 2 x 240 TDH at design flow 297 feet (13 APR 2008)

McGuire Nuclear Station UFSAR Table 6-94 (Page 2 of 3)

Shut-off head 328 feet NPSH required at design point 11.2 feet

c. Pressure Relief Valves
1) External Headers 2 - installed Set pressure (for thermal expansion 180 psig of glycol)

Capacity at set pressure (each) 75 gpm

2) Floor Cooling System Heater (1 per containment)

Set pressure, Floor Cooling Relief 180 psig Valve

d. Refrigeration Medium (glycol) - UCAR Thermofluid 17 or equal Design Concentration, ethylene glycol in water 50 weight % or 47.8 volume %.

At temperature: -5°F 0°F 100°F Specific gravity 1.083 1.082 1.056 Absolute viscosity centipoises 25.0 20.5 2.3 Kinematic-viscosity, centistokes 23.1 18.9 2.18

3. Ice Condenser - per one Containment unit
a. Ice Bed Amount of ice initially stored per unit, 3.0 x 106 nominal lbs Minimum amount of ice in storage (per 1.89 x 106 Tech Spec) lbs Ice displacement per year, design 2%

objective Design predicted ice displacement per <0.3%

year, to wall panels for normal operation Ice melt during maximum LOCA, 0.5 x 106 during blowdown period calculated, lbs.

approx.

Average Temperature of ice & static air 15°F nominal Pressure at lower doors due to cold 0.68 psf head, nominal Inlet opening pressure, design 1 psf (13 APR 2008)

McGuire Nuclear Station UFSAR Table 6-94 (Page 3 of 3)

b. Air Handling Units - 30 dual packages installed per Containment AHU Refrigeration requirements per 67.5 tons containment, calculated nominal Gross capacity per dual package rated 2.5 tons Glycol entering temperature, approx. -5°F Glycol exit temperature, approx. 1°F Glycol flow per air handler (1/2 6 gpm package)

Total AHU glycol flow, 30 x 2 x 6 360 gpm Glycol pressure drop, estimated 50 feet Air blower head 2" H2O Air entering temperature, nominal 19°F Air exit temperature 10°F Note:

1. Nominal refrigeration rating based on 85°F (design) cooling water.

(13 APR 2008)

McGuire Nuclear Station UFSAR Table 6-95 (Page 1 of 1)

Table 6-95. Lower Inlet Door Design Parameters and Loads

1. Normal Operation Temperature, Lower Compartment, °F 120 Maximum Temperature, Ice Bed, °F 10 Minimum Pressure across Doors, psf 1.0 Nominal
2. Seismic Response of Crane Wall at Door Elevation Horizontal, 1/2 SSE, g 0.20 g Vertical, 1/2 SSE, g 0.05 g Horizontal, SSE, g 0.40 g Vertical, SSE, g 0.10 g
3. Accident Conditions Temperature, Lower Compartment, °F 250 Maximum
1) Pressure across doors as shown in Figure ________.

For design purposes a 40% margin shall be applied to differential pressure given in this figure.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-96 (Page 1 of 2)

Table 6-96. Design Loads Three Pier Lower Support Structure. (See Figure 6-142)

LOAD DESCRIPTION BASIC VALUE

1. Gravity
a. Structural and Ice Weight (2000 lbs/Ice Basket) 1.0 g
b. Wall Panel Weight (lbs/Lattice Frame Bay1 4000
c. Lattice Frames (for eight/Lattice Frame Bay) in lbs 9600 2
d. Intermediate Deck (lbs/LSS Bay) 2200
e. Lattice Frame Columns each in lbs 989
2. Thermal Loads
a. Normal Operating 70°F to 10°F
b. DBA Thermal Loading 70°F to 250°F 3.
a. Seismic Vertical SSE
1) Vertical Seismic Load 0.55 g
b. Seismic Vertical 1/2 SSE
1) Vertical Seismic Load 0.35 g 4.
a. Radial Horizontal SSE Seismic
1) Radial Direction - Structural Acceleration 1.22 g
2) Seismic Load on Ice Basket (lbs/Lattice Frame Bay) 14000
b. Radial 1/2 SSE Seismic
1) Radial Direction Structural Acceleration 0.61 g
2) Seismic Ice Basket Loads (lbs/Lattice Frame Bay) 10000 5.
a. Tangential Horizontal DBE Seismic
1) Tangential Direction Structural Acceleration 1.55 g
2) Seismic Load on Ice Basket (lbs/Lattice Frame Bay) 11500
b. Tangential 1/2 SSE Seismic
1) Tangential Direction Structural Acceleration 0.78 g
2) Seismic Load on Ice Basket (lbs/Lattice Frame Bay) 9500 6.
a. Vertical Blowdown
1) Drag on Inner Radial Beam (kips/ft) 0.0567 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-96 (Page 2 of 2)

LOAD DESCRIPTION BASIC VALUE

2) Drag on Outer Radial Beam (kips/ft) 0.0885
3) Drag on Ice Basket (kips/Basket) 2.354
4) Drag on Horizontal Platform Inner and Outer Bracing (kips/LSS 2.192 Bay)
5) Drag on Lattice Frame - Eight Frames (kips/Lattice Frame Bay) 31.727
6) Drag on Intermediate Deck (kips/LSS Bay) 116
b. Horizontal Blowdown
1) Horizontal Load on Middle Circumferential Beam (kips/LSS 31.114 Bay) at 45° Angle
2) Floor Turning Vane on Middle Column (kips/LSS Bay) 9.911
3) Upper Turning Vanes each (kips/LSS Bay) 15.221
4) Slotted Plate (kips/LSS Bay) 36.391
5) Outer Circumferential Beam Load (kips/ft) 1.728
6) Radial Load on Ice Basket (kips/Basket) 0.054
c. Impact Loading of Inner Portal
1) Tangential (kips/Column Line) 60
2) Radial (kips/Column Line) 48.2
d. Tangential Blowdown Force
1) Tangential Drag Force (kips/Basket) 0.071 Note:
1. One Lattice Frame Bay in Plan is equivalent to 1/3 of the Lower Support Structure bay or three radial beams.
2. Lower Support Structure.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-97 (Page 1 of 1)

Table 6-97. Design Loads and Parameters Top Deck Plant Parameters Ambient temperature before cooldown, maximum, °F 100 Ambient temperature, upper surface and hinge bar, range, °F 75-100 Ambient temperature, lower surface, minimum, °F 15 Post-LOCA temperature, lower surface, minimum, °F 15 Post-LOCA temperature (no P applied), maximum, °F 190 Dead Weight Air handling unit and support structure, lbs/bay 2500 Grating, lbs per ft2 7.7 Blanket panel, lbs per ft2 1.33 Hinge bar, lbs per ft 53 Static design equivalent of live load (personnel traffic), psf 100 LOCA Loading Maximum drag load on horizontal beam surfaces, lbs/ft2 177 Maximum drag load on grating, lbs/ft2 25.7 Maximum back pressure following LOCA, psi 0.28 Maximum drag load on AHU, lbs 1,250 Note:

1. Margin and dynamic load factor are to be applied to tabulated values as appropriate.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-98 (Page 1 of 1)

Table 6-98. Summary of Results Upper Blanket Door Structural Analysis - LOCA Code Allowable Stress Max.

Item Area Calculated Stress Design1 Basis 1 Skin and bands, direct tension 4.17 Note 2 2 Hinge bar - bending 6.30 Note 1 3 Anchor bolts - tension 6.50 Note 3 4 Floor grating - bending 4.55 Note 4 5 Insulation tip stress - tear 2.01 Note 4 Insulation tip stress - tensile 16.70 Note:

1. Allowable value per AISC-69 limits
2. ASTM-177 minimum tensile with AISC allowable
3. ASTM-A325 minimum tensile with AISC allowable
4. Strength values per Manufacturer's literature (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-99 (Page 1 of 1)

Table 6-99. Design Loads and Parameters Intermediate Deck

1. Normal Operations
a. Ambient temperature before cooldown, maximum, °F 100
b. Ambient temperature, minimum, °F 15
c. Temperature differential across deck, estimated, °F +/-1
2. Dead Weight
a. Panel, lbs per ft2, maximum 5.5
b. Static design equivalent of live load (personnel traffic), psf 100
3. Accident Conditions
a. Post-LOCA temperature (No P applied), max. °F 190
b. Pressure across intermediate deck Figure ________

Note:

1. For design purposes a 40% margin is applied to the differential pressure given in Figure ________.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-100 (Page 1 of 1)

Table 6-100. Summary of Waltz Mill Tests Compaction Tests One foot diameter wire mesh baskets, loaded with flake ice to various heights, lead weights added to simulate additional weight of ice.

Equivalent Compaction Length of Height of Bed (& Volume In Test Started Terminated Test (months) (feet) First Year)

D' 2/21/69 8/28/70 18.0 22 24.5 E' 2/21/69 8/28/70 18.0 7.5 5.5 Shear Tests One foot diamter wire mesh baskets, loaded with flake ice to various heights, temporarily supported between two wooden discs by pegs which are removed after one month.

Test Started Terminated Length of Actual Height Shear Rate1 Test (months) of Bed (feet) (Inches/year)

G' 9/16/69 8/28/70 11.4 5 0.9 H' 9/16/69 8/28/70 11.4 3 0.9 I' 9/16/69 8/28/70 11.4 1 0.4 Note:

1. Shear rate approximated, based on 6 months of data; not applicable for greater than 6 months.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-101 (Page 1 of 1)

Table 6-101. Ice Condenser Allowable Limits(1)

Elastic Analysis Limit Analysis(3)

Mechanical and Load Combination Mechanical(2) Thermal Fatigue (Load Factors) Test (Load Factors)

D + 1/2 SSE S 3S AISC Part 1 1.43 1.87 D + DBA 1.33 S N.A. N.A. 1.3 1.43 D + SSE 1.33 S N.A. N.A. 1.3 1.43 D + SSE +/- DBA 1.65 S N.A. N.A. 1.18 1.3 Note:

1. For particular components that do not meet these limits specific justification shall be provided on a case by case basis.
2. Membrane (direct) stresses shall no larger than 0.7 Su (70 percent of ultimate stress).
3. For mechanical loads only Mechanical plus thermal expansion, combination and fatigue shall satisfy the elastic analysis limits.

S = Allowable stresses as defined in Sections 1.5 and 1.6 of the AISC Part I Specification.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-102 (Page 1 of 1)

Table 6-102. Summary of Duke-McGuire Loads-Tangential Case Obtained Using the Two-Mass Dynamic Model Design Values Earthquake Condition and Wall Panel Wall Panel Load-Direction Load-kips Impact Loads-lbs kips Impact Load-lbs 1/2 SSE, N-S 4.4 298 8.0 1000 1/2 SSE, E-W 5.2 382 8.0 1000 SSE, N-S 7.0 652 10.0 1400 SSE, E-W 8.0 701 10.0 1400 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-103 (Page 1 of 1)

Table 6-103. Summary of Duke-McGuire Loads-Radial Case Obtained Using the Two-Mass Dynamic Model Design Values Earthquake Condition and Wall Panel Wall Panel Load-Direction Load-kips Impact Loads-lbs kips Impact Load-lbs 1/2 SSE, N-S 6.75 250 10.0 1000 1/2 SSE, E-W 7.1 273 10.0 1000 SSE, N-S 10.0 417 14.0 1400 SSE, E-W 10.3 424 14.0 1400 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-104 (Page 1 of 1)

Table 6-104. Summary of Load Results of Five Non-Linear Dynamic Models (Loads Are For East-West SSE Earthquake)

Maximum Load Average of 4 48 Foot Beam Phasing Mass Earthquakes 2 Mass Model 3 Mass Model 9 Mass Model Model2 Model1 Design Load Tangential Impact Load 701 604 526 570 1400 Tangential Wall Panel Load 8000 7308 6300 7825 10000 Radial Impact Load 424 688 376 1400 Radial Wall Panel Load 10300 8496 11000 14000 Note:

1. Case shown represents 75 percent freezeover (75 percent of the ice baskets are assumed to be frozen in the lattice frames and 25 percent of the ice baskets are assumed to be free to move within the gap). This was the case producing the highest load, 11432 lbs, in the link between the lattice frames.
2. 48 foot beam model results are for earthquake #4 only. This is the earthquake which produced the highest loads using the two-mass model.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-105 (Page 1 of 1)

Table 6-105. Summary of Parameters Used in the Seismic Analysis Item Description McGuire Parameters 1 Lower Support Structure Stiffness Radial Direction 430,000 lbs/in Tangential Direction 670,000 lbs/in 2 Lattice Frame Wall Panels Combined Stiffness Radial Direction 50,000 lbs/in Tangential Direction 23,900 lbs/in 3 Local Impact Stiffness Radial Direction 4.8 to 9.2 kip/in Tangential Direction 4.8 to 11.8 kip/in 4 Ice Basket Weight with ice 41.7 lbs/ft 5 Gap Size 0.5 in 6 Ice Basket Stiffness Bending Rigidity (EI) 330 x 106 lbs/in2 where: E = modulus of elasticity, I = moment of inertia, (14 APR 2005)

McGuire Nuclear Station UFSAR Table 6-106 (Page 1 of 1)

Table 6-106. Selection of Steels in Relation to Prevention of Non-Ductile Fracture of Ice Condenser Components Section Thickness Properties 5/8-inch thick and under over 5/8-inch thickness Energy Absorption Level None required 1. 20 ft-lb CVN at -20°F for steel over 36,000 psi yield strength

2. 15 ft-lb CVN at -20°F for steel under 36,000 psi yield strength Heat Treatment None required 1. Normalizing Steel can be used in the hot rolled condition 2. Quench and Temper Type of Steel 1. Rimed (a) 1. Killed
2. Semi-killed (b) 2. Killed-fine grain practice
3. Killed (b,c)
4. Killed - fine grain practice Note:
1. Hot rolled, normalized or quenched and tempered steels are used where applicable.
2. Charpy-V Notch (CVN) impact testing shall be performed in accordance with the requirements of ASTM-A370.
a. Rimmed steel shall be used only for carbon steel sheet products.
b. These type steels shall be applied for components which remains within AISC code stress limits for all load conditions.
c. Killed steels for above AISC Code stress limits shall be upgraded by heat treatment, e.g., bolting.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-107 (Page 1 of 1)

Table 6-107. Deleted Per 1999 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-108 (Page 1 of 1)

Table 6-108. Annulus Ventilation System Malfunction Analysis Component Malfunction Comments and Consequences

1. Annulus ventilation fan Fan fails to start or stops Two full capacity fans are provided.

running and cannot be restarted.

2. Annulus ventilation Filter failure Two full capacity trains are provided.

filter train

3. Annulus ventilation Eliminator failure Two full capacity eliminators are moisture eliminator provided.
4. Damper Fails to open Parallel dampers providing two 100 percent flow paths are provided in suction header. Redundant dampers open. Each fan train, including discharge isolation damper, is a 100 percent flow path.
5. Carbon Filter Carbon ignition due to Dispersion of the radioiodine throughout excessive localized the filter influent and uniform filter flow radioiodine deposition. distribution assures uniform filter loading therein precluding carbon ignition.
6. Annulus ventilation fan LOCA coincident with loss Power supplied to redundant annulus of offsite power and with a ventilation fans from the emergency diesel single failure. generators.
7. Pressure Transmitter Fails to terminate exhaust Lo-Lo pressure transmitter (-7.0 inwg.)

and start re-circ mode at - trips fan if dampers are in exhaust 3.5 inwg. alignment to prevent underpressurization.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-109 (Page 1 of 3)

Table 6-109. Annulus Ventilation Discharge. (Pressure setpoint range -4.2 inwg to -1.2 inwg)

Discharge Initiation of Time of Volumetric Quantity Sequence Discharge Initiation of Discharge Flow Rate Discharged Number (sec) Recirc. (sec) (sec) (CFM) (ft3) 1 34 175 141 See Note 1 18467 2 222 265 43 8000 5733 3 327 363 36 8000 4800 4 449 481 32 8000 4267 5 591 620 29 8000 3867 6 820 846 26 8000 3467 7 1095 1127 32 See Note 2 3627 8 1367 1399 32 6800 3627 9 1633 1665 32 6800 3627 10 1901 1932 31 6800 3513 11 2231 2262 31 6800 3513 12 2511 2543 32 6800 3627 13 2279 2811 32 6800 3627 14 3041 3073 32 6800 3627 15 3263 3296 33 6800 3740 16 3460 3494 34 6800 3853 17 3660 3694 34 6800 3853 18 3880 3913 33 6800 3740 19 4107 4140 33 6800 3740 20 4340 4373 33 6800 3740 21 4577 4610 33 6800 3740 22 4817 4849 32 6800 3627 23 5058 5090 32 6800 3627 24 5301 5333 32 6800 3627 25 5545 5577 32 6800 3627 26 5790 5822 32 6800 3627 27 6035 6067 32 6800 3627 28 6281 6313 32 6800 3627 29 6526 6558 32 6800 3627 30 6771 6803 32 6800 3627 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-109 (Page 2 of 3)

Discharge Initiation of Time of Volumetric Quantity Sequence Discharge Initiation of Discharge Flow Rate Discharged Number (sec) Recirc. (sec) (sec) (CFM) (ft3) 31 7017 7049 32 6800 3627 32 7262 7294 32 6800 3627 33 7507 7539 32 6800 3627 34 7752 7784 32 6800 3627 35 7997 8029 32 6800 3627 36 8242 8274 32 6800 3627 37 8488 8520 32 6800 3627 38 8734 8766 32 6800 3627 39 8980 9012 32 6800 3627 40 9226 9258 32 6800 3627 41 9473 9505 32 6800 3627 42 9720 9752 32 6800 3627 43 9967 9999 32 6800 3627 44 10214 10246 32 6800 3627 45 10461 10493 32 6800 3627 46 10708 10740 32 6800 3627 47 10955 10987 32 6800 3627 48 11203 11235 32 6800 3627 49 11450 11482 32 6800 3627 50 11697 11729 32 6800 3627 51 11944 11976 32 6800 3627 52 12191 12223 32 6800 3627 53 12437 12469 32 6800 3627 54 12684 12716 32 6800 3627 55 12931 12963 32 6800 3627 56 13178 13210 32 6800 3627 57 13426 13458 32 6800 3627 58 13673 13705 32 6800 3627 59 13921 13953 32 6800 3627 60 14168 14200 32 6800 3627 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-109 (Page 3 of 3)

Discharge Initiation of Time of Volumetric Quantity Sequence Discharge Initiation of Discharge Flow Rate Discharged Number (sec) Recirc. (sec) (sec) (CFM) (ft3)

Note:

1. Fan has a 5 second acceleration time to full speed. During this 5 second period, (34-39 seconds),

one fan is assumed to average half speed flow rate, or 4000 CFM. From 39 seconds up, the fan is at full speed, 8000 CFM.

2. The annulus ventilation filter train loads at 900 seconds and flow is reduced 15% to 6800 CFM.
3. From sequence 60 to 700,000 seconds add 247 seconds to the previous discharge value to obtain a new time for discharge. Each discharge will always be 32 seconds at a rate of 6800 CFM.
4. From 700,000 seconds to 30 days following the accident, the long term Annulus inleakage rate is 810 CFM.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-110 (Page 1 of 6)

Table 6-110. Comparison of Engineered Safety Feature Ventilation Systems With Regulatory Guide 1.52 (Rev. 0)

Control Area HVAC Pressurizing System Paragraph (VC) Annulus Ventilation System (VE)

Compliance Status With Regulatory Guide 1.52 C-1-a In compliance In compliance C-1-b In compliance In compliance C-1-c In compliance In compliance C-1-d In compliance In compliance C-1-e In compliance In compliance C-2-a See Exceptions and Comments section of this In compliance table C-2-b In compliance See Exceptions and Comments section of this table C-2-c In compliance In compliance C-2-d See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-2-e In compliance In compliance C-2-f In compliance In compliance C-2-g In compliance In compliance C-2-h In compliance In compliance C-2-i See Exceptions and Comments section of this In compliance table C-2-j See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-2-k In compliance In compliance (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-110 (Page 2 of 6)

Control Area HVAC Pressurizing System Paragraph (VC) Annulus Ventilation System (VE)

Compliance Status with Regulatory Guide 1.52 C-2-l See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-2-m See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-3-a In compliance In compliance C-3-b In compliance In compliance C-3-c In compliance In compliance C-3-d In compliance In compliance C-3-e In compliance In compliance C-3-f In compliance In compliance C-3-g In compliance In compliance C-3-h In compliance In compliance C-3-i In compliance In compliance C-3-j In compliance In compliance C-3-k In compliance In compliance C-3-l In compliance In compliance C-3-m In compliance In compliance C-3-n In compliance In compliance C-4-a In compliance In compliance C-4-b In compliance In compliance C-4-c See Exceptions and Comments section of this See Exceptions and Comments section of this table list (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-110 (Page 3 of 6)

Control Area HVAC Pressurizing System Paragraph (VC) Annulus Ventilation System (VE)

Compliance Status with Regulatory Guide 1.52 C-4-d See Exceptions and Comments section of this See Exceptions and Comments section of this table list C-4-e In compliance In compliance C-4-f In compliance In compliance C-4-g In compliance In compliance C-4-h In compliance In compliance C-4-i In compliance In compliance C-4-j In compliance In compliance C-4-k In compliance In compliance C-4-l In compliance In compliance C-4-m In compliance In compliance C-5-a See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-5-b In compliance In compliance C-5-c See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-5-d See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-6-a See Exceptions and Comments section of this See Exceptions and Comments section of this table table C-6-b See Exceptions and Comments section of this See Exceptions and Comments section of this table table Exceptions and Comments for Control Area HVAC Pressurizing System (VC)

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-110 (Page 4 of 6)

Control Area HVAC Pressurizing System Paragraph (VC) Annulus Ventilation System (VE)

Compliance Status with Regulatory Guide 1.52 C-2-a There is compliance with this paragraph with the exception of item 5, i.e., HEPA after-filters. Compliance with this item is not practical because the engineering and design of the system was at an irreversible state of completion prior to issuance of Reg.

Guide 1.52.

C-2-d There are no ESF filters that would be subjected to containment pressure surge.

C-2-i When a high radiation signal is received by either Control Room Outside Air Intake radiation monitor, the intake which is the source of contamination is manually closed. In the event the high radiation signal is sensed at both intakes, the least contaminated intake is selected.

C-2-j Filter trains will not be removable as intact units. Gasketless filter adsorbers will be used - the design of which permits the fluidizing of carbon for external filling and removal which will permit a minimum of exposure to operating personnel. All other high activity accumulating elements can decay safely in place prior to removal as safe radwaste.

C-2-l No ESF filter units, primary or secondary, will be located in high radiation zones, or where there will be any DBA pressure surges.

C-2-m The design of non-engineered safety clean-up systems is to the same level of quality required for that of ESF filter trains including seismic qualification.

C-4-c The cross-sectional physical dimensions of control area units are too small for an individual to enter. The entire side panel of the HEPA compartment is removable providing reach-in type service. Also, vacuum breakers are not required since redundant units are supplied.

C-4-d It is recognized that 5'-0 is needed upstream of carbon tray design; however, this design is based on the gasketless, adsorbers which does not require 5'-0 linear feet upstream for servicing. A space of 23 is provided between the HEPA and the nearest upstream obstacle. Since the trains are too small physically for an individual to enter and the HEPA filters are serviced by an individual standing outside the housing, we do not feel that the 5'-0 is necessary for servicing. Also, the entire side panel of the HEPA filter compartment is removable and there is only one HEPA to be removed, thus providing easy access.

C-5-a The ANSI N510-1975, Appendix "A", "check list for visual inspection" was used as a guideline to develop the visual inspection checklist used at MNS. Applicability to all items is impractical because the design of the filter train was established prior to the issuance of Regulatory Guide 1.52.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-110 (Page 5 of 6)

Control Area HVAC Pressurizing System Paragraph (VC) Annulus Ventilation System (VE)

Compliance Status with Regulatory Guide 1.52 C-5-c The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." Silicone sealants are used as gasket material for bolted/flanged joints as found in ductwork to eqiupment (i.e.,

dampers, fans, etc.) joints.

C-5-d The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." After the adsorber bypass leakage test is complete, the filtration system will be operated for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to purge the filter media of refrigerant gas.

C-6-a Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

C-6-b In lieu of the sample canister method, carbon test samples will be extracted by deep bed sampling, using a grain theft method.

Also, testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

Exceptions and Comments for Annulus Ventilation System (VE)

C-2-b The Annulus Ventilation Systems are separated by 3.5 feet. The two trains (per unit) are confined within a space bordered on one side by the Reactor Building wall and on another side by a missile wall. The only rotating machinery in the immediate vicinity is the fans serving the filters themselves. Due to the physical arrangement of the fans relative to the filters the inertial energy of the wheel would cause any missile generated by the wheel itself to move in a direction away from the filters. The only other piece of rotating machinery is 25 feet from the filters which is a centrifugal fan. Its inertial energy would cause it to move at right angles to the filters. Further, the centrifugal wheel is contained in the fan scroll itself and further shielded from the Annulus Ventilation filter trains by the Reactor Building Purge Exhaust filter train. In essence, the generation of missiles has been considered in the design arrangement.

C-2-d There are no ESF filters that would be subjected to containment pressure surge.

C-2-j Filter trains will not be removable as intact units. Gasketless filter adsorbers will be used - the design of which permits the fluidizing of carbon for external filling and removal which will permit a minimum of exposure to operating personnel. All other high activity accumulating elements can decay safely in place prior to removal as safe radwaste.

C-2-l No ESF filter units, primary or secondary, will be located in high radiation zones, or where there will be any DBA pressure surges.

C-2-m The design of non-engineered safety clean-up systems is to the same level of quality required for that of ESF filter trains including seismic qualification.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-110 (Page 6 of 6)

Control Area HVAC Pressurizing System Paragraph (VC) Annulus Ventilation System (VE)

Compliance Stauts with Regulatory Guide 1.52 C-4-c There will be a minimum door size of 20x50 in filter trains. Also, vacuum breakers are not required since redundant units are supplied.

C-4-d It is recognized that 5'-0 is needed upstream of carbon tray designs; however, this design is based on the gasketless, adsorbers which does not require 5'-0 linear feet upstream for servicing. There is a distance of 2'-8 from the HEPA mounting frame to the nearest obstacle. Compliance with the 5'-0 separation requirement is not practical because space at locations for this filter train were established prior to the issuance of Regulatory Guide 1.52.

C-5-a The ANSI N510-1975, Appendix "A", "check list for visual inspection" was used as a guideline to develop the visual inspection checklist used at MNS. Applicability to all items is impractical because the design of the filter train was established prior to the issuance of Regulatory Guide 1.52.

C-5-c The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." Silicone sealants are used as gasket material for bolted/flanged joints as found in ductwork to eqiupment (i.e.,

dampers, fans, etc.) joints.

C-5-d The need to conduct in-place DOP testing of HEPA filters following the effects of welding, painting, fire, and chemical release are defined in the MNS, "Ventilation Filter Testing Program." The penetration criteria is defined in the MNS "Standardized Technical Specifications." After the adsorber bypass leakage test is complete, the filtration system will be operated for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to purge the filter media of refrigerant gas.

C-6-a Testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

C-6-b In lieu of the sample canister method, carbon test samples will be extracted by deep bed sampling, using a grain theft method.

Also, testing of the activated carbon is in accordance with the MNS "Standardized Technical Specifications."

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-111 (Page 1 of 21)

Table 6-111. Containment Piping Penetration Data. (See Table 6-114 for description of notes.)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M216 PRESSURIZER RELIEF TANK MAKEUP NC B1 3 5-1 NC57 PRESSURIZER RELIEF TANK MAKEUP 5-1 NC56B M212 NITROGEN TO PRESSURIZER RELIEF TANK NC A1 1 5-1 NC54A NITROGEN TO PRESSURIZER RELIEF TANK 5-1 NC53B M274 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NC B3 4 5-1 NC59 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NS 1.5 6-194 NS2 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NS 1.5 6-194 NS19 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO ND 1.5 5-28 ND56 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO ND 1.5 5-28 ND64 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO ND 1 5-28 ND61 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO ND 1 5-28 1ND120 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NI 1 6-177 NI151 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NI 1 6-177 NI102 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NI 1 6-177 NI119 PRT (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 2 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NI 1 6-177 NI161 PRT CONT. SPRAY, RHR, SI, + CVCS RELIEF TO NV 1.5 9-96 NV229 PRT M339 REACTOR COOLANT PUMP SEAL WATER NV D6 2 9-96 NV45 SUPPLY M343 REACTOR COOLANT PUMP SEAL WATER NV D6 2 9-96 NV77 SUPPLY M344 REACTOR COOLANT PUMP SEAL WATER NV D6 2 9-96 NV61 SUPPLY M350 REACTOR COOLANT PUMP SEAL WATER NV D6 2 9-96 NV29 SUPPLY M256 REACTOR COOLANT PUMP SEAL WATER NV A7 4 9-96 NV94A,C SUPPLY REACTOR COOLANT PUMP SEAL WATER 0.75 9-96 NV96 RETURN REACTOR COOLANT PUMP SEAL WATER 4 9-96 NV95B RETURN M329 CHARGING LINE NV B1 3 9-98 NV12 CHARGING LINE 3 9-98 NV245B M347 LETDOWN LINE NV A6 2 9-98 NV458A LETDOWN LINE 2 9-98 NV35A LETDOWN LINE 2 9-98 NV457A LETDOWN LINE 2 9-98 NV6 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 3 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number LETDOWN LINE 3 9-98 NV7B M259 REACTOR MAKEUP WATER TANK TO NV NB B1 1 9-110 NB262 SYSTEM REACTOR MAKEUP WATER TANK TO NV 1 9-110 NB260B SYSTEM M394 ICE CONDENSER ICE BLOWING AIR IN NF C3 5 ICE CONDENSER ICE BLOWING AIR IN 5 M371 ICE CONDENSER ICE BLOWING AIR OUT NF C3 6 ICE CONDENSER ICE BLOWING AIR OUT M373 ICE CONDENSER GLYCOL IN NF B1 4 NF229 ICE CONDENSER GLYCOL IN 4 NF228A Deleted Per 2012 Update M372 ICE CONDENSER GLYCOL OUT NF A7 4 NF234A ICE CONDENSER GLYCOL OUT 4 NF233B ICE CONDENSER GLYCOL OUT 0.5 NF1464 M300 STEAM GENERATOR BLOWDOWN BB A1 2 10-51 BB5A STEAM GENERATOR BLOWDOWN 2 10-51 BB1B M301 STEAM GENERATOR BLOWDOWN BB A1 2 10-51 BB6A STEAM GENERATOR BLOWDOWN 2 10-51 BB2B M304 STEAM GENERATOR BLOWDOWN BB A1 2 10-51 BB8A STEAM GENERATOR BLOWDOWN 2 10-51 BB4B M303 STEAM GENERATOR BLOWDOWN BB A1 2 10-51 BB7A (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 4 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number STEAM GENERATOR BLOWDOWN 2 10-51 BB3B M314 RHR OUT FROM LOOPS ND D5 14 5-28 ND2A,C RHR OUT FROM LOOPS 4 5-28 ND3 M351 BORON INJECTION NI B4 3 6-176 NI-12 BORON INJECTION 0.75 6-176 2NI-11 BORON INJECTION 4 6-176 NI-9A BORON INJECTION 4 6-176 NI-10B Deleted per 2015 Update M330 NITROGEN TO ACCUMULATORS NI B1 1 6-176 NI48 NITROGEN TO ACCUMULATORS 1 6-176 NI47A M321 SAFETY INJECTION TEST LINE NI A7 0.75 6-176 NI95A SAFETY INJECTION TEST LINE 0.75 6-176 NI96B SAFETY INJECTION TEST LINE 0.75 6-176 NI120B SAFETY INJECTION TEST LINE 1 6-176 NI436 M316 SAFETY INJECTION PUMP TO HOT LEG NI B5 2 6-177 NI-124 SAFETY INJECTION PUMP TO HOT LEG 2 6-177 NI-128 SAFETY INJECTION PUMP TO HOT LEG 4 6-177 NI-121A SAFETY INJECTION PUMP TO HOT LEG 0.75 NI-122B M319 SAFETY INJECTION PUMP TO HOT LEG NI B5 2 6-177 NI-156 SAFETY INJECTION PUMP TO HOT LEG 2 6-177 NI-159 SAFETY INJECTION PUMP TO HOT LEG 4 6-177 NI-152B (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 5 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number SAFETY INJECTION PUMP TO HOT LEG 0.75 NI-153 M352 SAFETY INJECTION PUMP TO COLD LEG NI B5 2 6-176 NI-165 SAFETY INJECTION PUMP TO COLD LEG 2 6-176 NI-167 SAFETY INJECTION PUMP TO COLD LEG 2 6-176 NI-169 SAFETY INJECTION PUMP TO COLD LEG 2 6-176 NI-171 SAFETY INJECTION PUMP TO COLD LEG 4 6-177 NI-162A SAFETY INJECTION PUMP TO COLD LEG 1 NI-163 M336 RHR PUMP TO COLD LEG NI B5 6 6-177 NI180 RHR PUMP TO COLD LEG 6 6-177 NI181 RHR PUMP TO COLD LEG 1 NI179 RHR PUMP TO COLD LEG 8 6-177 NI178B M306 RHR PUMP TO COLD LEG NI B4 6 6-177 NI175 RHR PUMP TO COLD LEG 6 6-177 NI176 RHR PUMP TO COLD LEG 1 NI174 RHR PUMP TO COLD LEG 8 6-177 NI173A M277 RHR PUMP TO HOT LEG NI B5 8 6-177 NI125 RHR PUMP TO HOT LEG 8 6-177 NI129 RHR PUMP TO HOT LEG 12 6-177 NI183B RHR PUMP TO HOT LEG 1 NI154 M278 RHR OUT FROM SUMP NI C1 18 6-176 NI184B RHR OUT FROM SUMP NI C1 1 6-176 NI861 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 6 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number RHR OUT FROM SUMP NI C1 1 6-176 NI862 RHR OUT FROM SUMP NI C1 3/4 6-176 NI863 RHR OUT FROM SUMP NI C1 3/4 6-176 NI864 RHR OUT FROM SUMP NI C1 1 6-176 NI869 RHR OUT FROM SUMP NI C1 1 6-176 NI870 RHR OUT FROM SUMP NI C1 1/2 6-176 NI871 RHR OUT FROM SUMP NI C1 1/2 6-176 NI872 M302 RHR OUT FROM SUMP NI C1 18 6-176 NI185A RHR OUT FROM SUMP NI C1 1 6-176 NI865 RHR OUT FROM SUMP NI C1 1 6-176 NI866 RHR OUT FROM SUMP NI C1 3/4 6-176 NI867 RHR OUT FROM SUMP NI C1 3/4 6-176 NI868 RHR OUT FROM SUMP NI C1 1 6-176 NI873 RHR OUT FROM SUMP NI C1 1 6-176 NI874 RHR OUT FROM SUMP NI C1 1/2 6-176 NI875 RHR OUT FROM SUMP NI C1 1/2 6-176 NI876 M348 PALS DISCHARGE WL A6 2 WL1302A PALS DISCHARGE 2 WL1301B M362 CONTAINMENT SPRAY IN NS B1 8 6-194 NS33 CONTAINMENT SPRAY IN 8 6-194 NS32A (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 7 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M370 CONTAINMENT SPRAY IN NS B1 8 6-194 NS30 CONTAINMENT SPRAY IN 8 6-194 NS29A M380 CONTAINMENT SPRAY IN NS B1 8 6-194 NS16 CONTAINMENT SPRAY IN 8 6-194 NS15B M387 CONTAINMENT SPRAY IN NS B1 8 6-194 NS13 CONTAINMENT SPRAY IN 8 6-194 NS12B M369 RHR TO CONTAINMENT SPRAY NS B1 8 6-194 NS46 RHR TO CONTAINMENT SPRAY 8 6-194 NS43A M381 RHR TO CONTAINMENT SPRAY NS B1 8 6-194 NS41 RHR TO CONTAINMENT SPRAY 8 6-194 NS-38B M374 CONT FLOOR SUMP INCORE INST. SUMP WL A6 4 11-1 WL-64A DISCHARGE CONT FLOOR SUMP INCORE INST. SUMP 4 11-1 WL-65B DISCHARGE CONT FLOOR SUMP INCORE INST. SUMP 0.75 11-1 WL-264 DISCHARGE M360 RCDT GAS SPACE TO WASTE GAS SYSTEM WL A1 0.75 11-1 WL-39A RCDT GAS SPACE TO WASTE GAS SYSTEM 0.75 11-1 WL-41B M375 RCDT HEAT EXCHANGER DISCHARGE WL A7 3 11-1 WL-2A RCDT HEAT EXCHANGER DISCHARGE 0.5 11-1 WL-24 RCDT HEAT EXCHANGER DISCHARGE 3 11-1 WL1B (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 8 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M235 PRESSURIZER SAMPLE NM A6 1 9-90 NM3A,C PRESSURIZER SAMPLE 1 9-90 NM6A,C PRESSURIZER SAMPLE 0.75 9-90 NM420 PRESSURIZER SAMPLE 1 9-90 NM7B M309 REACTOR COOLANT HOT LEG SAMPLE NM A7 1 9-90 NM-22A,C REACTOR COOLANT HOT LEG SAMPLE 1 9-90 NM-25A,C REACTOR COOLANT HOT LEG SAMPLE 0.75 9-90 NM-421 REACTOR COOLANT HOT LEG SAMPLE 1 9-90 NM-26B M280 SAFETY INJECTION SAMPLE NM A6 1 9-90 NM-72B SAFETY INJECTION SAMPLE 1 9-90 NM-75B SAFETY INJECTION SAMPLE 1 9-90 NM-78B SAFETY INJECTION SAMPLE 1 9-90 NM-81B SAFETY INJECTION SAMPLE 0.75 9-90 NM-69 SAFETY INJECTION SAMPLE 1 9-90 NM-82A M335 STEAM GENERATOR BLOWDOWN SAMPLE NM A7 1 9-91 NM-190A STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-187A STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-424 STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-191B M338 STEAM GENERATOR BLOWDOWN SAMPLE NM A7 1 9-91 NM-200B STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-197B (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 9 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-425 STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-201A M340 STEAM GENERATOR BLOWDOWN SAMPLE NM A7 1 9-91 NM-210A STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-207A STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-426 STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-211B M341 STEAM GENERATOR BLOWDOWN SAMPLE NM A7 1 9-91 NM-220B STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-217B STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-427 STEAM GENERATOR BLOWDOWN SAMPLE 1 9-91 NM-221A M376 COMPONENT COOLING TO RCDT HX KC B1 4 9-57 KC322 COMPONENT COOLING TO RCDT HX 3 9-57 KC320A M355 COMPONENT COOLING FROM RCDT HX KC A7 3 9-57 KC332B COMPONENT COOLING FROM RCDT HX 1 9-57 KC280 COMPONENT COOLING FROM RCDT HX 3 9-57 KC333A M327 KC TO RX VESSEL SUPPORT COOLERS + RCP KC B1 8 9-57 KC340 COOLERS KC TO RX VESSEL SUPPORT COOLERS + RCP 8 9-57 KC338B COOLERS M320 KC FROM RX VESSEL SUPPORT COOLERS + KC A7 8 9-57 KC424B RCP COOLERS KC FROM RX VESSEL SUPPORT COOLERS + 1 9-57 KC279 RCP COOLERS (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 10 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number KC FROM RX VESSEL SUPPORT COOLERS + 8 9-57 KC425A RCP COOLERS M218 COMPONENT COOLING TO EXCESS KC D1 3 9-57 KC305B LETDOWN HX M217 COMPONENT COOLING FROM EXCESS KC D1 3 9-57 KC315B LETDOWN HX M322 COMP COOLING TO COMP COOLING DRAIN KC A7 2 9-57 KC429B TRAIN COMP COOLING TO COMP COOLING DRAIN 0.75 9-57 KC47 TRAIN COMP COOLING TO COMP COOLING DRAIN 2 9-57 KC430A TRAIN M307 NUCLEAR SERVICE WATER TO REACTOR RN A1 6 9-31 RN253A COOLANT PUMP NUCLEAR SERVICE WATER TO REACTOR 6 9-31 RN252B COOLANT PUMP Deleted Per 2012 Update NUCLEAR SERVICE WATER TO REACTOR 0.75 RN1102 COOLANT PUMP M315 NUCLEAR SERVICE WATER FROM REACTOR RN A6 6 9-31 RN276A COOLANT PUMP NUCLEAR SERVICE WATER FROM REACTOR 6 9-31 RN277B COOLANT PUMP NUCLEAR SERVICE WATER FROM REACTOR 0.75 9-31 RN1103 COOLANT PUMP M213 INCORE INSTRUMENTATION ROOM PURGE IN VP A5 12 9-121 VP17A (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 11 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number INCORE INSTRUMENTATION ROOM PURGE IN 9-121 VP18B M138 INCORE INSTRUMENTATION ROOM PURGE VP A5 24 9-121 VP19A OUT INCORE INSTRUMENTATION ROOM PURGE 9-121 VP20B OUT M367 UPPER COMPARTMENT PURGE INLET VP A5 24 9-121 VP2A UPPER COMPARTMENT PURGE INLET 9-121 VP1B M454 UPPER COMPARTMENT PURGE INLET VP A5 24 9-121 VP4A UPPER COMPARTMENT PURGE INLET 9-121 VP3B M357 LOWER COMPARTMENT PURGE INLET VP A5 24 9-121 VP7A LOWER COMPARTMENT PURGE INLET 9-121 VP6B M456 LOWER COMPARTMENT PURGE INLET VP A5 24 9-121 VP9A LOWER COMPARTMENT PURGE INLET 9-121 VP8B M368 CONTAINMENT PURGE EXHAUST VP A5 24 9-121 VP10A CONTAINMENT PURGE EXHAUST 9-121 VP11B M455 CONTAINMENT PURGE EXHAUST VP A5 24 9-121 VP12A CONTAINMENT PURGE EXHAUST 24 9-121 VP13B M119 CONTAINMENT PURGE VP A5 24 9-121 VP15A CONTAINMENT PURGE 24 9-121 VP16B M440 FEEDWATER CF D1 18 10-45 CF26A,B FEEDWATER CF 2 10-45 CF-137 M308 FEEDWATER CF D1 18 10-45 CF28A,B (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 12 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number FEEDWATER CF 2 10-45 CF-136 M262 FEEDWATER CF D1 18 10-45 CF30A,B FEEDWATER CF 2 10-45 CF-135 M153 FEEDWATER CF D1 18 10-45 CF-35AB FEEDWATER CF 2 10-45 CF-134 M441 MAIN STEAM SM D3 34 10-11 SM-1AB MAIN STEAM 6 10-11 SV-2 MAIN STEAM 6 10-11 SV-3 MAIN STEAM 6 10-11 SV-4 MAIN STEAM 6 10-11 SV-5 MAIN STEAM 6 10-11 SV-6 MAIN STEAM 6 10-11 SV-1AB MAIN STEAM 3 10-11 SM-9AB Deleted Per 2003 Update MAIN STEAM 2 10-11 SM-101 Deleted Per 2005 Update M393 MAIN STEAM SM D3 6 10-11 SA-1 MAIN STEAM .75 10-11 SA-77 MAIN STEAM 34 10-11 SM-3AB MAIN STEAM 6 10-11 SV-8 MAIN STEAM 6 10-11 SV-9 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 13 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number MAIN STEAM 6 10-11 SV-10 MAIN STEAM 6 10-11 SV-11 MAIN STEAM 6 10-11 SV-12 MAIN STEAM 6 10-11 SV-7ABC MAIN STEAM 3 10-11 SM10AB Deleted Per 2003 Update MAIN STEAM 2 10-11 SM-95 Deleted Per 2005 Update M261 MAIN STEAM SM D3 6 10-11 SA-2 MAIN STEAM .75 10-11 SA-78 MAIN STEAM 34 10-11 SM-5AB MAIN STEAM 6 10-11 SV-14 MAIN STEAM 6 10-11 SV-15 MAIN STEAM 6 10-11 SV-16 MAIN STEAM 6 10-11 SV-17 MAIN STEAM 6 10-11 SV-18 MAIN STEAM 6 10-11 SV13AB MAIN STEAM 3 10-11 SM11AB Deleted Per 2003 Update MAIN STEAM 2 10-11 SM89 Deleted Per 2005 Update (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 14 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M154 MAIN STEAM SM D3 34 10-11 SM-7AB MAIN STEAM 6 10-11 SV-20 MAIN STEAM 6 10-11 SV-21 MAIN STEAM 6 10-11 SV-22 MAIN STEAM 6 10-11 SV-23 MAIN STEAM 6 10-11 SV-24 MAIN STEAM 6 10-11 SV-19AB MAIN STEAM 3 10-11 SM12AB Deleted Per 2003 Update MAIN STEAM 2 10-11 SM-83 Deleted Per 2005 Update M337 DEMINERALIZED WATER YM B1 2 9-73 YM-116 DEMINERALIZED WATER 2 9-73 YM-115B M240 CONTAINMENT VENTILATION COOLING RV A6 12 10-29 RV33B WATER IN CONTAINMENT VENTILATION COOLING 12 10-29 RV32A WATER IN CONTAINMENT VENTILATION COOLING .75 10-29 RV445 WATER IN 1M385 CONTAINMENT VENTILATION COOLING RV A6 6 10-29 1RV80B WATER IN CONTAINMENT VENTILATION COOLING 6 10-29 1RV79A WATER IN (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 15 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number 1M385 CONTAINMENT VENTILATION COOLING RV A6 .75 10-29 1RV481 WATER IN 2M385 CONTAINMENT VENTILATION COOLING RV A6 .75 10-29 2RV480 WATER IN 2M385 CONTAINMENT VENTILATION COOLING RV A6 6 10-29 2RV80B WATER IN CONTAINMENT VENTILATION COOLING 6 10-29 2RV79A WATER IN CONTAINMENT VENTILATION COOLING .75 10-29 2RV480 WATER IN M390 CONTAINMENT VENTILATION COOLING RV A6 6 10-29 RV101A WATER OUT CONTAINMENT VENTILATION COOLING 6 10-29 RV102B WATER OUT Deleter Per 2012 Update

.75 10-29 RV484 M279 CONTAINMENT VENTILATION COOLING RV A6 12 10-29 RV76A WATER OUT CONTAINMENT VENTILATION COOLING 12 10-29 RV77B WATER OUT CONTAINMENT VENTILATION COOLING .75 RV446 WATER OUT M220 INSTRUMENT AIR VI B1 2 9-79 VI40 INSTRUMENT AIR 2 9-79 VI129B (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 16 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M219 STATION AIR VS B1 2 9-83 VS13 STATION AIR 2 9-83 VS12B M215 BREATHING AIR VB B1 2 VB50 BREATHING AIR 2 VB49B M118 CONTAINMENT PRESSURE SENSOR NS 0.5 NSSV5560 M239 CONTAINMENT PRESSURE SENSOR NS 0.5 NSSV5570 M402 CONTAINMENT PRESSURE SENSOR NS 0.5 NSSV5590 M313 CONTAINMENT PRESSURE SENSOR NS 0.5 NSSV5580 M402A NARROW RANGE CONTAINMENT PRESSURE NS 1 NSSV5550 1 NSSV5551 M378 CONTAINMENT SAMPLE OUT VX A2 1 6-107 VX33B CONTAINMENT SAMPLE OUT 1 6-107 VX31A CONTAINMENT SAMPLE OUT 1 6-107 VX34 M325 CONTAINMENT SAMPLE IN VX B1 1 6-107 VX30 CONTAINMENT SAMPLE IN 1 6-107 VX40 M156 AUXILIARY FEEDWATER CA/CF D1 4 10-47 CA62A AUXILIARY FEEDWATER 4 10-47 CA66A,C AUXILIARY FEEDWATER 6 10-45 CF126B AUXILIARY FEEDWATER 2 10-45 CF-183 AUXILIARY FEEDWATER 2 BW-3 AUXILIARY FEEDWATER 0.75 YA-47 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 17 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M286 AUXILIARY FEEDWATER CA/CF D1 4 10-47 CA54AC AUXILIARY FEEDWATER 4 10-47 CA58A AUXILIARY FEEDWATER 6 10-45 CF127B AUXILIARY FEEDWATER 2 10-45 CF-184 AUXILIARY FEEDWATER 2 BW-12 0.75 YA-48 M3100 AUXILIARY FEEDWATER CA/CF D1 4 10-47 CA46B AUXILIARY FEEDWATER 4 10-47 CA50B AUXILIARY FEEDWATER 6 10-45 CF128B AUXILIARY FEEDWATER 2 10-45 CF-185 AUXILIARY FEEDWATER 2 BW-21 AUXILIARY FEEDWATER 0.75 YA-49 M465 AUXILIARY FEEDWATER CA/CF D1 4 10-47 CA38B AUXILIARY FEEDWATER 4 10-47 CA42B AUXILIARY FEEDWATER 6 10-45 CF129B AUXILIARY FEEDWATER 2 10-45 CF-186 AUXILIARY FEEDWATER 2 BW-30 AUXILIARY FEEDWATER 0.75 YA-50 M358 REFUELING CAVITY TO RW PUMP FW A4 4 9-65 FW11 REFUELING CAVITY TO RW PUMP 4 9-65 FW13 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 18 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number REFUELING CAVITY TO RW PUMP 0.75 9-65 1FW67/

2FW63 M377 REFUELING CAVITY FROM TW TANK FW B2 6 9-65 FW5 REFUELING CAVITY FROM TW TANK 6 9-65 FW4 M331 HYDROGEN PURGE IN VE B1 4 VE11 HYDROGEN PURGE IN 4 VE10A M346 HYDROGEN PURGE OUT VE A5 4 VE-5A HYDROGEN PURGE OUT 4 VE-6B M354 FUEL TRANSFER CANAL KF C2 24 M326 RCP MOTOR DRAIN TANK TO WASTE OIL NC A4 2 NC-141 STORAGE RCP MOTOR DRAIN TANK TO WASTE OIL 2 NC-142 STORAGE RCP MOTOR DRAIN TANK TO WASTE OIL 0.75 NC261 STORAGE M221 CONT VENT UNITS COND. DRAINS TO DRAIN WL A7 6 11-1 WL321A TANK CONT VENT UNITS COND. DRAINS TO DRAIN 6 11-1 WL322B TANK CONT VENT UNITS COND. DRAINS TO DRAIN 1 11-1 WL385 TANK M359 INSTRUMENT AIR VI B1 2 9-79 VI161 INSTRUMENT AIR 2 9-79 VI160B (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 19 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M386 INSTRUMENT AIR VI B1 2 9-79 VI149 INSTRUMENT AIR 2 9-79 VI148B INSTRUMENT AIR 2 9-79 VI362A M317 INSTRUMENT AIR VI B1 2 9-79 VI124 INSTRUMENT AIR 2 9-79 VI150B M243 CONTAINMENT AIR RELEASE VQ A5 6 9-150 VQ-1A CONTAINMENT AIR RELEASE 9-150 VQ-2B M384 CONTAINMENT AIR ADDITION VQ A5 6 9-150 VQ-6A CONTAINMENT AIR ADDITION 9-150 VQ-5B M361 REACTOR COOLANT PUMP MOTOR OIL NC A7 2 NC-196A SUPPLY REACTOR COOLANT PUMP MOTOR OIL 2 NC-195B SUPPLY REACTOR COOLANT PUMP MOTOR OIL 0.75 NC259 SUPPLY 1M353 FIRE PROTECTION HEADER RF B2 4 9-124 1RF823 FIRE PROTECTION HEADER 4 9-124 1RF821A 2M353 FIRE PROTECTION HEADER RF B2 4 9-124 1RF834 FIRE PROTECTION HEADER 4 9-124 1RF832A M228 AUXILIARY SPRAY TO PRESSURIZER NV B2 2 9-98 NV841 1M228 AUXILIARY SPRAY TO PRESSURIZER NV B2 2 9-98 1NV840 2M228 AUXILIARY SPRAY TO PRESSURIZER NV B2 2 9-98 2NV1053 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 20 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number M342 STANDBY MAKEUP PUMP TO RCS SEALS NV B1 2 9-96 NV1002 STANDBY MAKEUP PUMP TO RCS SEALS 2 9-96 NV849A,C M383 ICE BASKET WATER ADDITION NF C3 8 ICE BASKET WATER ADDITION 1M255A/ ILRT TEST CONNECTION MI A4 0.5 MIMV6980 2E118A ILRT TEST CONNECTION 0.5 MIMV7010 1M255B/ ILRT TEST CONNECTION MI A4 0.5 MIMV6990 2E118B ILRT TEST CONNECTION 0.5 MIMV7020 1M255C/ ILRT TEST CONNECTION MI A4 0.5 MIMV7000 2E118C ILRT TEST CONNECTION 0.5 MIMV7030 M239A CONTAINMENT HYDROGEN SAMPLE MI A1 0.5 MISV6870 CONTAINMENT HYDROGEN SAMPLE 0.5 MISV6890 M239B CONTAINMENT HYDROGEN SAMPLE MI A1 0.5 MISV6880 CONTAINMENT HYDROGEN SAMPLE 0.5 MISV6900 M239C CONTAINMENT HYDROGEN SAMPLE MI A1 0.5 MISV6910 CONTAINMENT HYDROGEN SAMPLE 0.5 MISV6930 M239D CONTAINMENT HYDROGEN SAMPLE MI A1 0.5 MISV6920 CONTAINMENT HYDROGEN SAMPLE 0.5 MISV6940 M323A RADIATION MONITORING MI A1 0.75 MISV5581 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-111 (Page 21 of 21)

FSAR System Pen Class Line Size Figure Valve Pen No. Penetration Name Note 2 Note 5 Note 6 No. Number RADIATION MONITORING 0.75 MISV5580 M323B RADIATION MONITORING MI A1 0.75 MISV5583 RADIATION MONITORING 0.75 MISV5582 C152 LOWER PERSONNEL LOCK RX DOOR RELIEF IAE NA 2 3-67 IAECV537 (CONT SIDE) 0 C152 LOWER PERSONNEL LOCK RX DOOR RELIEF IAE NA 2 3-67 IAECV539 (PAL SIDE) 0 C392 UPPER PERSONNEL LOCK RX DOOR RELIEF IAE NA 2 3-67 IAECV536 (CONT SIDE) 0 C392 UPPER PERSONNEL LOCK RX DOOR RELIEF IAE NA 2 3-67 IAECV538 (PAL SIDE) 0 (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-112 (Page 2 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 1ND120 CONT. SPRAY, RHR, SI, + CVCS OUTSIDE RELIEF N RELIEF TO PRT NI151 CONT. SPRAY, RHR, SI, + CVCS OUTSIDE RELIEF N RELIEF TO PRT NI102 CONT. SPRAY, RHR, SI, + CVCS OUTSIDE RELIEF N RELIEF TO PRT NI119 CONT. SPRAY, RHR, SI, + CVCS OUTSIDE RELIEF N RELIEF TO PRT NI161 CONT. SPRAY, RHR, SI, + CVCS OUTSIDE RELIEF N RELIEF TO PRT NV229 CONT. SPRAY, RHR, SI, + CVCS OUTSIDE RELIEF N RELIEF TO PRT NV45 REACTOR COOLANT PUMP M339 INSIDE CHECK 1 A N SEAL WATER SUPPLY NV77 REACTOR COOLANT PUMP M343 INSIDE CHECK 1 A N SEAL WATER SUPPLY NV61 REACTOR COOLANT PUMP M344 INSIDE CHECK 1 A N SEAL WATER SUPPLY NV29 REACTOR COOLANT PUMP M350 INSIDE CHECK 1 A N SEAL WATER SUPPLY NV94A,C REACTOR COOLANT PUMP M256 INSIDE GATE 1 A N SEAL WATER RETURN (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 3 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NV96 REACTOR COOLANT PUMP INSIDE CHECK N SEAL WATER RETURN NV95B REACTOR COOLANT PUMP OUTSIDE GATE N SEAL WATER RETURN NV12 CHARING LINE M329 INSIDE CHECK 1 A N NV245B CHARING LINE OUTSIDE GATE N NV458A LETDOWN LINE M347 INSIDE GATE 1 A N NV457A LETDOWN LINE INSIDE GATE N NV35A LETDOWN LINE INSIDE GATE N NV6 LETDOWN LINE INSIDE RELIEF N NV7B LETDOWN LINE OUTSIDE GLOBE N NB262 REACTOR MAKEUP WATER M259 INSIDE CHECK NORMAL 2 C TANK TO NV SYSTEM NB260B REACTOR MAKEUP WATER OUTSIDE GLOBE NORMAL C TANK TO NV SYSTEM ICE CONDENSER ICE BLOWING M394 INSIDE BLANK NORMAL 2 B AIR IN FLANGE ICE CONDENSER ICE BLOWING OUTSIDE BLANK NORMAL B AIR IN FLANGE ICE CONDENSER ICE BLOWING M371 INSIDE BLANK NORMAL 1 H B AIR OUT FLANGE (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 4 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 ICE CONDENSER ICE BLOWING OUTSIDE BLANK NORMAL B AIR OUT FLANGE NF229 ICE CONDENSER GLYCOL IN M373 INSIDE CHECK NORMAL 2 C NF228A ICE CONDENSER GLYCOL IN OUTSIDE DIAPHRAGM NORMAL C NF234A ICE CONDENSER GLYCOL OUT M372 OUTSIDE DIAPHRAGM NORMAL 2 C NF233B ICE CONDENSER GLYCOL OUT INSIDE DIAPHRAGM NORMAL C NF1464 ICE CONDENSER GLYCOL OUT INSIDE CHECK NORMAL C BB5A STEAM GENERATOR M300 INSIDE GATE 1 B N BLOWDOWN BB1B STEAM GENERATOR OUTSIDE GATE N BLOWDOWN BB6A STEAM GENERATOR M301 INSIDE GATE 1 B N BLOWDOWN BB2B STEAM GENERATOR OUTSIDE GATE N BLOWDOWN BB8A STEAM GENERATOR M304 INSIDE GATE 1 B N BLOWDOWN BB4B STEAM GENERATOR OUTSIDE GATE N BLOWDOWN BB7A STEAM GENERATOR M303 INSIDE GATE 1 B N BLOWDOWN BB3B STEAM GENERATOR OUTSIDE GATE N BLOWDOWN ND2A,C RHR OUT FROM LOOPS M314 INSIDE GATE 1 A N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 5 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 ND3 RHR OUT FROM LOOPS INSIDE RELIEF N NI-12 BORON INJECTION M351 INSIDE CHECK 1 A N 2NI-11 BORON INJECTION INSIDE GLOBE N NI-9A BORON INJECTION OUTSIDE GATE N NI-10B BORON INJECTION OUTSIDE GATE N Deleted Per 2015 Update NI48 NITROGEN TO ACCUMULATORS M330 INSIDE CHECK NORMAL 2 C NI47A NITROGEN TO ACCUMULATORS OUTSIDE GLOBE NORMAL C NI95A SAFETY INJECTION TEST LINE M321 INSIDE GLOBE REVERS 2 C E

NI96B SAFETY INJECTION TEST LINE OUTSIDE GLOBE NORMAL C NI120B SAFETY INJECTION TEST LINE OUTSIDE GLOBE NORMAL C NI436 SAFETY INJECTION TEST LINE INSIDE CHECK NORMAL C NI-124 SAFETY INJECTION PUMP TO M316 INSIDE CHECK 1 A N HOT LEG NI-128 SAFETY INJECTION PUMP TO INSIDE CHECK N HOT LEG NI-121A SAFETY INJECTION PUMP TO OUTSIDE GATE N HOT LEG NI-122B SAFETY INJECTION PUMP TO INSIDE GLOBE N HOT LEG (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 6 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NI-156 SAFETY INJECTION PUMP TO M319 INSIDE CHECK 1 A N HOT LEG NI-159 SAFETY INJECTION PUMP TO INSIDE CHECK N HOT LEG NI-152B SAFETY INJECTION PUMP TO OUTSIDE GATE N HOT LEG NI-153 SAFETY INJECTION PUMP TO INSIDE GLOBE N HOT LEG NI-165 SAFETY INJECTION PUMP TO M352 INSIDE CHECK 1 A N COLD LEG NI-167 SAFETY INJECTION PUMP TO INSIDE CHECK N COLD LEG NI-169 SAFETY INJECTION PUMP TO INSIDE CHECK N COLD LEG NI-171 SAFETY INJECTION PUMP TO INSIDE CHECK N COLD LEG NI-162A SAFETY INJECTION PUMP TO OUTSIDE GATE N COLD LEG NI-163 SAFETY INJECTION PUMP TO INSIDE GLOBE N COLD LEG NI180 RHR PUMP TO COLD LEG M336 INSIDE CHECK 1 A N NI181 RHR PUMP TO COLD LEG INSIDE CHECK N NI179 RHR PUMP TO COLD LEG INSIDE GLOBE N NI178B RHR PUMP TO COLD LEG OUTSIDE GATE N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 7 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NI175 RHR PUMP TO COLD LEG M306 INSIDE CHECK 1 A N NI176 RHR PUMP TO COLD LEG INSIDE CHECK N NI174 RHR PUMP TO COLD LEG INSIDE GLOBE N NI173A RHR PUMP TO COLD LEG OUTSIDE GATE N NI125 RHR PUMP TO HOT LEG M277 INSIDE CHECK 1 A N NI129 RHR PUMP TO HOT LEG INSIDE CHECK N NI183B RHR PUMP TO HOT LEG OUTSIDE GATE N NI154 RHR PUMP TO HOT LEG INSIDE GLOBE N NI184B RHR OUT FROM SUMP M278 OUTSIDE GATE 1 A N NI861 RHR OUT FROM SUMP M278 OUTSIDE GLOBE REVERS 2 C E

NI862 RHR OUT FROM SUMP M278 OUTSIDE GLOBE REVERS 2 C E

NI863 RHR OUT FROM SUMP M278 OUTSIDE GLOBE REVERS 2 C E

NI864 RHR OUT FROM SUMP M278 OUTSIDE GLOBE REVERS 2 C E

NI869 RHR OUT FROM SUMP M278 OUTSIDE BALL NORMAL 2 C NI870 RHR OUT FROM SUMP M278 OUTSIDE BALL NORMAL 2 C NI871 RHR OUT FROM SUMP M278 OUTSIDE BALL NORMAL 2 C NI872 RHR OUT FROM SUMP M278 OUTSIDE BALL NORMAL 2 C NI185A RHR OUT FROM SUMP M302 OUTSIDE GATE 1 A N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 8 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NI865 RHR OUT FROM SUMP M302 OUTSIDE GLOBE REVERS 2 C E

NI866 RHR OUT FROM SUMP M302 OUTSIDE GLOBE REVERS 2 C E

NI867 RHR OUT FROM SUMP M302 OUTSIDE GLOBE REVERS 2 C E

NI868 RHR OUT FROM SUMP M302 OUTSIDE GLOBE REVERS 2 C E

NI873 RHR OUT FROM SUMP M302 OUTSIDE BALL NORMAL 2 C NI874 RHR OUT FROM SUMP M302 OUTSIDE BALL NORMAL 2 C NI875 RHR OUT FROM SUMP M302 OUTSIDE BALL NORMAL 2 C NI876 RHR OUT FROM SUMP M302 OUTSIDE BALL NORMAL 2 C WL1302A PALS DISCHARGE M348 INSIDE GLOBE REVERS 2 C E

WL1301B PALS DISCHARGE OUTSIDE GLOBE NORMAL C NS33 CONTAINMENT SPRAY IN M362 INSIDE CHECK 1 A N NS32A CONTAINMENT SPRAY IN OUTSIDE GATE N NS30 CONTAINMENT SPRAY IN M370 INSIDE CHECK 1 A N NS29A CONTAINMENT SPRAY IN OUTSIDE GATE N NS16 CONTAINMENT SPRAY IN M380 INSIDE CHECK 1 A N NS15B CONTAINMENT SPRAY IN OUTSIDE GATE N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 9 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NS13 CONTAINMENT SPRAY IN M387 INSIDE CHECK 1 A N NS12B CONTAINMENT SPRAY IN OUTSIDE GATE N NS46 RHR TO CONTAINMENT SPRAY M369 INSIDE CHECK 1 A N NS43A RHR TO CONTAINMENT SPRAY OUTSIDE GATE N NS41 RHR TO CONTAINMENT SPRAY M381 INSIDE CHECK 1 A N NS-38B RHR TO CONTAINMENT SPRAY OUTSIDE GATE N WL-64A CONT FLOOR SUMP INCORE M374 INSIDE DIAPHRAGM REVERS 2 C INST. SUMP DISCHARGE E WL-65B CONT FLOOR SUMP INCORE OUTSIDE DIAPHRAGM NORMAL C INST. SUMP DISCHARGE WL-264 CONT FLOOR SUMP INCORE INSIDE RELIEF REVERS C INST. SUMP DISCHARGE E 1WL-39A RCDT GAS SPACE TO WASTE M360 INSIDE GLOBE REVERS 2 C GAS SYSTEM E 1WL-41B RCDT GAS SPACE TO WASTE OUTSIDE GLOBE NORMAL C GAS SYSTEM 2WL39A RCDT GAS SPACE TO WASTE 2M360 INSIDE DIAPHRAGM REVERS 2 C GAS SYSTEM E 2WL41B RCDT GAS SPACE TO WASTE OUTSIDE DIAPHRAGM NORMAL C GAS SYSTEM WL-2A RCDT HEAT EXCHANGER M375 INSIDE DIAPHRAGM NORMAL 2 C DISCHARGE WL-24 RCDT HEAT EXCHANGER INSIDE CHECK NORMAL C DISCHARGE (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 10 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 WL1B RCDT HEAT EXCHANGER OUTSIDE DIAPHRAGM NORMAL C DISCHARGE NM3A,C PRESSURIZER SAMPLE M235 INSIDE GLOBE NORMAL 2 C NM6A,C PRESSURIZER SAMPLE INSIDE GLOBE NORMAL C NM420 PRESSURIZER SAMPLE INSIDE CHECK NORMAL C NM7B PRESSURIZER SAMPLE OUTSIDE GLOBE NORMAL C NM- REACTOR COOLANT HOT LEG M309 INSIDE GLOBE NORMAL 2 C 22A,C SAMPLE NM- REACTOR COOLANT HOT LEG INSIDE GLOBE NORMAL C 25A,C SAMPLE NM-421 REACTOR COOLANT HOT LEG INSIDE CHECK NORMAL C SAMPLE NM-26B REACTOR COOLANT HOT LEG OUTSIDE GLOBE NORMAL C SAMPLE NM-72B SAFETY INJECTION SAMPLE M280 INSIDE GLOBE NORMAL 2 C NM-75B SAFETY INJECTION SAMPLE INSIDE GLOBE NORMAL C NM-78B SAFETY INJECTION SAMPLE INSIDE GLOBE NORMAL C NM-81B SAFETY INJECTION SAMPLE INSIDE GLOBE NORMAL C NM-69 SAFETY INJECTION SAMPLE INSIDE RELIEF REVERS C E

(13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 11 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NM-82A SAFETY INJECTION SAMPLE OUTSIDE GLOBE NORMAL C NM-190A STEAM GENERATOR M335 INSIDE GLOBE 1 B N BLOWDOWN SAMPLE NM-187A STEAM GENERATOR INSIDE GLOBE N BLOWDOWN SAMPLE NM-424 STEAM GENERATOR INSIDE CHECK N BLOWDOWN SAMPLE NM-191B STEAM GENERATOR OUTSIDE GLOBE N BLOWDOWN SAMPLE NM-200B STEAM GENERATOR M338 INSIDE GLOBE 1 B N BLOWDOWN SAMPLE NM-197B STEAM GENERATOR INSIDE GLOBE N BLOWDOWN SAMPLE NM-425 STEAM GENERATOR INSIDE CHECK N BLOWDOWN SAMPLE NM-201A STEAM GENERATOR OUTSIDE GLOBE N BLOWDOWN SAMPLE NM-210A STEAM GENERATOR M340 INSIDE GLOBE 1 B N BLOWDOWN SAMPLE NM-207A STEAM GENERATOR INSIDE GLOBE N BLOWDOWN SAMPLE NM-426 STEAM GENERATOR INSIDE CHECK N BLOWDOWN SAMPLE NM-211B STEAM GENERATOR OUTSIDE GLOBE N BLOWDOWN SAMPLE (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 12 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 NM-220B STEAM GENERATOR M341 INSIDE GLOBE 1 B N BLOWDOWN SAMPLE NM-217B STEAM GENERATOR INSIDE GLOBE N BLOWDOWN SAMPLE NM-427 STEAM GENERATOR INSIDE CHECK N BLOWDOWN SAMPLE NM-221A STEAM GENERATOR OUTSIDE GLOBE N BLOWDOWN SAMPLE KC322 COMPONENT COOLING TO M376 INSIDE CHECK NORMAL 2 C RCDT HX KC320A COMPONENT COOLING TO OUTSIDE DIAPHRAGM NORMAL C RCDT HX KC332B COMPONENT COOLING FROM M355 INSIDE DIAPHRAGM NORMAL 2 C RCDT HX KC280 COMPONENT COOLING FROM INSIDE CHECK NORMAL C RCDT HX KC333A COMPONENT COOLING FROM OUTSIDE DIAPHRAGM NORMAL C RCDT HX KC340 KC TO RX VESSEL SUPPORT M327 INSIDE CHECK NORMAL 2 C COOLERS + RCP COOLERS KC338B KC TO RX VESSEL SUPPORT OUTSIDE BUTTERFLY NORMAL C COOLERS + RCP COOLERS KC424B KC TO RX VESSEL SUPPORT M320 INSIDE BUTTERFLY NORMAL 2 C COOLERS + RCP COOLERS (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 13 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 KC279 KC TO RX VESSEL SUPPORT INSIDE CHECK NORMAL C COOLERS + RCP COOLERS KC425A KC TO RX VESSEL SUPPORT OUTSIDE BUTTERFLY NORMAL C COOLERS + RCP COOLERS KC305B COMPONENT COOLING TO M218 OUTSIDE GATE 1 B N EXCESS LETDOWN HX KC315B COMPONENT COOLING FROM M217 OUTSIDE GATE 1 B N EXCESS LETDOWN HX KC429B COMP COOLING TO COMP M322 INSIDE GLOBE NORMAL 2 C COOLING DRAIN TRAIN KC47 COMP COOLING TO COMP INSIDE CHECK NORMAL C COOLING DRAIN TRAIN KC430A COMP COOLING TO COMP OUTSIDE GLOBE NORMAL C COOLING DRAIN TRAIN RN253A NUCLEAR SERVICE WATER TO M307 INSIDE DIAPHRAGM REVERS 2 C REACTOR COOLANT PUMP E RN252B NUCLEAR SERVICE WATER TO OUTSIDE DIAPHRAGM NORMAL C REACTOR COOLANT PUMP Deleted Per 2012 Update RN1102 NUCLEAR SERVICE WATER INSIDE RELIEF REVERS C TO REACTOR COOLANT PUMP E RN276A NUCLEAR SERVICE WATER M315 INSIDE DIAPHRAGM REVERS 2 C FROM REACTOR COOLANT E PUMP (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 14 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 RN277B NUCLEAR SERVICE WATER OUTSIDE DIAPHRAGM NORMAL C FROM REACTOR COOLANT PUMP RN1103 NUCLEAR SERVICE WATER M315 INSIDE RELIEF REVERS C FROM REACTOR COOLANT E PUMP VP17A INCORE INSTRUMENTATION M213 INSIDE BUTTERFLY REVERS 2 C ROOM PURGE IN E VP18B INCORE INSTRUMENTATION OUTSIDE BUTTERFLY NORMAL C ROOM PURGE IN VP19A INCORE INSTRUMENTATION M138 INSIDE BUTTERFLY REVERS 2 C ROOM PURGE OUT E VP20B INCORE INSTRUMENTATION OUTSIDE BUTTERFLY NORMAL C ROOM PURGE OUT VP2A UPPER COMPARTMENT M367 INSIDE BUTTERFLY REVERS 2 C PURGE INLET E VP1B UPPER COMPARTMENT OUTSIDE BUTTERFLY NORMAL C PURGE INLET VP4A UPPER COMPARTMENT M454 INSIDE BUTTERFLY REVERS 2 C PURGE INLET E VP3B UPPER COMPARTMENT OUTSIDE BUTTERFLY NORMAL C PURGE INLET VP7A LOWER COMPARTMENT M357 INSIDE BUTTERFLY REVERS 2 C PURGE INLET E (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 15 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 VP6B LOWER COMPARTMENT OUTSIDE BUTTERFLY NORMAL C PURGE INLET VP9A LOWER COMPARTMENT M456 INSIDE BUTTERFLY REVERS 2 C PURGE INLET E VP8B LOWER COMPARTMENT OUTSIDE BUTTERFLY NORMAL C PURGE INLET VP10A CONTAINMENT PURGE M368 INSIDE BUTTERFLY REVERS 2 C EXHAUST E VP11B CONTAINMENT PURGE OUTSIDE BUTTERFLY NORMAL C EXHAUST VP12A CONTAINMENT PURGE M455 INSIDE BUTTERFLY REVERS 2 C EXHAUST E VP13B CONTAINMENT PURGE OUTSIDE BUTTERFLY NORMAL C EXHAUST VP15A CONTAINMENT PURGE M119 INSIDE BUTTERFLY REVERS 2 C E

VP16B CONTAINMENT PURGE OUTSIDE BUTTERFLY NORMAL C CF26AB FEEDWATER M440 OUTSIDE GATE 1 B N CF-137 FEEDWATER OUTSIDE GLOBE N CF28AB FEEDWATER M308 OUTSIDE GATE 1 B N CF-136 FEEDWATER OUTSIDE GLOBE N CF30A,B FEEDWATER M262 OUTSIDE GATE 1 B N CF-135 FEEDWATER OUTSIDE GLOBE N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 16 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 CF-35AB FEEDWATER M153 OUTSIDE GATE 1 B N CF-134 FEEDWATER OUTSIDE GLOBE N Deleted Per 2005 Upate SM-1AB MAIN STEAM OUTSIDE GATE N SV-2 MAIN STEAM OUTSIDE SAFETY N SV-3 MAIN STEAM OUTSIDE SAFETY N SV-4 MAIN STEAM OUTSIDE SAFETY N SV-5 MAIN STEAM OUTSIDE SAFETY N SV-6 MAIN STEAM OUTSIDE SAFETY N SV-1AB MAIN STEAM OUTSIDE GATE N SM-9AB MAIN STEAM OUTSIDE GATE N Deleted Per 2003 Update SM-101 MAIN STEAM OUTSIDE GLOBE N Deleted Per 2005 Update SA-1 MAIN STEAM M393 OUTSIDE GATE 1 B N SA-77 MAIN STEAM OUTSIDE GATE N SM-3AB MAIN STEAM OUTSIDE GATE N SV-8 MAIN STEAM OUTSIDE SAFETY N SV-9 MAIN STEAM OUTSIDE SAFETY N SV-10 MAIN STEAM OUTSIDE SAFETY N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 17 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 SV-11 MAIN STEAM OUTSIDE SAFETY N SV-12 MAIN STEAM OUTSIDE SAFETY N SV-7ABC MAIN STEAM OUTSIDE GATE N SM10AB MAIN STEAM OUTSIDE GATE N Deleted Per 2003 Update SM-95 MAIN STEAM OUTSIDE GLOBE N SA-2 MAIN STEAM M261 OUTSIDE GATE 1 B N SA-78 MAIN STEAM OUTSIDE GATE N Deleted Per 2005 Update SM-5AB MAIN STEAM OUTSIDE GATE N SV-14 MAIN STEAM OUTSIDE SAFETY N SV-15 MAIN STEAM OUTSIDE SAFETY N SV-16 MAIN STEAM OUTSIDE SAFETY N SV-17 MAIN STEAM OUTSIDE SAFETY N SV-18 MAIN STEAM OUTSIDE SAFETY N SV13AB MAIN STEAM OUTSIDE GATE N SM11AB MAIN STEAM OUTSIDE GATE N Deleted Per 2003 Update SM89 MAIN STEAM OUTSIDE GLOBE N Deleted Per 2005 Update (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 18 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 SM-7AB MAIN STEAM OUTSIDE GATE N SV-20 MAIN STEAM OUTSIDE SAFETY N SV-21 MAIN STEAM OUTSIDE SAFETY N SV-22 MAIN STEAM OUTSIDE SAFETY N SV-23 MAIN STEAM OUTSIDE SAFETY N SV-24 MAIN STEAM OUTSIDE SAFETY N SV-19AB MAIN STEAM OUTSIDE GATE N SM12AB MAIN STEAM OUTSIDE GATE N Deleted Per 2003 Update SM-83 MAIN STEAM OUTSIDE GLOBE N YM-116 DEMINERALIZED WATER M337 INSIDE CHECK NORMAL 2 C YM-115B DEMINERALIZED WATER OUTSIDE GLOBE NORMAL C RV33B CONTAINMENT VENTILATION M240 INSIDE BUTTERFLY REVERS 2 C COOLING WATER IN E RV32A CONTAINMENT VENTILATION OUTSIDE BUTTERFLY NORMAL C COOLING WATER IN RV445 CONTAINMENT VENTILATION INSIDE RELIEF REVERS C COOLING WATER IN E 1RV80B CONTAINMENT VENTILATION 1M385 INSIDE DIAPHRAGM REVERS 2 C COOLING WATER IN E 1RV79A CONTAINMENT VENTILATION OUTSIDE DIAPHRAGM NORMAL C COOLING WATER IN (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 19 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 2RV80B CONTAINMENT VENTILATION 2M385 INSIDE DIAPHRAGM REVERS 2 C COOLING WATER IN E 2RV79A CONTAINMENT VENTILATION OUTSIDE DIAPHRAGM NORMAL 2 C COOLING WATER IN 2RV480 CONTAINMENT VENTILATION INSIDE RELIEF REVERS C COOLING WATER IN E 1RV481 CONTAINMENT VENTILATION 1M385 INSIDE RELIEF REVERS C COOLING WATER IN E 2RV480 CONTAINMENT VENTILATION 2M385 INSIDE RELIEF REVERS C COOLING WATER IN E 1RV101A CONTAINMENT VENTILATION 1M390 INSIDE DIAPHRAGM REVERS 2 C COOLING WATER OUT E 1RV102B CONTAINMENT VENTILATION OUTSIDE DIAPHRAGM NORMAL C COOLING WATER OUT 2RV101A CONTAINMENT VENTILATION 2M390 INSIDE DIAPHRAGM REVERS 2 C COOLING WATER OUT E 2RV102B CONTAINMENT VENTILATION OUTSIDE DIAPHRAGM NORMAL C COOLING WATER OUT 2RV484 CONTAINMENT VENTILATION INSIDE RELIEF REVERS C COOLING WATER OUT E RV76A CONTAINMENT VENTILATION M279 INSIDE BUTTERFLY REVERS 2 C COOLING WATER OUT E RV77B CONTAINMENT VENTILATION OUTSIDE BUTTERFLY NORMAL C COOLING WATER OUT (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 20 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 RV446 CONTAINMENT VENTILATION INSIDE RELIEF REVERS C COOLING WATER OUT E VI40 INSTRUMENT AIR M220 INSIDE CHECK NORMAL 2 C VI129B INSTRUMENT AIR OUTSIDE GLOBE NORMAL C VS13 STATION AIR M219 INSIDE CHECK NORMAL 2 C VS12B STATION AIR OUTSIDE GLOBE NORMAL C VB50 BREATHING AIR M215 INSIDE CHECK NORMAL 2 C VB49B BREATHING AIR OUTSIDE GATE NORMAL C NOTE 11 CONTAINMENT PRESSURE M118 OUTSIDE GLOBE 1 G C SENSOR NOTE 11 CONTAINMENT PRESSURE M239 OUTSIDE GLOBE 1 G C SENSOR NOTE 11 CONTAINMENT PRESSURE M402 OUTSIDE GLOBE 1 G C SENSOR NOTE 11 CONTAINMENT PRESSURE M313 OUTSIDE GLOBE 1 G C SENSOR VX33B CONTAINMENT SAMPLE OUT M378 INSIDE DIAPHRAGM REVERS 2 C E

VX31A CONTAINMENT SAMPLE OUT INSIDE DIAPHRAGM NORMAL C VX34 CONTAINMENT SAMPLE OUT OUTSIDE DIAPHRAGM NORMAL C VX30 CONTAINMENT SAMPLE IN M325 INSIDE CHECK NORMAL 2 C VX40 CONTAINMENT SAMPLE IN OUTSIDE DIAPHRAGM REVERS C E

(13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 21 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 CA62A AUXILIARY FEEDWATER M156 OUTSIDE GATE 1 B N CA66AC AUXILIARY FEEDWATER OUTSIDE GATE N CF126B AUXILIARY FEEDWATER OUTSIDE GATE N CF-183 AUXILIARY FEEDWATER OUTSIDE GATE N BW-3 AUXILIARY FEEDWATER OUTSIDE GATE N YA-47 AUXILIARY FEEDWATER OUTSIDE GATE N NSSV5550 NARROW RANGE M402A INSIDE GLOBE NORMAL 2 C CONTAINMENT PRESSURE NSSV5551 NARROW RANGE OUTSIDE GLOBE NORMAL 2 C CONTAINMENT PRESSURE CA54AC AUXILIARY FEEDWATER M286 OUTSIDE GATE 1 B N CA58A AUXILIARY FEEDWATER OUTSIDE GATE N CF127B AUXILIARY FEEDWATER OUTSIDE GATE N CF184 AUXILIARY FEEDWATER OUTSIDE GATE N BW12 AUXILIARY FEEDWATER OUTSIDE GATE N YA48 AUXILIARY FEEDWATER OUTSIDE GATE N CA46B AUXILIARY FEEDWATER M3100 OUTSIDE GATE 1 B N CA50B AUXILIARY FEEDWATER OUTSIDE GATE N CF128B AUXILIARY FEEDWATER OUTSIDE GATE N CF185 AUXILIARY FEEDWATER OUTSIDE GATE N BW21 AUXILIARY FEEDWATER OUTSIDE GATE N (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 22 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 YA49 AUXILIARY FEEDWATER OUTSIDE GATE N CA38B AUXILIARY FEEDWATER M465 OUTSIDE GATE 1 B N CA42B AUXILIARY FEEDWATER OUTSIDE GATE N CF129B AUXILIARY FEEDWATER OUTSIDE GATE N CF186 AUXILIARY FEEDWATER OUTSIDE GATE N BW30 AUXILIARY FEEDWATER OUTSIDE GATE N YA50 AUXILIARY FEEDWATER OUTSIDE GATE N FW11 REFUELING CAVITY TO RW M358 INSIDE DIAPHRAGM NORMAL 2 C PUMP FW13 REFUELING CAVITY TO RW OUTSIDE DIAPHRAGM NORMAL C PUMP 1FW67/ REFUELING CAVITY TO RW INSIDE CHECK NORMAL C PUMP 2FW63 FW5 REFUELING CAVITY FROM TW M377 INSIDE CHECK NORMAL 2 C TANK FW4 REFUELING CAVITY FROM TW OUTSIDE GATE NORMAL C TANK VE11 HYDROGEN PURGE IN M331 INSIDE CHECK NORMAL 2 C VE10A HYDROGEN PURGE IN OUTSIDE DIAPHRAGM NORMAL C VE-5A HYDROGEN PURGE OUT M346 INSIDE GATE NORMAL 1 F C VE-6B HYDROGEN PURGE OUT OUTSIDE GATE NORMAL C (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 23 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 FUEL TRANSFER CANAL M354 INSIDE BLANK 1 E B FLANGE 1NC-141 RCP MOTOR DRAIN TANK TO M326 INSIDE GATE NORMAL 2 C WASTE OIL STORAGE 2NC-141 RCP MOTOR DRAIN TANK TO M326 INSIDE GATE NORMAL 2 C WASTE OIL STORAGE 1NC-142 RCP MOTOR DRAIN TANK TO OUTSIDE GATE NORMAL C WASTE OIL STORAGE 2NC-142 RCP MOTOR DRAIN TANK TO OUTSIDE GATE NORMAL C WASTE OIL STORAGE NC261 RCP MOTOR DRAIN TANK TO INSIDE CHECK NORMAL C WASTE OIL STORAGE WL321A CONT VENT UNITS COND. M221 INSIDE BUTTERFLY NORMAL 2 C DRAINS TO DRAIN TANK WL322B CONT VENT UNITS COND. OUTSIDE BUTTERFLY NORMAL C DRAINS TO DRAIN TANK WL385 CONT VENT UNITS COND. INSIDE CHECK NORMAL C DRAINS TO DRAIN TANK VI161 INSTRUMENT AIR M359 INSIDE CHECK NORMAL 2 C VI160B INSTRUMENT AIR OUTSIDE GLOBE NORMAL C VI149 INSTRUMENT AIR M386 INSIDE CHECK NORMAL 2 C VI148B INSTRUMENT AIR OUTSIDE GLOBE NORMAL C VI362A INSTRUMENT AIR OUTSIDE GLOBE NORMAL C (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 24 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 VI124 INSTRUMENT AIR M317 INSIDE CHECK NORMAL 2 C VI150B INSTRUMENT AIR OUTSIDE GLOBE NORMAL C VQ1A CONTAINMENT AIR RELEASE M243 INSIDE DIAPHRAGM REVERS 2 C E

VQ2B CONTAINMENT AIR RELEASE OUTSIDE DIAPHRAGM NORMAL C VQ6A CONTAINMENT AIR ADDITION M384 INSIDE DIAPHRAGM REVERS 2 C E

VQ5B CONTAINMENT AIR ADDITION OUTSIDE DIAPHRAGM NORMAL C NC196A REACTOR COOLANT PUMP M361 INSIDE GLOBE NORMAL 2 C MOTOR OIL SUPPLY NC195B REACTOR COOLANT PUMP OUTSIDE GLOBE NORMAL C MOTOR OIL SUPPLY NC259 REACTOR COOLANT PUMP INSIDE CHECK NORMAL C MOTOR OIL SUPPLY 1RF823 FIRE PROTECTION HEADER 1M353 INSIDE CHECK NORMAL 2 C 1RF821A FIRE PROTECTION HEADER OUTSIDE DIAPHRAGM NORMAL C 1RF834 FIRE PROTECTION HEADER 2M353 INSIDE CHECK NORMAL 2 C 1RF832A FIRE PROTECTION HEADER OUTSIDE DIAPHRAGM NORMAL C NV841 AUXILIARY SPRAY TO M228 INSIDE CHECK 1 A N PRESSURIZER 1NV840 AUXILIARY SPRAY TO 1M228 OUTSIDE GLOBE 1 A N PRESSURIZER (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 25 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 2NV1053 AUXILIARY SPRAY TO 2M228 OUTSIDE GLOBE 1 A N PRESSURIZER NV1002 STANDBY MAKEUP PUMP TO M342 INSIDE CHECK NORMAL 2 C RCS SEALS NV849A,C STANDBY MAKEUP PUMP TO OUTSIDE GLOBE NORMAL C RCS SEALS ICE BASKET WATER ADDITION M383 INSIDE BLANK 1 H C FLANGE ICE BASKET WATER ADDITION OUTSIDE BLANK C FLANGE MIMV6980 ILRT TEST CONNECTION 1M255A/ INSIDE GLOBE NORMAL 2 C 2E118A MIMV7010 ILRT TEST CONNECTION OUTSIDE GLOBE NORMAL C MIMV6990 ILRT TEST CONNECTION 1M255B/ INSIDE GLOBE NORMAL C 2E118B MIMV7020 ILRT TEST CONNECTION OUTSIDE GLOBE NORMAL C MIMV7000 ILRT TEST CONNECTION 1M255C INSIDE GLOBE NORMAL C

/

2E118C MIMV7030 ILRT TEST CONNECTION OUTSIDE GLOBE NORMAL C MISV6870 CONTAINMENT HYDROGEN M239A INSIDE GLOBE NORMAL 2 C SAMPLE (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 26 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 MISV6890 CONTAINMENT HYDROGEN OUTSIDE GLOBE NORMAL 2 C SAMPLE MISV6880 CONTAINMENT HYDROGEN M239B INSIDE GLOBE NORMAL 2 C SAMPLE MISV6900 CONTAINMENT HYDROGEN OUTSIDE GLOBE NORMAL 2 C SAMPLE MISV6910 CONTAINMENT HYDROGEN M239C INSIDE GLOBE NORMAL 2 C SAMPLE MISV6930 CONTAINMENT HYDROGEN OUTSIDE GLOBE NORMAL 2 C SAMPLE MISV6920 CONTAINMENT HYDROGEN M239D INSIDE GLOBE NORMAL 2 C SAMPLE MISV6940 CONTAINMENT HYDROGEN OUTSIDE GLOBE NORMAL 2 C SAMPLE MISV5581 RADIATION MONITORING M323A INSIDE GLOBE NORMAL 2 C MISV5580 RADIATION MONITORING OUTSIDE GLOBE NORMAL 2 C MISV5583 RADIATION MONITORING M323B INSIDE GLOBE NORMAL 2 C MISV5582 RADIATION MONITORING OUTSIDE GLOBE NORMAL 2 C IAECV5360 UPPER PERSONNEL LOCK Rx C392 INSIDE CHECK NORMAL 1 A C DOOR RELIEF (CONT SIDE)

IAECV5370 LOWER PERSONNEL LOCK Rx C152 INSIDE CHECK NORMAL 1 A C DOOR RELIEF (CONT SIDE)

IAECV5380 UPPER PERSONNEL LOCK Rx C392 OUTSIDE CHECK NORMAL 1 A C DOOR RELIEF (PAL SIDE)

(13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-112 (Page 27 of 27)

Test Leak Pressure Class Leak Test Direction Valve Pen Valve Note Ref Type No. Penetration Name Number Location Valve Type Note 8 3 Note 3 Note 7 IAECV5390 LOWER PERSONNEL LOCK Rx C152 OUTSIDE CHECK NORMAL 1 A C DOOR RELIEF (PAL SIDE)

(13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-113 (Page 1 of 38)

Table 6-113. Containment Isolation Valve Data. (See Table 6-114 for description of notes.)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NC57 PRESSURIZER M216 RELIEF TANK MAKEUP 1NC56B PRESSURIZER MOTOR T OPEN AS IS CLOSED 15 RELIEF TANK MAKEUP 2NC56B PRESSURIZER DIAPHRAGM T OPEN CLOSED CLOSED 15 RELIEF TANK MAKEUP NC54A NITROGEN TO M212 MOTOR T OPEN AS IS CLOSED 10 PRESSURIZER RELIEF TANK NC53B NITROGEN TO MOTOR T OPEN AS IS CLOSED 10 PRESSURIZER RELIEF TANK NC59 CONT. SPRAY, M274 RHR, SI, + CVCS RELIEF TO PRT NS2 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT NS19 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT ND56 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 2 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 ND64 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT ND61 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT 1ND120 CONT, SPRAY, RHR, SI, + CVCS RELIEF TO PRT NI151 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT NI102 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT NI119 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT NI161 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT NV229 CONT. SPRAY, RHR, SI, + CVCS RELIEF TO PRT NV45 REACTOR M339 COOLANT PUMP SEAL WATER SUPPLY (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 3 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NV77 REACTOR M343 COOLANT PUMP SEAL WATER SUPPLY NV61 REACTOR M344 COOLANT PUMP SEAL WATER SUPPLY NV29 REACTOR M350 COOLANT PUMP SEAL WATER SUPPLY NV94A,C REACTOR M256 MOTOR T OPEN AS IS CLOSED 10 COOLANT PUMP SEAL WATER RETURN NV96 REACTOR COOLANT PUMP SEAL WATER RETURN NV95B REACTOR MOTOR T OPEN AS IS CLOSED 10 COOLANT PUMP SEAL WATER RETURN NV12 CHARGING LINE M329 NV245B CHARGING LINE MOTOR S OPEN AS IS CLOSED 10 NV458A LETDOWN LINE M347 DIAPHRAGM T CLOSED CLOSED CLOSED 15 (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 4 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NV457A LETDOWN LINE DIAPHRAGM T CLOSED CLOSED CLOSED 15 NV35A LETDOWN LINE PISTON T OPEN CLOSED CLOSED 15 NV6 LETDOWN LINE NV7B LETDOWN LINE MOTOR T OPEN AS IS CLOSED 10 NB262 REACTOR M259 MAKEUP WATER TANK TO NV SYSTEM NB260B REACTOR MOTOR T CLOSED AS IS CLOSED MAKEUP WATER TANK TO NV SYSTEM ICE M394 CONDENSER ICE BLOWING AIR IN ICE CONDENSER ICE BLOWING AIR IN ICE M371 CONDENSER ICE BLOWING AIR OUT ICE CONDENSER ICE BLOWING AIR OUT (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 5 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NF229 ICE M373 CONDENSER GLYCOL IN NF228A ICE DIAPHRAGM T OPEN CLOSED CLOSED 15 CONDENSER GLYCOL IN NF234A ICE M372 DIAPHRAGM T OPEN CLOSED CLOSED 15 CONDENSER GLYCOL OUT NF233B ICE DIAPHRAGM T OPEN CLOSED CLOSED 15 CONDENSER GLYCOL OUT NF1464 ICE CONDENSER GLYCOL OUT BB5A STEAM M300 PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN BB1B STEAM PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN BB6A STEAM M301 PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN BB2B STEAM PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 6 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 BB8A STEAM M304 PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN BB4B STEAM PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN BB7A STEAM M303 PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN BB3B STEAM PISTON T OPEN CLOSED CLOSED 10 GENERATOR BLOWDOWN ND2A,C RHR OUT FROM M314 MOTOR MANUAL CLOSED AS IS OPEN/

LOOPS CLOSED ND3 RHR OUT FROM LOOPS NI-12 BORON M351 INJECTION 2NI-11 BORON DIAPHRAGM MANUAL CLOSED CLOSED INJECTION NI-9A BORON MOTOR S CLOSED AS IS OPEN NOTE 13 INJECTION NI-10B BORON MOTOR S CLOSED AS IS OPEN NOTE 13 INJECTION Deleted per 2015 update.

NI48 NITROGEN TO M330 ACCUMULA-TORS (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 7 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NI47A NITROGEN TO MOTOR T CLOSED AS IS CLOSED 15 ACCUMULA-TORS NI95A SAFETY M321 MOTOR T CLOSED AS IS CLOSED 10 INJECTION TEST LINE NI96B SAFETY MOTOR T CLOSED AS IS CLOSED 10 INJECTION TEST LINE NI120B SAFETY MOTOR T CLOSED AS IS CLOSED 10 INJECTION TEST LINE NI436 SAFETY INJECTION TEST LINE NI-124 SAFETY M316 INJECTION PUMP TO HOT LEG NI-128 SAFETY INJECTION PUMP TO HOT LEG NI-121A SAFETY MOTOR REMOTE/ CLOSED AS IS OPEN/ NOTE 13 INJECTION MAN CLOSED PUMP TO HOT LEG (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 8 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NI-122B SAFETY MOTOR T CLOSED AS IS CLOSED INJECTION PUMP TO HOT LEG NI-156 SAFETY M319 INJECTION PUMP TO HOT LEG NI-159 SAFETY INJECTION PUMP TO HOT LEG NI-152B SAFETY MOTOR REMOTE CLOSED AS IS OPEN/ NOTE 13 INJECTION CLOSED PUMP TO HOT LEG NI-153 SAFETY DIAPHRAGM MANUAL CLOSED CLOSED INJECTION PUMP TO HOT LEG NI-165 SAFETY M352 INJECTION PUMP TO COLD LEG NI-167 SAFETY INJECTION PUMP TO COLD LEG (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 9 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NI-169 SAFETY INJECTION PUMP TO COLD LEG NI-171 SAFETY INJECTION PUMP TO COLD LEG NI-162A SAFETY MOTOR REMOTE/ OPEN AS IS OPEN NOTE 13 INJECTION MAN PUMP TO COLD LEG NI-163 SAFETY DIAPHRAGM MANUAL CLOSED CLOSED INJECTION PUMP TO COLD LEG NI180 RHR PUMP TO M336 COLD LEG NI181 RHR PUMP TO COLD LEG NI179 RHR PUMP TO DIAPHRAGM MANUAL/ REM CLOSED CLOSED COLD LEG NI178B RHR PUMP TO MOTOR MANUAL OPEN AS IS OPEN NOTE 13 COLD LEG NI175 RHR PUMP TO M306 COLD LEG NI176 RHR PUMP TO COLD LEG (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 10 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NI174 RHR PUMP TO DIAPHRAGM MANUAL/ REM CLOSED CLOSED COLD LEG NI173A RHR PUMP TO MOTOR MANUAL OPEN AS IS OPEN NOTE 13 COLD LEG NI125 RHR PUMP TO M277 HOT LEG NI129 RHR PUMP TO HOT LEG NI183B RHR PUMP TO MOTOR REMOTE/ CLOSED AS IS OPEN/ NOTE 13 HOT LEG MAN CLOSED NI154 RHR PUMP TO DIAPHRAGM MANUAL CLOSED CLOSED HOT LEG NI184B RHR OUT FROM M278 MOTOR REMOTE/ CLOSED AS IS OPEN/ NOTE 13 SUMP MAN CLOSED NI0861 RHR OUT FROM M278 SUMP NI0862 RHR OUT FROM M278 SUMP NI0863 RHR OUT FROM M278 SUMP NI0864 RHR OUT FROM M278 SUMP NI0869 RHR OUT FROM M278 SUMP NI0870 RHR OUT FROM M278 SUMP (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 11 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NI0871 RHR OUT FROM M278 SUMP NI0872 RHR OUT FROM M278 SUMP NI185A RHR OUT FROM M302 MOTOR REMOTE/ CLOSED AS IS OPEN/ NOTE 13 SUMP MAN CLOSED NI0865 RHR OUT FROM M302 SUMP NI0866 RHR OUT FROM M302 SUMP NI0867 RHR OUT FROM M302 SUMP NI0868 RHR OUT FROM M302 SUMP NI0873 RHR OUT FROM M302 SUMP NI0874 RHR OUT FROM M302 SUMP NI0875 RHR OUT FROM M302 SUMP NI0876 RHR OUT FROM M302 SUMP WL1302A PALS M348 MOTOR T CLOSED AS IS CLOSED DISCHARGE WL1301B PALS MOTOR T CLOSED AS IS CLOSED DISCHARGE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 12 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NS33 CONTAINMENT M362 SPRAY IN NS32A CONTAINMENT MOTOR REMOTE/MAN CLOSED AS IS OPEN/

SPRAY IN CLOSED NS30 CONTAINMENT M370 SPRAY IN NS29A CONTAINMENT MOTOR REMOTE/MAN CLOSED AS IS OPEN SPRAY IN CLOSED NS16 CONTAINMENT M380 SPRAY IN NS15B CONTAINMENT MOTOR REMOTE/MAN CLOSED AS IS OPEN SPRAY IN CLOSED NS13 CONTAINMENT M387 SPRAY IN NS12B CONTAINMENT MOTOR REMOTE/MAN CLOSED AS IS OPEN SPRAY IN CLOSED NS46 RHR TO M369 CONTAINMENT SPRAY NS43A RHR TO MOTOR REMOTE/ CLOSED AS IS OPEN/

CONTAINMENT MAN CLOSED SPRAY NS41 RHR TO M381 CONTAINMENT SPRAY NS-38B RHR TO MOTOR REMOTE/ CLOSED AS IS OPEN/

CONTAINMENT MAN CLOSED SPRAY (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 13 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 WL-64A CONT FLOOR M374 MOTOR T OPEN AS IS CLOSED 15 SUMP INCORE INST. SUMP DISCHARGE WL-65B CONT FLOOR MOTOR T OPEN AS IS CLOSED 15 SUMP INCORE INST. SUMP DISCHARGE WL-264 CONT FLOOR CLOSED AUTO AUTO SUMP INCORE INST. SUMP DISCHARGE WL-39A RCDT GAS M360 MOTOR T OPEN AS IS CLOSED 10 SPACE TO WASTE GAS SYSTEM WL-41B RCDT GAS MOTOR T OPEN AS IS CLOSED 10 SPACE TO WASTE GAS SYSTEM WL-2A RCDT HEAT M375 MOTOR T OPEN AS IS CLOSED 10 EXCHANGER DISCHARGE WL-24 RCDT HEAT EXCHANGER DISCHARGE WL1B RCDT HEAT MOTOR T OPEN AS IS CLOSED 10 EXCHANGER DISCHARGE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 14 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NM3A,C PRESSURIZER M235 MOTOR T OPEN AS IS CLOSED 15 SAMPLE NM6A,C PRESSURIZER MOTOR T CLOSED AS IS CLOSED 15 SAMPLE NM420 PRESSURIZER SPRING CLOSED AUTO AUTO SAMPLE NM7B PRESSURIZER MOTOR T OPEN AS IS CLOSED 15 SAMPLE NM-22A,C REACTOR M309 MOTOR T OPEN AS IS CLOSED 15 COOLANT HOT LEG SAMPLE NM-25A,C REACTOR MOTOR T CLOSED AS IS CLOSED 15 COOLANT HOT LEG SAMPLE NM-421 REACTOR SPRING CLOSED AUTO AUTO COOLANT HOT LEG SAMPLE NM-26B REACTOR MOTOR T OPEN AS IS CLOSED 15 COOLANT HOT LEG SAMPLE NM-72B SAFETY M280 MOTOR T CLOSED AS IS CLOSED 15 INJECTION SAMPLE NM-75B SAFETY MOTOR T CLOSED AS IS CLOSED 15 INJECTION SAMPLE NM-78B SAFETY MOTOR T CLOSED AS IS CLOSED 15 INJECTION SAMPLE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 15 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NM-81B SAFETY MOTOR T CLOSED AS IS CLOSED 15 INJECTION SAMPLE NM-69 SAFETY SPRING CLOSED AUTO AUTO INJECTION SAMPLE NM-82A SAFETY MOTOR T CLOSED AS IS CLOSED 15 INJECTION SAMPLE NM-190A STEAM M335 MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-187A STEAM MOTOR T CLOSED AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-424 STEAM SPRING CLOSED AUTO AUTO GENERATOR BLOWDOWN SAMPLE NM-191B STEAM MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-200B STEAM M338 MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 16 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NM-197B STEAM MOTOR T CLOSED AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-425 STEAM SPRING CLOSED AUTO AUTO GENERATOR BLOWDOWN SAMPLE NM-201A STEAM MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-210A STEAM M340 MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-207A STEAM MOTOR T CLOSED AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-426 STEAM SPRING CLOSED AUTO AUTO GENERATOR BLOWDOWN SAMPLE NM-211B STEAM MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 17 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NM-220B STEAM M341 MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-217B STEAM MOTOR T CLOSED AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE NM-427 STEAM SPRING CLOSED AUTO AUTO GENERATOR BLOWDOWN SAMPLE NM-221A STEAM MOTOR T OPEN AS IS CLOSED 15 GENERATOR BLOWDOWN SAMPLE KC322 COMPONENT M376 COOLING TO RCDT HX KC320A COMPONENT DIAPHRAGM T OPEN CLOSED CLOSED 15 COOLING TO RCDT HX KC332B COMPONENT M355 DIAPHRAGM T OPEN CLOSED CLOSED 15 COOLING FROM RCDT HX KC280 COMPONENT COOLING FROM RCDT HX (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 18 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 KC333A COMPONENT DIAPHRAGM T OPEN CLOSED CLOSED 15 COOLING FROM RCDT HX KC340 KC TO RX M327 VESSEL SUPPORT COOLERS +

RCP COOLERS KC338B KC TO RX MOTOR P OPEN AS IS CLOSED 40 VESSEL SUPPORT COOLERS +

RCP COOLERS KC424B KC TO RX M320 MOTOR P OPEN AS IS CLOSED 40 VESSEL SUPPORT COOLERS +

RCP COOLERS KC279 KC TO RX VESSEL SUPPORT COOLERS +

RCP COOLERS KC425A KC TO RX MOTOR P OPEN AS IS CLOSED 40 VESSEL SUPPORT COOLERS +

RCP COOLERS (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 19 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 KC305B COMPONENT M218 MOTOR T CLOSED AS IS CLOSED 30 COOLING TO EXCESS LETDOWN HX KC315B COMPONENT M217 MOTOR T CLOSED AS IS CLOSED 30 COOLING FROM EXCESS LETDOWN HX KC429B COMP COOLING M322 MOTOR T OPEN AS IS CLOSED 15 TO COMP COOLING DRAIN TRAIN KC47 COMP COOLING TO COMP COOLING DRAIN TRAIN KC430A COMP COOLING MOTOR T OPEN AS IS CLOSED 15 TO COMP COOLING DRAIN TRAIN RN253A NUCLEAR M307 MOTOR P OPEN AS IS CLOSED 30 SERVICE WATER TO REACTOR COOLANT PUMP (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 20 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 RN252B NUCLEAR DIAPHRAGM P OPEN CLOSED CLOSED 30 SERVICE WATER TO REACTOR COOLANT PUMP Deleted Per 2012 Update RN1102 NUCLEAR SPRING CLOSE AUTO AUTO SERVICE WATER FROM REACTOR COOLANT PUMP RN276A NUCLEAR M315 MOTOR P OPEN AS IS CLOSED 30 SERVICE WATER FROM REACTOR COOLANT PUMP RN277B NUCLEAR DIAPHRAGM P OPEN CLOSED CLOSED 30 SERVICE WATER FROM REACTOR COOLANT PUMP RN1103 NUCLEAR M315 SPRING CLOSED AUTO AUTO SERVICE WATER FROM REACTOR COOLANT PUMP (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 21 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 VP17A INCORE M213 DIAPHRAGM T CLOSED CLOSED CLOSED INSTRUMENTA-TION ROOM PURGE IN VP18B INCORE DIAPHRAGM T CLOSED CLOSED CLOSED INSTRUMENTA-TION ROOM PURGE IN VP19A INCORE M138 DIAPHRAGM T CLOSED CLOSED CLOSED INSTRUMENTA-TION ROOM PURGE OUT VP20B INCORE DIAPHRAGM T CLOSED CLOSED CLOSED INSTRUMENTA-TION ROOM PURGE OUT VP2A UPPER M367 DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP1B UPPER DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP4A UPPER M454 DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP3B UPPER DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 22 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 VP7A LOWER M357 DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP6B LOWER DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP9A LOWER M456 DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP8B LOWER DIAPHRAGM T CLOSED CLOSED CLOSED COMPARTMENT PURGE INLET VP10A CONTAINMENT M368 DIAPHRAGM T CLOSED CLOSED CLOSED PURGE EXHAUST VP11B CONTAINMENT DIAPHRAGM T CLOSED CLOSED CLOSED PURGE EXHAUST VP12A CONTAINMENT M455 DIAPHRAGM T CLOSED CLOSED CLOSED PURGE EXHAUST VP13B CONTAINMENT DIAPHRAGM T CLOSED CLOSED CLOSED PURGE EXHAUST VP15A CONTAINMENT M119 DIAPHRAGM T CLOSED CLOSED CLOSED PURGE VP16B CONTAINMENT DIAPHRAGM T CLOSED CLOSED CLOSED PURGE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 23 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 CF26A,B FEEDWATER M440 PISTON S OPEN AS IS CLOSED 10 CF137 FEEDWATER MANUAL LOCKED CLOSED AS IS CLOSED CLOSED CF28A,B FEEDWATER M308 PISTON S OPEN AS IS CLOSED 10 CF136 FEEDWATER MANUAL LOCKED CLOSED AS IS CLOSED CLOSED CF30A,B FEEDWATER M262 PISTON S OPEN AS IS CLOSED 10 CF135 FEEDWATER MANUAL LOCKED CLOSED AS IS CLOSED CLOSED CF-35A,B FEEDWATER M153 PISTON S OPEN AS IS CLOSED 10 CF134 FEEDWATER MANUAL LOCKED CLOSED AS IS CLOSED CLOSED SM-1A,B MAIN STEAM M441 PISTON P OPEN CLOSED CLOSED 8 SV-2 MAIN STEAM SPRING CLOSED AUTO AUTO SV-3 MAIN STEAM SPRING CLOSED AUTO AUTO SV-4 MAIN STEAM SPRING CLOSED AUTO AUTO SV-5 MAIN STEAM SPRING CLOSED AUTO AUTO SV-6 MAIN STEAM SPRING CLOSED AUTO AUTO SV-1A,B MAIN STEAM PISTON CLOSED CLOSED CLOSED 60 SM-9A,B MAIN STEAM DIAPHRAGM P CLOSED CLOSED CLOSED 8 Deleted Per 2003 Update SM-101 MAIN STEAM DIAPHRAGM OPEN CLOSED CLOSED Table 6-114 Note 10 (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 24 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 Deleted Per 2005 Update SA-1 MAIN STEAM M393 MANUAL OPEN OPEN OPEN Table 6-114 Note 12 SA-77 MAIN STEAM MANUAL OPEN OPEN OPEN Table 6-114 Note 12 SM-3A,B MAIN STEAM PISTON P OPEN CLOSED CLOSED 8 SV-8 MAIN STEAM SPRING CLOSED AUTO AUTO SV-9 MAIN STEAM SPRING CLOSED AUTO AUTO SV-10 MAIN STEAM SPRING CLOSED AUTO AUTO SV-11 MAIN STEAM SPRING CLOSED AUTO AUTO SV-12 MAIN STEAM SPRING CLOSED AUTO AUTO SV-7A,B,C MAIN STEAM PISTON CLOSED CLOSED CLOSED 60 SM10A,B MAIN STEAM DIAPHRAGM P CLOSED CLOSED CLOSED 8 Deleted Per 2003 Update SM 95 MAIN STEAM DIAPHRAGM OPEN CLOSED CLOSED Table 6-114 Note 10 Deleted Per 2005 Update SA-2 MAIN STEAM M261 MANUAL OPEN OPEN OPEN Table 6-114 Note 12 SA-78 MAIN STEAM MANUAL OPEN OPEN OPEN Table 6-114 Note 12 SM-5A,B MAIN STEAM PISTON P OPEN CLOSED CLOSED 8 (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 25 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 SV-14 MAIN STEAM SPRING CLOSED AUTO AUTO SV-15 MAIN STEAM SPRING CLOSED AUTO AUTO SV-16 MAIN STEAM SPRING CLOSED AUTO AUTO SV-17 MAIN STEAM SPRING CLOSED AUTO AUTO SV-18 MAIN STEAM SPRING CLOSED AUTO AUTO SV13A,B MAIN STEAM PISTON CLOSED CLOSED CLOSED 60 SM11A,B MAIN STEAM DIAPHRAGM P CLOSED CLOSED CLOSED 8 Deleted Per 2003 Update SM89 MAIN STEAM DIAPHRAGM OPEN CLOSED CLOSED Note 10 Deleted Per 2005 Update SM-7A,B MAIN STEAM M154 PISTON P OPEN CLOSED CLOSED 8 SV-20 MAIN STEAM SPRING CLOSED AUTO AUTO SV-21 MAIN STEAM SPRING CLOSED AUTO AUTO SV-22 MAIN STEAM SPRING CLOSED AUTO AUTO SV-23 MAIN STEAM SPRING CLOSED AUTO AUTO SV-24 MAIN STEAM SPRING CLOSED AUTO AUTO SV-19A,B MAIN STEAM PISTON CLOSED CLOSED CLOSED 60 SM12A,B MAIN STEAM DIAPHRAGM P CLOSED CLOSED CLOSED 8 Deleted Per 2003 Update (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 26 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 SM 83 MAIN STEAM DIAPHRAGM OPEN CLOSED CLOSED Note 10 Table 6-114 Deleted Per 2005 Update YM-116 DEMINERALIZ- M337 ED WATER YM-115B DEMINERALIZ- MOTOR T OPEN AS IS CLOSED 15 ED WATER RV33B CONTAINMENT M240 MOTOR P OPEN AS IS CLOSED 60 VENTILATION COOLING WATER IN RV32A CONTAINMENT MOTOR P OPEN AS IS CLOSED 60 VENTILATION COOLING WATER IN RV445 CONTAINMENT SPRING CLOSED AUTO AUTO VENTILATION COOLING WATER IN 1RV481 CONTAINMENT 1M385 SPRING CLOSED AUTO AUTO VENTILATION COOLING WATER IN 2RV480 CONTAINMENT 2M385 SPRING CLOSED AUTO AUTO VENTILATION COOLING WATER IN (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 27 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 1RV80B CONTAINMENT 1M385 DIAPHRAGM P OPEN CLOSED CLOSED 30 VENTILATION COOLING WATER IN 1RV79A CONTAINMENT DIAPHRAGM P OPEN CLOSED CLOSED 30 VENTILATION COOLING WATER IN 2RV80B CONTAINMENT 2M385 DIAPHRAGM P OPEN CLOSED CLOSED 30 VENTILATION COOLING WATER IN 2RV79A CONTAINMENT DIAPHRAGM P OPEN CLOSED CLOSED 30 VENTILATION COOLING WATER IN 2RV480 CONTAINMENT SPRING CLOSED AUTO AUTO VENTILATION COOLING WATER IN RV101A CONTAINMENT M390 DIAPHRAGM P OPEN CLOSED CLOSED 30 VENTILATION COOLING WATER OUT RV102B CONTAINMENT DIAPHRAGM P OPEN CLOSED CLOSED 30 VENTILATION COOLING WATER OUT (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 28 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 RV484 CONTAINMENT SPRING CLOSE AUTO AUTO VENTILATION COOLING WATER OUT RV76A CONTAINMENT M279 MOTOR P OPEN AS IS CLOSED 60 VENTILATION COOLING WATER OUT RV77B CONTAINMENT MOTOR P OPEN AS IS CLOSED 60 VENTILATION COOLING WATER OUT RV446 CONTAINMENT SPRING CLOSED AUTO AUTO VENTILATION COOLING WATER OUT VI40 INSTRUMENT M220 AIR VI129B INSTRUMENT MOTOR P OPEN AS IS CLOSED 15 AIR VS13 STATION AIR M219 VS12B STATION AIR MOTOR T CLOSED AS IS CLOSED 15 VB50 BREATHING AIR M215 VB49B BREATHING AIR MOTOR T CLOSED AS IS CLOSED 15 NSSV5560 CONTAINMENT M118 MOTOR OPEN AS IS OPEN PRESSURE SENSOR (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 29 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NSSV5570 CONTAINMENT M239 MOTOR OPEN AS IS OPEN PRESSURE SENSOR NSSV5590 CONTAINMENT M402 MOTOR OPEN AS IS OPEN PRESSURE SENSOR NSSV5580 CONTAINMENT M313 MOTOR OPEN AS IS OPEN PRESSURE SENSOR NSSV5550 NARROW M402A SOLENOID T OPEN CLOSED CLOSED 2 RANGE CONTAINMENT PRESSURE NSSV5551 NARROW SOLENOID T OPEN CLOSED CLOSED 2 RANGE CONTAINMENT PRESSURE VX33B CONTAINMENT M378 DIAPHRAGM T CLOSED CLOSED CLOSED 5 SAMPLE OUT VX31A CONTAINMENT DIAPHRAGM T CLOSED CLOSED CLOSED 5 SAMPLE OUT VX34 CONTAINMENT MANUAL LOCKED/ CLOSED CLOSED CLOSED SAMPLE OUT CLOSED VX30 CONTAINMENT M325 SAMPLE IN VX40 CONTAINMENT MANUAL LOCKED/ CLOSED AS IS CLOSED SAMPLE IN CLOSED CA62A AUXILIARY M156 MOTOR OPEN AS IS OPEN FEEDWATER (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 30 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 CA66AC AUXILIARY MOTOR OPEN AS IS OPEN FEEDWATER CF126B AUXILIARY MOTOR S CLOSED AS IS CLOSED 10 FEEDWATER CF-183 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED BW-3 AUXILIARY MANUAL: LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED YA-47 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED CA54AC AUXILIARY M286 MOTOR OPEN AS IS OPEN FEEDWATER CA58A AUXILIARY MOTOR OPEN AS IS OPEN FEEDWATER CF127B AUXILIARY MOTOR S CLOSED AS IS CLOSED 10 FEEDWATER CF-184 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED BW-12 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED YA-48 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED CA46B AUXILIARY M3100 MOTOR OPEN AS IS OPEN FEEDWATER CA50B AUXILIARY MOTOR OPEN AS IS OPEN FEEDWATER (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 31 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 CF128B AUXILIARY MOTOR S CLOSED AS IS CLOSED 10 FEEDWATER CF-185 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED BW-21 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED YA-49 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED CA38B AUXILIARY M465 MOTOR OPEN AS IS OPEN FEEDWATER CA42B AUXILIARY MOTOR OPEN AS IS OPEN FEEDWATER CF129B AUXILIARY MOTOR S CLOSED AS IS CLOSED 10 FEEDWATER CF-186 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED BW-30 AUXILIARY MANUAL LOCKED CLOSED AS IS CLOSED FEEDWATER CLOSED YA-50 MANUAL LOCKED CLOSED AS IS CLOSED CLOSED FW11 REFUELING M358 MANUAL LOCKED CLOSED AS IS CLOSED CAVITY TO RW PUMP FW13 REFUELING MANUAL LOCKED CLOSED AS IS CLOSED CAVITY TO RW PUMP (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 32 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 1FW67/ REFUELING M377 2FW63 CAVITY TO RW PUMP FW5 REFUELING CAVITY FROM TW TANK FW4 REFUELING MANUAL LOCKED CLOSED CAVITY FROM TW TANK VE11 HYDROGEN M331 PURGE IN VE10A HYDROGEN MOTOR T CLOSED AS IS CLOSED 15 PURGE IN /OPEN VE-5A HYDROGEN M346 MOTOR T CLOSED AS IS CLOSED 15 PURGE OUT /OPEN VE-6B HYDROGEN MOTOR T CLOSED AS IS CLOSED 15 PURGE OUT /OPEN FUEL M354 BOLTED CLOSED AS IS CLOSED TRANSFER CANAL NC-141 RCP MOTOR M326 MANUAL LOCKED CLOSED AS IS CLOSED DRAIN TANK TO WASTE OIL STORAGE NC-142 RCP MOTOR MANUAL LOCKED CLOSED AS IS CLOSED DRAIN TANK TO WASTE OIL STORAGE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 33 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 NC261 RCP MOTOR DRAIN TANK TO WASTE OIL STORAGE WL321A CONT VENT M221 MOTOR T OPEN AS IS CLOSED 15 UNITS COND.

DRAINS TO DRAIN TANK WL322B CONT VENT MOTOR T OPEN AS IS CLOSED 15 UNITS COND.

DRAINS TO DRAIN TANK WL385 CONT VENT UNITS COND.

DRAINS TO DRAIN TANK VI161 INSTRUMENT M359 AIR VI160B INSTRUMENT MOTOR P OPEN AS IS CLOSED 15 AIR VI149 INSTRUMENT M386 AIR VI148B INSTRUMENT MOTOR T OPEN AS IS CLOSED 15 AIR VI362A INSTRUMENT MOTOR T OPEN AS IS CLOSED 15 AIR VI124 INSTRUMENT M317 AIR (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 34 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 VI150B INSTRUMENT MOTOR P OPEN AS IS CLOSED 15 AIR VQ-1A CONTAINMENT M243 DIAPHRAGM T CLOSED CLOSED CLOSED 3 AIR RELEASE VQ-2B CONTAINMENT DIAPHRAGM T CLOSED CLOSED CLOSED 3 AIR RELEASE VQ-6A CONTAINMENT M384 DIAPHRAGM T CLOSED CLOSED CLOSED 3 AIR ADDITION VQ-5B CONTAINMENT DIAPHRAGM T CLOSED CLOSED CLOSED 3 AIR ADDITION NC-196A REACTOR M361 MOTOR T CLOSED AS IS CLOSED COOLANT PUMP MOTOR OIL SUPPLY NC-195B REACTOR MOTOR T CLOSED AS IS CLOSED COOLANT PUMP MOTOR OIL SUPPLY NC259 REACTOR COOLANT PUMP MOTOR OIL SUPPLY 1RF823 FIRE 1M353 PROTECTION HEADER 1RF821A FIRE DIAPHRAGM T CLOSED CLOSED CLOSED 15 PROTECTION HEADER (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 35 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 1RF834 FIRE 2M353 PROTECTION HEADER 1RF832A FIRE DIAPHRAGM T CLOSED CLOSED CLOSED 15 PROTECTION HEADER 1NV840 AUXILIARY 1M228 DIAPHRAGM CLOSED CLOSED SPRAY TO PRESSURIZER NV841 AUXILIARY M228 SPRAY TO PRESSURIZER 2NV1053 AUXILIARY 2M228 MANUAL LOCKED/ CLOSED AS IS CLOSED SPRAY TO CLOSED PRESSURIZER NV1002 STANDBY M342 CLOSED CLOSED MAKEUP PUMP TO RCS SEALS NV849A,C STANDBY MOTOR T CLOSED AS IS CLOSED 15 MAKEUP PUMP TO RCS SEALS ICE BASKET M383 WATER ADDITION ICE BASKET WATER ADDITION MIMV6980 ILRT TEST 1M255A/ MANUAL CLOSED AS IS CLOSED CONNECTION 2E118A (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 36 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 MIMV7010 ILRT TEST MANUAL CLOSED AS IS CLOSED CONNECTION MIMV6990 ILRT TEST 1M255B/ MANUAL CLOSED AS IS CLOSED CONNECTION 2E118B MIMV7020 ILRT TEST MANUAL CLOSED AS IS CLOSED CONNECTION MIMV7000 ILRT TEST 1M255C/ MANUAL CLOSED AS IS CLOSED CONNECTION 2E118C MIMV7030 ILRT TEST MANUAL CLOSED AS IS CLOSED CONNECTION MISV6870 CONTAINMENT M239A SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV6890 CONTAINMENT SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV6880 CONTAINMENT M239B SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV6900 CONTAINMENT SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV6910 CONTAINMENT M239C SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV6930 CONTAINMENT SV OPEN CLOSED OPEN HYDROGEN SAMPLE (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 37 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 MISV6920 CONTAINMENT M239D SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV6940 CONTAINMENT SV OPEN CLOSED OPEN HYDROGEN SAMPLE MISV5581 RADIATION M323A SV T OPEN CLOSED CLOSED MONITORING MISV5580 RADIATION SV T OPEN CLOSED CLOSED MONITORING MISV5583 RADIATION M323B SV T OPEN CLOSED CLOSED MONITORING MISV5582 RADIATION SV T OPEN CLOSED CLOSED MONITORING IAECV536 UPPER C392 NA NA CLOSED CLOSED CLOSED NA 0 PERSONNEL LOCK Rx DOOR RELIEF (CONT SIDE)

IAECV537 LOWER C152 NA NA CLOSED CLOSED CLOSED NA 0 PERSONNEL LOCK Rx DOOR RELIEF (CONT SIDE)

IAECV538 UPPER C392 NA NA CLOSED CLOSED CLOSED NA 0 PERSONNEL LOCK Rx DOOR RELIEF (PAL SIDE)

(13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-113 (Page 38 of 38)

Valve Position Actuation Isolation Penetration Pen Valve Signal Time (Sec)

Valve No Name Number Operator Note 1 Normal Fail Incident Note 9 IAECV539 LOWER C152 NA NA CLOSED CLOSED CLOSED NA 0 PERSONNEL LOCK Rx DOOR RELIEF (PAL SIDE)

(13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-114 (Page 1 of 3)

Table 6-114. Containment Piping Penetrations and Isolation Valve Data. (Notes to Table 6-111, Table 6-112 and Table 6-113.)

NOTES:

1. Definition of Actuation Signals
a. S - Safety Injection Signals (T signals also activated by S signal)
b. T - Containment Isolation Signal (Phase A containment isolation)
c. P - Containment High-High Pressure Signal 2.

CA - Auxiliary Feedwater MI - Miscellaneous Instrumentation NB - Boron Recycle System CF - Feedwater System NC - Reactor Coolant System BB - Steam Generator Blowdown Recycle System NV - Chemical and Volume Control KF - Spent Fuel Cooling System System KC - Component Cooling System VS - Station Air System NI - Safety Injection System VI - Instrument Air System ND - Residual Heat Removal System VB - Breathing Air System IAE - Containment Personnel Air Lock VE - Annulus Ventilation System WL - Liquid Waste Recycle System VP - Containment Purge Ventilation System VX - Containment Air Return Exchange and Hydrogen Skimmer System NS - Containment Spray System RV - Containment Ventilation Cooling Water System RN - Nuclear Service Water System NM - Sampling System YM - Demineralized Water System SM - Main Steam System NF - Ice Condenser System RF - Fire Protection System VQ - Containment Air Release and Addition System FW - Refueling Water System SV - Main Steam Vent to Atmosphere (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-114 (Page 2 of 3)

3. Thru line leak class 1.

Leak Ref:

Thru line leak class 1 is characteristic of valves which would not release containment atmosphere during a LOCA if valve leakage did occur. Each valve was reviewed separately and was characteristic of one of the following:

a. Piping and equipment external to the outer isolation valve are seismically designed, terminating in either normally closed seismic valve, seismic non-radioactive tank or a closed loop. The system is designed in accordance with Quality Group B standards and designed to at least the primary Containment pressure and temperature. The piping is protected from pipe whip, missiles, jet forces. The allowable protection types are documented in Section 3.6.5.2.
b. Same as statement (3a) except the piping and equipment is internal to the outer isolation valve.
c. deleted
d. deleted
e. The fuel transfer canal terminates at the bottom of the spent fuel pool. The minimum water level in the spent fuel pool is such that leakage from containment could only occur during the time that containment pressure exceeds 14.1 psig.
f. The hydrogen purge out terminates in the Annulus and thus does not represent a bypass leakage path.
g. Impulse line and transmitter are Type C leak rate tested with no detectable leakage allowed.
h. The ice condenser, ice blowing out and ice basket water addition terminate in the annulus and thus do not represent a bypass leakage path.

Thru line leak class 2.

Non-seismic external piping. These valves are a source of bypass leakage when a seismic event is postulated concurrent with a LOCA.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-114 (Page 3 of 3)

4. Containment isolation valves and operators will be designed to withstand internal conditions of the process piping and external conditions due to Post-LOCA temperature, pressure, humidity, and radiation.
5. Refer to Figure 6-172 for an explanation of penetration class.
6. Line size is nominal diameter.
7. Test type:

B: Type B test as defined by 10CFR Part 50, Appendix J C: Type C test as defined by 10CFR Part 50, Appendix J N: No local test is required

8. Test Pressure Direction:

Pressure Application Direction relative to expected pressure (Type C only)

9. Max Isolation Time (sec):

The specified containment isolation valve closure times are nominal valves, and were primarily based on ANSI N271-1976.

10. The assured method of closing these valves is via local, manual operation. This valve does not have safety grade controls or an automatic signal.
11. Containment isolation valves NSSV5560, NSSV5570, NSSV5580 and NSSV5590 for penetrations M118, M239, M313 and M402, respectively, are open during type C leak test which challenges the closed loop pressure transmitters.
12. This value is manually closed as needed during certain accidents.
13. Refer to Table 6-123 for ECCS valve stroke times.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-115 (Page 1 of 1)

Table 6-115. Bi directional Leakage Test Results for Typical Diaphragm Value TEST DESCRIPTION A 2" diaphragm valve was flanged on both sides. Test connections were provided on both flanges. A leak was imposed by inserting a 26 gauge wire under the valve seat.

Twelve (12) test runs with different leak magnitudes (by changing the torque on the valve seat) were performed at 14.2 PSIG.

D E

% Leak Rate Repeatability A B C Left Direction Right Direction Right Direction B A CB D= x100 E= x100 Leak Rate Leak Rate Leak Rate C C Run (SCCM) (SCCM) Repeated (SCCM) (%) (%)

1 146 146 0.

2 160 160 0.

3 178 185 3.780 4 195 197 1.011 5 213 224 4.910 6 239 241 0.829 7 256 256 0.

8 283 278 281 1.766 1.060 9 307 300 303 2.280 0.990 10 332 324 326 2.409 0.613 11 357 348 350 2.521 0.571 12 382 371 375 2.880 1.066 (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-116 (Page 1 of 1)

Table 6-116. Deleted Per 2008 Update (13 APR 2008)

McGuire Nuclear Station UFSAR Table 6-117 (Page 1 of 2)

Table 6-117. Parameters Used to Determine Hydrogen Generation Reactor Thermal Power 3,411 Mwt Reactor Operating Time 980 Days Containment Free Volume 1.170E+6 Deleted Per 2009 Update Zirconium Weight 45,680 lbs Deleted Per 2009 Update Hydrogen Dissolved in Primary Coolant 483 scf Corrodable Metals Aluminum, Zinc Deleted Per 2009 Update Zinc Corrosion Rate Design Curve Figure 6-198 Hydrogen Generated From Radiolysis Core Radiolysis Sump Radiolysis

1. Sources
a. Percent of total halogens retained 50 50 in solution
b. Percent of total noble gases 0 0 retained in solution
c. Percent of other fission products 99 1 retained in solution
2. Energy Distribution
a. Percent of total decay energy - 50 50 Gamma
b. Percent of total decay energy - 50 50 Beta
3. Energy Absorption by the Solution
a. Percent of gamma energy 7.4 100 absorbed
b. Percent of beta energy absorbed 0 100
4. Molecules H2 Produced per 100 ev 0.44 0.30 Energy Absorbed Corrodable Metal Inventory in Containment Aluminum Inventory in Containment Representative Sources of Aluminum Westinghouse NSSS Equipment Electrical Equipment (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-117 (Page 2 of 2)

Seismic Instrumentation Fisher Control Valves Cont. Floor Sump Pump Motor Inc. Inst. Tunnel Sump Pump Motor Lower Cont. Cooling Unit Motors Aluminum Valve Tags Welding Receptacle Resemount Transmitters DRPI Backshells Welding Receptacle Welding Machines CRDM Cable Connectors Ice Condenser Temp. switches Lower Cont. Cooling Fans (VL)

Ice Condenser Receptacle Covers

  • The exposed surface area of aluminum in Containment is assumed to be 1500 square feet and that value is used in the hydrogen generation analysis to account for any aluminum additions to Containment in the future.

Zinc Inventory in Containment Representative Sources of Zinc Ice Condenser Air Ducts Ice Baskets, Lattice Frames, etc.

Miscellaneous Containment Zinc

  • To account for any zinc additions to Containment in the future, it is assumed that the zinc exposed surface area is 1,000,000 ft2 and that value is used in the hydrogen generation analysis.
  • The Zinc and Aluminum inventories were used in the original post-LOCA Hydrogen generation analyses. The analyses is no longer part of the current licensing bases. Revision 3 of Regulatory Guide 1.7 does state that materials within containment that would yield hydrogen gas by corrosion from the ECCS or containment spray solutions should be identified, and their use should be limited, as much as practicable.

Aluminum inventories must further be limited, due to the potential for ECCS strainer chemical effects and resultant potential headloss.

    • Table contains "historical" documentation (Refer to 6.1.7)

(24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-118 (Page 1 of 1)

Table 6-118. Total Hydrogen Generation 2. (TID-14844 Release Model - 5.0 Percent Zirconium-Water Reaction)

Day Sump Core Aluminum Zinc Total (1) H2 Total Rate Total Rate Total Rate Total Rate Total Rate Volume (scfm) (scf) (scfm) (scf) (scfm) (scf) (scfm) (scf) (scfm) (scf) Perecent 0.5 1.74 2315 2.05 2060 0.17 121 1.79 1320 5.75 25241 2.22 1.0 1.04 3294 1.71 3390 0.17 243 1.84 2615 4.76 28967 2.53 2.0 0.66 4483 1.42 5605 0.17 485 1.76 5166 4.01 35163 3.03 5.0 0.35 6466 0.99 10658 0.17 1212 1.69 12626 3.21 50387 4.25 8.0 0.27 7771 0.82 14520 0.17 1940 1.63 19800 2.88 63455 5.27 10.0 0.23 8491 0.74 16770 0.17 2425 1.57 24423 2.71 71534 5.89 12.0 0.21 9130 0.70 18856 0.17 2909 1.54 28920 2.62 79241 6.47 14.0 0.19 9707 0.66 20817 0.17 3394 1.49 33288 2.52 86631 7.01 18.0 0.16 10708 0.60 24447 0.17 4364 1.41 41644 2.34 100587 8.03 24.0 0.13 11933 0.53 29320 0.17 5820 1.27 53222 2.10 119721 9.38 30.0 0.11 12929 0.49 33666 0.17 7278 1.34 63663 2.10 136961 10.56 Note:

1. Includes hydrogen generated by the zirconium-water reaction and dissolved in the primary coolant.
2. Table contains historical documentation (Refer to 6.1.7).

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-119 (Page 1 of 1)

Table 6-119. Deleted Per 1991 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-120 (Page 1 of 1)

Table 6-120. Fission Product Decay Deposition in Sump Solution 1 1 PERCENT OTHER FISSION 50 PERCENT HALOGENS PRODUCTS TOTAL Time After Integrated Energy Energy Release Integrated Energy Energy Release Integrated Energy Reactor Trip Energy Release Release watt- Rate watts/MWt Release watt- Rate watts/MWt x Release watt-days Rate watt/MWt day/MWt x 10-2 x 10-1 day/MWt x 10 -2 10-1 day/MWt x 10-2 1 145 4.27 3.78 0.536 13.23 0.491 3 49.4 5.88 2.90 1.18 7.85 0.787 5 31.0 6.65 2.59 1.73 5.69 0.923 10 18.2 7.82 2.2 2.92 4.03 1.07 20 7.63 9.03 1.77 4.89 2.53 1.39 30 3.22 9.54 1.49 6.51 1.81 1.61 40 1.36 9.76 1.30 7.90 1.44 1.77 60 0.241 9.89 1.98 10.3 1.10 2.02 80 0.043 9.91 0.985 12.3 0.910 2.22 100 0.008 9.92 0.822 14.0 0.823 2.39 Note(s):

1. Table contains historical documentation for Section 6.2.6.4 (Refer to 6.1.7).

(`10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-121 (Page 1 of 1)

Table 6-121. Total Hydrogen Generation - Westinghouse Basis (TID Release Model - Noble Gas in Core; 0.5 Percent Zirconium-Water Reaction 2)

Total Sump Total Core Total Corrosion Grand Total1 Rate Total H2 Rate Total H2 Rate Total H2 Rate Total H2 Vol.

Day SCFMx10E+2 SCFMx10E-4 SCFMx10 SCFx10E-4 SCFMx10E+2 SCFx10E-3 SCFMx10 SCFx10E-4 Pct 1 96.7 0.367 11.6 0.256 3.98 0.076 21.6 0.922 0.87 2 55.8 0.420 9.43 0.405 3.98 0.134 15.4 1.18 1.10 5 30.1 0.639 7.54 0.763 3.98 0.306 10.9 1.72 1.60 10 21.3 0.819 6.39 1.26 3.98 0.592 8.92 2.43 2.23 20 13.4 1.06 5.06 2.08 3.98 1.17 6.80 3.55 3.21 30 9.57 1.22 4.24 2.74 3.98 1.74 5.59 4.43 3.96 40 7.61 1.35 3.71 3.31 3.98 2.31 4.87 5.18 4.59 60 5.83 1.54 3.07 4.28 3.98 3.46 4.05 6.45 5.62 80 4.97 1.69 2.66 5.10 3.98 4.60 3.55 7.54 6.48 100 4.35 1.81 2.34 5.82 3.98 5.75 3.17 8.51 7.23 Note:

1. Include hydrogen generated by the zirconium-water reaction and primary coolant system.
2. Table contains historical documentation (Refer to 6.1.7).

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-122 (Page 1 of 1)

Table 6-122. Total Hydrogen Generation - NRC Basis (TID-14844 Release Model - 1.5% Zirconium-Water Reaction 2)

Total Sump Total Core Total Corrosion Grand Total1 Rate Total H2 Rate Total H2 Rate Total H2 Rate Total H2 Vol.

Day SCFMx10E+2 SCFMx10E-4 SCFMx10 SCFx10E-4 SCFMx10E+2 SCFx10E-3 SCFMx10 SCFx10E-4 Pct 1 181.0 0.612 17.1 0.371 5.22 0.0928 33.8 0.164 1.53 2 93.1 0.783 14.2 0.592 5.22 0.168 24.0 0.204 1.89 5 50.1 1.06 11.4 1.13 5.22 0.394 17.0 0.288 2.64 10 35.5 1.36 9.74 1.89 5.22 0.769 13.8 0.398 3.59 20 23.3 1.77 7.76 3.14 5.22 1.52 10.5 0.571 5.04 30 15.9 2.04 6.50 4.16 5.22 2.26 8.62 0.707 6.13 40 12.7 2.24 5.69 5.03 5.22 3.03 7.48 0.822 7.02 60 9.72 2.56 4.71 6.52 5.22 4.53 6.20 1.018 8.49 80 8.28 2.82 4.08 7.78 5.22 6.03 5.43 1.185 9.69 100 7.25 3.04 3.59 8.88 5.22 7.54 4.83 1.332 10.70 Note:

1. Include hydrogen generated by the zirconium-water reaction and primary coolant system.
2. Table contains historical documentation (Refer to 6.1.7).

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-123 (Page 1 of 3)

Table 6-123. Emergency Core Cooling System Component Parameters Component Parameters Cold Leg Injection Accumulators Number 4 Design Pressure, psig 700 Design Temperature, °F 300 Operating Temperature, °F 60-150 Normal Operating Pressure, psig 590-633 Minimum Operating Pressure, psig 585 Total Volume, ft3 1363 each Minimum Water Volume, ft3 918 each 3

Maximum N2 Gas Volume ft 445 each Boric Acid Concentration, Nominal, fuel cycle ppm specific value given in Core Operating Limits Report Relief Valve Setpoint, psig 700 Centrifugal Charging Pumps Number 2 Design Pressure, psig 2800 Design Temperature, °F 300 1

Design Flow Rate, gpm 150 Design Head, ft. 5800 Maximum Flow Rate, gpm 560 Head at Maximum Flow Rate, ft. 1400 Discharge Head at Shutoff, ft. 6000 3

Motor Rating, bhp 600 Safety Injection Pumps Number 2 Design Pressure, psig 1750 Design Temperature, °F 300 Design Flow Rate, gpm 400 Design Head, ft. 2600 Maximum Flow Rate, gpm 675 Head at Maximum Flow Rate, ft. 1750 (05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-123 (Page 2 of 3)

Component Parameters Discharge Pressure at Shutoff, psig 1520 Motor Rating, bhp+ 400 Residual Heat Removal Pumps & Refer to Section 5.5.7 for parameter Heat Exchangers information Valves All Motor-Operated Valves which Maximum Opening or Closing Time must Function on safety injection ("S")

signal

1. up to and including 8 inches Time, sec 102
2. over 8 inches Time, sec. Not Applicable4 All Other Motor-Operated Valves Maximum Opening or Closing Time
1. up to and including 8 inches Time, sec. 102
2. over 8 inches Inches per minute 492 Leakage
1. Conventional Globe Valves Disc Leakage, cc/hr/in of nominal pipe 3 size Backseat Leakage cc/hr/in of stem 10 diameter
2. Gate Valves Disc Leakage, cc/hr/in of nominal pipe 3 size Backseat Leakage cc/hr/in of stem 10 diameter
3. Check Valves Disc Leakage, cc/hr/in of nominal pipe 3 size
4. Diaphragm Valves Disc Leakage None
5. Pressure Relief Valves Disc Leakage, cc/hr/in of nominal pipe 3 size
6. Accumulator Check Valves Disc Leakage, cc/hr/in of nominal pipe 3 size (05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-123 (Page 3 of 3)

Component Parameters Note:

1. Includes miniflow
2. Stroke times in excess of these valves are permissible as supported by formal design analyses
3. 1.15 Service factor not included
4. The Cold Leg Accumulator block valves are administratively controlled open prior to exceeding 1000 psig (05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-124 (Page 1 of 1)

Table 6-124. Normal Operating Status of Emergency Core Cooling System Components for Core Cooling Number of Safety Injection Pumps Operable 2 Number of Charging Pumps Operable 2 Number of Residual Heat Removal Pumps Operable 2 Number of Residual Heat Exchangers Operable 2 Refueling Water Storage Tank Volume, Gal., minimum 383,146 Boron Concentration in Refueling Water Storage Tanks, minimum ppm fuel cycle specific value given in Core Operating Limits Report Boron Concentration in Cold Leg Accumulator, minimum ppm fuel cycle specific value given in Core Operating Limits Report Number of Accumulators 4 Minimum Indicated Cold Leg Accumulator Pressure, psig 585 3

Minimum Cold Leg Accumulator Water Volume, ft 918 System Valves, Interlocks, and Piping Required for the Above Components which All are Operable (30 NOV 2012)

McGuire Nuclear Station UFSAR Table 6-125 (Page 1 of 3)

Table 6-125. Sequence of Operations: Injection to Cold Leg Recirculation The following steps occur automatically when 2 out of 3 level instruments indicate an FWST level at or below the Low Level setpoint in conjunction with an "S" signal:

A1. The Containment Sump Isolation Valves (NI-185A and NI-184B) OPEN.

A2. Once the Containment Sump Isolation Valves are FULLY OPEN, the FWST Isolation Valves to the ND Pumps (ND-19A and ND-4B) CLOSE.

The following steps would be taken by the Operators when terminating the Injection Mode and starting the Cold Leg Recirculation Mode (at FWST Lo Level Alarm):

M1. Monitor Foldout Page.

M2. Operator verifies Containment Sump Level is adequate to supply suction to ND Pumps.

M3. Operator resets Safety Injection signal.

M4. Operator resets D/G Load Sequencers.

M5. Operator aligns the "A" and "B" Trains of ND for Recirc as follows:

a. Operator checks the Containment Sump valves to ND Pumps (NI-185A and NI-184B) are OPEN.
b. Operator enables the power disconnect and CLOSES the FWST Supply to ND Pumps (FW-27A).
c. Operator checks the ND Pumps Suction Valves from the FWST (ND-19A and ND-
48) are CLOSED.
d. Operator verifies that any ND Pump is running.

The remaining manual actions to complete the switchover are delayed until the FWST Low-Low Level is reached. At that time, the Operator immediately resumes the Transfer Procedure to re-align the suctions for the medium head and high head injection pumps (the NI and NV Pumps) from the FWST to the suction supply from the ND Pumps ("Piggyback" alignment).When the "FWST Low-Low" alarm is received, completion of these steps must be performed without delay to prevent vortex-induced air entrapment into the suction piping of the medium and high head injection pumps. In the interim period (after the ND pumps are aligned to the Sump, but before the FWST Low-Low Level alarm being received), the Operators may perform the manual actions to align the Containment Spray (NS) System as follows (note: the procedure will align both trains of NS to the Containment Sump, but only one train will be placed in service, and it will be placed in service ONLY if Containment Pressure is greater than 3psig):

M6. Operator checks the NS Pumps are OFF.

M7. Operator CLOSES the NS Pump Suctions from the FWST (NS-20A and NS-3B)

M8. Operator verifies that Containment Pressure is greater than 3 psig.

M9. Operator verifies adequate Containment Sump Level exists to supply suction to the NS Pump.

Steps M11 through M19 are to align and start ONE NS Pump to take suction from the Containment Sump. The Operator checks to see if the "A" NS Pump is available to be started. If it is available, the "A" NS Pump is aligned and started; however, if, for any reason, the "A" Pump is unavailable to run, the Operator's actions are immediately diverted to align (13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-125 (Page 2 of 3) and start the "B" NS Pump starting back at M10, but using the valves/equipment shown in the

{brackets}.

M10. Operator checks that the "A" NS Pump is AVAILABLE TO RUN M11. Operator verifies that the "A" Train NS/ND Suction from the Containment Sump (NI-185A) is OPEN. {for "B" Train, NI-184B}

M12. Operator checks that the opposite train NS Pump is OFF.

M13. Operator checks the "A" Nuclear Service Water (RN) Pump is ON. {for "B" Train, check the "B" RN Pump is on}

M14. Operator OPENS the first "A" NS Heat Exchanger Outlet Containment Isolation Valve (NS-32A). {For "B" Train, NS-12B}.

M15. Operator OPENS the second "A" NS Heat Exchanger Outlet Containment Isolation Valve (NS-29A). {For "B" Train, NS-15B}.

M16. Operator verifies that the "A" NS Pump Suction Isolation from the FWST (NS-20A) is CLOSED. {For "B" Train, NS-3B}.

M17. Operator OPENS the "A" NS Pump Suction from the Containment Sump (NS-18A).

{For "B" Train, NS-1B}.

M18. Operator starts NS Pump A. {N5 Pump B}.

M19. Operator aligns cooling water to the NS Heat Exchanger for the NS Pump that was started:

(13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-125 (Page 3 of 3)

a. Operator OPENS the RN Inlet Isolation valve for the "A" NS HX. (RN-134A). {For "B" HX, RN-235B}.
b. Operator will THROTTLE OPEN the NS HX RN Outlet Isolation for "A" NS HX (RN-137A) to the desired flow. {For "B" HX, RN-238B}.

M20. Operator checks N5 Alignment and ensures both trains are aligned to the Containment Sump.

When it has been verified that the FWST LOW-LOW LEVEL setpoint has been reached (Annunciator Alarm), the Operator IMMEDIATELY resumes the procedure and aligns the medium and high head injection pumps (NI and NV) to receive suction from the ND Pumps as follows (However, after Containment Spray is aligned, if time allows prior to FWST Low-Low Level being reached, the Operators can perform steps M24, M25, and M26 early):

M21. Operator verifies that adequate Containment Sump Level exists.

M22. Operator verifies that both ND Pumps are ON.

M23. Operator CLOSES the train-related ND to Reactor Coolant System Hot Leg Isolation Valves (ND-30A and ND-15B).

M24. Operator verifies Reactor Coolant (NC) Pressure is LESS than the pressure at which the Safety Injection (NI) Pumps can inject (if not, the Operator is directed to STOP the NI Pumps).

M25. Operator CLOSES the NI Pump Miniflow Isolation valves (NI-115B and NI-144B).

M26. Operator restores power to and CLOSES the NI Pumps Miniflow Header Isolation (NI-147A).

M27. Operator checks that at least one of the Centrifugal Charging Pump Recirc Isolation Valves (NV-151A and/or NV-150B) is closed.

M28. Operator ensures that the NV and NI Pumps Suction Crossover Block valve is OPEN (NI-334B).

M29. Operator OPENS the train related NV & NI Pumps Suction Crossover Valves (NI-332A and NI-333B)

M30. Operator aligns the ND Discharge to the Suction of the NI and NV Pumps by opening the train related isolation valves (ND-58A and NI-136B).

M31. Operator verifies that at least one train of ND is aligned to provide suction to the NV and NI Pumps:

a. "A" ND Pump running AND ND-58A OPEN AND/OR
b. "B" ND Pump running AND NI-136B OPEN M32. Operator isolates the NI Pumps from FWST by restoring power to and CLOSING the FWST to NI Pumps Isolation Valve (NI-100B).

M33. Operator isolates the NV Pumps from the FWST by closing BOTH of the FWST supply valves to the NV Pumps (NV-221A AND NV-222B).

(13 OCT 2018)

McGuire Nuclear Station UFSAR Table 6-126 (Page 1 of 1)

Table 6-126. Deleted Per 2009 Update (10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-127 (Page 1 of 2)

Table 6-127. Failure Analysis for Switchover to Cold Leg Recirculation Failure Effect Comment Operator Error During Manual Switchover Skips Step M1 None No credited actions on Foldout Page.

Administrative step.

Skips Step M2 None Operator would have secured ND pump at Pre-Low level alarm for inadequate sump level if needed.

Skips Step M3 Prohibits sequencer reset Operator will discover and operation of ESF valves. omission in next step.

Skips Step M4 Prohibits NS pump start and Opeator will discover when NI pump stop performing M18 or M24.

Skips Step M5.a None The automatic switchover system will open NI-185A and NI-185B with sufficient water remaining in FWST to complete switchover.

Skips Step M5.b None Valves ND-4B and ND-19A isolate the FWST from ND automatically.

Skips Step M5.c None Confirmation of automatic alignment.

Skips Step M5.d None Both RHR pumps are sequenced on via S/I signal.

Skips Step M21 None Confirmation of expected condition.

Skips Step M22 None Operator will discover omission in step M31.

Skips Step M23 None Closing of redundant crossover isolation valve completes train separation.

Skips Step M24 If NC pressure < 1600 PSIG, If NC pressure greater than then there is no effect. If NC 1600 PSIG, then NV pumps pressure > than 1600 PSIG, will be able to maintain then NI Pump miniflow will be pressure.

isolated on running pumps.

Skips Step M25 None NI pump miniflow will be isolated n Step M26.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-127 (Page 2 of 2)

Failure Effect Comment Skips Step 26 None NI pump miniflow was isolated in Steps M25.

Miniflow will be single isolated rather than double isolated.

Skips Step M27 None Redundant train valve will isolate Centrifugal Charging Pump Recirc isolation Valve.

Skips Step M28 None Valve NI334B is normally open; thereforeshould not be closed. If it is closed, B Train ND will be aligned to supply both trains of NI.

Skips Step M29 None B train ND will be aligned through one of the redundant, parallel valves (NI-332A/NI-333B).

Skips Step M30 None Opposite Train ND (either ND-58A or NI-136B) will be aligned to both trains of NV and NI.

Skips Step M31 None Confirmation of expected alignment.

Skips Step M32 None Check valve NI-101 prevents flow back to the FWST.

Skips Step M33 None Check valve NV-223 prevents flow back to the FWST.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-128 (Page 1 of 1)

Table 6-128. Sequence of Operations: Cold Leg Recirculation to Residual Containment Spray The following steps would be taken for residual spray alignment (at approximately 50 minutes after initiation of the LOCA or following switchover to recirculation, whichever occurs later).

1. Close the valve between the A RHR pump discharge and two RCS cold legs (NI173A).
2. Open the valve between the discharge of the A RHR pump and the A residual spray header (NS43A).

Note: The valve between the discharge of the A RHR pump and the A residual spray header is interlocked such that it cannot be opened unless the Containment sump valve to the A RHR pump is open.

OR

3. Close the valve between the B RHR pump discharge and two RCS cold legs (NI178B).
4. Open the valve between the discharge of the B RHR pump and the B residual spray header (NS38B).

Note: The valve between the discharge of the B RHR pump and the B residual spray header is interlocked such that it cannot be opened unless the Containment sump valve to the B RHR pump is open.

After the containment pressure drops to an allowable level, the RHR pump discharge may be realigned to the RCS cold legs by the following procedure:

5. Close the valve between the discharge of the A RHR pump and the A residual spray header (NS43A).
6. Open the valve between the A RHR pump discharge and two RCS cold legs (NI173A).

OR

7. Close the valve between the discharge of the B RHR pump and the B residual spray header (NS38B).
8. Open the valve between the B RHR pump discharge and two RCS cold legs (NI178B).

Note: Residual Containment Spray is initiated manually when required by the operator and only if 1) the Emergency Core Cooling System is operating in the recirculation mode, 2) more than 50 minutes have passed since the initiation of the accident, and 3) containment pressure exceeds a setpoint. Residual Containment Spray is not required to maintain containment pressure within design values.

(30 NOV 2012)

McGuire Nuclear Station UFSAR Table 6-129 (Page 1 of 1)

Table 6-129. Sequence of Operations: Cold Leg Recirculation to Hot Leg Recirculation The following steps would be taken when re-aligning the ECCS from the cold leg recirculation mode to the hot leg recirculation mode.

Note: Prior to realigning the ECCS for hot leg recirculation, power must be restored (as applicable) to the following valves: NI173A, NI178B, NI183B, NI121A, NI162A, NI152B.

1. Stop A safety injection pump.
2. Close A safety injection pump crosstie isolation valve (NI118A).
3. Open A safety injection pump hot leg isolation valve (NI121A).
4. Start A safety injection pump.
5. Stop B safety injection pump.
6. Close B safety injection pump cold leg and crosstie isolation valves. (NI162A and NI150B)
7. Open B safety injection pump hot leg isolation valve (NI152B).
8. Start B safety injection pump.
9. Verify hotleg flow from at least one safety injection train, if not proceed with steps below to align one train RHR hotleg recirculation.
10. Check ND-1B, 2A, C, 30A and 15B are closed.
11. Open RHR hotleg isolation NI-183B.

If residual containment spray is required from an operating RHR train, that train is not aligned to RHR hot leg injection in order to preserve residual containment spray flow. Align either train RHR as follows ('B' train in parenthesis).

12. Check NS-43A (NS-38B) closed.
13. Close RHR pump cold leg isolation NI-173A (NI-178B).
14. Open RHR discharge cross-tie isolation ND-30A (ND-15B).

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-130 (Page 1 of 1)

Table 6-130. Deleted Per 2017 Update (22 APR 2017)

McGuire Nuclear Station UFSAR Table 6-131 (Page 1 of 2)

Table 6-131. Materials Employed for Emergency Core Cooling System Components Component Material Cold Leg Accumulators Carbon Steel, Clad with Austenitic Stainless Steel Centrifugal Charging Pumps Stainless Steel Safety Injection Pumps Stainless Steel Residual Heat Removal Pumps Stainless Steel Residual Heat Exchangers Shell Carbon Steel Shell End Cap Carbon Steel Tubes Austenitic Stainless Steel Channel Austenitic Stainless Steel Channel Cover Austenitic Stainless Steel Tube Sheet Forged Carbon Steel with Stainless Steel Weld Overlay Face Valves Motor Operated Valves Containing Radioactive Austenitic Stainless Steel or Equivalent Fluids Pressure Containing Parts Body-to-bonnet Bolting & Nuts Low Alloy Steel Seating Surfaces Stellite No. 6 or Equivalent Stems Austenitic Stainless Steel, 17-4PH Stainless, or Equivalent Motor Operated Valves Containing Non- Carbon Steel Radioactive, Boron-Free Fluids Bonnet and Stem Corrosion Resistant Steel Diaphragm Valves Austentic Stainless Steel Accumulator Check Valves Parts Contacting Borated Water Austentic Stainless Steel or Equivalent Clapper Arm (Unit 2 Only) Austenitic Stainless Relief Valves Stainless Steel Bodies Stainless Steel Carbon Steel Bodies Carbon Steel All Nozzles, Discs, Spindles and Guides Austenitic Stainless Steel or Equivalent Bonnets for Stainless Steel Valves Stainless Steel All other Bonnets Carbon Steel (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-131 (Page 2 of 2)

Component Material Piping All Piping in Contact with Borated Water Austenitic Stainless Steel (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-132 (Page 1 of 1)

Table 6-132. ECCS Relief Valve Data Fluid Normal Inlet Relieving Set Pressure, Back Pressure Description Discharged Temp,°F Temp, °F Psig Constant, Psig Build-up, Psig Capacity N2 supply to N2 120 70 700 0 0 1500 scfm cold leg injection accumulators SI Pump Borated Water 100 190 1740 3 50 20 gpm Discharge RHR Pumps SI Borated Water 120 350 600 3 50 60 gpm(1)

Line SI Pumps Borated Water 100 190 240 3 50 20 gpm Suction Header Cold leg N2 Gas 120 120 700 0 0 1500 scfm accumulator to containment NC Check Borated Water 120 250 2485 0 0 20 gpm Valve Test Header &

Penetration Note:

(1)

Relief Valve 2ND-64 capacity is 80gpm per EC415533 (13 APR 2020)

McGuire Nuclear Station UFSAR Table 6-133 (Page 1 of 2)

Table 6-133. Single Active Failure Analysis for Emergency Core Cooling System Components Component Malfunction Comments Short Term Phase

1. Pumps
a. Centrifugal Charging Pumps. Fails to start Two provided. Evaluation based on operation of one.
b. Safety Injection Pumps. Fails to start Two provided. Evaluation based on operation of one.
c. Residual Heat Removal Pumps. Fails to start Two provided. Evaluation based on operation of one.
2. Automatically Operated Valves in Charging System
a. Suction line to Refueling Water Storage Tank Fails to open Two parallel lines; only one valve in either line is required to open.
b. Discharge line to normal charging path Fails to close Two valves in series; only one valve required to close.
c. Suction from Volume Control Tank Fails to close Two valves in series; only one valve required to close.
3. Valves Operated from Control Room - CCP minimum flow bypass Fails to close Two valves in series; only one line valve required to close.

Long Term Phase

1. Valves Operated from Control Room for Recirculation
a. Containment sump recirculation isolation Fails to open Two lines parallel; only one valve in either line is required to open.
b. Residual Heat Removal Pump suction line from Refueling Fails to close Check valve in series with one Water Storage Tank gate valve; operation of only one valve required.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-133 (Page 2 of 2)

Component Malfunction Comments

c. Safety Injection Pump suction line from Refueling Water Fails to close Check valve in series with gate Storage Tank valve; operation of only one valve required.
d. Centrifugal Charging Pump suction line from Refueling Water Fails to close Check valve in series with two Storage Tank parallel gate valves. Operation of either the check valve or both of the gate valves required.
e. High head pump suction line at discharge of Residual Heat Fails to open Separate and independent high Exchanger head injection path taking suction from discharge of Residual Heat Exchanger.
2. Pumps
a. Residual Heat Removal Pump Fails to start Two provided. Evaluation based on operation of one.
b. Centgrifugal Charging Pump Fails to operate Same as phase.1
c. Safety Injection Pumps Fails to operate Same as short term phase.1 Note:
1. Either a Centrifugal Charging Pump or a Safety Injection Pump required.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-134 (Page 1 of 1)

Table 6-134. Emergency Core Cooling System Recirculation Piping Passive Failure Analysis - Long Term Phase Flow Path Indication of Loss of Flow Path Alternate Flow Path Low Head Recirculation From Containment sump to low head Accumulation of water in a Residual Heat Via the independent, identical low head flow injection header via the Residual Heat Removal Pump compartment or Auxiliary path utilizing the second Residual Heat Removal Pumps and the Residual Heat Building sump Exchanger Exchangers High Head Recirculation From Containment sump to the high head Accumulation of water in a Residual Heat From Containment sump to the high head injection header via Residual Heat Removal Pump compartments or the injection headers via alternate Residual Heat Removal Pump, Residual Heat Exchanger Auxiliary Building sump Exchanger and the alternate high head and the high head injection pumps charging pump.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-135 (Page 1 of 8)

Table 6-135. Valves Required to Ensure Safe Shutdown of the Reactor Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria Reactor Coolant System 3 Relief 6 P 1/2NC1, 2, 3 Pressurizer #1 Safety Relief ---- Note 1 Chemical and Volume Control System 2 Globe 2 Motor 1/2NV150B Centrifugal Charging Pumps H.W. Note 2 Recirc 1/2NV151A 2 Gate 4 Motor 1/2NV141A Volume Control Tank #1 H.W. Note 2 Outlet 1/2NV142B 2 Gate 3 Motor 1/2NV244A Charging Line Containment H.W. Note 2 Iso.

1/2NV245B 2 Gate 8 Motor 1/2NV222B Cent. Charging Pumps Suction H.W. Note 2 From FW System 1/2NV221A 1 Globe 2 Motor 1/2NV265B Boric Acid to Charging Pumps H.W. Note 2 Residual Heat Removal System 2 Gate 14 Motor 1/2ND1B ND Suction from NC Loop 3 H.W. Note 1 1/2ND2AC 2 Gate 8 Motor 1/2ND30A ND Heat-exchangers Outlet H.W. Note 2 Crossover Isolation 1/2ND15B 2 Gate 14 Motor 1/2ND4B ND Pump 1B Suction from NC H.W. Note 2 Loop 3 + RWST 1/2ND19A ND Pump 1A Suction from NC H.W. Note 2 Loop 3 + RWST Safety Injection System (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 2 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 4 Gate 10 Motor 1/2NI54A, 65B, Accumulator Discharge Iso. H.W. Note 1 76A, 88B 8 Check 10 P 1/2NI59, 60, 70, 71, Accumulator Discharge to NC ---- Note 1 81, 82, 93, 94 System Check 4 Check 6 P 1/2NI175, 176, 180, ND to NC System Cold Legs ---- Note 1 181 Check 4 Check 2 P 1/2NI165, 167, 169, NI Pumps to NC System Cold ---- Note 1 171 Legs Check 4 Check 2 P 1/2NI128, 124, 156, NI Pumps to NC System Hot ---- Note 1 159 Legs Check 2 Check 8 P 1/2NI125, 129 ND Pumps to NC System Hot ---- Note 1 Legs Check 4 Check 6 P 1/2NI134, 126, NC System Hot Legs Inlet ---- Note 1 1NI-157, 160 Check (2NI-157, 160 were made 2")

1 Gate 8 Motor 1/2NI100B RWST to Safety Inj. Pumps H.W. Note 2 1 Check 8 P 1/2NI101 RWST to Safety Inj. Pumps ---- Note 2 Check 1 Gate 8 Motor 1/2NI136B ND HX 1B to Safety Inj. Pump H.W. Note 2 1B 2 Gate 6 Motor 1/2NI135B, 103A NI Pumps Suction from RWST H.W. Note 2 1 Gate 6 Motor 1/2NI334B NI Pump Suction Crossover H.W. Note 2 from NV Isolation 2 Gate 6 Motor 1/2NI332A, 333B NI Pump Suction Crossover H.W. Note 2 from NV Isolation (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 3 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 2 Check 4 P 1/2NI116, 148 NI Pumps Discharge Check ---- Note 2 2 Gate 4 Motor 1/2NI118A, 150B NI Pumps Cold Leg Inj. Lines H.W. Note 2 Iso.

2 Gate 4 Motor 1/2NI121A, 152B NI Pumps to NC Hot Leg Iso. H.W. Note 2 1 Gate 4 Motor 1/2NI162A NI Pumps Cold Leg Inj. Hdr. H.W. Note 2 Iso.

2 Gate 8 Motor 1/2NI173A, 178B ND Hdr. to NC Cold Legs H.W. Note 2 1 Gate 12 Motor 1/2NI183B ND Hdr. to NC Hot Legs Iso. H.W. Note 2 2 Gate 18 Motor 1/2NI184B, 185A Cont. Recirculation Sump Line H.W. Note 2 Iso.

Containment Spray System 4 Check 8 P 1/2NS13, 16, 30, 33 NS Pumps Discharge Lines ---- Note 1 Check 2 Check 8 P 1/2NS41, 46 ND Pumps Disch. to Aux. ---- Note 2 Spray Nozzles Check 2 Gate 12 Motor 1/2NS3B, 20A NS Pumps Suction from H.W. Note 2 RWST 2 Gate 12 Motor 1/2NS18A, 1B NS Pumps Suction from Cont. H.W. Note 2 Recirc. Sump 4 Gate 8 Motor 1/2NS12B, 15B, NS Pumps Disch. Iso. H.W. Note 2 29A, 32A 2 Gate 8 Motor 1/2NS38B, 43A ND Pumps Disch. to Aux. H.W. Note 2 Spray Nozzles Containment Air Return Exchange and H2 Skimmer System 2 Butterfly 8 Motor 1/2VX1A, 2B H2 Skimmer Fan Inlet Iso. H.W. Note 1 (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 4 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 2 Diaphragm 1 Air 1/2VX33B, 31A Cont. Sample Blower Inlet H.W. Note 1 Diaphragm 1 Check 1 P 1/2VX30 Cont. Sample Blower Outlet ---- Note 1 Annulus Ventilation System 1 Gate 4 Motor 1/2VE8A H2 Purge Inlet Blower Inlet H.W. Note 2 1 Check 4 P 1/2VE7 H2 Purge Inlet Blower Inlet ---- Note 2 Check 1 Diaphragm 4 Motor 1/2VE10A H2 Purge Inlet Blower Outlet H.W. Note 2 1 Gate 4 Motor 1/2VE6B H2 Purge from Cont. to H.W. Note 2 Annulus 1 Check 4 P 1/2VE11 H2 Purge Inlet Blower Outlet ---- Note 1 Check 1 Gate 4 Motor 1/2VE5A H2 Purge from Cont. to H.W. Note 1 Annulus Component Cooling System 2 Butterfly 16" Motor 1/2KC56A Cooling Water to RHR HX's A H.W. Note 2 and B Auto Iso.

1/2KC81B 2 Gate 8" Motor 1/2KC230A Train A and B Cooling to H.W. Note 2 Reactor Bldg. Non-Ess. Supply 1/2KC228B Hdr. Auto Isolation 2 Butterfly 20" Motor 1/2KC50A Train A and B Cooling to Aux. H.W. Note 2 Bldg. Non-Ess. Supply Hdr.

1/2KC53B Auto Isolation 2 Butterfly 20" Motor 1/2KC1A Aux. Bldg. Non-Ess. Return H.W. Note 2 Auto. Isolation to Train A and 1/2KC2B B Cooling Water HX's (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 5 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 2 Gate 10" Motor 1/2KC3A Reactor Bldg. Non-Ess. Return H.W. Note 2 Auto. Iso. to Tran A and B 1/2KC18B Cooling Water HX's Main Steam System 4 Globe 34 Air Piston 1/2SM1AB Main Steam 1D Isolation ---- Note 2 1/2SM3AB Main Steam 1/2C Isolation 1/2SM5AB Main Steam 1B Isolation 1/2SM7AB Main Steam 1A Isolation Feedwater System 4 Gate 12 Hydraulic 1/2CF26AB Steam Gen. 1D Containment Note 2 Piston Isolation 1/2CF28AB Steam Gen. 1/2C Containment Isolation 1/2CF30AB Steam Gen. 1B Containment Isolation 1/2CF35AB Steam Gen. 1A Containment Isolation Nuclear Service Water System 4 Butterfly 36 Motor 0RN10AC Low Level Supply Shutoff H.W. Note 2 0RN11B 0RN12AC 0RN13A 4 Butterfly 36 Motor 0RN2B Condenser Circulating Water H.W. Note 2 0RN3A Supply Shutoff 0RN4AC 0RN5B (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 6 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 2 Butterfly 24 Motor 0RN301AC Containment Ventilation H.W. Note 2 System Supply Isolation 0RN302B 2 Butterfly 36 Motor 1/2RN16A RN Supply Isolation H.W. Note 2 1/2RN18B 2 Butterfly 36 Motor 0RN14A RN Supply Crossover Isolation H.W. Note 2 0RN15B 2 Butterfly 36 Motor 0RN7A Standby Nuclear Service Water H.W. Note 2 Pond Supply Shutoff 0RN9B 4 Butterfly 36 Motor 0RN147AC Condenser Circulating Water H.W. Note 2 0RN148AC Discharge Isolation 0RN283AC 0RN284B 2 Butterfly 36 Motor 1/2RN296A Essential Header Return H.W. Note 2 1/2RN297B 2 Butterfly 36 Motor 0RN149A Standby Nuclear Service Water H.W. Note 2 Pond Discharge Isolation 0RN152B 2 Butterfly 36 Motor 0RN150A RN Discharge Crossover H.W. Note 2 Isolation 0RN151B Deleted per 2012 Update 2 Diaphragm 6 Air 1/2RN21A RN Strainer Backwash --- Note 2 Diaphragm Inlet Isolation 1/2RN25B 2 Butterfly 8 Motor 1/2RN70A Diesel Gen. Heat Exchanger H.W. Note 2 Supply Isolation 1/2RN171B (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 7 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 2 Butterfly 20 Motor 1/2RN86A Component Cooling Heat H.W. Note 2 Exchanger Supply Isolation 1/2RN187B 2 Diaphragm 11/2 Air 1/2RN140A Fuel Pool Cooling Pump --- Note 2 Diaphragm Motor Ess. Cooler Supply 1/2RN240B Isolation 2 Butterfly 18 Motor 1/2RN134A Containment Spray Heat H.W. Note 2 Exchanger Supply Isolation 1/2RN235B 2 Diaphragm 2 Air 1/2RN103A Centrifugal Charging Pump --- Note 2 Diaphragm Motor Cooler Complex Supply 1/2RN204B Isolation 2 Diaphragm 2 Air 1/2RN126A Containment Spray Pump --- Note 2 Diaphragm Motor ES Cooler Supply 1/2RN227B Isolation 2 Diaphragm 2 Air 1/2RN130A Residual Heat Removal Pump --- Note 2 Diaphragm Motor ES Cooler Supply 1/2RN231B Isolation 2 Diaphragm 2 Air 1/2RN114A Safety Injection Pump Cooler --- Note 2 Diaphragm Complex Supply Isolation 1/2RN215B 2 Gate 8 Motor 1/2RN69A Assured Supply to Auxiliary H.W. Note 2 Feedwater Pumps Isolation 1/2RN162B Auxiliary Control Panel 3 Butterfly 10 Motor 1/2RN40A Nonessential Header Supply H.W. Note 2 1/2RN41B Isolation 1/2RN43A (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-135 (Page 8 of 8)

Type of Size Actuation Means of Environmental Qty. Valve (in) Type Valve Number Valve Name Controlling Design Criteria 1 Butterfly 10 Motor 1/2RN42A Auxiliary Building H.W. Note 2 Nonessential Supply Isolation 2 Butterfly 6 Motor 1/2RN299A Auxiliary Building Ventilation H.W. Note 2 Units Cooling Water Discharge 1/2RN279B Isolation 2 Butterfly 10 Motor 1/2RN64A Auxiliary Building H.W. Note 2 Nonessential Discharge 1/2RN63B Isolation 2 Diaphragm 2 Air 1/2RN166A Auxiliary Feedwater Pump --- Note 2 Diaphragm 1/2RN170B Motor Cooler RN Control 4 Diaphragm 2 Air 1/2RN112A Component Cooling Water --- Note 2 Diaphragm 1/2RN117A Pump Motor Cooler RN 1/2RN213B Control 1/2RN218B 2 Diaphragm 1 1/2 Air 1/2RN68A Nuclear Service Water Pump --- Note 2 Diaphragm 1/2RN161B Motor Cooler RN Control Refueling Water System 2 Gate 8" Motor 1/2FW1A Refueling Water Loop H.W. Note 2 Isolation 1/2FW32B Note:

1. Temp, °F: 110 to 250 Pressure, Psig: -1.5 to 19 Humidity, %: 0 to 100
2. Temp, °F: 50 to 150 Pressure, Psig: -0.3 to 0.3 Humidity, %: 0 to 100 (24 APR 2014)

McGuire Nuclear Station UFSAR Table 6-136 (Page 1 of 1)

Table 6-136. Emergency Core Cooling System Shared Functions Evaluation Component Normal Operating Arrangement Accident Arrangement During Injection Refueling Water Storage Tank Lined up to suction of Safety Lined up to suction of injection, containment spray, residual centrifugal charging, heat removal pumps. safety injection and residual heat removal pumps.

Centrifugal Charging Pumps Lined up for charging service. Lined up for injection Suction from volume control tanks. from RWST. Valves for realignment meet single failure criteria.

Residual Heat Removal Pumps Lined up to cold legs of reactor Lined up to cold legs coolant piping. of reactor coolant piping.

Residual Heat Exchangers Lined up for residual heat removal Lined up for residual pump operation. heat removal pump operation.

Safety Injection Pumps Lined up to cold legs of reactor Lined up to cold legs coolant piping.(1) of reactor coolant piping.

Note(s):

1. With the exception of periodic cold-leg accumulator make-up.

(05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-137 (Page 1 of 1)

Table 6-137. Parameters for Boron Precipitation Analysis Reactor Core Power 3479 MWt Total Inventory of Boric Acid Solution (Includes RCS, SI Accumulators, RWST and 7.1 x 106 lbm Ice Bed)

Boron Concentration Measurement Uncertainty 1.0%

Effective Vessel Volume (Core and Upper Plenum Volume to the bottom of hot leg 972 nozzles)

Safety Injection Subcooling 55 BTU/lbm Containment Pressure 14.7 psia Ice Condenser Maximum Boron Concentration 2330 ppm (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-138 (Page 1 of 1)

Table 6-138. Control Area Ventilation System Failure Analysis Component Failure Comments and Consequences Control Area AHU Fan Fail Redundant Fan Available Control Area O.A.P.F.T. Fan Fail Redundant Fan Available Control Area Fail Redundant Unit Available Cooling Coil Units Outside Air Intake Isolation Fail in open position when Redundant valve will close Valve activity is present Outside Air Intake Valve Fail in closed position Redundant intake supply line will supply pressurizing air Deleted Per 2009 Update Outside Air Pressure Filter Train Fail Redundant train available Outside Air Pressure Filter Train Single Power Failure Dampers spring return to the Isolation Dampers open position. Redundant filter train available.

Switchgear AHUs and Single Power Failure AHU fails and the isolation switchgear outlet isolation dampers, by spring force, fail to dampers the open position. Redundant Filter train air flow is degraded, but operable. Failed train damper can be closed if switchgear room temperature exceeds acceptable limits.

(10 OCT 2009)

McGuire Nuclear Station UFSAR Table 6-139 (Page 1 of 2)

Table 6-139. Containment Spray System Component Parameters CSS Pump Data Characteristics Data NS Pumps Quanity per Unit Two Type Vertical, single-stage centrifugal Pumped fluid Borated water Design pressure, psig 300 Design temperature, °F 200 Design flow rate, gpm 3400 Design head, ft 380 NPSH required at design flow rate, ft 15 Deleted per 2005 Update Shutoff head, ft 450 Materials of construction Casing Stainless Steel, A351 Impeller Stainless Steel, A296 Shaft Stainless Steel, A276 Driver:

Type Solid shaft induction Service factor 1.25 Nameplate rating, hp 400 Voltage 4000/3-phase RPM 1790 NS Heat Exchangers Quantity per Unit 2 Type Shell and Tube Heat Transfer per Unit (BTU/hr) 82.3 x 106 (84.15 x 106)

Flow, tube side, gpm 3400 (3800)2 Flow, shell side, gpm 38002 (3400)

Shell Side Inlet Temperature, °F 84.3 (153.8)

Shell Side Outlet Temperature, °F 117.8 (105.3)

Tube Side Inlet Temperature, °F 153.8 (84.3)

Tube Side Outlet Temperature, °F 105.4 (128.6)

(05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-139 (Page 2 of 2)

Characteristics Data Material Shell/Tube Carbon Steel/Stainless Steel (Stainless Steel, Titanium)

Design Pressure, Shell/Tube, psig 200/230 (252/135)

Design Temperature, Shell/Tube, °F 200/200 (200/200)

NS Spray Nozzles Manufacturer Spraco Model Number 1713A Pressure Drop, psi 40 Flow Rate, gpm 15.2 Median Spray Droplet Diameter, Microns 230 Mean Spray Droplet Diameter, Microns 355 Note:

1. NS Heat Exchanger parameters in parentheses ( ) are applicable to the Unit 2 B Train heat exchanger only.
2. Nominal value - reference MCC-1223.24-00-0076 "RN/NS Heat Exchanger Tube Plugging Analysis."

(05 APR 2011)

McGuire Nuclear Station UFSAR Table 6-140 (Page 1 of 1)

Table 6-140. Types and Location of Insulation Used in the Containment Reflective (See Notes) Mass Steam Generators Encapsulated Foam Glass Pressurizer Ice Condenser Air Handling Unit Drain Lines R.C. Pumps Ice Condenser Floor Drains R.C. Loops Ice Condenser Walls Surge Line Ice Condenser Glycol Supply and Return Spray Line and Bypass Lines RHR Lines Ice Condenser Top Deck Accumulator Injection Lines Safety Injection Lines Boron Injection Lines CVCS Charging Lines CVCS Letdown Lines Feedwater Lines Main Steam Lines Reactor Vessel Note:

1. Reflective Insulation may be replaced with flexible blanket insulation at selective locations.

These replacements are controlled by the modification process, and are documented in MCC-1552.08-00-0387, GSI-191 Debris Generation Calculation.

2. All mirror insulation on the steam generators from upper lateral support and above has been replaced with flexible blanket insulation.

Deleted Per 2012 Update.

(09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-141 (Page 1 of 1)

Table 6-141. Single Failure Analysis-Containment Spray System Component Malfunction Comments and Consequences Spray Clogged The large number of nozzles (approximately 345 per Containment Spray train) plus the ECCS sump strainer, which removes debris during the recirculation phase of operation, makes the clogging of a significant number of nozzles incredible.

Spray Pump Stops running or fails to start Two 100 percent capacity pumps provide redundancy.

Heat Tube leak Two 100 percent capacity heat Exchangers exchangers provide redundancy.

Valve Fails to open Two 100 percent flow paths.

Check Valves Fails to Open Two 100 percent flow paths (Pump Fails to Close Two 100 percent flow paths Discharge) Leakage Two 100 percent flow paths (09 OCT 2015)

McGuire Nuclear Station UFSAR Table 6-142 (Page 1 of 1)

Table 6-142. Swivel Bracket Stress Summary. (Ref. 80, Section 6.2.8) Load Case IV Empty (250 lb) 1222 lb Basket Basket SIDE BRACKETS (Top Coupling Piece, IB1)

Combined bending + tension, side section 0.478 0.494 Shear stress, lip 0.099 0.107 CLEVIS (Bottom Lug, IB2)

Shear at 5/16 neck 0.161 0.173 1/2 inch wide section tension 0.106 0.114 Bottom section, bending 0.383 0.412 1/2 inch wide side section, bending 0.089 0.056 1 round section 0.134 0.145 1/2 INCH DIAMETER ROD (Clevis Pin, IB4)

Shear stress 0.504 0.542 3/8 INCH DIAMETER SCREWS (Part IB3)

Tension 0.383 0.412 PLATFORM ASSEMBLIES 2 Lug stress (combined uplift and moment)

  • 0.307 Support bar bending
  • 0.197 Support bar local stress at attachment point
  • 0.383 Shear reaction support bar
  • 0.064 OUTER PLATFORM ASSEMBLY 2 Inner channel bending
  • 0.600 Outer beam bending
  • 0.269 INNER PLATFORM ASSEMBLY 2 Outer channel bending
  • 0.450 Inner beam bending
  • 0.168 BASKET STRESSES 2 Screw shear
  • 0.423 Note:
1. only evaluated for the more critical empty basket case.
2. Lower Support Structure and Ice Bakset Loads increased to account for 5/8 gap in clevis assembly.

The worst uplift load conservatively analyzed or 1222 lb (safety margin limit) and empty basket.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 1 of 7)

Table 6-143. Containment Coatings Surface Coating Systems Dry Film Manufacturer Notes Thickness

1. Carbon Original System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-200°F Prime Coat DP#12-1 13-F-12KR-00 MZ#7 2.0 mils DFT Mobil/Valspar Finish Coat DP#34-1 89-Series-00 High Build Epoxy 5.0 mils DFT Mobil/Valspar 7.0 mils DFT Maintenance System over Original DP-SP28 Power Tool Cleaning 1,2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils Carboline DFT New System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Prime Coat DP#12-1 Carbo Zinc 11 SG 2.0 mils DFT Carboline Finish Coat DP#78-1 Carboline 890 5.0 mils DFT Carboline 7.0 mils DFT
2. Carbon Original System DP-SP10 Near White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-200°F Prime Coat DP#17-1 89-R-10-00 High Build Epoxy 2.0 mils DFT Mobil/Valspar DP#34-1 76-Series-00-High Build Epoxy 5.0 mils DFT Mobil/Valspar 7.0 mils DFT (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 2 of 7)

Surface Coating Systems Dry Film Manufacturer Notes Thickness Maintenance System over Original DP-SP28 Power Tool Cleaning 1.2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils Carboline DFT New System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Prime Coat DP#78-1 Carboline 890 2.0 mils DFT Carboline Finish Coat DP#78-1 Carboline 890 5.0 mils DFT Carboline

3. Carbon Original System DP-SP10 Near White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-200°F Prime Coat DP#17-1 89-R-10--00 High Build Epoxy 2.0 mils DFT Mobil/Valspar Finish Coat DP#69-1 76-Series-00 High Build Epoxy 5.0 mils DFT Mobil/Valspar 7.0 mils DFT Maintenance System over Original DP-SP28 Power Tool Cleaning 1,2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils Carboline DFT New System DP-SP10 Near White Metal Blast Cleaning 1,2,3,4,5,6 Prime Coat DP#78-1 Carboline 890 3.0 mils DFT Carboline (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 3 of 7)

Surface Coating Systems Dry Film Manufacturer Notes Thickness Finish Coat DP#78-1 Carboline 890 4.0 mils DFT Carboline 7.0 mils DFT

4. Carbon Original System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-750°F Prime Coat DP#12-1 13-F-12KR-00-MZ#7 3.0 mils DFT Mobil/Valspar New System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Prime Coat DP#12-1 Carbo Zinc 11 SG 3.0-5.0 mils DFT Carboline
5. Carbon Original System DP-SP10 Near White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-200°F Prime Coat DP#34-1 89-Series-00 High Build Epoxy 2.0 mils DFT Mobil/Valspar DP#34-1 89-Series-00 High Build Epoxy 5.0 mils DFT Mobil/Valspar 7.0 mils DFT Maintenance System over Original DP-SP28 Power Tool Cleaning 1,2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils Carboline DFT New System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Prime Coat DP#78-1 Carboline 890 2.0 mils DFT Carboline (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 4 of 7)

Surface Coating Systems Dry Film Manufacturer Notes Thickness Finish Coat DP#78-1 Carboline 890 5.0 mils DFT Carboline 7.0 mils DFT

6. Carbon Original System DP-SP10 Near White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-200°F Prime Coat DP#69-1 76-Series-00 High Build Epoxy 2.0 mils DFT Mobil/Valspar DP#69-1 76-Series-00 High Build Epoxy 5.0 mils DFT Mobil/Valspar 7.0 mils DFT Maintenance System over Original DP-SP28 Power Tool Cleaning 1,2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 7.0 mils Carboline DFT New System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Prime Coat DP#78-1 Carboline 890 2.0 mils DFT Carboline Finish Coat DP#78-1 Carboline 890 5.0 mils DFT Carboline 7.0 mils DFT
7. Carbon Original System DP-SP10 Near White Metal Blast Cleaning Steel 200°F-750°F (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 5 of 7)

Surface Coating Systems Dry Film Manufacturer Notes Thickness Prime Coat DP#80 1 8674-00 Silicone Alkyd Stainless Steel 1.0 mils DFT Keeler and 3,4,5,6 Long Finish Coat DP#80-1 8674-00 Silicone Alkyd Stainless 1.0 mils DFT Keeler and Steel Long 2.0 mils DFT

8. Carbon Original System DP-SP5 White Metal Blast Cleaning 1,2,3,4,5,6 Steel 0°F-250°F Prime Coat DP#71-1 7155HHB Plasite Phenolic 4.0 mils DFT Wisconsin Tank Intermediate Coat DP#71-1 7155HHB Plasite Phenolic 4.0 mils DFT Wisconsin Lining Finish Coat DP#71-1 7155HHB Plasite Phenolic 4.0 mils DFT Wisconsin 12.0 mils DFT
9. Concrete Prime Coat DP#36-1 46-X-29-00 Epoxy Surfacer Seal Concrete Mobil/Valspar 1,2,3,4,5,6 Floors Finish Coat DP#69-1 76-Series-00 High Build Epoxy 8.0 mils DFT Mobil/Valspar 8.0 mils DFT Maintenance System over Original DP-SP25 1,2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 8.0 mils Carboline DFT New System DP-SP25 1,2,3,4,5,6 Prime Coat DP#36-1 Starglaze 2011S Seal Concrete Carboline Finish Coat DP#78-1 Carboline 890 8.0 mils DFT Carboline (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 6 of 7)

Surface Coating Systems Dry Film Manufacturer Notes Thickness 8.0 mils DFT

10. Concrete Original Systems DP-SP17 1,2,3,4,5,6 Walls Prime Coat DP#36-1 46-X-29-00 Epoxy Surfacer Seal Concrete Mobil/Valspar Finish Coat DP#69-1 76-Series-00 High Build Epoxy 5.0 mils DFT Mobil/Valspar 5.0 mils DFT Maintenance System over Original DP-SP17 1,2,3,4,5,6 System Maintenance Coat DP#78-1 Carboline 890 2.0 to 5.0 mils Carboline DFT New System DP-SP17 1,2,3,4,5,6 Prime Coat DP#36-1 Starglaze 2011S Seal Concrete Carboline Finish Coat DP#78-1 Carboline 890 5.0 mils DFT Carboline 8.0 mils DFT (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-143 (Page 7 of 7)

Surface Coating Systems Dry Film Manufacturer Notes Thickness Note:

1. Original, Maintenance, and New Coating Systems for civil components meet Regulatory Guide 1.54. Mechanical and Electrical equipment was ordered prior to issuance of Regulatory Guide 1.54 therefore coatings on these components are documented as unqualified.
2. Coating Systems are qualified by Engineering in accordance with ANSI N101.2 AND ANSI N101.4 for (A)LOCA Conditions and (B)

Radiation Tolerance.

3. Coating specifications for shop and field application include the following: Scope, Coating System, Approved Materials, Application Procedures, Touchup Procedures, Workmanship Guide, Inspection Requirements, Record Requirements, and Product Data Sheets.
4. A Materials Certification of each batch of coating material procured is provided by the Manufacturer and is in accordance with ANSI N101.4.
5. Calculation MNC-1167.01-00-0001 is maintained documenting the square feet of unqualified coatings in containment.
6. Containment Coating Specifications and Coating Schedules are distributed through Document Control.

(14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-144 (Page 1 of 1)

Table 6-144. Deleted Per 1999 Update (14 OCT 2000)

McGuire Nuclear Station UFSAR Table 6-145 (Page 1 of 1)

Table 6-145. McGuire Cold Leg Pump Discharge Break - Sequence of Events Event Time (seconds)

Cold leg break occurs 0 Ss, Sp signals obtained ~1 End of blowdown ~ 30 Cold Leg Accumulators (CLAs) injection starts 54 Initiation of Containment Spray (NS) 120 Initiation of Containment Air Return Fan (VX) 600 FWST Lo-Level reached 1435 ND flow from sump starts 1530 NI + NV flow from sump starts 1650 NS flow from FWST stops 3000 Initiation of auxiliary containment spray (ND) 3000 NS flow from sump starts 3240 End of ice melting ~ 6000 Time of peak containment pressure ~ 6700 End of transient simulation 15000 (05 APR 2011)

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