ML20087C303

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Rev 0 to VEGP Unit 1 Presure & Temperature Limits Rept
ML20087C303
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/03/1995
From:
GEORGIA POWER CO.
To:
Shared Package
ML20087C301 List:
References
NUDOCS 9508090132
Download: ML20087C303 (33)
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Text

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VOGTLE ELECTRIC GENERATING PLA . - UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT REVISION 0

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UMT 1 ]

PRESSURE AND TEMPERATURE LIMITS REPORT  ;

i 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 1 3.0 Supplemental Data Tables 5 4.0 Reactor Vessel Material Surveillance Program 15 5.0 References .15 List of Figures Figure Page 2.1-1 Unit 1. Reactor Coolant System Heatup Limitations 2 .

(IIcatap 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 D4ference Between Pressure Instrumentation and Reactor Vessel Beltline Region).

2.1-2 Unit 1 Reactor Coolant System Cooldown Limitations 3 (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). j 2.2-1 Unit 1 Maximum Allowable Nominal PORV Setpoint for the Cold Overpressure Protection System 4

. o t: *

' VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Page 3.0-1 Comparison of the Vogtle Unit 1 Surveillance Material 30 ft-lb 6 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 7 Capsule Data 3.0-3 Vogtle Unit i Reactor Vessel Toughness Table (Unirradiated) 8 3.0-4 Vogtle Unit 1 Reactor Vessel Surface Fluence Values at 16 EFPY 8 (Fluence Based on E > 1.0 MeV 3.0-5 Summary of Adjusted Reference Temperatures (ARTS) for the 9 Vogtle Unit 1 Reactor Vessel Beltline Materials at the 1/4-T and 3/4-T Locations for 16 EFPY 3.0-6 Calculation of Adjusted Reference Temperature at 16 EFPY 10 for the Limiting Vogtle Unit 1 Reactor Vesse! Material (Intermediate Shell Plate B8805-2) 3.0-7 Neutron Exposure Projections at Key Locations on the Vogtle 11 Unit 1 Pressure Vessel Clad / Base Metal Interface 3.0-8 RTns Values for Vogtle Unit I for 4.64 EFPY 12 3,0-9 RTrrs Values for Vogtle Unit I for 32 EFPY 13 3.0-10 RTns Values for Vogtle Unit i for 48 EFPY 14 l

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s' VOGTLE ELEC'IRIC GENERATING PLANT (VEGP)- UNIT 1

' PRESSURE AND TEMPERATURE . LIMITS REPORT 1.0 Reactor Coolant System (RCS) Pressure and Temoeratu;_e Limits Report (PTLR) - Unit 1 This PTLR for VEGP Unit I has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.6. The TS addressed in this report are listed below:

LCO 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.12 Cold Overpressure Protection Systems (COPS) 2.0 Onerating Limits The parameter limits for the specifications listed in section 1.0 are presented in the i following subsections. These limits have been developed using the NRC-approved

' methodology specified in Specification 5.6.6 (Ref.1).

2.I RCS Pressure and Temperature (P/T) 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 egne! 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 for heamp and cooldown are specified by Figures 2.1-I and 2.1-2, respectively.

2.2 Cold Overpressure Protection System (COPS) Setpoints (LCO 3.4.12) i The power-operated relief valves (PORVs) shall each have lift settir.gs in accordance with Figure 2.2-1.

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LaakTest Umit , Criticality

<\ I t Umit for 60*F/hr 2250 Heatup

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Criticality 2000 Umit for

  • i 100*FAr Heatup 1750 I

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Operation 4/

- 1500 I) i /' '

1250 j

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f Operation 1000 Heatbp Rate up tos [

750 I I

[ crecemy umit eased 500 j ' / on inservice:risa Test Tbmperature f/ / L246*F) for the Service -

5eriod up to 16 EFPY 250 0 I

O 50 100 150 200 250 300 350 400 450. 500 Indicated Temperature ('F)

MATERIAL FASIS CopprcAenc Aamuned- NAWT%

(Assual 0.083WT%)

ETginatal: Aamsned.NA V-(Assued-209)

P.rgy At te EFPY: @ 1/4T= 100.7V

$ 3/4T= 84.11 Figure 0,' -

S- 2.l**

Unit 1 Reactor Coolant System Heatup Iimitations (Heatus, rates up to 100*F/ht). Applicabli for the first 16 EFPY (With Margins of 10*F and 60 psig for Instrumentation Errors and Margin of 74 psig f or Pressure Difference Between Pressure Instrumentation and Reactor vessel Beltline Region) .

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'2500 f

2250 2000

- Uriacceptable -

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1750

- 1500 i

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e wOperation ue 1000 i 750 "'

C00ldowft Rates Y/hr 500 l

250 1 u 0

0 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (T) umnw.aAsis Copper Contene Amewned NAWI%

(Adual 1.083 WT%)

RTNOTI ntiet: Assuned. NA1 (Adva'- 209)

RTNOTAt 16 EFPY: @ 1/4T = 100.71

@ 3/4T. 84.1T Figure 0.,  ; 2.j" E Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown rates up to 100*F/hr)

Applicable for the first 16 EFPY (With Margins of 10*r and 60 psig for Instrumentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Instrur.nontation and Reactor Vessel Beltline Region).

J (Jn

800 780 760

_ g 740 _

g  : (212.72e) (380,72s) 700 0

660 640 620 1600 580  ;

560 540 (70 # # ,

520 500 50 100 150 200 250 300 350 1

TRTD - Auctioneered Low Measured RCS Temperature (*F) i Figure h 2. 2 ~f Unit 1 Maximum Allowable Nominal PORV Setpoint for the Cold overpressure Protection System l

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r VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 3.0 Supplemental Data Tabics 8

Table 3.0-1 is a ccmparison of the measured surveillance material 30 ft-lb transition temperature shifl3 and upper shelf energy decreases with Regulatory Guide 1.99, Revision 2 predictions.

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.

l 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).

Table 3.0-7 provides a summary of the fluences used in the PTS evaluation.-

Table 3.0-8 provides RTns values for Vogtle Unit I for 4.64 EFPY.

Table 3.0-9 provides RTns values for Vogtle Unit I for 32 EFPY.

Table 3.0-10 provides RTns values for Vogtle Unit 1 for 48 EFPY.

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.01 Comparison of the Vogtle Unit i Surveillance Material 30 ft-lb Transition Temperature Shias and Upper Shelf Energy Decrease with Regulatory Guide 1.99 Revision 2 Predictions 30 n lb Transition Upper Shelf Energy Fluence Temperature Shin Decrease (x 10" n'em

Predicted'* Measured Predicted'* Measured'*

Material Capsule E > l.0 MeV) ,,

.)

Interrnediate Shell U 0.344 27 15 15 0 Plate 138805 3 (I.ongitidinal) Y 1.24 41 40 20 0 Intermediate Shell U 0.344 27 0 15 0 Plate I18805-3 (Transverse) Y 1.24 41 20 20 0 U 0.344 23 15 15 0 i Weld Metal Y 1.24 35 0 20 1 U 0.344 -

0 -

6 IIA 7, Metal Y 1.24 -

25 -

9 (a) liased on Regulatory Guide 1.99, Revision 2, methodology using mean wt. % values of Cu and Ni.

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 )

PRESSURE AND TEMPERATURE LIMITS REPORT l

Table 3.0-2 Vogtle Unit 1 Calculation of Chemistry Factors Using Surveillance Capsule Data Matenal Capsule Fluence (f) FF" ART. FF* A RTm FF2 (n/cm', ( F) ("F)

F,> l.0 MeV) latermediate Shell Plate U 3 437 x 10 O.706 15 10.585 0 498

!!8805 3 (1,ongitudmal) Y 1.242 x 10 l.060 40 42.4 1.124 Intermediate Shell Plate U 3.437 x 10 O.706 0 0 0.498 H8805-3 (Transverse) Y 1.242 x 10" l.060 20 21.2 1.124 Sum: 74.185 3.244 Chemistry Factor = 74. I85 + 3.244 = 22.9 Wcld 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 = f*"**0 7

i

' VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-3 l

Vogtle Unit i Reactor Vessel Toughness Table (Unirradiated)

Material Description Cu(%P) Ni(%P) Initial RTm( F)N Closure Ilead Flange -- 0.70 20'4

]

Vessel Flange --

0.71 0(4 I Intermediate Shell Plate B88051 0.083 0.597 0 Intermediate Shell Plate B8805-2 0.083 0 610 20 l

l 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 Lower Shell Plate B8606-3 0 067 0.623 10 Intermediate & Lower Shell Vertical 0.039 0.102 -80 l Weld Seams and Girth Seam Weld (a) The rverage values of copper and nickel content.

l (b) Initial RT, 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 I, the minimum boltup temperature is 60 "F.

Table 3.0-4 Vogt!e Unit 1 Reactor Vessel Surface Fluence Values at 16 EFI Y (Fluence Based on E > 1.0 MeV)

Azimuthal 0 15 25 30 15" 45 Surface 6 216E+ 18 9 236E+18 1.088E+19 6 897E+18 9 043(+18 1.015E+19 8

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-VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT <

Table 3.0-5 Summary of Adjusted Reference Temperatures (ARTS) for the Vegtle Unit 1 Reactor Vessel /

Ilcitline Materials at the 1/4-T and 3/4-T Locations fer 16 EFPY

== -

16 EFPY ARTM Con;mnent 1/4-T ( F) 3/4-T (F)

Interrxdiate Shell Plate B38051 80.7 64.1 Internaliate Shell Plate B8805-2 100.7* 84.IN Intermediate SFM Plate B8805-3 97.5 76.4 Intermedi4L hhcIl Plate B8805-3 67.1 57.6

ITsing S/C Data -

Lov er Shell Plate B86061 77.6 59.6 '

Lower Shell Plate B%06-2 81.9 62.5 Lower Sheli Plate B8606-3 ti';.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 -48.5W Long. Weld 101-124B -30.0'* -4 7.060 I,ong. Weld 101-124C -30.0'* -47.0'*

Long. Weld 10! 142A -30.0'* -47.0'*

Long. Weld 101-1428 -31 8'd 48.5W l.ong. Weld 101-142C 30 0'* -4 7. 0'*

2 (a) The ARTS presented here are based on the peak reactor vessel surface 11uence of 1.088 x 10" n/cm (E > 1.0 MeV) unless noted. l l

(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" n/cm2 (E > 1.0 MeV) at 0 (d) These ARTS were calculated using the peak vessel 11uence of 6.897 x 10" n/cm' (E > 1.0 MeV) at 30 .

9 1

VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TE31PERATURE LIMITS REPORT u--.-.

Table 3 0-6 Calculation of Adjusted Reference Temperature at 16 EFPY for the Limiting Vogtle (Jnit i Reactor Vesel Material (Intermediate Shell Plate B8805-2)

Parameter ART Value Operating Time 16 EFPY Material B8805 2 B8805-2 Location 1/4-T 3/4-T Chemistry Factor, CF (T) 53.1 53.1 Fluence + 10" n/cm (E > 1.0 MeV), fo 2

0 6485 0.2303 Fluence Factor, FF" 6.879 0.604 A RTwr = CF x FF,("F) 46 653 32.056 Initial RTwr, I( F) 20 20 Margin, M ("F)W 34 32.056 ART = 1 + (CF x FF) + M ("F) 100.7 84.1 per Regulatory Guide 1.99, Revision 2 (a) Fluence, f, is based upon f.,(10" n/cm , 2E > 1.0 MeV) = 1.088 at 16 EFPY. The Vogtle (Jnit 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 defmed as FF = f'2" "*

(c) Margin is calculated as M = 2(o,' + c,2)" The standard deviation for the initial RTsm margin term, o,,is 0 F since the initial RT,,m is a measured value. The Standard deviation Ibr ARTsw term o , is 17 F for the plate, except that o, need not exceed 0.5 times the mean value of a RTwr.

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 J-PRESSURE AND TEMPERATURE LIMITS REPORT-l l

Table 3.0-7 l Neutron Exposure Projections

  • at Key Locations on the Vogtle Unit 1 Pressure Vessel Clad / Base Metal Interface EFPY 0 15" 25 30 35 45 p 4 64 0.1802 0.2678 0.3155 0.2000 0.2622 0.2942

) 32 1.243 1.847 2.176 1.379 ' l.809 2.029 j- 48 I863 2.769 3.262 2.068 2.7 I i 3.041 l 2 (I) Fluence in 10" n/cm (E > 1.0 McV).

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-8 RT, Values for Vogtle Unit I for 4 64 EFPY Material CF Surface Fluence FF ARTmr I M RTm (F) (n/cm', (CF x FF) (T) (F) (F)

E > I,0 MeV) (T)

Inter Shell Plate 53.1 3.155 x 10" 0.6833 36.3 0 34 70.3 118803 1 l Inter. Shell Plate 53.1 3155 x 10" 0.6833 36.3 20 34 90.3 I 113803 2 Inter Shell Plate 38 4 3.155 x 10" 0.6833 26.2 30 34 90.2 138803 3 Inter. Shell Plate 22.9 3.155 x 10 O.6833 15.6 30 34 79.6 l I18805 3 1.tsing S C Dat/"

lower Shell Plate 32 8 3.155 x 10" 0.6833 22.4 20 34 76.4

!!8606 1 lamer Shell Plate 35.2 3.155 x 10 O.6833 24.1 20 34 78.1 nx606 2 1.ower Shell Plate 41.9 3.155 x 10 0 6833 28 6 10 34 72.6 l 118606-3 Cire. Weid 33.2 3.155 x 10" 0.6833 22.7 -80 56 -1.3 101 171 '

Weld sletal 6.5 3155 x 10 O6833* 4.4 -80 56 -19.6

!! sing S'C Dati" long Weld 33.2 1.802 x 10" 05448 18.1 80 56 -5.9 101 124A long Weld 33.2 2.0 x 10" 0.5694 18.9 -80 56 -5.1 101 12411 tons Weld 33 2 2.0 x 10" 0.5694 I89 -80 56 -5.I 101 124C leng Wcld 33 2 2.0 x 10" 0.5694 I89 -80 56 -5.I 101 142A long Weld 33 2 1.802 x 10 O5448 18.1 -80 56 -5.9 101 14211 tens Weld 33.2 2.0 x 10" 0 5694 18.9 -80 56 -5.1 f t o s.142c (1) Numbers were calculated usmg a chemistry factor (CF) based on surveillance capsule da,a.

(2) Peak tluence factor which represents most limiting case for weld metal.

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT l

l Table 3 0-9 1 1

RTm Values for Vogtle Unit I fbr 32 EFPY j Material CF Surface Fluence FF c.RTm 1 M RTm (F) (n/cm 2, (CF x FF) (F) (F) ( F) ,

E > 1.0 MeV) ( F) l bder ShellPlate 53.1 2.176 x 10 l.2110 64.3 0 34 98.3 I 118R051 Inter. Shell Plate 53.1 2.176 x 10 l.2110 64.3 20 34 118.3 118805 2 Inter. Shell Plate 38 4 2.176 x 10 l.2110 46.5 30 34 110.5 118805 3 i inter. Shell Plate 22.9 2.176 x 10 l.2110 27.7 30 34 91.7 118805 3 Using S. C Data"'

lower Shell Plate 32.8 2.176 x 10 l.2110 39.7 20 34 93.7 D8606-1 lower Shell Plate 35.2 2.I76 x 10" l.2110 42.6 20 34 96.6

[18606-2 tower Shell Plate 41,9 2.176 x 10 l.2110 50.7 10 34 94.7 118606-3 Cire. weld 33.2 2.176 x 10 l.2110 40.2 -80 56 16.2 101 171 Weld Metal 6.5 2176 x 10 l.2110m 7.9 -80 56 -16.1 Using S.C Data'"

1 tong weld 33.2 1.243 x 10 l.0606 35.2 -80 56 11.2 101 124A i l

long Weld 33 2 1379 x 10 l.0893 36.2 -80 56 12.2 I 101 12411 tong Weld 33 2 1.379 x 10" l.0893 36.2 -80 56 12.2 101 124C tong. 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 11.2 101-142fl long Weld 33.2 1.379 x 10 l.0893 36.2 -80 56 12.2 101 142C (I) Numbers wcre calculated using a chenustry factor (CI') based on surveillance capsule data.

(2) Peak fluence f actor wtuch represents nwst Imuting case fir wcld metal.

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VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT.1 PRESSURE AND TEMPERATURE LIMITS REPORT l

i Table 3.0-10 RTm Values fbr Vogtle Unit I for 48 EFPY l

Materni CF Surface Fluence FF ART , I M RTrrs (F) (n/cm2, (CF x FF) (F) ("F) (F)

E > 1.0 MeV) ("F)

Inter. shell Plate 53 1 3.262 x 10" 1.3104 69.6 0 34 103.6 118803 1 Inter. shell Plate 53.1 3.262 x 10" 1.3104 69.6 20 34 123.6 11880$-2 Inter. Shell Plate 38.4 3.262 x 10 l.3104 50.3 30 34 114.3 113805-3 Inter. Shell Plate 22.9 3.262 x 10" 1.3104 30.0 30 34 94.0 DE203 3 l'aing S C Data'"

tower Shell Plate 32.8 3.262 x 10" 1.3104 43.0 20 34 97.0 D86061 tower shell Plate 35.2 3 262 x 10" 1.3104 46.1 20 34 100.1 Il8606-2 tower shell Ptate 41.9 3 262 x 10" 1.3104 54.9 10 34 98.9 118606-3 cire. weld 33.2 3.262 x 10" 1.3104 43.5 -80 56 19.5 101 171 Weld kfetal 6.5 3 262 x 10" 1.3104* 8.5 -80 56 15.5 tIsing sic Data">

Ient Weld 33 2 1.863 x 10 l.1705 38.9 -80 56 14.9 101 124A long weld 33.2 2.068 x 10" 1.1978 39.8 -80 56 15.8 101 12411 tong wetd 33 2 2.068 x 10" 1.1978' 39.8 -80 56 15 8 101 124C tong Weld 33.2 2.068 x 10" 1.1978 39.8 -80 56 15.8 101 142A tong weld 33 2 1863 x 10" l.1705 38.9 -80 56 14.9 101 14211 lent Weld 33.2 2.068 x 10" 1.1978 39.8 -80 56 15 8 ioi.142c (1) Numbers were calculated using a chemistg factor (CF) based on surveillance capsule data. ,

(2) l'eak lluence factor w hich represents most limiting case for weld metal.

14

1

y. , a d i 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 II, and is described in section 16.3 of the VEGP FSAR.

5.0 References

1. WCAP-14040, Revision 1, December 1994, " Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves.

1

2. Louis L. Wheeler to C. K. McCoy, dated June 8,1995, " Issuance of Amendments -

Vogtle Electric Generating Plant, Units 1 and 2 (TAC Nos. M90966 and M90967)."

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VOGTLE ELECTRIC GENERATING PLANT - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT REVISION 0

[DATE]

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VOGTLE ELECI'RIC GENERATING PLANT - UNIT 2 '!

-1 l

PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents . ,

1 Section Page..

.\

1.0 Reactor Coolant System (RCS) Pressure and Tempenture 1- i

~

Limits Report - Unit 2 2.0 ' Operating Limits 1_

I 2.1 RCS Pressure and Temperature (P/T) Limits 1 2.2 Cold Overpressure Protection System (COPS) Setpoints 1 3.0 Supplemental Data Tables ~5 4.0 Reactor Vessel Material Surveillance Program 14 5.0 References 14 List if Figures Figure Page-2.1-1 Unit 2 Reactor Coolant System Heatup Limitations 2 (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 Beltline Region).

2.1-2 Unit 2 Reactor Coolant System Cooldown Limitations 3 (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). l 2.2- 1 Unit 2 Maximum Allowable Nominal PORV Setpoint

. for the Cold Overpressure Protection System 4 i

E t* e- , . . - ..~r ,e-. ,--r.zr- w. , , w- + m

.n VOGTLE ELECTRIC GENERATING PLANT- UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT List ofTables Table Page 3.0-1 Comparison of the Vogtle Unit 2 Surveillance Material 30 R-lb 6 Transition Temperature Shins and Upper Shelf Energy Decrease with Regulatory Guide 1.99, Revision 2, Predictions 3.0-2 Vogtle Unit 2 Calculation of Chemistry Factors Using Surveillance 7 Capsule Data 3.0-3 Vogtle Unit 2 Reactor Vessel Toughness Table (Unirradiated) 8 3.0-4 Vogtle Unit 2 Reactor Vessel Surface Fluence Values at 16 EFPY 8 (Fluence Based on E > 1.0 MeV 3.0-5 Summary of Adjusted Reference Temperatures (ARTS) for the 9 Vogtle Unit 2 Reactor Vessel Beltline Materials at the 1/4-T and 3/4-T Locations for 16 EFPY 3.0-6 Calculation of Adjusted Reference Temperature at 16 EFPY -10 for the Limiting Vogtle Unit 2 Reactor Vessel Material (Lower Shell Plate B8628-1) 3.0-7 Neutron Exposure Projections at Key Locations on the Vogtle 11 Unit 2 Pressure Vessel Clad / Base Metal Interface 3.0-8 RTrrs Values for Vogtle Unit 2 for 32 EFPY 12 3.0-9 RTrrs Values for Vogtle Unit 2 for 48 EFPY 13 i

I iii a

VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2

~

PRESSURE AND TEMPERATURE LIMITS REPORT 1_0 Esactor Coolant System (RCS) Pressure and Temocrature Limits Reoort (PTLR)- Unit 2 This PTLR for VEGP Unit 2 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.6. The TS addressed in this report are listed below:

LCO 3.4.3 RCS Pressure and Temperature (Pff) Limits LCO 3.4.12 Cold Overpressure Protection Systems (COPS) 2.0 Ooeratinu Limits The parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodology specified in Specification 5.6.6 (Ref.1).

2.1 RCS Pressure and Temperature (P/T) 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 .;'

l-hour period during inservice hydrostatic and leak testing operations

, above the heatup and cooldown limit curves.

~

2.1.2 The RCS Pfr limits for heatup and cooldoivn are specified by Figures 2.1-I and 2.1-2, respectively.

22 Cold Overpressure Protection System (COPS) Setpoints (LCO 3.4.12)

The power-operated relief valves (PORVs) shall each have lift settings in accordance with Figure 2.2-1.

i l

. _ . _ _ _ . _ . _ . . _ = _

.- . 2500 I Cr'iticality l l '

Laak Test Umit N Umit for I , 60*F/hr 2250 j Heatup ~

L 2000  % Criticality Unacceptable ,

W" - Heatup 1750 h/

s_

1250

== ~l/ I w.- _

E F 1000 Heatup Rate l

'( -

up to 100*Fhir -

f Umit Based

/ on W,6ms y 500 / Test Temperature -

f i 'F) for the Service ~

m I up to 16 EFPY l 1

250 0

0 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (*F) unmuAa.sAsa Copper Contenc Asmanssi.NAWi%

(Aalual.0.OB WT%)

RTNOT N h.NA Y (Assual.507)

RTNDT At is EFPY: @ -'1/47 = 112V

@ 3/4T.84V rigure 6 7..l-l Unit 2 Reactor Coolant Sys*:em Heatup Limitations (Heatup rates up to 100*F/hr) Applicable for the First 16 ETPY (with Margins of 10*r and 60 psig for Instrentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Inststaku... tion and Reactor Vessel Beltline Region).

6  ;/ ^ L.- l

i 2500 2250

_ l 1750 Unacceptable operation

/

f

- 1500 l

1250 dt Amwe i 1000 ,

W z50 /

Rates 'F/hr e

500 ' [

0 250 ,gg / -

0 0 50 100 150 200 250 300 350 400 450 500 Indicated Temperature (*F)

MATERW.8 ASIS

- Copper Content: Asowned.NAWI%

(Actual.0.0s WT%)

RTET nimal:

I Assuned NAY (Assual.sov)

RTETAt 16 EFPP. @ 1/4T.112T

@ 3/4T = 941 Figure M E. ! ** L Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown rates up to 100*F/hr) l Applicable for the First 16 EFPY (With Margins of 10*r and 60 psig for Instrumentation Errors and Margin of 74 psig for Pressure Difference Between Pressure Instrunnentation and Reactor Vessel Beltline Region).

vv . _.: ~* T: 1- 2  ;, , , , , . . /

800 780 760 j

~ 740 ~~

(222,7am (ago.7am 720
700 680 660 f

6@ A 620

a / .

J 580 I 50 /

'5 g )

520 @]16)

/

500 50 100 150 200 250 300 350 TRTD - Auctioneered Low Measured RCS Temperature ('F) i i

j s

Figure N 2e E ~l Unit 2 Maximum Allowable Nominal PORV Setpoint for the Cold Overpressure Protection System f g

~*

VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2

?RESSURE AND TEMPERATURE LIMITS REPORT 3.0 Supolemental Data Tables Tabb 3.0-1 is a comparison of the measured surveillance material 30 f1-lb transition 1 . temperature shifts and upper shelf energy decreases with Regulatory Guide 1.99, Revision 2 predictions.

Table 3.0-2 shows the calculation of the surveillance material chemistry factors using surveillance capsule data. However, since there has been only one surveillance capsule removed from the Vogtle Unit 2 reactor vessel, this table has been intentionally left blank.

Table 3.0 3 provides the unirradiated Vogtle Unit 2 reacter 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 2 reactor vessel beltline materials at the 1/4-T and 3/4-T locations for 16 EFPY. i Table 3.0-6 shows the calculation of the ART at 16 EFPY for the limiting Vogtle Unit 2 j reactor vessel material lower shell plate B8628-1). _

. 1 Table 3.0-7 provides a summary of the fluences used in the PTS evaluation. i Table 3.0-8 provides RTrrs values for Vogtle Unit 2 for 32 EFPY.

Table 3.0-9 provides RTers values for Vogtle Unit 2 for 48 EFPY.

, 5

~

l

. \

VOGTLE ELECTRIC GEN ERATING t? ANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT i able 3.0-1 Comparison of the Vogtle Unit 7 Surveillance Material 3011-lb Transition Temperature Shifts and Upper Shelf linergy Dxrease with Regulatog Guide 1.99 Revision 2 Predictions 3011 lb Transition Upper Shelf Energy Fluence Temperature Shift Decrease

(* ' '**

Predicted) Measured Predicted'*) Measured Material Capsule E > l 0 MeV)

( F) ("F) (%) (%)

Lower Shell Plate B8628 l U 0.444 24 0 16 0 (longitidinal) lamer Shell Plate 118628-1 U 0444 24 0 16 0 (Transverse)

Weld Metal U 0.444 28 0 16 0 llAZ Metal U 0 444 - 0 - 0 (a) Based on Regulatory Guide 1.99, Revision 2, methodology using mean wt % values of Cu and Ni.

1 6 i l

1

, 1 VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT i Table 3.0-2M Vogtic Unit 2 Calculation of Chemistry Factors Using Surveillance Capsule Data Material Capsule Fluence (f) FF" A RT, FF* A RTmyr FF2 (n/cm2, ("F) (F)

E > 1.0 MeV)

Sum:

< Chemistry Factor =

3 Weld Metal Sum:

Chemistry Factor =

(a) Fluence Factor (FF) per Regulatory Guide 1.99, Revision 2, is defined as FF = f" *'0

(*) This table was intentionally left blank since only one surveillance capsule has been removed from Vogtle Unit 2 to date.

1 i

7

.- - . . _ _ . .- . - -. - .~. . .

N VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

)

Table 3.0-3 Vogtle Unit 2 Reactor Vessel Toughness Table (Unitradiated) I Material Description Cu(%P) Ni(%P) Initial RTm(OFP) l Closure Ilead Flange -- -- 10") ,

i Vessel Flange -- -- -60'o l

Intennediate Shell Plate R4-1 0 06 0.64 10 Intermediate Shell Plate R4-2 0.05 0.62 10 intermediate Shell Plate R4 3 0.05 0.59 30 Lower Shell Plate B8825-1 0.05 0.59 40 Lower Shell Plate R8-1 0.06 0.62 40 Lower Shell Plate B8628-1 0.05 0.59 50 Longitudinal Welds 0.07 0. 3 -10 Circumferential Weld 0.06 0.12 -30 (a) The average values of copper and nickel content.

5 (b) InitialRTwr values are measured values.

(c) These values are used for considering tlange requirements fbr the heatup/cooldown curves. Per the metinlology given in WCAP-14040, Revision 1, the minimum boltup temperature is 60 F.

Table 3.0-4 4

Vogtle Unit 2 Reactor Vessel Surface Fluence Values at 16 EFPY 4

(Fluence Based on E > 10 MeV)

Azimuthal 0 15 -25 35 45 Surface 8.99E+ 18 1.34E+19 1.52E+19 1.24E+19 1.42E+19

.a 8

!(

3; i , ,

.,. ( .,

I E

VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2 f PRESSURE AND TEMPERATURE LIMITS REPORT i-

.l 1

Table 2 0-5 ]

l l '-

Summary of Adjustrd Reference Temperatures (ARTS) for the Vogtle Unit 2 Rea< tor Vessel ,

Ileft:ine Materials at the 1/4-T and 3/4-T Locations for 16 EFPY l 16 EFPY ARTN l/4-T ( F) 3/4 T ( F)

Intermediate Shell Plate R41 80 61 Intennediate Shell Plate R4-2 70 53 tutermediate Shell Plate R4-3 90 73 Lower Shet! Plate B8825-1 100 83 Lower Shell Plate R8-1 110* 9; Lower Shell Plate B8628-1 110* 93N i

Longitudinal Welds 81 55 Circumferential Weld 54 29 (a) The ARTS presented here are based on the peak reactor vessel surface 11uence of 1.52 x 10" n/cm'(E > 1.0 MeV) at 16 EFPY, which is conservative for the longitudinal weld seams.

(b) These ART values are used to generate the heatup and cooldown curves.

, )

i-i 9 j i

L

e VOGTLE ELECTRIC GENERATING PIANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-6 Calculation of Adjusted Reference Temperature at 16 EFF Y for the Limiting Vogtle Unit 2 Reactor Vesel Material (lower Shell Plate B86281)

Parameter ART Value Operating Tin

  • 16 EFPY Material B8628-1 B8628-1 location 1/4-T 3/4-T Chemistry Factor, CF ("F) 31 31 Fluence + 10" n/cm'(E > l.0 MeV), f4 0.9057 0.3215 Fluence Factor, Fl* 0.972 0.688 ARTum = CF x FF,( F) 30 21.5 j 1

Initial RTum,I( F) 50 50 i Margin, M ( F)"' 30 21.5 ART = 1 + (CF x FF) + M ( F) I10 93 per Regulatory Guide 1.99, Revision 2 (a) Fluence, f, is based upon f,,,,(10" n/cm 2, E > 1.0 MeV) = 1.52 at 16 EFPY. The Vogtle Unit 2 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*"*'t 4 (c) Margin is calculated as M = 2(o,' + o,')" The standard deviation for the initial RTsmmargin term, o,, is 0 F since the initial RTsm is a measured value. The Standard deviation for ART,mterm o,,is 17 F for the plate, i execpt that o, need not exceed 0 5 times the mean value of aRTum.

I

( J 10

t VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0 7 Neutron Exposure Projections"> at Key Locations on the Vogtle Unit 2 Pressure Vessel Clad / Base MetalInterface 3FPY 0 15 25 35 45 32 1,80 2.69 3.04 2.47 2.84

_ 48 2.70 4.05 4.56 3.69 4.26 2

(1) Fluence in 10" n/cm (E > 1.0 MeV).

l 1

11

.. _ - _ _ _ - _ _ _ _ _ _ _ _ . _ _ = . _ _ _ .

i VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.0-8 RT,,,, Values for Vogtle thiit 2 lbr 32 EFTY Material CF Surface Fluence FF cRTm I M RTm (F) (n/cm 2, (Cii FF) (F) (F) (F)

E > 1.0 MeV) ( F; Inter. Shell Plate 37 3 04 x 10" 1.29 47.7 10 34 92 R4-1 Inter. Shell Plate 31 3 04 x 10" 1.29 40.0 10 34 84 R4-2 Inter. Shell Plate 31 3.04 x 10" 1.29 40.0 30 34 104

R4-3 lower Shell Plate 31' 3 04 x 10" 1.29 40.0 40 34 114-138825-1 lower Shell Plate 37 3 04 x 10" 1.29 47.7 40 34  ! 122 R8-1 Iower Shell Plate 31 3 04 x 10" 1.29 40f 50 34 124 B8628-1
longitudinal 47 3.04 x 10" 1.29 60.6 -10 56 !07 l Weld Circumferential 43 3.04 x 10" 1.29 55.5 30 56 82 Weld (1) RTm values were calculated using the peak 32 EFPY vessel ch4 base metalinterface fluence of 3.04 x 10" n/cm 2(H > 1.0 MeV), which is conservative for the longitudine'. weld seams (See Table 3.0-7).

8 4

l

]'

, )

12

-r pwn- g-,----n,- , - - , --

VOGTLE ELECTRIC GENERATING PIANT(VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS IMPORT n:== = ,

Table 3.0-9 ,

1 RT,,, Values for Vogtle Unit 2 lbr 48 EFPY ,

Material CF Surface Fluence FF aRTm I M RTm

("F) (n/cm', (CF x FF) ( F) (F) ( F)

II > 1.0 MeV) ("F)

Inter. Shell Plate 37 4.56 x 10" 1.384 51.2 10 34 95 R4-l Inter. Shell Plate 31 4.56 x 10" 1.384 42.9 10 34 87 R4-2 Inter. Shell Plate 31 4.56 x 10" 1 391 42.9 30 34 107 R4-3 1.ower Shell Plate 31 4.56 x 10" 1.384 42.9 40 34 117 B8825-1 1 ower Shell Plate 37 4.56 x 10" 1.384 51.2 40 34 125 R8-1 1.ower Shell Plate 31 4.56 x 10" 1.384 42.9 50 34 127 B8628-1 I.ongitudmal 47 4.56 x 10" 1.384 65.0 -10 56 11' Weld Circumtetential 43 4 56 x 10" 1.384 59.5 -30 56 86 ,

Weld (I) RT values m were calculated usmg the peak 48 EFPY vessel clad /hase metal interface lluence of 4.56 x 10"

]

r/cm' (E > 10 MeV), which is comervative Ibr the longitudinal weld seams (See Table 3.0-7).

13 l

,o_.

VOGTLE ELECTRIC GENERATING PLANT (VEGP)- UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 4.0 Reactor Vessel MatenalSurveillance Procram 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.

5.0 References

1. WCAP-14040, Revision 1, December 1994, " Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves ."
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) "

i l

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l 14 c- -w ,y ,-,.g - . .g. -. , .y - w w- rr--' s wi- *

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