ML20100B917
| ML20100B917 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/23/1996 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20100B914 | List: |
| References | |
| NUDOCS 9601290232 | |
| Download: ML20100B917 (31) | |
Text
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VOGTLE ELECTRIC GENERATING PLANT - UNIT 1 i
PRESSURE AND TEMPERATURE LIMITS REPORT l
REVISION 0 1
h /[25 6 Prepared by:
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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents Section Page 1.0 Reactor Coolant System (RCS) Pressure and Temperature 1
Limits Report (PTLR)- Unit 1 2.0 Operating Limits 1
2.1 RCS Pressure and Temperature (P/T) Limits 1
2.2 Cold Overpressure Protection System (COPS) Setpoints 2
\\
3.0 Supplemental Data Tables 9
4.0 Reactor Vessel Material Surveillance Program 19 5.0 Reactor Vessel Surveillance Data Credibility 19 6.0 References 25 ii
VOGTLE ELECTRIC GENERATING PLANT (VEGP) - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures Figure Page 2.1-1 Unit 1 Reactor Coolant System Heatup Limitations 3
0 (Heatup rates up to 100 F/hr). Applicable for the First 16 EFPY (With Margins of 10 F and 60 psig for Instrumentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Instrumentation and Reactor Vessel Erltline Region).
2.1-2 Unit 1 Reactor Coolant System Cooldown Limitations 5
(Cooldown rates up to 100 F/hr). Applicable for the First 16 EFPY (With Margins of 10 F and 60 psig for Instrumentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Instrumentation and Reactor Vessel Beltline Region).
2.2-1 Unit 1 Maximum Allowable Nominal PORV Setpoint 7
for the Cold Overpressure Protection System e
i iii
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Page j
2.1 -1 Data Points for Unit 1 Reactor Coolant System Heatup Limitations 4
2.1-2 Data Points for Unit 1 Reactor Coolant System Cooldown Limitations 6
2.2-1 Data Points for Unit 1 PORV Setpoints 8
)
3.0-1 Comparison of the Vogtle Unit 1 Surveillance Material 30 ft-lb 10 Transition Temperature Shifts and Upper Shelf Energy Decrease with Regulatory Guide 1.99, Revision 2, Predictions 3.0-2 Vogtle Unit 1 Calculation of Chemistry Factors Using Surveillance 11 Capsule Data 3.0-3 Vogtle Unit 1 Reactor Vessel Toughness Table (Unitradiated) 12 3.0-4 Vogtle Unit 1 Reactor Vessel Surface Fluence Values at 16 EFPY 12 (Fluence Based on E > 1.0 MeV 3.0-5 Summary of Adjusted Reference Temperatures (ARTS) for the 13 Vogtle Unit 1 Reactor Vessel Beltline Mat: rials at the 1/4-T and 3/4-T Locations for 16 EFPY 3.0-6 Calculation of Adjusted Reference Temperature at 16 EFPY 14 for the Limiting Vogtle Unit i Reactor Vessel Material (Intermediate Shell Plate B8805-2) iv
l VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables (continued) 1 3.0-7 Neutron Exposure Projections at Key Locations on the Vogtle 15 i
Unit 1 Pressure Vessel Clad / Base Metal Interface 3.0-8 RTns Values for Vagtle Unit 1 for 4.64 EFPY 16 3.0-9 RTns Values for Vogtle Unit 1 for 32 EFPY 17 3.0-10 RTns Values for Vogtle Unit 1 for 48 EFPY 18 5.0-1 Calculation of Best Line Drawn as Described in Regulatory 22 Position 2.1 of Regulatory Guide 1.99, Revision 2 i
V l
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)-
Unit I This PTLR for VEGP Unit I has been prepared in accordance with the requirernents of Technical Specification (TS) 5.6.6. The TS addressed in this report are listed below:
I.C O 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.12 Cold Overpressure Protection Systems (COPS) 2.0 Operating Limits The parameter limits for the specifications listed in section 1.0 are presented in the following subseedons. The current limits were developed using a methodology that is in accordance with the NRC-approved methodology specified in Specification 5.6.6 (Ref.1) with two exceptions. The two exceptions are the fluence methodology used to calculate j
the heatup and cooldown limits and the incorporation of random pressure uncertainty in j
the cold overpressure protection system setpoints. Future changes to these limits will be made in full compliance with the NRC-approved methodology, and the first revision to the limits after initial implementation of this PTLR will be submitted to the NRC lbr prior approval. Subsequent revisions will be made in accordance with the NRC-approved methodology without prior approval. It should be noted that the heatup and cooldown limit curves and the cold overpressure protection system setpoints were approved by the NRC staff by Amendment 87 dated June 8,1995.
2.1 RCS Pressure and Temperature (PTT) Limits (LCO 3.4.3) 2.1.1 The RCS temperature rate-of-change limits are (Ref. 2):
a.
A maximum heatup of 100 F in any 1-hour period.
- b. A maximum cooldown of 100 "F in any 1-hour period.
- c. A maximum temperature change ofless than or equal to 10 F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
2.1.2 The RCS P/T limits fbr heatup and cooldown are specified by Figures 2.1-1 and 2.1-2, respe:tively.
l 1
=.
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT l
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2.2 Cold Overpressure Protection System (COPS) Setpoints (LCO 3.4.12)
The power-operated relief valves (PORVs) shall each have li,ft settings in accordance with Figure 2.2-1.
The setpoints in combination with the relief capacity of the PORVs will protect the RCS from the limiting mass injection transient of two centrifugal charging pumps plus the positive displacement pump injecting into the RCS and the limiting heat input transient of starting a RCP with the RCS 50 F colder than the secondary coolant.
l 4
2
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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 2500 Leak Test Limit <
- Criticality Umit for f
t 60'F/hr 2250
/ / l Heatup l
MATERIAL BASIS 2000
. copper Content:
hume NA %'P' gg RT initial:
Assumed - NA T 100'F/hr (Actual 20T)
Heatup RT, at 16 EFPY:
@ 1/4 T=100.7 T 1750
@ 3/4 T=84.I T f
f UO,er -
1500 H I i
1250 He Rgup to g j
Operanon 1000 Heatus Rate up tos 100'F/hr r
750
,,,,, Cia ;f Umit 92 sed
)
'F.#
on inser; ice.4, Jim Test Temperatuta
/
500 f/
(246*F) for the Service --"
/
Pened up to 16 EFi3Y I
250 0
0 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (*F)
Figure 2.1-1 Unit 1 Reactor Coolant System Heatup Limitations (11eatup Rates up to 100 F/hr) Applicable for the First 16 EFPY (With Margins of 10 F and 60 psig for Instrumentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Instrumentation and Reactor Vessel Beltline Region).
3
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.1-1 Data Points for Unit 1 Reactor Coolant System Heatup Limitations Ceuumhey Crincality 80HU thmit 100 HU lhmis
- Isak Test T
P T
F T
P T
F T
P 70 411.59 246 0.00 70 37939 246 0.00 225 2000 75 4II39 246 4IIJ9 75 37939 246 379.59 246 2485 80 411.59 246 411.59 80 37939 246 379.59 85 411.59 246 411.59 85 379.59 246 379.59 90 4Il.59 2# 411.59 90 37939 246 379.59 95 4Il.59 2# 411.59 95 379.59 24 379.59 100 413.02 24 413.02 100 379.59 246 379.59 105 416.63 246 416.63 105 379.59 2# 379.59 110 422.40 24 422.40 110 379.59 246 379.59 115 429.94 246 429.94 115 379.59 2# 379.59 120 43934 246 439.34 120 381.23 246 381.23 125 450.36 246 45036 125 384.46 246 384.46 130 462.96 246 462.96 130 389.32 246 38932 135 477.28 246 477.28 135 395.71 246 395.71 140 487.00 246 487.00 140 403.67 246 403.67 145 487.00 246 487.00 145 413.05 246 413.05 150 487.00 246 487.00 150 424.12 246 424.12 150 530.18 24 530.18 155 436.75 2# 436.75 155 551.31 24 55131 160 451.02 246 451.02 160 574.18 246 574.18 165 466.81 246 466.81 165 599.11 246 599.11 170 484.47 246 484.47 170 625.99 24 625.99 175 503.91 246 503.91 175 654.97 246 654.97 180 $25.12 246 525.12 180 686.48 2# 686.48 185 548.41 24 548.41 185 720.23 24 720.23 190 573.65 246 573.65 190 756.57 24 756.57 195 601.20 246 601.20 195 795.85 246 795.85 200 630.96 2# 630.96 200 837.97 2# 817.97 205 663.11 246 663.11 205 883.21 246 883.21 210 698.05 250 698.05 210 931.85 250 931.85 215 735.63 255 735.63 215 984D6 255 984.06 220 776.14 260 776.14 220 1039.90 260 1039.90 225 819.75 265 819.75 225 1100.16 265 1100.16 230 866.71 270 866.71 230 1164.70 270 1164.70 235 917.23 275 917.23 235 1233.69 275 1233.69 240 971.48 200 971.48 240 1308.02 280 1308.02 245 1029.79 285 1029.79 245 1387.43 285 1387.43 250 1092.22 290 1092.22 250 1472.31 290 1472.31 255 1159.47 295 1159.47 255 1563.28 295 1563.28 260 1231.28 300 1231.28 260 1660.77 300 1660.77 265 1308.60 305 1308.60 265 1765.08 305 1765.08 270 139131 310 1391.31 270 1876.53 310 1876.53 275 1479.80 315 1479.80 275 1995.33 315 1995.33 280 157432 320 1574.52 280 2122.41 320 2122.41 285 1675.74 325 1675.74 285 2257.67 325 2257.67 290 1783.98 330 1783.98 290 2401.70 330 2401.70 2 2 1999.51 335 189931 300 2013D6 340 2023.06 305 2154.59 345 215439 310 2294.65 350 2294.65 4
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT 2500 l
2250 2000 f
Unacceptable Operadon 1750
- 1500 1
1250 Acceptable i
Operadon 1000 750 Cooldown copper content:
Assumed.NAW1%
Rates T/hr (Actuel o.osswry) 500 RT i
NOT nWal:
Aamumed NAT 0[/
(Amuel 207) 20/
RTNOTAt16 EFPY: @ 1/4T-100.71 d
A 250 1Lu-0 0
50 100 150 200 250 300 350 400 450 500 Indicated Temperature (T)
Figure 2.1-2 Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100 "F/hr)
Applicable for the First 16 EFPY (With Margins of 10 "F and 60 psig for instrumentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Instrumentation and Reactor Vessel Beltline Region).
4 5
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.1-2 Data Points for Unit 1 Reactor Coolant System Cooldown Limitations Saeedy Seals 20 CD 40 CD 60 CD 100 CD T
P T
P T
P T
P T
P 70 441.06 70 401.75 70 361.89 70 321.34 70 238.56 75 449.91 75 410.96 75 371.60 75 331.70 75 250.28 80 459.29 80 420.95 80 382.15 80 342.88 80 262.93 85 469.52 85 431.74 85 393.56 85 354.98 85 276.69 i
l 90 480.51 90 44333 90 405.83 90 367.93 90 291.47
)
95 487D0 95 455.84 95 418.98 95 382.03 95 307.58 100 487.00 100 469.15 100 433.25 100 397.22 100 324.90 105 487.00 105 483.64 105 448.66 105 413.54 105 343.74 110 487.00 110 487.00 110 465.11 110 431.24 110 364.07 115 487.00 115 487.00 115 483.00 115 450.35 115 385.99 120 487.00 120 487D0 120 487D0 120 470.81 120 409.73 125 487.00 125 487D0 125 487.00 125 487.00 125 435.30 130 487.00 130 487.00 130 487.00 130 487.00 130 462.87 135 487.00 135 487D0 135 487.00 135 487.00 135 48720 140 487.00 140 487.00 140 487.00 140 4F7.00 140 487D0 145 487D0 145 487.00 145 487.00 145 487.00 145 487D0 150 487.00 150 487.00 150 487.00 150 487.00 150 487.00 150 697.52 150 674.44 150 652.71 150 63235 150 597.16 155 725.51 155 70435 155 684.91 155 666.93 155 637.55 160 755.50 160 736.74 160 719.47 160 704.15 160 68123 165 787.98 165 77139 165 756.69 165 744.45 165 727.95 170 822.71 170 808.59 170 7 %.90 170 787.66 170 778.47 175 859.97 175 848.62 175 840.01 175 834.17 175 832.90 180 900.00 180 891.83 180 88637 180 884.17 180 891.46 185 943.02 185 934.13 185 936.26 185 937.98 190 989.43 190 987.88 195 1038.93 200 109231 205 1149.67 210 1211.10 215 1276.80 220 1347.74 225 1423.41 23G 1504.91 235 1591.99 240 168530 245 1785.26 250 1892.15 255 2006.55 260 2128.76 265 2259.41 270 2398.54 l
l l~
6 l
l
4 s
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 800 780
{
760 140 (212,726)
(380,728) 1 720 680 660 640 620 1600 580 560 (70,538) s g
520 500 50 100 150 200 250 300 350 TRTD - Auctioneered Low Measured RCS Temperature (*F)
Figure 2.2-1 Unit 1 Maximum Allowable Nominal PORV Setpoint for the Cold Overpressure Protection System 7
4 VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.2-1 Data Points for Unit 1 PORV Setpoints a
Temperature ( F)
Pressure (psig) 70 538 100 538 130 540 160 550 180 560 200 576 210 660 212 726 350 726 8
l 1
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 3.0 Supplemental Data Tables l
Table 3.0-1 is a comparison of the measured surveillance material 30 fl-lb transition temperature shifts and upper shelf energy decreases with Regulatory' Guide 1.99, l
Revision 2 predictions.
l Table 3.0-2 shows the calculation of the surveillance material chemistry factors using surveillance capsule data.
Table 3.0-3 provides the unirradiated Vogtle Unit I reactor vessel toughness data. The bolt-up temperature is also included in this table.
Table 3.0-4 provides a summary of the fluences used in the generation of the heatup and cooldown curves.
Table 3.0-5 provides a summary of the adjusted reference temperatures (ARTS) of the Vogtle Unit I reactor vessel beltline materials at the 1/4-T and 3/4-T locations for 16 EFPY.
Table 3.0-6 shows the calculation of the ART at 16 EFPY for the limiting Vogtle Unit I reactor vessel material (intermediate shell plate B8805-2).
i Table 3.0-7 provides a summary of the fluences used in the PTS evaluation.
Table 3.0-8 provides RTers values for Vogtle Unit I for 4.64 EFPY.
Table 3.0-9 provides RTrTs values for Vogtle Unit 1 for 32 EFPY.
Table 3.0-10 provides RTrrs values for Vogtle Unit I for 48 EFPY.
9
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-1 Comparison of the Vogtle Unit 1 Surveillance Material 30 fbib Transition Temperature Shifts and Upper Shelf Energy Decrease with Regulatcry Guide 1.99 Revision 2 Predictions 30 ft-lb Transition Upper Shelf Energy Fluence Temperature Shift Decrease I* I Predicted'd Measured Predicted'd Measured'd Material Capsule E > l.0 MeV) op) og
,7 Intermediate Shell U
0.344 27 15 15 0
Plate B8805-3 (Longitudinal)
Y 1.24 41 40 20 0
Intermediate Shell U
0.344 27 0
15 0
Plate B8805-3 (Transverse)
Y 1.24 41 20 20 0
U 0.344 23 15 15 0
Weld Metal Y
1.24 35 0
20 1
6 U
0.344 0
HAZ Metal Y
1.24 25 9
(a) Based on Regulatory Guide 1.99, Revision 2, methodology using mean wt. % values of Cu and Ni.
10
.m VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-2 Vogtle Unit I Calculation of Chemistry Factors Using Surveillance Capsule Dath Material Capsule Fluence (f)
FPC ARTum FF* ARTum FF2 (n/cm,
(op)
(op) 2 E > l.0 MeV)
)
Intermediate Shell Plate U
3.437 x 10
O.706 15 10.585 0.498 i
B8805-3 l
(Longitudinal)
Y 1.242 x 10*
l.060 40 42.4 1.124 l
Intermediate Shell Plate U
3.437 x 10
O.706
~ 0 0
0.498 B8805-3 Y
1.242 x 10" l.060 20 21.2 1.124 (Transverse)
Sum:
74.185 3.244 Chemistry Factor = 74.185 + 3.244 = 22.9 Weld Metal U
3.437 x 10
O.706 15 10.585 0.498 Y
1.242 x 10" l.060 0
0 1.124 Sum:
10.585 1.622 Chemistry Factor = 10.585 + 1.622 = 6.5 (a) Fluence Factor (FF) per Regulatory Guide 1.99, Revision 2, is defined as FF = fo 2a.o ioios o I1
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 j
PRESSURE AND TEMPERATURE LIMITS REPORT l
Table 3.0-3 Vogtle Unit i Reactor Vessel Toughness Table (Unirradiated)
Material Description Cu(%yd Ni (%Y" Initial RTw ( FP)
Closure Head Flange 0.70 20")
Vessel Flange 0.71 Ok)
Intermediate Shell Plate B8805-1 0.083 0.597 0
Intermediate Shell Plate B8805-2 0.083 0.610 20 Intermediate Shell Plate B8805-3 0.062 0.598 30 Lower Shell Plate B8606-1 0.053 0.593 20 Lower Shell Plate B8606-2 0.057 0.600 20 l
Lower Shell Plate B8606-3 0.067 0.623 10 Intermediate & Lower Shell Vertical 0.039 0.102
-80 Weld Seams and Girth Seam Weld (a) The average values of copper and nickel content.
(b) Initial RTm values are measured values.
(c) These values are used for considering flange requirements for the heatup/cooldown curves. Per the methodology given in WCAP-14040, Revision 1, the minimum boltup temperature is 60 F.
l Table 3.0-4 Vogtle Unit i Reactor Vessel Surface Fluence Values at 16 EFPY (Fluence Based on E > 1.0 MeV)
Azimuthal 0
15 25 30 35 45 Surface 6.216E+18 9.236E+18 1.088E+ 19 6.897E+18 9.043E+18 1.015E+19 12
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT l
Table 3.0-5 Summary of Adjusted Reference Temperatures (ARTS) for the Vogtle Unit 1 Reactor Vessel Beltline Materials at the 1/4-T and 3/4-T Locations for 16 EFPY' 16 EFPY AR'Pd Component I/4 T( F) 3/4-T( F)
Intermediate Shell Plate B8805 1 80.7 64.1 Intermediate Shell Plate B8805-2 100.7*)
84.l*)
Intermediate Shell Plate B8805-3 97.5 76.4 Intermediate Shell Plate B8805 3 67.1 57.6 Using S/C Data Lower Shell Plate B8606-1 77.6 59.6 Lower Shell Plate B8606-2 81.9 62.5 Lower Shell Plate B8606-3 80.8 60.6 Cire. Weld 101-171
-21.7
-39.9 Cire. Weld 101-171
-68.6
-72.2 Using S/C Data Long. Weld 101-124A
-31.8'd
-48.5(d Long. Weld 101-1248
-30.0'*
-47.0'*
Long. Weld 101-124C
-30.0'd)
-47.0'd)
Long. Weld 101-142A
-3 0.0'*
-47.0'*
Long. Weld 101-142B
-31.8'd
-48.5(4 Long. Weld 101 142C
-30.0'd)
-47.0'*
(a) The ARTS presented here are based on the peak reactor vessel surface fluence of 1.088 x 10 n/cm (E > 1.0 2
MeV) unless noted.
(b) These ART values are used to generate the heatup and cooldown curves.
(c) These ARTS were calculated using the peak vessel fluence of 6.216 x 10'8 n/cm (E > 1.0 MeV) at 0.
2 2
(d) These ARTS were calculated using the peak vessel fluence of 6.897 x 10 n/cm (E > 1.0 MeV) at 30.
13 p
w
--4.
-c-
l VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-6 Calculation of Acated Reference Temperature at 16 EFPY for the Limiting Vogtle Unit i Reactor Vessel l
Material (Intermediate Shell Plate B8805-2) l Parameter ART Value l
Operating Time 16 EFPY Material B8805-2 B8805-2 Location 1/4-T 3/4-T Chemistry Factor, CF ("F) 53.1 53.1 2
Fluence + 10 n/cm (E > 1.0 MeV), f*)
0.6485 0.2303 Fluence Factor, FF" 0.879 0.604 ARTsor = CF x FF,( F) 46.653 32.056 Initial RTyor,I( F) 20 20 Margin, M ( F)")
34 32.056 ART = 1 + (CF x FF) + M ( F) 100.7 84.1 per Regulatory Guide 1.99, Revision 2 2
(a) Fluence, f, is based upon f,,(10 n!cm, E > 1.0 MeV) = 1.088 at 16 EFPY. The Vogtle Unit i reactor vessel wall thickness is 8.625 inches at the beltline region.
(b) Fluence Factor (FF) per Regulatory Guide 1.99, Revision 2, is defined as FF = f"' '"*'n, (c) Margin is calculated as M = 2(o + o,2)" The standard deviation for the initial RTmn margin term, o,, is 0 F 2
since the initial RTwor is a measured value.. The Standard deviation for ARTuor term o., is 17 F for the plate, except that o, need not exceed 0.5 times the mean value of ARTwor.
i 14
~_
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 i
PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-7 i
Neutron Exposure Projections") at Key Locations on the Vogtle Unit 1 Pressure Vessel Clad / Base Metal Interface EFPY 0
15 25 30 35 45 4.64 0.1802 0.2678 0.3155 0.2000 0.2622 0.2942 32 1.243 1.847 2.176 1.379 1.809 2.029 48 1.863 2.769 3.262 2.068 2.711 3.041 2
(1) Fluence in 10 n/cm (E > 1.0 MeV).
15
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-8 RTm Values for Vogtle Unit I for 4.64 EFPY Material CF Surface Fluence FF ARTm i
M RTrrs i
2
( F)
(n/cm,
(F)
( F)
(F)
E > l.0 MeV)
(*F)
Inter. Shell Plate 53.1 3.155 x 10
O.6833 36.3 0
34 70.3 B8805 1 Inter. Shell Plate 53.1 3.155 x 10
O.6833 36.3 20 34 90.3 B8805-2 1
1 Inter. Shell Plate 38.4 3.155 x 10'8 0.6833 26.2 30 34 90.2 B8805-3 1
t Inter. Shell Plate 22.9 3.155 x 10
O.6833 15.6 30 34 79.6 D8805 3 Using S/C Data'"
tower Shell Plate 32.8 3.155 x 10
O.6833 22.4 20 34 76.4 B8606-1 1.ower Shell Plate 35.2 3.155 x 10
O.6833 24.1 20 34 78.1 B8606-2 Lower Shell Plate 41.9 3.155 x 10
O.6833 28.6 10 34 72.6 B8606-3 j
Cire. Weld 33.2 3.155 x 10'8 0.6833 22.7
-80 56
-1.3 i
101 171 Weld Metal 6.5 3.155 x 10
O.6833*
4.4
-80 56
-19.6 Using S/C Data'"
i tong. Weld 33.2 1.802 x 10
O.5448 18.1
-80 56 5.9 101-124A l
long. Weld 33.2 2.0 x 10
O.5694 18.9
-80 56
-5.1 101 124B l
Long. Weld 33.2 2.0 x 10
O.5694 18.9
-80 56
-5.1 101 124C Long. Weld 33.2 2.0 x 10
O.5694 18.9
-80 56
-5.1 101 142A Long. Weld 33.2 1.802 x 10
O.5448 18.1
-80 56
-5.9 101 142B long. Weld 33.2 2.0 x 10
O.5694 18.9
-80 56
-5.1 101 142C (1) Numbers were calculated using a chemistry factor (CF) based on surveillance capsule data.
(2) Peak fluence factor which represents most limiting case for weld metal.
16
l VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Tid,le 3.0-9 RT,1s Values for Vogtle Unit I for 32 EFPY Material CF Surface Fluence FF aRTmr 1
M RTrrs 2
( F)
(n/cm,
(F)
(F)
(F)
E > l.0 MeV)
( F)
Inter. Shell Plate 53.1 2.176 x 10
l.2110 64.3 0
34 98.3 B8805 1 Inter. Shell Plate 53.1 2.176 x 10
l.2110 64.3 20 34 118.3 B8805-2 Inter. Shell Plate 38.4 2.176 x 10
l.2110 46.5 30 34 110.5 B8805-3 Inter. Shell Plate 22.9 2.176 x 10
l.2110 27.7 30 34 91.7 88805 3 Using S/C Data"'
Lower Shell Plate 32.8 2.176 x 10" l.2110 39.7 20 34 93.7 B8606-1 Lower Shell Plate 35.2 2176 x 10
l.2110 42.6 20 34 96.6 B8606-2 Lower Shell Plate 41.9 2.176 x 10
l.2110 50.7 10 34 94.7 B8606 3 j
cire. Weld 33.2 2.176 x 10
l.2110 40.2
-80 56 16.2 101-171 1
Weld Metal 6.5 2.176 x 10" l.2110'2) 7.9
-80 56
-16.1 Using S/C Data'"
teng. Weld 33.2 1743 x 10*
l.0606 35.2
-80 56 11.2 101 124 A tong. Weld 33.2 1.379 x 10
l.0893 36.2
-80 56 12.2 101-124B Long. Weld 33.2 1.379 x 10
l.0893 36.2
-80 56 12.2 101 124C Long. Weld 33.2 1.379 x 10
l.0893 36.2
-80 56 12.2 101 142A Long. Weld 33.2 1.243 x 10" l.0606 35.2
-80 56 11.2 101-142B Long. Weld 33.2 1.379 x 10
l.0893 36.2
-80 56 12.2 101-142C (1) Numbers were calculated using a chemistry factor (CF) based on surveillance capsule data.
(2) Peak fluence factor which represents most limiting case for weld metal.
I7
l VOGTLE ELECTRIC GENERATING PLANT (VEGP) - UNIT 1 l
PRESSURE AND TEMPERATURE LIMITS REPORT i
Table 3.0-10 RTm Values for Vogtle Unit I for 48 EFPY Material CF Surface Fluence FF ART,
1 M
RTns 2
(F)
(n/cm,
(F)
(F)
(F) 1 E > 1.0 MeV)
( F) l Inter. Shell Plate 53.1 3.262 x 10" l.3104 69.6 0
34 103.6 l
D8805 1 I
inter. Shell Plate 53.1 3.262 x 10
l.3104 69.6 20 34 123.6 B8805-2 Inter. Shell Plate 38.4 3.262 x 10"
.l.3104 50.3 30 34 114.3 88805-3 Inter. Shell Plate 22.9 3.262 x 10
l.3104 30.0 30 34 94.0 B8805-3 Using S/C Data"'
Lower Shell Plate 32.8 3.262 x 10" l.3104 43.0 20 34 97.0 B8606-1 Lower Shell Plate 35.2 3.262 x 10" l.3104 46.1 20 34 100.1 B8606-2 Lower Shell Plate 41.9 3.262 x 10
l.3104 54.9 10 34 98.9 BB606-3 Cire. Weld 33.2 3.262 x 10*
l.3104 43.5
-80 56 19.5 101 171 Weld Metal 6.5 3.262 x 10" l.3104*
8.5
-80 56
-15.5 i
Using S/C Data")
long. Weld 33.2 1.863 x 10
l.1705 38.9 80 56 14 9 101-124A 1.ong. Weld 33.2 2.068 x 10" l.1978 39.8
-80 56 15.8 101 124B tong. Wetd 33.2 2.068 x 10
l.1978 39.8
-80 56 15.8 101 124C Long. Weld 33.2 2.068 x 10
l.1978 39.8
-80 56 15.8 101 142A Long. Weld 33.2 1.863 x 10
l.1705 38.9
-80 56 14.9 101-142B Long. Weld 33.2 2.068 x 10
l.1978 39.8
-80 56 15.8 101-142C (1) Numbers were calculated using a chemistry factor (CF) based on surveillance capsule data.
(2) Peak Quence factor which represents most limiting case for weld metal.
I8
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 4.0 Reactor Vessel Material Surveillance Program The reactor vessel material surveillance program is in compliance with 10 CFR 50, Appendix H, and is described in section 16.3 of the VEGP FSAR. The withdrawal schedule is presented in FSAR table 16.3-3. The Unit 1 surveillance capsule reports are as follows:
- 1. WCAP-12256, May 1989, " Analysis of Capsule U From the Georgia Power Company Vogtle Unit 1 Reactor Vessel Radiation Surveillance Program."
- 2. WCAP-13931, February 1994, " Analysis of Capsule Y From the Georgia Power Company Vogtle Unit 1 Reactor Vessel Radiation Surveillance Program."
5.0 Reactor Vessel Surveillance Data Credibility Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data. The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.
To date, there have been two surveillance capsules removed from the Vogtle Unit I reactor vessel. To use these surveillance data sets, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five criteria that must be met for the surveillance data to be judged credible.
The purpose of this evaluation is to apply the credibility criteria of Regulatory Guide 1.99, Revision 2, to the Vogtle Unit I reactor vessel surveillance data and determine if the Vogtle Unit I surveillance data is credible.
Criterion 1:
Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.
The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50,
" Fracture Toughness Requirements," May 27,1983 to be:
19
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1
]
PRESSURE AND TEMPERATURE LIMITS REPORT "the reactor vessel (shell material including welds, heat affected zones, and plates or i
forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience suffi,cient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."
The Vogtle Unit I reactor vessel consists of the following beltline region materials:
a) Intermediate shell longitudinal weld seams 101-124A, B, and C, lower shell longitudinal seams 101-142A, B, and C, and intermediate to lower shell j
circumferential weld seam 101-171 (all beltline weld seams were fabricated with 3/16 inch Mil B-4 weld filler wire, heat number 83653 and Linde flux, lot number 3536),
b) Intermediate shell plates B8805-1, heat number C0613-1, B8805-2, heat number C0613-2, and B8805-3, heat number C0623-1, and c) Lower shell plates B8606-1, heat number C2146-1, B8606-2, heat number C2146-2, and B8606-3, heat number C2085-2.
At the time the surveillance capsule was developed, Regulatory Guide 1.99, Revision I was in effect. Per the Regulatory Guide 1.99, Revision 1, calculational methodology, intermediate shell plate B8805-3 was projected to have the highest end oflife (EOL)
RT, of all beltline plate materials. Hence, intermediate shell plate B8805-3 wasjudged j
to be most limiting and was used in the surveillance program. Since the surveillance i
weld metal and all of the Vogtle Unit I reactor vessel beltline welds were made of the same heat, flux, and flux lot, the surveillance weld represents the most limiting weld 1
metalin the beltline region.
The materials selected for use in the Vogtle Unit I surveillance program were those judged to be most likely controlling with regard to radiation embrittlement according to the accepted methodology at the time the surveillance program was developed.
Therefore, the Vogtle Unit I surveillance program meets this criteria.
Criterion 2:
Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.
20
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Plots of Charpy energy versus temperature for the unirradiated condition are presented in i
WCAP-11011, " Georgia Power Company Alvin W. Vogtle Unit No.1 Reactor Vessel Radiation Surveillance Program," dated February 1986.
Plots of Charpy energy versus temperature for the irradiated condition are presented in WCAP-12256, " Analysis of Capsule U from the Georgia Power Company Vogtle Unit 1 Reactor Vessel Radiation Surveillance Program," dated May 1989 and WCAP-13931, Revision 1, " Analysis of Capsule Y from the Georgia Power Company Vogtle Unit 1 Reactor Vessel Radiation Surveillance Program," dated August 1995.
Based on engineering judgement, the scatter in the data presented in these plots is small enough to permit the determination of the 30-ft Ib temperature and the upper shelf energy of the Vogtle Unit I surveillance materials unambiguously. Therefore, the Vogtle Unit I surveillance program meets this criteria.
Criterion 3:
When there are two or more sets of surveillance data from one reactor, the scatter of ARTor values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28 F for welds and 17 'F for base metal. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice those values.
Even if the data fail this criterion for use in shift calculations, they may be credible for determir.ing decrease in upper shelf energy !f the upper shelf can be clearly determined, following the definition given ASTM E185-82.
The least squares method as described in Regulatory Position 2.1 will be utilized to determine a best-fit line for this data and to determine if the scatter of these ARTer values about this line is less than 28 F for welds and 17 F for the plate.
21 i
._- =., _
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT I 4
j PRESSURE AND TEMPERATURE LIMITS REPORT i
l Table 5.0-1 4
Vogtle Unit 1 Surveillance Capsule Data Calculation of Best Line Drawn as Described in Regulatory Position 2'.1 of l
Regulatory Guide 1.99, Revision 2 l
Material Capsule P"
FF2)
ARTer FF*ARTer FF2 m
2 (x)
(y)
(xy)
(x )
Intermediate Shell U
0.3437 0.706 15 10.585 0.498 i
Plate B8805 3 (Longitudinal)
Y 1.242 1.060 40 42.4 1.124 l
1 Intermediate Shell U
0.3437 0.706 0
0 0.498 Plate B8805-3 (Transverse)
Y 1.242 1.060 20 21.2 1.124 j
J Dm 3.532 75 74.185 3.244 Weld Metal U
0.3437 0.706 15 10.585 0.498 Y
1.242 1.060 0
0 1.124 D,.,
1.766 15 10.585 1.622 (1) F = Fluence (10" n/cm, E>l.0 MeV) 2 (2) FF = Fluence Factor = P 2n i io.r>
(3) ARTer values do not include the adjustment ratio procedure of Regulatory Guide 1.99, Revision 2, Position 2.1, since the sun'eillance materials are identical to the actual beltline material.
Per the 27'h Edition of the CRC Standard Mathematical Tables (page 497), for a straight line fit by the method ofleast squares, the values ba and b, are obtained by solving the normal equations nbo + b Exi = Eyi and i
boExi + b Ex,2 = gx,y, i
These equations can be rewritten as follows:
n n
Ey, = an + bEx, and i=1 i=1 n
n n
EXyg = rex, + bEX,
!=1 i=1 1-1 22
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 i
PRESSURE AND TEMPERATURE LIMITS REPORT Intermediate Shell Plate B8805-3:
)
Based on the data provided in Table 5.0-1, these equations become:
75 = 4a + 3.532b and 74.185 = 3.532a + 3.244b Thus, b = 63.556 and a = -37.37, and the equation of the straight line which provides the best fit in the sense ofleast squares is:
Y' = 63.556 (X)- 37.37 The error in predicting a value Y corresponding to a given X value is :
e = Y - Y' Intermediate Shell FF ARTwor Best Fit Scatter of Plate B8805-3 (30 ft-Ib)
ARTwor ARTuor
Orientation"
('F)
( F)
( F)
Longitudinal 0.706 15 7.50 7.50 1.060 40 30.0 10.0 Transverse 0.706 0
7.50
-7.50 1.060 20 30.0
-10.0 The scatter of ARTun7 values about a best-fit line drawn as described in Regulatory Position 2.1 is less than 17 F as shown above. Therefore, this criteria is met for the sun eillance plate material.
Weld Metal:
Based on the data provided in Table 5.0-1, the equations become:
15 = 2a + 1,766b and 10.585 = 1.766a + 1.622b 23
VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT l
Thus a = 45.007 and b = -42.477, and the equation of the straight line which provides the best fit in the sense ofleast squares is:
Y' = -42.477 (X) + 45.007 The error in predicting a value Y corresponding to a given X value is:
e = Y - Y' FF ARTm (30 ft-lb)
Best Fit ARTm Scatter of ARTm
('F)
('F)
('F) 0.706 15 15.0182
-0.0182 1.060 0
-0.0186
-0.0186 The scatter of ARTm values about a best-fit line drawn as described in Regulatory l
Position 2.1 is less than 28 F as shown above. Therefore, this criteria is met for the surveillance weld material.
Criterion 4:
The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding / base metal interface within +/- 35 F.
The capsule specimens are located in the reactor between the core barrel and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the neutron pads. The location of the specimens with respect to the reactor vessel beltline provides assurance that the reactor vessel wall and the specimens experience equivalent operating conditions and will not differ by more than 25 F.
Criterion 5:
The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material.
The Vogtle Unit I surveillance program does not include correlation monitor material.
Therefore, this criterion is not applicable to Vogtle Unit 1.
24
VOGTLE ELECTRIC GENERATING PLANT (VEGP) - UNIT 1 i
PRESSURE AND TEMPERATURE LIMITS REPORT 6.0 References
- l. WCAP-14040, Revision 1, December 1994," Methodology Used,to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," as approved by the NRC by letter dated October 16,1995 (TAC M91749).
- 2. Louis L. Wheeler to C. K. McCoy, dated June 8,1995, " Issuance of Amendments -
Vogtle Electric Generating Plant Units I and 2 (TAC Nos. M90966 and M90967)."
25
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