L-2018-053, Turkey Point, Units 3 & 4, Replacement Pages to Enclosure 3, Slra Section 4: Difference between revisions

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{{Adams
#REDIRECT [[L-2018-053, Replacement Pages to Enclosure 3, Slra Section 4]]
| number = ML18078A027
| issue date = 02/16/2018
| title = Turkey Point, Units 3 & 4, Replacement Pages to Enclosure 3, Slra Section 4
| author name =
| author affiliation = Florida Power & Light Co
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000250, 05000251
| license number =
| contact person =
| case reference number = L-2018-053
| package number = ML18053A123
| document type = License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 13
}}
 
=Text=
{{#Wiki_filter:Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.2-1 RT PTS Calculations for Turkey Point Unit 3 Extended Beltline Materials at 72 EFPY Table 4.2.2-1: RT PTS Calculations for Turkey Point Unit 3 Extended Beltline Materials at 72 EFPY Cu Reactor Vessel Material (Wt.%) Upper Shell (US) Forging [ l Intermediate Shell (IS} Forging 0.058 IS using Surveillance Data 0.058 Lower Shell (LS} Forging 0.079 LS using Surveillance Data 0.079 Lower Head Ring (transition
) [ l Inlet Nozzle 1 0.16 Inlet Nozzle 2 0.16 Inlet Nozzle 3 0.16 Outlet Nozzle 1 0.16 Outlet Nozzle 2 0.16 Outlet Nozzle 3 0.16 Inlet Nozzle Weld 1 0.19 Inlet Nozzle Weld 2 0.16 Inlet Nozzle Weld 3 0.23 Outlet Nozzle Weld 0.19 US to IS Circumferential Weld 0.26 IS to LS Circumferential Weld 0.23 Turkey Point Nuclear Plant Units 3 and 4 Subsequen t License Renewal Application Ni (Wt.%) 0.68 0.70 0.70 0.67 0.67 0.69 0.76 0.74 0.8 0.79 0.72 0.72 0.57 0.57 0.59 0.57 0.60 0.59 CF<1> Fluence RT NDT(U)(3) (oF) (n/cm2, E>1.0 MeV) FF<2> (oF) 67.7 1.13x1019 1.03 50 37.0 1.08 X 1020 1.52 40 6.9 1.08 X 1020 1.52 40 51.0 9.86 X 1019 1.51 30 48.7 9.86 X 1019 1.51 30 175.2 1.36 X 1017 0.13 [ l 122.00 2.37 X 1017 0.19 [ l 121.50 2.37 X 1017 0.19 [ l 123.00 2.37 X 1017 0.19 [ l 122.8 2.00 X 1017 0.17 [ l 121.00 2.00 X 1017 0.17 [ l 121.00 2.00 X 1017 0.17 [ l 152.4 2.37 X 1017 0.19 [ l 143.9 2.37 X 1017 0.19 [ l 167.6 2.37 X 1017 0.19 [ l 152.4 2.00 X 1017 0.17 [ l 180.0 1.13x1019 1.03 -33.2 167.6 9.86 X 1019 1.51 -53.5 &#xa3;\RT NDT(4) C1 (3) u c,1/5) (OF) (OF) (oF) 70 0.0 17.0 56 0.0 17.0 10 0.0 5.2 77 0.0 17.0 74 0.0 8.5 24 [ l 11.8 23 [ l 11.6 23 [ l 11.6 23 [ l 11.7 21 [ l 10.6 21 [ l 10.4 21 [ l 10.4 29 [ l 14.5 27 [ l 13.7 32 [ l 16.0 26 [ l 13.1 186 12.2 28.0 253 12.8 28.0 PTS Margin RTPTS Limit (oF) (oF) (oF) 34.0 154 270 34.0 130 270 10.5 61 270 34.0 141 270 17.0 121 270 64.7 96 270 64.5 96 270 64.5 95 270 64.6 96 270 63.8 93 270 63.7 92 270 63.7 92 270 49.0 73 270 48.0 71 270 50.7 78 270 47.3 69 270 61.1 214 300 61.6 261 300 Page 4.2-7 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.2-1: RT PTS Calculations for Turkey Point Unit 3 Extended Beltline Materials at 72 EFPY PTS Cu Ni CF(1l Fluence RT NDT(U)(3l tiRT NDT(4) CJ (3) (16(5) Margin RTPTS Limit u Reactor Vessel Material (Wt.%) (Wt.%) (OF) (n/cm2, E>1.0 MeV) FF(2) (oF) (OF) (OF) (OF) (oF) (oF) (oF) IS to LS using Surveillance Data 0.23 0.59 151.1 9.86 X 1019 1.51 -53.5 228 12.8 28.0 61.6 236 300 LS to Transition Ring Circumferent ial 0.23 0.52 157.4 1.36x1017 0.13 [ l 21 [ l 10.6 44.7 61 300 Weld Notes for Table 4.2.2-1 1. Value calculated using Regulatory Guide 1.99, Revision 2. 2. FF= fluence factor= f (0-28-0 10*log(f))
_ 3. Initial RT NDT values are for unirradiated material.
Note that au = 0&deg;F for measured test values. 4. t.RT NOT= CF* FF where CF= chemistry factor. 5. Per 10 CFR 50.61, the base metal a ti= 17&deg;F for Position 1.1 and ati = 8.5&deg;F for Position 2.1 with credible surveillance data; the weld metal ati = 28&deg;F for Position 1.1 and ati = 14&deg;F for Position 2.1 with credible surveillance data. However, ati need not exceed 0.5 *t.RT NDT* Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Page 4.2-8 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.2-2 RT PTS Calculations for Turkey Point Unit 4 Extended Beltline Materials at 72 EFPY Table 4.2.2-2:
RT PTS Calculations for Turkey Point Unit 4 Extended Beltline Materials at 72 EFPY Cu Reactor Vessel Material (Wt.%) Upper Shell (US) Forging [ l Intermediate Shell (IS) Forging 0.054 Lower Shell (LS) Forging 0.056 LS using Surveillance Data 0.056 Lower Head Ring (transition) [ l Inlet Nozzle 1 0.08 Inlet Nozzle 2 0.16 Inlet Nozzle 3 0.16 Outlet Nozzle 1 0.16 Outlet Nozzle 2 0.16 Outlet Nozzle 3 0.16 Inlet Nozzle Weld 1 0.19 Inlet Nozzle Weld 2 0.16 Inlet Nozzle Weld 3 0.34 Outlet Nozzle Weld 1 0.16 Outlet Nozzle Weld 216) 0.34 US to IS Circumferential Weld<7l 0.26 IS to LS Circumferential Weld 0.23 Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Ni (Wt.%) 0.70 0.69 0.74 0.74 0.69 0.71 0.84 0.75 0.78 0.68 0.70 0.57 0.57 0.68 0.57 0.68 0.60 0.59 CFl1l Fluence RT NDT(U) <3) FFl2l (*F) (n/cm2, E>1.0 MeV) (*F) 67.9 1.15 X 1019 1.04 40 33.4 1.08 X 1020 1.52 50 34.6 9.81 X 1019 1.51 40 4.9 9.81 X 1019 1.51 40 175.2 1.36 X 1017 0.13 [ l 51.0 2.49 X 1017 0.20 [ l 123.4 2.49 X 1017 0.20 [ l 121.8 2.49 X 1017 0.20 [ l 122.5 2.01 X 1017 0.17 [ l 120.0 2.01 X 1017 0.17 [ l 120.5 2.01 X 1017 0.17 [ l 152.4 2.49 X 1017 0.20 [ l 143.9 2.49 X 1017 0.20 [ l 220.6 2.49 X 1017 0.20 [ l 143.9 2.01 X 1017 0.17 [ l 220.6 2.01 X 1017 0.17 [ l 180.0 1.15x1019 1.04 -33.2 167.6 9.81 X 1019 1.51 -53.5 ilRT NDT(4) CJ (3) u CJ6(5) (*F) (*F) (*F) 71 0.0 17.0 51 0.0 17.0 52 0.0 17.0 7 0.0 3.7 24 [ l 11.8 10 [ l 5.0 24 [ l 12.1 24 [ l 12.0 21 [ l 10.6 21 [ l 10.4 21 [ l 10.4 30 [ l 15.0 28 [ l 14.1 43 [ l 21.7 25 [ l 12.4 38 [ l 19.0 187 12.2 28.0 253 12.8 28.0 Margin RTPTS PTS Limit (*F) (*F) (*F) 34.0 145 270 34.0 135 270 34.0 126 270 7.3 55 270 64.7 96 270 61.0 79 270 64.9 97 270 64.8 96 270 63.8 93 270 63.7 92 270 63.7 92 270 49.5 75 270 48.5 72 270 59.8 96 270 46.6 67 270 56.1 87 270 61.1 215 300 61.6 261 300 Page 4.2-9 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.2-2:
RT PTS Calculations for Turkey Point Unit 4 Extended Beltline Materials at 72 EFPY Cu Ni CF(1l Fluence RT NDT(U)(3l t.RTNDT(4)
CJ (3) CJ ,l (5) Margin RTPTS PTS Reactor Vessel Material FF(2) u Limit (Wt.%) (Wt.%) (oF) (n/cm2, E>1.0 MeV) (OF) (oF) (OF) (OF) (OF) (OF) (OF) IS to LS using Surveillance Data 0.23 0.59 151.1 9.81 X 1019 1.51 -53.5 228 12.8 28.0 61.6 236 300 LS to Transition Ring Circumferential 0.23 0.52 157.4 1.36x1017 0.13 [ l 21 [ l 10.6 44.7 61 300 Weld Notes for Table 4.2.2-2 1. Value calculated using Regulatory Guide 1.99, Revision
: 2. 2. FF= fluence factor= f (0.28-0*10*1og(f))_ 3. Initial RT NOT values are for unirradiated material.
Note that au = 0&deg;F for measured test values. 4. .6RT NDT = CF
* FF where CF = chemistry factor. 5. Per 10 CFR 50.61, the base metal at.= 17&deg;F for Position 1.1 and at.= 8.5&deg;F for Position 2.1 with credible surveillance data; the weld metal at.= 28&deg;F for Position 1.1 and at.= 14&deg;F for Position 2.1 with credible surveillance data. However, at. need not exceed 0.5 *.6RT NOT* 6. Unit 4 has an additional outlet weld because of use of different material.
: 7. Inside 67%. Outside 33% N/A for PTS. Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Page 4.2-10 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.3-1 Turkey Point Unit 3 Predicted Position 1.2 USE Values at 72 EFPY Reactor Vessel Material Upper Shell (US) Forging Intermediate Shell (IS) Forging Lower Shell (LS) Forging Lower Head Ring (transition) US to IS Circumferential Weld IS to LS Circumferential Weld LS to Transition Ring Circumferent ial Weld Inlet Nozzle 1 Inlet Nozzle 2 Inlet Nozzle 3 Outlet Nozzle 1 Outlet Nozzle 2 Outlet Nozzle 3 Inlet Nozzle Weld 1 Inlet Nozzle Weld 2 Inlet Nozzle Weld 3 Outlet Nozzle Weld Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Cu (Wt.%) [ l 0.058 0.079 [ l 0.26 0.23 0.23 0.16 0.16 0.16 0.16 0.16 0.16 0.19 0.16 0.23 0.19 Unirradiated
%T EOL Fluence!1) USE (n/cm2, E>1.0 MeV) (ft-lb) 6.59 X 1011:l 99 6.78 X 1019 93 6.19 X 1019 100 1.02x1017 97 7.10 X 1018 [ l 6.19x1019 [ l 1.02 X 1017 [ l 1.27 X 1017 109 1.27x1017 109 1.27x1017 109 1.05 X 1017 109 1.05 X 1017 109 1.05 X 1017 109 1.27 X 1017 [ l 1.27 X 1017 [ l 1.27x1017 [ l 1.05 X 1017 [ l Projected Projected USE Decrease EOL (%)(2)(3)
USE(ft-lb) 17 82 30 65 30 70 19 58 36 41(4) 60 25(4) 22 50 15 93 15 93 15 93 15 93 15 93 15 93 20 51 18 52 22 50 19 52 Page 4.2-16 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.3-2 Turkey Point Unit 4 Predicted Position 1.2 USE Values at 72 EFPY Reactor Vessel Material Upper Shell (US) Forging Intermediate Shell (IS) Forging Lower Shell (LS) Forging Lower Head Ring (transition)
US to IS Circumferential Weld (Inner 67%) US to IS Circumferent ial Weld (Outer 33%) IS to LS Circumferential Weld LS to Transition Ring Circumferential Weld Inlet Nozzle 1 Inlet Nozzle 2 Inlet Nozzle 3 Outlet Nozzle 1 Outlet Nozzle 2 Outlet Nozzle 3 Inlet Nozzle Weld 1 Inlet Nozzle Weld 2 Inlet Nozzle Weld 3 Outlet Nozzle Weld 1 Outlet Nozzle Weld 2(6) Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Cu (Wt.%) [ l 0.054 0.056 [ l 0.26 0.32 0.23 0.23 0.08 0.16 0.16 0.16 0.16 0.16 0.19 0.16 0.34 0.16 0.34 %T EOL Fluence(1l Unirradiated USE (n/cm2, E>1.0 MeV) (ft-lb) 6.70 X 10115 103 6.78 X 1019 88 6.16 X 1019 97 1.02 X 1017 109 7.22 X 1018 [ l 2.85 X 1018 [ l 6.16 X 1019 [ l 1.02 X 1017 [ l 1.45 X 1017 109 1.45 X 1017 109 1.45 X 1017 105 1.17x1017 107 1.17x1017 104 1.17x1017 93 1.45 X 1017 [ l 1.45 X 1017 [ l 1.45 X 1017 [ l 1.17x1017 [ l 1.17x1017 [ l Projected Projected USE Decrease EOL (o/o)l 2 )(3) USE(ft-lb) 17 85 30 62 30 68 19 88 36 41 (4) 36 41(4)(5) 60 25(4) 11 50 15 97 15 93 15 89 15 91 15 88 15 79 20 51 18 52 30 45(4) 18 52 30 45(4) Page 4.2-18 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.4-1 Turkey Point Unit 3 ART Calculations for 72 EFPY Table 4.2.4-1: Turkey Point Unit 3 ART Calculations for 72 EFPY Reg. Guide 1.99 Y.T Fluence Y.T Y.T 3/.T Fluence 3/.T 3/.T Rev. 2 CF RTNDT(U) C1u (1 .,.,(1) Margin (n/cm2, Y.T ~RTNDT ART (n/cm2, 3/.T ~RTNDT ART Reactor Vessel Material Position (OF) Upper Shell (US) Forging 1.1 67.7 Intermediate Shell (IS) Forging 1.1 37.0 IS using Surveillance Data 2.1 6.9 Lower Shell (LS) Forging 1.1 51.0 LS using Surveillance Data 2.1 48.7 Lower Head Ring (transition
) 1.1 175.2 Inlet Nozzle 1 1.1 122.0 Inlet Nozzle 2 1.1 121.5 Inlet Nozzle 3 1.1 123.0 Outlet Nozzle 1 1.1 122.8 Outlet Nozzle 2 1.1 121.00 Outlet Nozzle 3 1.1 121.00 Inlet Nozzle Weld 1.1 152.4 Inlet Nozzle Weld 1.1 143.9 Inlet Nozzle Weld 1.1 167.6 Outlet Nozzle Weld 1.1 152.4 US to IS Circumferential Weld 1.1 180.0 Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application (OF) (OF) (OF) 50 0.0 17.0 40 0.0 17.0 40 0.0 5.0 30 0.0 17.0 30 0.0 17.0 [ l [ l 9.9 [ l [ l 8.3 [ l [ l 8.3 [ l [ l 8.4 [ l [ l 7.5 [ l [ l 7.4 [ l [ l 7.4 [ l [ l 10.4 [ l [ l 9.8 [ l [ l 11.4 [ l [ l 9.3 -33.2 12.2 28.0 (OF) E>1.0 MeV) FF (OF) (OF) E>1.0 MeV) FF (OF) (OF) 34.0 6.59 X 1018 0.88 59.8 144 2.24 X 1018 0.60 40 124 34.0 6.78 X 1019 1.46 53.9 128 2.68 X 1019 1.26 47 121 10.0 6.78 X 1019 1.46 10.0 60 2.68 X 1019 1.26 9 59 34.0 6.19 X 1019 1.44 73.6 138 2.44 X 1019 1.24 63 127 34.0 6.19x1019 1.44 70.2 134 2.44 X 1019 1.24 60 124 63.3 1 04 X 1017 0.11 19.7 91 N/A(2l N/A N/A N/A 62.4 1.38 X 1017 0.14 16.6 87 N/A(2l N/A N/A N/A 62.4 1.38 X 1017 0.14 16.5 87 N/A(2) N/A N/A N/A 62.5 1.38 X 1017 0.14 16.7 87 N/A(2) N/A N/A N/A 62.0 1.17 X 1017 0.12 14.9 85 N/A<2) N/A N/A N/A 62.0 1.17 X 1017 0.12 14.7 84 NtA<2> N/A N/A N/A 62.0 1.17x1017 0.12 14.7 84 NtA<2) N/A N/A N/A 44.5 1.38 X 1017 0.14 20.7 60 NtA<2> N/A N/A N/A 44.0 1.38 X 1017 0.14 19.6 59 NtA<2l N/A N/A N/A 45.5 1.38 X 1017 0.14 22.8 63 NtA<2l N/A N/A N/A 43.5 1.17x1017 0.12 18.5 57 N/A<2l N/A N/A N/A 61.1 7.10x1018 0.90 162.7 191 2.80 X 1018 0.65 117 145 Page 4.2-21 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.4-1: Turkey Point Unit 3 ART Calculations for 72 EFPY Reg. Guide 1.99 Y.T Fluence Y.T '/.T '/. T Flue nee '!.T Rev.2 CF RTNDT(U)
O"u 0"1/1) Margin (n/cm2, 'l*T LiRT NDT ART (n/cm2, *1.1 LiRT NDT Reactor Vessel Material Position (oF) (OF) (oF) (oF) (oF) E>1.0 MeV) FF (oF) (oF) E>1.0 MeV) FF (oF) IS to LS Circumferentia l Weld 1.1 167.6 -53.5 12.8 28.0 61.6 6.19x1019 1.44 241.7 250 2.44 X 1019 1.24 208 IS to LS using Surveillance 2.1 151.1 -53.5 12.8 28.0 61.6 6.19 X 1019 1.44 217.5 226 2.44 X 1019 1.24 187 Data LS to Transition Ring 1.1 157.4 [ l [ l 8.8 43.1 1.02 X 1017 0.11 17.5 56 N/A<2l N/A N/A Circumferential Weld Notes for Table 4.2.4-1 1. For %T t.RT NOT that is less than a Li* the %T used the same value as the a Li for %T for simplicity since the t.RT NOT for these materials were not limiting.
: 2. For the inlet and outlet nozzles and welds, and the lower transition ring and weld, only the %T attenuated fluences were calculated and considered equal at the %T locations.
'!.T ART (OF) 216 195 N/A Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Page 4.2-22 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.2.4-2 Turkey Point Unit 4 ART Calculations for 72 EFPY Reg. Guide 1.99 Y.T Fluence Y.T Y.T %T Fluence 3/.T %T Rev.2 CF RTNDT(U) O'u 0'~(1) Margin (nlcm2, Y.T ~RTNDT ART (nlcm2, %T ~RTNDT ART Reactor Vessel Material Position (oF) Upper Shell (US) Forging 1.1 67.9 Intermediate Shell (IS) Forging 1.1 33.4 Lower Shell (LS) Forging 1.1 34.6 LS using Surveillance Data 2.1 4.9 Lower Head Ring (transition) 1.1 175.2 Inlet Nozzle 1 1.1 51.0 Inlet Nozzle 2 1.1 123.4 Inlet Nozzle 3 1.1 121.8 Outlet Nozzle 1 1.1 122.5 Outlet Nozzle 2 1.1 120.0 Outlet Nozzle 3 1.1 120.5 Inlet Nozzle Weld 1 1.1 152.4 Inlet Nozzle Weld 2 1.1 143.9 Inlet Nozzle Weld 3 1.1 220.6 Outlet Nozzle Weld 1 1.1 143.9 Outlet Nozzle Weld 2 1.1 220.6 US to IS Circumferential Weld 1.1 180.0 Inside 67%<3) US to IS Circumferential Weld 1.1 199.3 Outside 33%(4) IS to LS Circumferent ial Weld 1.1 167.55 IS to LS using Surveillance Data 2.1 151.1 LS to Transition Ring 1.1 157.4 Circumferential Weld Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application (OF) (oF) (oF) 40 0.0 17.0 50 0.0 17.0 40 0.0 17.0 50 0.0 3.5 [ l [ l 9.8 [ l [ l 3.6 [ l [ l 8.7 [ l [ l 8.5 [ l [ l 7.5 [ l [ l 7.3 [ l [ l 7.3 [ l [ l 10.7 [ l [ l 10.1 [ l [ l 15.5 [ l [ l 8.8 [ l [ l 13.5 -33.2 12.2 28.0 -31.1 13.7 28.0 -53.5 12.8 28.0 -53.5 12.8 28.0 [ l [ l 8.8 (oF) E>1.0 MeV) FF (OF) (OF) E>1.0 MeV) FF (oF) (oF) 34.0 6.70 X 10 10 0.89 60.3 134 2.28 X 10 10 0.60 41 115 34.0 6.78 X 1019 1.46 48.7 133 2.68 X 101" 1.26 42 126 34.0 6.16 X 101" 1.44 49.9 124 2.43x101" 1.24 43 117 7.0 6.16 X 101" 1.44 7.0 54 2.43x10rn 1.24 6 53 63.3 1.02 X 1011 0.11 19.5 90 NIAl2! NIA NIA NIA 60.6 1.45 X 101 I 0.14 7.2 75 NIAl2! NIA NIA NIA 62.6 1.45 X 1011 0.14 17.3 88 NIAl2J NIA NIA NIA 62.6 1.45 X 1011 0.14 17.1 87 NIN"! NIA NIA NIA 62.0 1.17 X 1011 0.12 14.9 85 NIN"! NIA NIA NIA 62.0 1.17 X 1011 0.12 14.6 84 NIN"! NIA NIA NIA 62.0 1.17x1011 0.12 14.7 84 NIN"! NIA NIA NIA 44.8 1.45x1017 0.14 21.4 61 NINL! NIA NIA NIA 44.3 1.45x1017 0.14 20.2 60 NIAl2! NIA NIA NIA 51.5 1.45 X 1011 0.14 31.0 76 NIAl2! NIA NIA NIA 43.1 1.17x1017 0.12 17.6 56 NIA<2J NIA NIA NIA 49.2 1.17x1017 0.12 26.9 69 NIN2J NIA NIA N/A 61.1 7.22 X 1018 0.91 163.6 191 NIA NIA N/A N/A 62.3 NIA N/A NIA N/A 2.85 X 1018 0.66 131 162 61.6 6.16 X 1019 1.44 241.5 250 2.43x101" 1.24 208 216 61.6 6.16 X 101" 1.44 217.7 226 2.43 X 101" 1.24 187 195 43.1 1.02 X 1017 0.11 17.5 56 N/A<2l N/A N/A NIA Page 4.2-23 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Table 4.3-1 PTN Unit 3 and Unit 4 60-Year Fatigue Cumulative Usage Factors for Reactor Coolant System Components Component Reactor Vessel Head flange Vessel flange Stud bolts Outlet nozzles Inlet nozzles Core support pad Shell at core support pads Bottom head to shell juncture Bottom-mounted instrumentation Shell to shell juncture Vent nozzle CROM housing J-weld CROM housing bi-metallic weld CROM latch housing CROM rod travel housing CROM cap CROM lower joint CROM middle joint CROM upper joint Reactor Vessel Internals Upper support plate Deep beam Upper core plate Upper core plate alignment pins Upper support columns Lower support plate Lower support plate to core barrel weld Lower core plate Lower support columns Core barrel flange Core barrel outlet nozzle Radial keys and clevis insert assembly Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Cumulative Usage o.oa3(1J 0.531(1) 0.81 (1) 0.063(1) 0.066(1) 0.020(1) o.509<1J 0.023(1) 0.002<1) 0.034(1) [ ll"I 0.730(1) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ ](2) [ 1(2) [ ](2) [ fl [ ](2) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ 1(2) [ ](2) Allowable 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Page 4.3-5 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses than 1. These additional analyses are further described below and provided in detail in the references noted below, copies of which are provided in Enclosure 4 (non-proprietary) and Enclosure 5 (proprietary)
. Reactor Vessel Flange -CUF:fill Screening=
3.333 A revised CU Fen was calculated by performing a more refined analysis and crediting 80-year projected design cycles for plant heatup, cooldown, loading, unloading
, and rapid power increases and decreases
.' CUFen Final= 0.373 Reference 4.3.6.25 Reactor Vessel Shell at Core Support Pads -CUFen Screening=
2.428 A revised CUF en was calculated by crediting 80-year projected design cycles for the hydrostatic test at 2485 psig pressure and 400&deg;F temperature
. CU Fen Final= 0.910 Reference 4.3.6.19 Reactor Vessel Vent Nozzle -CU F .en Screening
= [ ] A revised CU Fen was calculated by performing a finite element fatigue calculation using the methodology of Subarticle NB-3200 of Section Ill of the ASME Code. CUFen Final= 0.230 Reference 4.3.6.24 CROM Housing J-Weld -CUF.e.n Screening=
2.738 A revised CU Fen was calculated by performing a more refined analysis and crediting 80-year projected design cycles for plant heatup, cooldown, loading, unloading
, and rapid power increases and decreases
. CUFen Final= 0.274 Reference 4.3.6.22 CROM Housing Bi-metallic Weld -CUF.e.n Screening=
[ ] A revised CU Fen was calculated by performing a more refined analysis and crediting 80-year projected design cycles for plant heatup, cooldown, and reactor trips. CUFen Final= 0.695 Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Reference 4.3.6.21 Page 4.3-22 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses CROM Latch Housing -CUFM Screening=
[ ] A revised CU Fen was calculated by performing a more refined analysis and crediting 80-year projected design cycles for plant heatup, plant loading and reactor trips. CUFen Final= 0.269 Reference 4.3.6.23 CROM Lower Joint-CUFM Screening=
[ A revised CU Fen was calculated by performing a more refined analysis and crediting 80-year projected design cycles for plant heatup, 10% step load increases
, 50% step load decreases
, loss of load, loss of AC power, and reactor trips (Unit 4 only). CUFen Final= 0.749 Reference 4.3.6.26 Steam Generator Divider Plate -CUFM Screening=
[ ] A revised CU Fen was calculated by crediting 80-year projected design cycles for plant heatup and cooldown, loading and unloading and 10% step load increases and decreases.
CUFen Final= 0.881 Reference 4.3.6.20 Steam Generator Tubes -CUFM Screening=
[ ] A revised CU Fen was calculated by crediting 80-year projected design cycles for plant heatup and cooldown, loading and unloading and 10% step load increases and decreases
. CUFen Final= 0.903 Reference 4.3.6.20 Pressurizer Spray Nozzle -CUFM Screening=
[ ] A revised CU Fen was calculated by performing a finite element fatigue calculation using the methodology of Subarticle NB-3200 of Section Ill of the ASME Code and projected design cycles for plant heatup and cooldown. CUFen Final= 0.529 Reference 4.3.6.29 Pressurizer Upper Head -CUFfill Screening=
[ ] A revised CU Fen was calculated by crediting 80-year projected design cycles for plant loading, unloading
, and boron concentration equalization transients.
CUFen Final= 0.974 Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Reference 4.3.6.19 Page 4.3-23 Withheld from Public Disclosure Under 10 CFR 2.390 Section 4 -Time-Limited Aging Analyses Heater Well -CUF.M Screening=
[ ] A revised CUFen was calculated by performing a finite element fatigue calculation using the methodology of Subarticle NB-3200 of Section Ill of the ASME Code and projected design cycles for plant heatup and cooldown.
CUF en Final = 0.093 Reference 4.3.6.28 As described above, the projected environmentally assisted CUFs (CUFens) are maintained less than 1.0 for all applicable reactor coolant pressure boundary components with the exception of the pressurizer surge lines. In lieu of additional analyses to refine the CUFen for the pressurizer surge lines, PTN has selected aging management to address pressurizer surge line fatigue during the SPEO as is currently done for the PEO. In particular
, the potential for crack initiation and growth, including reactor water environmental
: effects, is adequately managed during the SPEO by the plant-specific PTN Pressurizer Surge Line Fatigue AMP (Section B.2.4.1 ). The technical basis and conclusions of the current flaw tolerance analysis of the pressurizer surge lines (Reference 4.3.6.12) remain applicable for the SPEO. The surge line inspection approach was submitted to the NRC for review in 2012 (Reference 4.3.6.13), and was subsequently approved by the NRC in 2013 (Reference 4.3.6.14). The flaw tolerance analysis of the pressurizer surge lines establishes inspection frequency for the Pressurizer Surge Line Fatigue AMP; however, the flaw tolerance analysis does not consider the life of the plant and is not a TLAA. In addition, there are no new aging affects requiring management for the pressurizer surge lines during the SPEO. For the SPEO, the effects of EAF for the PTN pressurizer surge line welds will continue to be managed by an inspection program consistent with the Pressurizer Surge Line Fatigue AMP approved by the NRC for the current PEO. Results of the pressurizer surge line examinations performed to date are presented in Section B.2.4.1. TLAA Disposition:
10 CFR 54.21(c)(1)(iii)
For the Class 1 reactor coolant pressure boundary components associated with the reactor vessels, pressurizers, steam generators, and reactor coolant pumps with calculated ASME Section Ill CUFs, and NUREG/CR-6260 locations
, the environmentally assisted fatigue analyses will be managed using the Fatigue Monitoring AMP (Section B.2.2.1) and assure that corrective action specified in the program is taken if any of the actual cycles approach 80 percent of their projected or design analyzed limits, as applicable
. For the pressurizer surge line, PTN will manage the effects of aging due to fatigue on the pressurizer surge line for the SPEO by implementing surface and volumetric examination of the welds using the Pressurizer Surge Line Fatigue AMP (Section B.2.4.1) in accordance with 10 CFR 54.21(c)(1)(iii)
. Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Page 4.3-24}}

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