ML20141K037

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Pressure & Temp Limits Rept
ML20141K037
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 05/21/1997
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20141J982 List:
References
NUDOCS 9705280293
Download: ML20141K037 (23)
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4 ATTACHMENT H *

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l 3 BRAIDWOOD UNIT I i

, PRESSURE AND TEMPERATURE LIMITS REPORT N

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. .g BRAIL WOOD- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents Section Page 1.0 Introduction 1

2.0 Operating Limits 1

2.1 RCS Pressure and Temperature (Pfr) Limits 1

2.2 Low Temperature Overpressure Protection (LTOP) System Setpoints 2

- 2.3 LTOP Enable Temperature 2 2.4 Reactor Vessel Boltup Temperature 3 2.5 Reactor Vessel Minimum Pressurization Temperature 3

., 3.0 Reactor Vessel Material Surveillance Program 9 4.0 Supplemental Data Tables 11 5.0 References i 18 1

Attachment WCAP-14824, " Byron Unit 1 Heatup and Cooldown Limit Cunes for Normal Operation and j Surveillance Weld MetcJ Integration for Byron and Braidwood," Revision 1, April 1997.

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l BRAIDWOOD- UNIT 1 i

PRESSURE AND TEMPERATURE LIMITS REPORT i

List of Figures r.

Figure Page ,

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2.1 Braidwood Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rates up to 4 l 100 F/hr) Applicable for the First 16 EFPY (Without Margins for Instrumentation  !

Errors) '

2.2 Braidwood Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up 5 ,

to 100 *F/hr) Applicable for the First 16 ETPY (Without Margins for Instrumentation  ;

Errors) f i

2.3 Braidwood Unit 1 Maximum Allowable Nominal PORV Setpoints for the Low 7 Temperature Overpressure Protection (LTOP) System Applicable for the First 16 EFPY '

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y BRAIDWOOD-UNIT 1 i*

l PRESSURE AND TEMPERATURE LIMITS REPORT l

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List of Tables Table Page  ;

2.1 Braidwood Unit 1 Heatup and Cooldown Data Points at 16 EFPY 6  :

(Without Margins for Instrumentation Errors) i

.l 2.2 Data Points for Braidwood Unit 1 Maximum Allowable PORV Setpoints 8 for the LTOP System Applicable for the First 16 EFPY 3.1 Braidwood Unit 1 Capsule Withdrawal Schedule 10 4.1 Braidwood Unit 1 Calculation of Chemistry Factors Using Surveillance 12 ,

Capsule Data i

4.2 Braidwood Unit 1 Reactor Vessel Material Properties 13 4.3 Summary of Braidwood Unit 1 Adjusted Reference Temperatures (ARTS) at 14 the 1/4T and 3/4T Locations for 16 EFPY ,

4.4 Braidwood Unit 1 Calculation of Adjusted Reference Temperatures (ARTS) at 15 16 EFPY at the Limiting Reactor Vessel Material Weld Metal WF562 (Based on Surveillance Capsule Data) 4.5 RTrrs Values for Braidwood Unit I for 32 EFPY 16

' 4.6 RTrrs Values for Braidwood Unit I for 48 EFPY 17 l

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BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT -

1.0 Introduction 1

Reference to Technical Specifications (TS) numbers are given in both the Braidwood Station l

current Technical Specifications (CTS) and Improved Technical Specifications (ITS). The CTS number is presented first, followed by the ITS number in brackets [ ].

This PTLR for Unit I has been prepared in accordance with the requirements of i TS 6.9.1.11/[lTS-5.6.6]. , Revisions to the PTLR shall be provided to the NRC after issuance. l The Technical Specifications addressed in this report are listed below:

LCO 3.4.9.1 Pressure / Temperature Limits; and LCO 3.4.9.3 Overpressure Protection Systems.

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[ITS-LCO 3.4.3 RCS Pressure and Temperature (P/T) Limits; and LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System].

2.0 Operating Limits The PTLR limits were developed using a methodology specified in the Technical Specifications.

The methodology listed in WCAP-14040-NP-A (Reference 1) was used with four exceptions: I

a. Use of ENDF/B-IV neutron transport cross-section library and ENDF/B-V dosimeter reaction cross-sections, .
b. Optional use of ASME Code Section XI, Appendix G, Article G-2000,1996 Addenda,
c. Use of ASME Code Case N-514, and
d. Use of RELAP computer code for calculation of LTOP setpoints for Unit I replacement steam l

generators.

WCAP-14824, Revision 1,is included as an attachment for reference. WCAP-14824 contains the P/T curves for Byron Unit 1, along with the weld metal data integration for Byron and Braidwood Units 1 and 2 and the Byron /Braidwood fluence methodologyjustification for ENDF/B-VI cross sections.

2.1 RCS Pressure and Temperature (P/T) Limits (LCO 3.4.9.1/ [ITS-LCO 3.4.3])

2.1.1 The RCS temperature rate-of-change limits defined in Reference 7 are:

a. A maximum heatup of 100*F in any 1-hour period, l b. A maximum cooldown of 100 F in any 1-hour period, and

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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.

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HRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT t Operating Limits (Continued) 2.1.2 The RCS P/T limits for heatup, inservice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.1. The RCS P/f limits for cooldown are shown in Figure 2.2 and Table 2.1. These limits are defined in Reference 7. Consistent with the methodology described in Reference 1, the RCS P/T limits for heatup and cooldown shown in Figures 2.1 and 2.2 are provided without margins for instrument error. In determining compliance with Figures 2.1 and 2.2 and Table 2.1, instrument uncertainties need not be i

considered since appropriate station operating procedures ensure that the limits contained in the figures and table are not exceeded. The criticality limit curve specifies pressure-temperature limits for core operation to provide additional margin during actual power production as specified in 10 CFR 50, Appendix G.

The P/T limits for core operation (except for low power physics testing) are that the reactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostatic test, and at least 40 F higher than the minimum permissible temperature in the corre::ponding Pff curve for heatup and cooldown.

2.2 Low Temperature Overpressure Protection (LTOP) System Setpoints (LCO 3.4.9.3/ l

[lTS-LCO 3.4.12]). i The power operated relief valves (PORVs) shall each have maximum lift settings in accordance with Figure 2.3 and Table 2.2. These limits are based on References 5,13, and 14.

The LTOP setpoints are based on the P/T limits established by 10 CFR 50, Appendix G without allowance for instrumentation error in accordance with the methodology described in Reference 1, the LTOP PORV maximum lift settings shown in Figure 2.3 and Table 2.3 account for appropriate instrument error.

2.3 LTOP Enable Temperature The as analyzed LTOP enable temperature is 220 F (Reference 5).

The TS required enable temperature for the PORVs shall be 2 350 F RCS temperature (Braidwood Unit 1 procedures governing the heatup and cooldown of the RCS require the arming of the LTOP System for RCS temperature of 350*F and below and disarming of LTOP for RCS temperature above 350 F).

Note that the last LTOP PORV segment in Table 2.2 extends to 450'F where the pressure setpoint is 2350 psig. This is intended to prohibit PORV lift for an inadvertent LTOP system arming at power.

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l l 1 BRAIDWOOD -UNIT 1 '

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PRESSURE AND TEMPERATURE LIMITS REPORT l Operating Limits (Continued) l

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2.4 Reactor Vessel Boltup Temperature (Non-Technical Specification)

TI: - :nimum boltup temperature for the Reactor Vessel Flange shall be 2 60 F. Boltup is a condition in which the Reactor Vessel head is installed with tension applied to any stud, l

and the RCS vented to atmosphere (Reference 7).

2.5 Reactor Vessel Minimum Pressurization Temperature (Non-Technical Specification)

The minimum temperature at which the Reactor Vessel may be pressurized (i.e., in an unvented condition) shall be 2 60*F, plus an allowance for the uncertainty of the temperature instrument, determined using a technique consistent with ISA-S67.04-1994.

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BRAIDWOOD - UNIT 1 ,

PRESSURE AND TEMPERATURE LIMITS REPORT i

MA'ITRIAL PROPERTY BASIS LIMITING MATERIAL: WELD METAL LIMITING ART VALUES AT 16 EFPY: 1/4-t, 76.6*F 3/4-t 65.4*F 2500 _ , , , ,,,,,,,, ,, , ,

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__ TEMPERATURI (280 F) FOR THE SERVICE PERIOD UP TO 18.0 EFPY 0  ; i i  ;  ;  ;

0 50 100 150 200 250 300 350 400 450 500 ,

Indicated Temperature (Deg.F)

Figure 2.1 .

Braidwood Unit 1 Reactor Coolant System Heatup Limitations (Heatup Rates up to 100 'F/hr) Applicable for the First 16 EFPY (Without Margins for Instrumentation Enors) l 4 l

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- BRAIDWOOD- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT MA1ERIAL PROPERTY BASIS r

i LIMITING MATERIAL: WELD METAL LIMITING ART VALUES AT 16 EFPY: 1/4-t. 76.6*F 3/4-t 65.4*F 2500 ,,,,, , 1 ,,,,

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

Figure 2.2 Braidwood Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100 'F/hr) Applicable for the First 16 EFPY (Without Margins for Instrumentation Errors)-

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I BRAIDWOOD- UNIT 1 1

PRESSURE AND TEMPERATURE LIMITS REPORT 1

Table 2.1 Braidwood Unit 1 Heatup and Cooldown* Data Points at 16 EFPY" (Without Margins forInstrumentation Errors) s 4

Cooldown Cwves Hantup Curve Steady state 25 DEG CD hek Test Data 50 DEG CD 100 DEG CD 100 DEG Cait. Lirnit T P T P T P T P T 60 620.27 P T P T P 60 577.45 60 534.28 60 446.98 60 565.09 210 0.00 65 621.00 65 590.68 188 2000 65 548.52 65 463.79 65 565.09 210 611.83 210 70 621.00 70 605.03 70 563.98 70 481.93 70 565.09 2485 15 621.00 75 620.51 210 597.56 75 580.67 75 501.49 75 565.09 210 585.60 80 621.00 80 621.00 80 59831 80 522.68 80 565.09 85 621.00 85 621.00 210 576.77 85 617.90 85 545.50 85 565.09 210 57035 1 l 90 621.00 90 621.00 90 621.00 90 570.23 90 565.09  !

95 621.00 95 621.00 210 566.61 i 95 621.00 95 596.53 95 565.09 210 565.09 l 100 621.00 100 621.00 100 621.00 100 621.00 105 621.00 105 621.00 105 621.00 105 621.00 100 565.87 210 565.87 {

110 621.00 105 568.69 210 568.69

!!O 621.00  !!0 621.00 110 621.00 110 573.56 210 573.56 110 795.92 110 766.92 110 739.27 110 690.04  !!$ 58030 i 115' 821.55 115 794.59 210 58030 115 769.53 115 726.24 120 588.84 210 588.84 120 849.00

  • 120 824.45 120 801.97 120 765.12 125 59936 125 878.42 125 856.54 210 59936 125 836.87 125 807.07 130 611.78 210 611.78 130 910.25 130 890.97 130 874.41 130 852.23 135 626.07 4

135 94434 135 928.00 210 626.07 135 915.03 135 900.91 140 642.16 210 642.16 140 540.89 140 % 7.79 140 958.57 140 95333 145 65036

] 145 1020.15 145 1010.84 210 66036

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145 1005.42 145 1009.81 150 680.59 210 680.59

' 150 106235 150 1056.88 150 1055.76 155 1107.92 155 702.80 210 702.80 155 110638 160 72733 210 72733 160 1156.42 165 754.07 165 1208.78 210 754.07 170 1265.05 170 783.17 210 783.17 175 814.98 215 814.98 175 1325.37 180 1390.04 180 84937 220 84937 185 1459.41 185 886.54 225 886.54 5

190 1533.55 190 926.73 230 926.73 195 1613.49 195 970.11 235 970.11 200 1016.91 240 1016.91 200 1699.01 1 205 106733 245 1067.33 205 1790.55 210 1121.63 210 1888.61 250 1121.63 215 1180.01 255 1180.01 215 1993.61 220 1242.62 220 2105.69 260 1242.62 225 1309.84 265 1309.84 225 2225.77 230 1382.03

230 2353.75 270 1382.03 J 235 1459.45 275 1459.45 240 1542.27 280 1542.27 245 1630.97 285 1630.97 250 1726.05 290 1726.05 255 1827.80 295 1827.80 260 1936.51 300 1936.51 265 205239 305 205239 i 270 217633 310 2176.33 j 275 2308.42 315 2308.42 i 280 2449.09 320 2449.09 i 4

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Heatup and cooldown data include vessel flange requirements of 110*F and 621 psig per 10 CFR 50, Appendix G.

" For each cooldown rate, the steady-state pressure values shall govern the temperature where no allowable i

{ pressure values are provided.

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BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT - I I

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' AUCTIONEERED LOW RCS TEMPERATURE (DEG. F) ,

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Figure 2.3 Braidwood Unit 1 Maximum Allowable Nominal PORV Setpoints for the Low j Temperature Overpressure Protection (LTOP) System Applicable for the First 16 EFPY 4

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BRAIDWOOD- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.2 i

Data Points for Braidwood Unit 1 Maximum Allowable PORV Setpoints l for the LTOP System Applicable for the First 16 EFPY l PCV-455A PCV-456 (1TY-0413M) (1TY-0413P)

AUCTIONEERED LOW RCS PRESSURE AUCTIONEERED LOW RCS PRESSURE  !

RCS TEMP. (DEG. F) (PSIG) RCS TEMP. (DEG. F) (PSIG)  !

50 497 50 513 I

, 70 497 70 513 100 497 100 513 110 497 l 110 513 160 497 160 513 200 618 200 634 250 603 250 619

.; 300 588 300 604

350 588 330 604 450 2350 450 2350 l

4 Note: To determine maximum allowable lift setpoints for RCS Pressure and RCS Temperatures greater than 350 F, linearly interpolate between the 350 F and 450 F data points shown above.

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BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 3.0 Reactor Vessel Material Surveillance Program The reactor vessel material irradiation surveillance specimens shall be removed and analyzed to determine changes in material properties. The removal schedule is provided in Table 3.1. The results of these analyses shall be used to update Figures 2.1 and 2.2 and Table 2.1. The time of specimen withdrawal may be modified to coincide with those refueling outages or reactor shutdowns most closely approaching the withdrawal schedule.

The pressure vessel material surveillance program (Reference 6) is in compliance with d

Appendix H to 10 CFR 50," Reactor Vessel Radiation Surveillance Program." The material test requirements and the acceptance standards utilize the reference nil-ductility temperature, RTuor, which is determined in accordance with ASTM E208. The empirical relationship between RTwo1 and the fracture toughness of the reactor vessel steel is developed in accordance with Appendix G,

" Protection Against Non-Ductile Failure," to Section XI of the ASME Boiler and Pressure Vessel Code. The surveillance capsule removal schedule meets the requirements of ASTM El85-82.

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BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT  !

Table 3.1 Braidwood Unit 1 Capsule Withdrawal Schedule Capsule Vessel Location Capsule Lead Removal Time"" Estimated Capsule (Degrees) Factor (EFPY) 2 Fluence (n/cm )

U 58.5' 4.03 1.10 (Removed) 3.814 x 10'8 X 238.5 4.03 4.234 (Removed) 1.144 x 10

W 121.5 4.03 7.95 (EOL Wall) 2.239 x 10 (b) i9 11.93 (1.5 EOL Z 301.5* 4.03 WallM) 3.359 x 10

V 61.0* 3.73 Standby ---

Y 241.0* 3.73 Standby ---

(a) Effective Full Power Years (EFPY) from plant startup.

(b) Maximum end oflicense (32 EFPY) inner vessel wall fluence.

(c) Derived from Table C-3 of WCAP-14824, (Reference 2, which is the Attachment to this report). '

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l HRAIDWOOD- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT .

4.0 Supplemental Data Tables l

The following tables provide supplemental information on reactor vessel material properties and are provided to be consistent with Generic Letter 96-03. Some of the material property values shown were used as inputs to the P/T limits.

Table 4.1 shows the calculation of the surveillance material chemistry factors using surveillance I capsule data.

3-Table 4.2 provides the reactor vessel material properties.

Table 4.3 provides a summary of the Braidwood Unit I adjusted reference temperatures (ARTS) at -

the 1/4T and 3/4T locations for 16 EFPY.

l Table 4.4 shows the calculation of ARTS at 16 EFPY for the limiting Braidwood Unit I reactor vessel material -Weld Metal WF562 (Based on Surveillance Capsule Data).

Table 4.5 provides the RTrrs values for Braidwood Unit I for 32 EFPY.

Table 4.6 provides the RTrrs values for Braidwood Unit 1 for 48 EFPY.

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HRAIDWOOD - UNIT 1 I l

l PRESSURE AND TEMPERATURE LIMITS REPORT '

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Table 4.1 Braidwood Unit 1 Calculation of Chemistry Factors Using Surveillance Capsule Data Fluence (n/cm2 ,

Material Capsule pp<a) Measured FF*ARTxor (FF)2 i E>1.0 ARTsor i Mev), f Lower Shell Forging U 3.814 x10'8 0.733 5 3.666 0.538 24-3 (Tangential)

X 1.144 x10 l.038 30 31.127 1.077 Lower Shell 8

Forging U 3.814 x10 0.733 0 0 0.538 24-3 (Axial) X 1.144x10 l.038 25 25.939 1.077 Sum: 60.733 l 3.228 Chemistry Factor (d) = 60.733 + 3.228 = 18.8'F Braidwood 1 Weld U 3.814x10'8 0.733 10(*) 7.333 0.538 Metal WF562(b) i X 1.144x10 1.038 25") 25.95 1.077 Braidwood 2 {

18 Weld U 3.933x10 0.741 0 0 0.550 Metal WF562") l X 1.126 x10 1.033 20") 20.66 1.067 l

Sum: 53.943 3.232 Chemistry Factor (d) = 53.943+ 3.232 = 16.7"F (a) FF = Fluence Factor = fm284:*ios o (b) Braidwood Unit 1 ARTsor values were obtained from WCAP-14243 (Reference 7).

(c) Braidwood Unit 2 capsule fluence, FF, and ARTsor values obtained from WCAP-14230 (Reference 12).

(d) Chemistry Factor = E (FF*ARTsor) / E ((FF) 2)

(e) ARTsor per Ratio Procedure of 10 CFR 50.61 (Reference 10) is not affected, since Ratio = 1.0. See Table B-4 of WCAP 14824 (Reference 2).

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l BRAIDWOOD- UNIT 1 I-I PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.2 Braidwood Unit 1 Reactor Vessel Material Properties Chemistry Initial Material Cu(%)(*) Ni (%)(*) Factor (*) RT war ( F)*)

Description Closure Head -- -- --

-20(')

Flange Vessel Flange -- -- -

-10(*)

Lower Shell 0.04 0.74 26.0 -20 Forging 24-3 Intermediate Shell 0.05 0.73 31.0 -30 Forging 24-2 i

Weld Metal 0.03 0.67 41.0 40 WF562  ;

(a) Chemistry Factors are calculated from Cu and Ni values per Regulatory  ;

Guide 1.99, Position 1 (Reference 11). l (b) Initial RTuorvalues are measured, WCAP-14243 (Reference 7).

(c) Closure head and vessel flange Initial RTNorvalues are used for considering flange requirements for the heatun/cooldown curves, WCAP-14243.

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, BRAIDWOOD- UNIT 1

, PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.3 i

Summary of Braidwood Unit 1 Adjusted Reference Temperatures (ARTS) at the 1/4T and 3/4T Locations for 16 EFPY(*)

16 EFPY Material Description 1/4T ART (*F) 3/4T ART ( F)

Lower Shell Forging 26.2 12.1 24-3 '

Using credible surveillance capsule data 13.4(b) 3.2(b)

(RG Position 2('))

i Intermediate Shell 25.1 8.2 Forging 24-2 (RG Position 1) 1 Circumferential Weld 112.9 90.5

(RG Position 1)

Using credible 76.6(6) 65.4(b) surveillance capsule data (RG Position 2(*)) .

(a) Calculated using a chemistry factor based ou Regulatory Guide (RG) 1.99, Position 2 (Reference 11).

(b) These ART values were used to generate the Braidwood Unit I heatup and cooldown curves, WCAP-14243 (Reference 7).

(c) Based on evaluation of WCAP-14243; however, applicability cate has been increased to 27.9 EFPY per evaluation in WCAP-14824, Appendix B: Weld Metal Integration for Braidwood Units 1 and 2 (Reference 2). ,

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BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.4 Braidwood Unit 1 Calculation of Adjusted Reference Temperatures (ARTS) at 16 EFPY(b) at k&itig he Vessd Wel Weld Metal WF562 (Based on Surveillance Capsule Data) t i

Parameter Values Operating Time 16 EFPYN i

Location (*) 1/4T ART 3/4T ART l Chemistry Factor, CF (*F) 20.6 20.6 Fluence (f), n/cm 2 6.73x10 s

2.43x10'8 (E>l.0 Mev))(*

Fluence Factor, FF 0.889 0.616 ARTunr= CFxFF ( F) 18.31 12.70 Initial RT unr., I (*F) 40 40 Margin, M ( F) 18.31 12.70-l ART = 1+(CF*FF)+M, F 76.6 65.4 p RG 1.99, Revision 2

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l (a) Fluence, f, is based uponsuf g(E>l.0 Mev) = 1.120x10" at 16 EFPY, WCAP-14241 (Reference 3).

(b) Based on evaluation of WCAP-14243; however, applicability date has been increased to 27.9 EFPY per evaluation in WCAP-14824, Appendix B: Weld Metal Integration for Braidwood Units 1 and 2 (Reference 2).

(c) The Braidwood Unit I reactor vessel wall thickness is 8.5 inches at the beltline l region. I i

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4 BRAIDWOOD - UNIT 1 l PRESSURE AND TEMPERATURE LIMITS REPORT l Table 4.5 RTpys Values for Braidwood Unit I for 32 EFPY CF pa) pp<d> M ARTpTs RTpTs RT NoT(u)

Material (*F) ( F) ( F) ( F) ( F)

Lower Shell Forging 26.0 2.239 1.218 31.68 -20 31.68 43.4 MK 24-3

Using Surveillance 18.8 2.239 1.218 17.0 -20 22.90 19.8
Capsule Data (*) '
Intermediate Shell Forging 31.0 2.239 1.218 34.0 -30 37.77 41.8 24-2 Circumferential Weld 41.0 2.239 1.218 49.95 40 49.95 139.9
Metal WF562 Using Surveillance 16.7 2.239 1.218 20.34 40 20.34 80.7 Capsule Data (*)

J 2

(a) 2.239x10 n/cm (E>1.0 Mev) for 32 EFPY from Braidwood 1 PTS repcit, WCAP-14242 (Reference 8). .

(b) FF (Fluence Factor) = fe.284tonos o (c) Calculated with CF based on surveillance capsule data per RG 1.99, Position 2 (Reference 11).

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. . l BRAIDWOOD- UNIT 1 4

PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.6 RTns Values for Braidwood Unit I for 48 EFPY.

_ CF p) pp(b) M RTwor(v) ARTers RTns Material (*F) ( F) (*F) ( F) (*F)

Lower Shell Forging 26.0 3.358 1.317 34.0 . -20 34.25 48.3 4

MK 24-3 Using Surveillance l

' 18.8 3.358 1.317 17.0 -20 24.76 21.8 Capsule Data (*)

Intermediate Shell Forging 31.0 3.358 1.317 34.0 -30 40.83 44.8 24-2

Circumferential Weld 41.0 3.358 1.317 54.00 40 54.00 148.0 Metal WF562
Using Surveillance 16.7 3.358 1.317 21.99 40 21.99 1

84.0 Capsule Data (*)

2 (a) 3.358x10 n/cm (E>1.0 Mev) for 48 EFPY from Braidwood 1 PTS report, WCAP-14242 (Reference 8).

(b) FF (Fluence Factor) = fm284toyog o l

4 (c) Calculated with CF based on surveillance capsule data per RG 1.99, Position 2 (Reference 11).

=

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BRAIDWOOD- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 5.0 References 3

1. Andrachek, J.D., et al., WCAP-14040-NP-A, " Methodology used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit i Curves," Revision 2, January 1996.
2. Grendys,P.A., WCAP-14824, " Byron Unit 1 Heatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Byron & Braidwood,"

Revision 1, April 1997.

t

3. Peter, P.A., et al., WCAP-14241, " Analysis of Capsule X from the Commonwealth Edison Company Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program,"

March 1995.

i

4. Terek, E., et al., WCAP-12685, " Analysis of Capsule U from the Commonwealth 4

Edison Company Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program,"  !

August 1990.

5. Westinghouse Letter to Commonwealth Edison Company, CCE-95-186, "Braidwood  ;

Unit 1 LTOPS Setpoints Based on 16 EFPY Pfr Limits," June 5,1995.

6. Yanichko, S.E., et al., WCAP-9807, " Commonwealth Edison Company, Braidwood Station Unit i Reactor Vessel Surveillance Program," February 1931.
7. Peter, P.A., WCAP-14243,"Braidwood Unit 1 Heatup and Cooldown Limit Curves for Normal Operation," March 1995.

l j 8. Peter, P.A., WCAP-14242," Evaluation of Pressurized Thermal Shock for Braidwood Unit 1," March 1995.

1

9. Lippencott, E.P., WCAP-14044, " Westinghouse Surveillance Capsule Neutron Fluence

, Reevaluation," April 1994.

t

10. 10 CFR 50.61," Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events,"(PTS Rule) January 18,1996.

I 1. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, " Radiation 4

Embrittlement of Reactor Vessel Materials," Revision 2, May 1988.

12. Peter, P.A., WCAP-14230,"Braidwood Unit 2 Heatup and Cooldown Limit Curves far
Normal Operation," March 1995. i 18

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

O BRAIDWOOD- UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT ,

l 1

References (Continued) l

13. Comed Calculation BRW-96-9061/BYR 96-293," Channel Accuracy for Power  !

Operated Relief Valve (PORV) Setpoints and Wide Range RCS Temperature Indication (Unit 1 Original Steam Generators and Replacement Steam Generators)," Revision 0.

14. Comed Nuclear Fuel Services Department, NDIT No. 960194, " Maximum Allowable LTOPS PORV Setpoints for Braidwood Unit I with RSGs," Revision 2.

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