L-2018-053, Replacement Pages to Enclosure 3, Slra Section 4

Replacement Pages to Enclosure 3, Slra Section 4

ML18078A027
Person / Time
Site:	Turkey Point
Issue date:	02/16/2018
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML18053A123	List: L-2018-053, Replacement Pages to Enclosure 3, SLRA Section 4
References
L-2018-053
Download: ML18078A027 (13)

Text

Withheld from Public Disclosure Under 10 CFR 2.390 Sect i on 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 She ll (US) Forging [ l Intermed iate Shell (IS} Forging 0.058 IS u s ing Surve illance Da ta 0.058 Lower S hell (LS} Forging 0.079 LS using Surve illance Data 0.079 Lower Head Ring (transition) [ l Inlet Nozz l e 1 0.16 Inlet Nozz le 2 0.16 Inlet Nozzle 3 0.16 Outlet No zzle 1 0.16 O utlet Nozzle 2 0.16 Outlet Nozzle 3 0.16 In let Nozzle Weld 1 0.19 In l et Nozzle Weld 2 0.16 Inlet Nozzle Weld 3 0.23 Out l et No zzle Weld 0.19 US to IS C ircumferential Weld 0.26 IS to LS C ircumferential Weld 0.23 Turk ey Po int Nuclear P l a nt Units 3 and 4 Subsequen t L ic ense Rene wal Application Ni (Wt.%) 0.68 0.7 0 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) (o F) (n/cm 2 , E>1.0 MeV) FF<2> (o F) 67.7 1.13x10 19 1.03 50 37.0 1.08 X 10 20 1.52 40 6.9 1.08 X 10 20 1.52 40 51.0 9.86 X 10 19 1.51 30 48.7 9.86 X 10 19 1.51 30 175.2 1.36 X 10 17 0.13 [ l 122.00 2.37 X 10 17 0.19 [ l 121.50 2.37 X 10 17 0.19 [ l 123.00 2.37 X 10 1 7 0.19 [ l 122.8 2.00 X 10 17 0.17 [ l 121.00 2.00 X 10 17 0.17 [ l 121.00 2.00 X 10 1 7 0.17 [ l 152.4 2.37 X 10 1 7 0.19 [ l 143.9 2.37 X 10 17 0.19 [ l 167.6 2.37 X 10 1 7 0.19 [ l 152.4 2.00 X 10 1 7 0.17 [ l 180.0 1.13x10 19 1.03 -3 3.2 167.6 9.86 X 10 19 1.51 -53.5 £\RT NDT (4) C1 (3) u c, 1/5) (O F) (OF) (oF) 70 0.0 1 7.0 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) (o F) 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 fr o m 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(1 l Fluence RT NDT(U)(3 l ti RT NDT(4) CJ (3) (1 6 (5) Margin RTPTS Li m it u Reactor Vessel Material (Wt.%) (Wt.%) (OF) (n/cm 2 , E>1.0 MeV) FF(2) (oF) (OF) (OF) (OF) (oF) (oF) (oF) IS to LS using Surve il lance Data 0.23 0.59 151.1 9.86 X 10 19 1.51 -53.5 228 12.8 28.0 61.6 236 300 LS to Transition Ring Circumferent i al 0.23 0.52 157.4 1.36x10 17 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 , Revisi o n 2. 2. FF= fluence factor= f (0-28-0 1 0*log(f))_ 3. Initial RT NDT values are for unirradiated material.

Note that au = 0°F for measured test values. 4. t.RT NOT= C F* FF wh e re CF= chemistry factor. 5. Per 10 CFR 50.61, the base metal a ti= 17°F for Position 1.1 and a ti = 8.5°F for Position 2.1 with credible surveillance data; the weld metal a ti = 28°F for Position 1.1 and a ti = 14°F for Position 2.1 with credible surveillance data. However , a ti need not exceed 0.5 *t.RT NDT* Turkey Point Nu c lear 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 Sh ell (IS) Forging 0.054 Lower Shell (LS) Forging 0.056 LS using Surveillance Data 0.056 Lower Head Ring (tr ansition) [ l Inlet Nozzle 1 0.08 Inlet Nozzle 2 0.1 6 Inlet Nozzle 3 0.16 Outlet No zzle 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 0.1 6 Outlet Nozzle Weld 21 6) 0.34 US to IS Circumfe renti al Weld<7 l 0.26 IS to LS C ircumferential Weld 0.23 Turkey Point Nuclear P lan t 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 CFl 1 l Fluence RT NDT(U) <3) FFl 2 l (*F) (n/cm 2 , E>1.0 MeV) (*F) 67.9 1.15 X 10 1 9 1.04 40 33.4 1.08 X 10 20 1.52 50 34.6 9.81 X 10 1 9 1.51 40 4.9 9.81 X 10 1 9 1.51 40 175.2 1.3 6 X 10 17 0.13 [ l 5 1.0 2.49 X 10 17 0.20 [ l 123.4 2.49 X 10 1 7 0.20 [ l 121.8 2.49 X 10 17 0.20 [ l 122.5 2.01 X 10 1 7 0.17 [ l 120.0 2.01 X 10 1 7 0.17 [ l 120.5 2.01 X 10 1 7 0.17 [ l 152.4 2.49 X 10 17 0.20 [ l 143.9 2.49 X 10 17 0.20 [ l 220.6 2.49 X 10 17 0.20 [ l 143.9 2.01 X 10 17 0.17 [ l 220.6 2.01 X 10 17 0.17 [ l 180.0 1.15x10 1 9 1.04 -33.2 167.6 9.81 X 10 19 1.51 -53.5 il RT NDT(4) CJ (3) u CJ 6 (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(1 l Fluence RT NDT(U)(3 l t.RTNDT(4)

CJ (3) CJ ,l (5) Margin RTPTS PTS Reactor Vessel Material FF(2) u Limit (Wt.%) (Wt.%) (oF) (n/cm 2 , 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 10 1 9 1.51 -53.5 228 12.8 28.0 61.6 236 300 LS to Transit i on Ring Circumferential 0.23 0.52 157.4 1.36x10 1 7 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*1 og (f))_ 3. Initial RT NOT values are for unirradiated material.

Note that au = 0°F for measured test values. 4. .6RT NDT = CF

• FF where CF = chemistry factor. 5. Per 10 CFR 50.61 , the base metal a t.= 17°F for Position 1.1 and a t.= 8.5°F for Position 2.1 with credible surveillance data; the weld metal a t.= 28°F for Position 1.1 and a t.= 14°F for Position 2.1 with credible surveillance data. However , a t. 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 (transit i on) US to IS Circumferential Weld IS to LS Circumferential Weld LS to Transition R i ng Circumferent i al We l d 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 N o zzle Weld Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Appl i cation 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/cm 2 , E>1.0 MeV) (ft-lb) 6.59 X 10 1 1:l 99 6.78 X 10 1 9 93 6.19 X 10 1 9 100 1.02x10 17 97 7.10 X 10 1 8 [ l 6.19x10 1 9 [ l 1.02 X 10 17 [ l 1.27 X 10 17 109 1.27x10 1 7 109 1.27x10 1 7 109 1.05 X 10 1 7 109 1.05 X 10 1 7 109 1.05 X 10 17 109 1.27 X 10 1 7 [ l 1.27 X 10 17 [ l 1.27x10 17 [ l 1.05 X 10 17 [ 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 S hell (LS) Forging Lower Head Ring (transition)

US to IS Circumferential Weld (Inner 67%) US to IS Circumferent i al Weld (Outer 33%) IS to LS Circumferential Weld LS to Transition Ring C ir cumferential Weld Inlet Nozzle 1 Inlet Nozzle 2 Inlet N o zzle 3 Outlet Nozzle 1 Outlet Nozzle 2 Outlet Nozzle 3 Inlet Nozzle Weld 1 Inlet Nozzle Weld 2 Inlet Nozzle Weld 3 Outlet N o zzle Weld 1 Outlet Nozzle Weld 2 (6) Turkey P o int Nuclear Plant Units 3 and 4 Subsequent License Renewal Applicat i on 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 0.1 6 0.19 0.16 0.34 0.16 0.34 %T EOL Fluence(1l Unirradiated USE (n/cm 2 , E>1.0 MeV) (ft-lb) 6.70 X 10 115 103 6.78 X 10 19 88 6.16 X 10 1 9 97 1.02 X 10 1 7 109 7.22 X 10 1 8 [ l 2.85 X 10 18 [ l 6.16 X 10 19 [ l 1.02 X 10 17 [ l 1.45 X 10 1 7 109 1.45 X 10 17 109 1.45 X 10 17 105 1.17x10 17 107 1.17x10 17 104 1.17x10 17 93 1.45 X 10 17 [ l 1.45 X 10 17 [ l 1.45 X 10 17 [ l 1.17x10 17 [ l 1.17x10 17 [ l Projected Projected USE Decrease EOL (o/o)l 2 )(3) U S E(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 S ecti o n 4 -Time-Lim i ted A g ing A n alyse s T ab l e 4.2.4-1 Turkey Point Unit 3 ART Ca l cu l ations for 72 EFP Y T able 4.2.4-1: Tu rk e y Poi nt Un i t 3 ART C a lcu la ti ons fo r 72 EFPY Reg. Gu i de 1.99 Y.T Fluence Y.T Y.T 3/.T Fluen c e 3/.T 3/.T Rev. 2 CF RT N DT(U) C1u (1 .,.,(1) Margin (n/cm 2 , Y.T ~RTNDT ART (n/cm 2 , 3/.T ~RTNDT ART Re a cto r Vessel Ma t e r ial Po si tio n (O F) Upper Shell (US) Forging 1.1 67.7 Intermediate S hell (I S) Forg i ng 1.1 37.0 IS using Surveillance D ata 2.1 6.9 Lower Shell (L S) F orging 1.1 51.0 LS using Surveil l ance Data 2.1 48.7 Lower H ead Ring (transition) 1.1 175.2 Inlet N ozzle 1 1.1 122.0 Inlet Nozz l e 2 1.1 121.5 I nl et Nozzle 3 1.1 123.0 O utlet Nozzle 1 1.1 122.8 O u t let N ozzle 2 1.1 12 1.00 O utlet N ozz l e 3 1.1 121.00 I nlet Nozzl e W e ld 1.1 152.4 I nlet N ozzle Weld 1.1 143.9 In l et N ozzle Weld 1.1 167.6 Out le t N ozzle W eld 1.1 152.4 US to IS C ir c umf e rentia l Weld 1.1 180.0 T u rk ey Poin t N u clea r P l an t Un it s 3 an d 4 S u bse qu ent Li c en se Re n ewa l A p pli c a t i o n (O F) (O F) (O F) 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 (O F) E>1.0 MeV) FF (O F) (O F) E>1.0 MeV) FF (O F) (O F) 34.0 6.59 X 10 1 8 0.8 8 59.8 144 2.24 X 10 18 0.60 40 124 34.0 6.78 X 10 1 9 1.46 53.9 128 2.68 X 10 19 1.26 47 121 10.0 6.78 X 10 1 9 1.46 10.0 60 2.68 X 10 19 1.26 9 59 34.0 6.19 X 10 1 9 1.44 73.6 138 2.44 X 10 19 1.24 63 1 27 34.0 6.19 x 10 1 9 1.44 70.2 134 2.44 X 10 1 9 1.24 60 124 63.3 1 04 X 10 17 0.1 1 19.7 91 N/A (2 l N/A N/A N/A 62.4 1.38 X 10 17 0.14 16.6 87 N/A (2 l N/A N/A N/A 62.4 1.38 X 10 17 0.14 16.5 87 N/A(2) N/A N/A N/A 62.5 1.38 X 10 1 7 0.14 16.7 87 N/A (2) N/A N/A N/A 62.0 1.17 X 10 17 0.12 14.9 85 N/A<2) N/A N/A N/A 62.0 1.17 X 10 17 0.12 14.7 84 NtA<2> N/A N/A N/A 62.0 1.17x10 1 7 0.12 14.7 84 N tA<2) N/A N/A N/A 44.5 1.38 X 10 1 7 0.14 20.7 60 N t A<2> N/A N/A N/A 44.0 1.38 X 10 17 0.14 19.6 59 N t A<2 l N/A N/A N/A 45.5 1.3 8 X 10 17 0.14 22.8 63 N tA<2 l N/A N/A N/A 43.5 1.17x10 17 0.12 18.5 57 N/A<2 l N/A N/A N/A 61.1 7.10x10 1 8 0.90 162.7 19 1 2.80 X 10 18 0.65 117 14 5 Page 4.2-2 1 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/cm 2 , 'l*T Li RT NDT ART (n/cm 2 , *1.1 Li RT NDT React o r Vessel Material Position (o F) (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 6.19x10 19 1.44 241.7 250 2.44 X 10 19 1.24 208 IS to LS using Surveillance 2.1 1 51.1 -53.5 12.8 28.0 61.6 6.19 X 10 19 1.44 217.5 226 2.44 X 10 19 1.24 187 Data LS to Transition Ring 1.1 157.4 [ l [ l 8.8 43.1 1.02 X 10 17 0.11 17.5 56 N/A<2 l 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 P o int Nuclear Plant Units 3 and 4 Subsequent License Renewal Application Page 4.2-22 Withheld from Public Disclosure Under 10 CFR 2.390 Se cti o n 4 -T ime-Li m it e d Aging An al y ses Tab l e 4.2.4-2 Turkey Po i nt Unit 4 ART Calculations fo r 72 EFPY Reg. Gu ide 1.99 Y.T Flue n ce Y.T Y.T %T Flu e nce 3/.T %T Rev.2 CF R TND T(U) O'u 0'~(1) Ma r gin (n l cm 2 , Y.T ~RTND T ART (nlcm 2 , %T ~RTNDT ART Reac t or Vessel Ma t erial Position (o F) Upp e r Shel l (US) F orging 1.1 6 7.9 Int ermedi a t e She ll (I S) Forging 1.1 33.4 L ower Shell (LS) F o r g i n g 1.1 34.6 LS using S urve i llance D ata 2.1 4.9 Lower He ad Ring (t r an s i ti o n) 1.1 1 75.2 In l et Nozzle 1 1.1 51.0 I n l et Nozzle 2 1.1 1 2 3.4 In l e t Nozzle 3 1.1 121.8 O utlet N ozzle 1 1.1 1 22.5 O utlet N ozz l e 2 1.1 1 20.0 Outlet No zz l e 3 1.1 1 2 0.5 Inlet N ozzle We l d 1 1.1 152.4 I n let Nozzle We l d 2 1.1 1 4 3.9 Inle t Nozzle We l d 3 1.1 220.6 Outlet Nozz l e Weld 1 1.1 1 4 3.9 O utle t No zz l e We l d 2 1.1 220.6 US to I S C ir cum f er e ntial W e l d 1.1 180.0 I n s i de 67%<3) US to I S C i r cumferen t ial We l d 1.1 1 9 9.3 Outs i de 33%(4) IS to L S C ir cumferent i a l Weld 1.1 16 7.55 I S to LS using S urv e i llance D ata 2.1 1 5 1.1 L S t o T r a nsition R ing 1.1 157.4 C i rcumferential We l d Tur k ey Po i n t N u clea r Plant U nit s 3 and 4 Subseq u e nt License Rene w a l A pp li c a t i o n (O F) (o F) (o F) 40 0.0 17.0 5 0 0.0 1 7.0 4 0 0.0 1 7.0 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 1 0.1 [ l [ l 15.5 [ l [ l 8.8 [ l [ l 13.5 -33.2 12.2 28.0 -31.1 1 3.7 28.0 -5 3.5 1 2.8 28.0 -53.5 12.8 28.0 [ l [ l 8.8 (o F) E>1.0 MeV) FF (O F) (OF) E>1.0 MeV) FF (o F) (o F) 3 4.0 6.70 X 10 10 0.89 6 0.3 134 2.28 X 10 10 0.60 41 115 34.0 6.7 8 X 10 19 1.46 48.7 13 3 2.68 X 10 1" 1.2 6 4 2 12 6 34.0 6.1 6 X 10 1" 1.44 49.9 12 4 2.4 3x 10 1" 1.24 4 3 1 17 7.0 6.16 X 10 1" 1.44 7.0 54 2.43 x 10 rn 1.24 6 53 6 3.3 1.02 X 10 11 0.11 19.5 90 N I A l 2! N I A N I A N I A 6 0.6 1.45 X 10 1 I 0.14 7.2 75 N I A l 2! N I A N I A N I A 6 2.6 1.45 X 10 11 0.14 17.3 8 8 N I A l 2 J N I A N I A N I A 62.6 1.45 X 1 0 11 0.1 4 17.1 8 7 N I N"! N I A N I A N I A 62.0 1.1 7 X 10 11 0.1 2 14.9 8 5 N I N"! N I A N I A N I A 62.0 1.1 7 X 10 11 0.1 2 1 4.6 84 N I N"! N I A N I A N I A 62.0 1.17 x 10 11 0.1 2 1 4.7 84 N I N"! N I A N I A N I A 44.8 1.45 x 10 17 0.1 4 2 1.4 6 1 N I N L! N I A N I A N I A 44.3 1.45 x 10 1 7 0.1 4 20.2 6 0 N I A l 2! N I A N I A N I A 51.5 1.45 X 10 1 1 0.14 3 1.0 76 N I A l 2! N I A N I A N I A 4 3.1 1.1 7x 10 1 7 0.1 2 17.6 56 N I A<2 J N I A N I A NI A 49.2 1.17 x 10 17 0.12 2 6.9 69 N I N 2 J N I A N I A N/A 6 1.1 7.22 X 10 1 8 0.91 1 63.6 19 1 N I A N I A N/A N/A 62.3 N I A N/A N I A N/A 2.85 X 10 18 0.66 131 162 61.6 6.16 X 10 19 1.44 241.5 250 2.43 x 10 1" 1.24 208 216 61.6 6.1 6 X 10 1" 1.44 21 7.7 2 2 6 2.4 3 X 10 1" 1.24 187 19 5 4 3.1 1.02 X 10 17 0.11 17.5 56 N/A<2 l N/A N/A N I A 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 Uni ts 3 and 4 Subsequent License Renewal Application Cumulative Usage o.oa3(1 J 0.531(1) 0.81 (1) 0.063(1) 0.066(1) 0.020(1) o.509<1 J 0.023(1) 0.002<1) 0.034(1) [ l l"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°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 I l l 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 F e n 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 Un i ts 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 credit i ng 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