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 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 PTS Cu Ni CF<1> Fluence RT NDT(U)( 3 ) £\RT NDT(4) C1 (3) u c, / 5) 1 Margin RTPTS Limit Reactor Vessel Material (Wt.%) (Wt.%) (oF) (n/cm 2 , E>1.0 MeV) FF<2 > (oF) (OF) (OF) (oF) (oF) (oF) (oF) 19 Upper Shell (US ) Forging [l 0.68 67 .7 1.13x10 1.03 50 70 0.0 17.0 34. 0 154 270 Intermediate Shell (IS} Forging 0.058 0.70 37.0 1.08 X 1020 1.52 40 56 0.0 17.0 34.0 130 270 20 IS using Surveillance Data 0.058 0.70 6.9 1.08 X 10 1.52 40 10 0.0 5.2 10.5 61 270 Lower Shell (LS } Forging 0.079 0.67 51 .0 9.86 X 10 19 1.51 30 77 0.0 17.0 34.0 141 270 LS using Surveillance Data 0.079 0.67 48.7 9.86 X 10 19 1.51 30 74 0.0 8.5 17.0 121 270 17 Lower Head Ring (transition ) [l 0.69 175.2 1.36 X 10 0.13 [l 24 [l 11.8 64 .7 96 270 Inlet Nozzle 1 0.16 0.76 122.00 2.37 X 10 17 0.19 [l 23 [l 11 .6 64.5 96 270 17 Inlet Nozzle 2 0.16 0.74 121 .50 2.37 X 10 0.19 [l 23 [l 11.6 64.5 95 270 17 Inlet Nozzle 3 0.16 0.8 123.00 2.37 X 10 0.19 [l 23 [l 11 .7 64.6 96 270 Outlet Nozzle 1 0.16 0.79 122.8 2.00 X 10 17 0.17 [l 21 [l 10.6 63.8 93 270 17 Outlet Nozzle 2 0.16 0.72 121 .00 2.00 X 10 0.17 [l 21 [l 10.4 63.7 92 270 Outlet Nozzle 3 0.16 0.72 121 .00 2.00 X 10 17 0.17 [l 21 [l 10.4 63.7 92 270 17 In let Nozzle Weld 1 0.19 0.57 152.4 2.37 X 10 0.19 [l 29 [l 14.5 49.0 73 270 In let Nozzle Weld 2 0.16 0.57 143.9 2.37 X 10 17 0.19 [l 27 [l 13.7 48.0 71 270 17 Inlet Nozzle Weld 3 0.23 0.59 167.6 2.37 X 10 0.19 [l 32 [l 16.0 50.7 78 270 Outlet Nozzle Weld 0.19 0.57 152.4 2.00 X 10 17 0.17 [l 26 [l 13.1 47.3 69 270 US to IS Circumferential Weld 0.26 0.60 180.0 1.13x10 19 1.03 -33.2 186 12.2 28 .0 61 .1 214 300 19 IS to LS Circumferential Weld 0.23 0.59 167.6 9.86 X 10 1.51 -53.5 253 12.8 28.0 61 .6 261 300 Turkey Point Nuclear Pla nt Units 3 and 4 Page 4 .2-7 Subsequent License Renewal Application

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) u (16 (5)

Margin RTPTS Li m it Reactor Vessel Material (Wt.%) (Wt.%) (OF) (n/cm 2 , E>1.0 MeV) FF( 2 ) (oF) (OF) (OF) (OF) (oF) (oF) (oF) 19 IS to LS using Surveillance Data 0.23 0.59 151 .1 9.86 X 10 1.51 -53 .5 228 12.8 28.0 61 .6 236 300 LS to Transition Ring Circumferential 0.23 0.52 157.4 1.36x10 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 on 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 ere CF= chemistry factor.

5. Per 10 CFR 50 .61, the base metal a ti= 17°F for Position 1.1 and ati = 8.5°F for Position 2 .1 with credible surveillance data; the

weld metal ati 28°F for Position 1.1 and ati 14°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 Page 4 .2-8 Subsequent License Renewal Application

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 Fluence 3 PTS Cu Ni CFl 1 l RT NDT(U) < ) ilRT NDT(4) CJ (3) CJ6 (5) Margin RTPTS Reactor Vessel Material FFl 2 l u Limit (Wt.%) (Wt.%) (*F) (n/cm 2 , E>1.0 MeV) (*F) (*F) (*F) (*F) (*F) (*F)

(*F)

Upper Shell (US) Forging [l 0.70 67.9 1.15 X 10 19 1.04 40 71 0.0 17.0 34 .0 145 270 20 Intermediate Shell (IS ) Forging 0.054 0.69 33.4 1.08 X 10 1.52 50 51 0.0 17.0 34.0 135 270 19 Lower Shell (LS) Forging 0.056 0.74 34.6 9.81 X 10 1.51 40 52 0.0 17.0 34.0 126 270 LS using Surveillance Data 0.056 0.74 4.9 9.81 X 10 19 1.51 40 7 0.0 3.7 7.3 55 270 17 Lower Head Ring (transition ) [l 0.69 175.2 1.36 X 10 0.13 [l 24 [l 11 .8 64.7 96 270 Inlet Nozzle 1 0.08 0.71 51.0 2.49 X 10 17 0.20 [l 10 [l 5.0 61 .0 79 270 17 Inlet Nozzle 2 0.1 6 0.84 123.4 2.49 X 10 0.20 [l 24 [l 12.1 64.9 97 270 17 Inlet Nozzle 3 0.16 0.75 121 .8 2.49 X 10 0.20 [l 24 [l 12.0 64.8 96 270 Outlet Nozzle 1 0.16 0.78 122.5 2.01 X 10 17 0.17 [l 21 [l 10.6 63.8 93 270 17 Outlet Nozzle 2 0.16 0.68 120.0 2.01 X 10 0.17 [l 21 [l 10.4 63.7 92 270 Outlet Nozzle 3 0.16 0.70 120.5 2.01 X 10 17 0.17 [l 21 [l 10.4 63.7 92 270 17 Inlet Nozzle Weld 1 0.19 0.57 152.4 2.49 X 10 0.20 [l 30 [l 15.0 49.5 75 270 Inlet Nozzle Weld 2 0.16 0.57 143.9 2.49 X 10 17 0.20 [l 28 [l 14.1 48.5 72 270 Inlet Nozzle Weld 3 0.34 0.68 220.6 2.49 X 10 17 0.20 [l 43 [l 21.7 59.8 96 270 17 Outlet Nozzle Weld 1 0.1 6 0.57 143.9 2.01 X 10 0.17 [l 25 [l 12.4 46.6 67 270 Outlet Nozzle Weld 216 ) 0.34 0.68 220.6 2.01 X 10 17 0.17 [l 38 [l 19.0 56.1 87 270 7 19 US to IS Circumfe rential Weld< l 0.26 0.60 180.0 1.15x10 1.04 -33.2 187 12.2 28 .0 61 .1 215 300 IS to LS Circumferential Weld 0.23 0.59 167.6 9.81 X 10 19 1.51 -53 .5 253 12.8 28.0 61.6 261 300 Turkey Point Nuclear P lant Units 3 and 4 Page 4 .2-9 Subsequent License Renewal Application

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 PTS Cu Ni CF( 1l Fluence FF(2) RT NDT(U)( 3l t.RTNDT(4) CJ u

(3) CJ,l(5) Margin RTPTS Reactor Vessel Material Limit (Wt.%) (Wt.%) (oF) (n/cm 2, E>1.0 MeV) (OF) (oF) (OF) (OF) (OF) (OF)

(OF) 19 IS to LS using Surveillance Data 0.23 0.59 151 .1 9.81 X 10 1.51 -53.5 228 12.8 28.0 61 .6 236 300 LS to Transition Ring Circumferential 0.23 0.52 157.4 1.36x10 17 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°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°F for Position 1.1 and at. = 8.5°F for Position 2.1 with credible surveillance data; the weld metal at. = 28°F for Position 1.1 and at. = 14°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 Page 4.2-10 Subsequent License Renewal Application

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 Unirradiated Projected Projected Cu %T EOL Fluence! 1) USE USE Decrease EOL Reactor Vessel Material (Wt.%) (n/cm 2, E>1.0 MeV) (ft-lb) (%)(2)(3) USE(ft-lb)

Upper Shell (US) Forging [l 6.59 X 10 11:l 99 17 82 19 Intermediate Shell (IS) Forging 0.058 6.78 X 10 93 30 65 Lower Shell (LS) Forging 0.079 6.19 X 10 19 100 30 70 17 Lower Head Ring (transition) [l 1.02x10 97 19 58 18 41 (4 )

US to IS Circumferential Weld 0.26 7.10 X 10 [l 36 IS to LS Circumferential Weld 0.23 6.19x10 19 [l 60 25 (4 )

LS to Transition Ring Circumferential Weld 0.23 1.02 X 10 17 [l 22 50 17 Inlet Nozzle 1 0.16 1.27 X 10 109 15 93 17 Inlet Nozzle 2 0.16 1.27x10 109 15 93 17 109 Inlet Nozzle 3 0.16 1.27x10 15 93 Outlet Nozzle 1 0.16 1.05 X 10 17 109 15 93 17 Outlet Nozzle 2 0.16 1.05 X 10 109 15 93 17 Outlet Nozzle 3 0.16 1.05 X 10 109 15 93 17 Inlet Nozzle Weld 1 0.19 1.27 X 10 [ l 20 51 Inlet Nozzle Weld 2 0.16 1.27 X 10 17 [ l 18 52 17 Inlet Nozzle Weld 3 0.23 1.27x10 [ l 22 50 17 Outlet Nozzle Weld 0.19 1.05 X 10 [ l 19 52 Turkey Point Nuclear Plant Units 3 and 4 Page 4 .2-16 Subsequent License Renewal Appl ication

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 Unirradiated Projected Projected Cu %T EOL Fluence(1l USE USE Decrease EOL Reactor Vessel Material (Wt.%) (n/cm 2, E>1.0 MeV) (ft-lb) (o/o)l 2)(3) USE(ft-lb)

Upper Shell (US) Forging [l 6.70 X 10 115 103 17 85 6.78 X 10 19 Intermediate Shell (IS) Forging 0.054 88 30 62 0.056 6 .16 X 10 19 Lower Shell (LS) Forging 97 30 68 17 Lower Head Ring (transition) [l 1.02 X 10 109 19 88 US to IS Circumferential Weld (Inner 67%) 0.26 7.22 X 10 18

[ l 36 41 (4) 18 41 (4)(5)

US to IS Circumferential Weld (Outer 33%) 0.32 2.85 X 10 [ l 36 IS to LS Circumferential Weld 0.23 6.16 X 10 19 [ l 60 25 (4)

LS to Transition Ring Circumferential Weld 0.23 1.02 X 10 17 [ l 11 50 1.45 X 10 17 Inlet Nozzle 1 0.08 109 15 97 0.16 1.45 X 10 17 109 Inlet Nozzle 2 15 93 Inlet Nozzle 3 0.16 1.45 X 10 17 105 15 89 17 Outlet Nozzle 1 0.16 1.17x10 107 15 91 17 Outlet Nozzle 2 0.16 1.17x10 104 15 88 17 Outlet Nozzle 3 0.1 6 1.17x10 93 15 79 Inlet Nozzle Weld 1 0.19 1.45 X 10 17 [ l 20 51 17 Inlet Nozzle Weld 2 0.16 1.45 X 10 [ l 18 52 Inlet Nozzle Weld 3 0.34 1.45 X 10 17

[ l 30 45( 4)

Outlet Nozzle Weld 1 0.16 1.17x10 17 [ l 18 52 Outlet Nozzle Weld 2(6) 0.34 1.17x10 17

[ l 30 45(4)

Turkey Point Nuclear Plant Units 3 and 4 Page 4.2-18 Subsequent License Renewal Application

Withheld from Public Disclosure Under 10 CFR 2.390 Secti on 4 - Time-Lim ited A ging A nalyses Table 4.2.4-1 Turkey Point Unit 3 ART Ca lcu lations for 72 EFPY Table 4.2 .4-1 : Tu rke y Poi nt Un it 3 ART C a lcu lati ons fo r 72 EFPY Reg.

Gu ide 1.99 Y.T Fluence Y.T Y.T 3/.T Fluen ce 3/.T 3/.T Rev. 2 CF RTNDT(U) C1u (1 .,.,(1 ) Margin (n/cm 2 , Y.T ~ RTNDT ART (n/cm 2 , 3/.T ~ RTNDT ART Reactor Vessel Material Positio n (O F) (O F) (OF) (OF) (OF) E>1 .0 MeV) FF (O F) (O F) E>1.0 MeV) FF (O F) (OF) 18 18 Upper Shell (US) Forging 1.1 67.7 50 0.0 17.0 34 .0 6.59 X 10 0.88 59 .8 144 2.24 X 10 0.60 40 124 19 19 Intermediate Shell (IS) Forg ing 1.1 37.0 40 0.0 17.0 34.0 6.78 X 10 1.46 53 .9 128 2.68 X 10 1.26 47 121 19 19 IS using Surveillance Data 2.1 6.9 40 0.0 5.0 10.0 6.78 X 10 1.46 10.0 60 2.68 X 10 1.26 9 59 19 19 Lower Shell (LS) Forging 1.1 51 .0 30 0.0 17.0 34 .0 6.19 X 10 1.44 73 .6 138 2.44 X 10 1.24 63 127 19 19 LS using Surveil lance Data 2.1 48 .7 30 0.0 17.0 34 .0 6.19 x 10 1.44 70 .2 134 2.44 X 10 1.24 60 124 Lower Head Ring (transition) 1.1 175.2 [l [l 9.9 63.3 1 04 X 10 17 0.1 1 19.7 91 N/A(2l N/A N/A N/A Inlet Nozzle 1 1.1 122.0 [l [l 8.3 62.4 1.38 X 10 17 0.14 16.6 87 N/A(2l N/A N/A N/A Inlet Nozzle 2 1.1 121.5 [l [l 8.3 62.4 1.38 X 10 17 0.14 16.5 87 N/A( 2 ) N/A N/A N/A Inlet Nozzle 3 1.1 123.0 [l [l 8.4 62.5 1.38 X 10 17 0.14 16.7 87 N/A(2 ) N/A N/A N/A Outlet Nozzle 1 1.1 122.8 [l [l 7.5 62.0 1.17 X 10 17 0.12 14.9 85 N/A<2 ) N/A N/A N/A Outlet Nozzle 2 1.1 121.00 [l [l 7.4 62.0 1.17 X 10 17 0.12 14.7 84 NtA<2 > N/A N/A N/A Outlet Nozzle 3 1.1 121.00 [l [l 7.4 62.0 1.17x10 17 0.12 14.7 84 NtA<2 ) N/A N/A N/A Inlet Nozzle Weld 1.1 152.4 [l [l 10.4 44.5 1.38 X 10 17 0.14 20 .7 60 NtA<2 > N/A N/A N/A Inlet Nozzle Weld 1.1 143.9 [l [l 9.8 44 .0 1.38 X 10 17 0.14 19.6 59 NtA<2 l N/A N/A N/A In let Nozzle Weld 1.1 167.6 [l [l 11.4 45 .5 1.38 X 10 17 0.14 22 .8 63 NtA<2 l N/A N/A N/A Outlet Nozzle Weld 1.1 152.4 [l [l 9.3 43 .5 1.17x10 17 0.12 18.5 57 N/A<2 l N/A N/A N/A US to IS Circumferentia l Weld 1.1 180.0 -33 .2 12.2 28.0 61 .1 7.10x10 18 0.90 162.7 191 2.80 X 10 18 0.65 117 145 Turkey Point N uclear P lant Un its 3 and 4 Page 4 .2-2 1 Subsequent Li cen se Re newa l A pplication

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 '!.T Rev. 2 CF RTNDT(U) O"u 0"1/ 1) Margin (n/cm 2 , 'l*T LiRT NDT ART (n/cm 2 , *1.1 LiRT NDT ART Reactor Vessel Material Position (oF) (OF) (oF) (oF) (oF) E>1.0 MeV) FF (oF) (oF) E>1 .0 MeV) FF (oF) (OF) 19 19 IS to LS Circumferential Weld 1.1 167.6 -53 .5 12.8 28.0 61 .6 6.19x10 1.44 241 .7 250 2.44 X 10 1.24 208 216 IS to LS using Surveillance 2.1 151 .1 -53.5 12.8 28.0 61 .6 6.19 X 10 19 1.44 217 .5 226 2.44 X 10 19 1.24 187 195 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<2l N/A N/A N/A Circumferential Weld Notes for Table 4.2.4-1

1. For %T t.RT NOT that is less than aLi* 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.

Turkey Point Nuclear Plant Units 3 and 4 Page 4.2-22 Subsequent License Renewal Application

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 .

Gu ide 1.99 Y.T Fluence Y.T Y.T %T Fluence 3/.T %T 0'~(1) 2 Rev.2 CF RTNDT(U) O'u Ma rgin (nl cm , Y.T ~ RTNDT ART (nlcm 2 , %T ~ RTNDT ART Reactor Vessel Material Position (oF) (OF) (oF) (oF) (oF) E>1 .0 MeV) FF (O F) (OF ) E>1.0 MeV) FF (oF) (oF)

Upper Shel l (US ) Forging 1.1 67.9 40 0.0 17.0 34.0 6.70 X 10 10 0.89 60.3 134 2.28 X 10 10 0.60 41 115 19 1 Intermediate Shell (IS) Forging 1.1 33.4 50 0.0 17.0 34.0 6.78 X 10 1.46 48 .7 133 2.68 X 10 " 1.26 42 126 Lower Shell (LS) Forging 1. 1 34 .6 40 0. 0 17. 0 34.0 6.1 6 X 10 1" 1.44 49 .9 124 2.43x 10 1" 1.24 43 117 1 2.43 x 10rn LS using Surve illance Data 2.1 4.9 50 0.0 3.5 7.0 6.16 X 10 " 1.44 7. 0 54 1.24 6 53 Lower Head Ring (transition) 1.1 175.2 [l [l 9.8 63. 3 1.02 X 10 11 0.11 19.5 90 NIAl 2! NIA NIA NIA In let Nozzle 1 1.1 51 .0 [l [l 3.6 60.6 1.45 X 10 1 I 0.14 7. 2 75 NIAl 2! NIA NIA NIA 11 NIAl 2 J Inlet Nozzle 2 1.1 123.4 [l [l 8.7 62.6 1.45 X 10 0.14 17.3 88 NIA NIA NIA 11 In let Nozzle 3 1.1 121 .8 [l [l 8.5 62 .6 1.45 X 10 0.1 4 17.1 87 NIN " ! NIA NIA NIA 11 Outlet Nozzle 1 1.1 122 .5 [l [l 7.5 62 .0 1.17 X 10 0.1 2 14.9 85 NIN "! NIA NIA NIA Outlet Nozzle 2 1.1 120.0 [l [l 7.3 62 .0 1.17 X 10 11 0.12 14.6 84 NIN "! NIA NIA NIA Outlet Nozzle 3 1.1 120.5 [l [l 7.3 62 .0 1.17 x 10 11 0.12 14.7 84 NIN "! NIA NIA NIA Inlet Nozzle Weld 1 1.1 152.4 [l [l 10.7 44.8 1.45 x 10 17 0.1 4 2 1.4 61 NIN L! NIA NIA NIA Inlet Nozzle Weld 2 1.1 143. 9 [l [l 10.1 44.3 1.45 x 10 17 0.1 4 20 .2 60 NIAl 2! NIA NIA NIA 11 Inlet Nozzle Weld 3 1.1 220 .6 [l [l 15.5 51 .5 1.45 X 10 0.14 31.0 76 NIAl 2 ! NIA NIA NIA Outlet Nozzle Weld 1 1.1 143.9 [l [l 8.8 43.1 1.17x 10 17 0.12 17.6 56 NIA<2 J NIA NIA NIA Outlet Nozzle Weld 2 1.1 220 .6 [l [l 13.5 49.2 1.17 x 10 17 0.12 26.9 69 NIN 2J NIA NIA N/A US to IS Circum ferential Weld 1.1 180.0 -33 .2 12.2 28.0 61.1 7.22 X 10 18 0.91 163.6 191 NIA NIA N/A N/A Inside 67%< 3)

US to IS Circumferential We ld 1.1 199.3 -31 .1 13.7 28.0 62 .3 NIA N/A NIA N/A 2.85 X 10 18 0.66 131 162 Outside 33%( 4 )

IS to LS Circumferential Weld 1. 1 167.55 -53.5 12.8 28 .0 61 .6 6.16 X 10 19 1.44 241 .5 250 2.43 x 10 1" 1.24 208 216 1

IS to LS using Surveillance Data 2.1 151.1 -53.5 12.8 28.0 61 .6 6.16 X 10 " 1.44 21 7.7 226 2.43 X 10 1" 1.24 187 195 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<2l N/A N/A NIA Circumferential Weld Turkey Point Nuclear Plant Units 3 and 4 Page 4.2-23 Subsequent License Renewal App lication

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 Cumulative Usage Allowable Reactor Vessel Head flange o.oa3( 1J 1.0 Vessel flange 0.531( 1) 1.0 Stud bolts 0.81 (1) 1.0 Outlet nozzles 0.063( 1) 1.0 Inlet nozzles 0.066( 1) 1.0 Core support pad 0.020( 1) 1.0 Shell at core support pads o.509< 1J 1.0 Bottom head to shell juncture 0.023( 1) 1.0 Bottom-mounted instrumentation 0.002< 1) 1.0 Shell to shell juncture 0.034( 1) 1.0 Vent nozzle [ ll"I 1.0 CROM housing J-weld 0.730( 1) 1.0 CROM housing bi-metallic weld [ 1(2) 1.0 CROM latch housing [ 1(2) 1.0 CROM rod travel housing [ 1(2) 1.0 CROM cap [ 1(2) 1.0 CROM lower joint [ 1(2) 1.0 CROM middle joint [ ](2) 1.0 CROM upper joint [ 1(2) 1.0 Reactor Vessel Internals Upper support plate [ ](2) 1.0 Deep beam [ fl 1.0 Upper core plate [ ](2) 1.0 Upper core plate alignment pins [ 1(2) 1.0 Upper support columns [ 1(2) 1.0 Lower support plate [ 1(2) 1.0 Lower support plate to core barrel weld [ 1(2) 1.0 Lower core plate [ 1(2) 1.0 Lower support columns [ 1(2) 1.0 Core barrel flange [ 1(2) 1.0 Core barrel outlet nozzle [ 1(2) 1.0 Radial keys and clevis insert assembly [ ](2) 1.0 Turkey Point Nuclear Plant Units 3 and 4 Page 4.3-5 Subsequent License Renewal Application

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 (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 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 Reference 4.3.6.21 Turkey Point Nuclear Plant Units 3 and 4 Page 4.3-22 Subsequent License Renewal Application

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 Reference 4.3.6 .19 Turkey Point Nuclear Plant Units 3 and 4 Page 4.3-23 Subsequent License Renewal Application

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 Page 4.3-24 Subsequent License Renewal Application