ML20198J553

Unit 1 Pressure & Temp Limits Rept

ML20198J553
Person / Time
Site:	Byron, Braidwood
Issue date:	01/07/1998
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20198J090	List: ML20198J083 ML20198J506 ML20198J520 ML20198J553 ML20198J564
References
NUDOCS 9801140158
Download: ML20198J553 (24)

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4 BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT t

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- BRAIDWOOD - 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 (P/T) 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 Reacter Vessel Material Surveillance Program 9

4.0 Supplemental Data Tables 11 3.0 References 18 Attachment WCAP-14824," Byron Unit 1 Heatup and Cooldown Limit Curves for Normal Operation and Survei.l. lance Weld Metal Integration for Byron and Braidwood," Revision 2, November 1997, i

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BRAIDWOOD-UNIT 1 -

PRESSURE AND TEMPERATURE LIMITS REPORT -

- List of Figures -

Figure -

Page 2.1

-Braidwood Unit 1 Reactor Coolant Sy ; tem Heatup Limitations (IIcatup Rates up to 4

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 EFPY (Without Margins for Instrumentatioe Errors) _

2.3 Braidwood Unit 1 Maximum Allowable Nominal PORV Setpoir.ts for the Low 7

Temperature Overpressure Protection (LTOP) System Applicable for the First 16 EFPY ii

BRAIDWOOD-UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables

. Table Page-r 2.1 -

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

(Without Margins for Instrumentation Errors) 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 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 1.ocations for 16 EFPY e

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 RTers Values for Braidwood Unit I for 48 EFPY 17 iii

BRAIDWOOD-UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT 1.0 Introduction 4

Reference to Technical Specifications (TS) numbers are given in both the Braidwood Sation -

cuuent 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 TS 6.9.1.11/[ITS 5.6.6]. Revisions to the PTLR shall be provided to the NRC after issuance.

'Ihe 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.

[ITS LCO 3.4.3 RCS Pressure and Temperature (Pfr) 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 L th: Technical Specifications.

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

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 0, Article G 2000,1996 Addenda (not used for Braidwood Unit 1 P-T curves),

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 generators.

WCAP-14824, Revision 2, is included as an attachment for reference. WCAP-14824, Rev. 2 contains the Pfr 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/r) Lir:'s (LCO 3.4.9.1/ [lTS-LCO 3.4.3])

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

a. A maximum hectup of 100*F in any 1-hour period,

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

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 Featup and cooldown limit curves.

I

BRAIDWOOD - UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT Operating Limits (Continued) 2.1.2 The RCS P/T limits for heatup, insersice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.1. The RCS P/r 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. 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/r limits for core operation (except for low power physics testing) are that the teactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostat:c test, and at least 40*F higher than the.iinimum permissible temperature in the corresponding P/r curve for heatup and coolNwn.

2.2 Low Temperature Overpressure Protection (LTOP) System S etpoints (LCG 3.4.9.3/

[lTS LCO 3.4.12]).

The power operated relief valves (PORVs) shall each have maw 1um lift settings in accordance with Figure 2.3 and Table 2.2. These limits are based on References 5,13, and

14. The Residual lleat Removal (RH) Suction Relief Valves are also analyzed to individually provide low temperatare overpressure protection. This analysis for the Ril Suction Relief Valves remains valid with the current Appendix G limits contained in this PTLR document and will be reevaluated in the future as the Appendix G limits are revised.

The LTOP setpoints are based on P/r limits which were 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 200*F (Reference 15).

The TS required enable temperature for the PORVs shall be ;t 350*F RCS tempi.rature (Braidwood Unit 1 procedures goveming 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 setpiint ia 2350 psig. This is intended to prohibit PORV lift for an inadvertent LTOP system arming at power.

2

BRAIDWOOD - UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT -

Operating Limits (Continued) 2.4. Reactor Vessel Boltup Temperature (Non-Technical Specification) -

The minimum 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 upplied to any stud, 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 MATERIAf_ PROPERTY BASIS 1.IMmNG MATERIAL WELD METAL LIMmNG ART VALUES AT 16 EFPY:

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BRAIDWOOD. UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.1 BRAIDWOOD Unit i Heatup* and Cooldown* Data Points at 16 EFPY" (Without margins for instrumentation errors)

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B'RAIDWOOD. UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT 4

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per RO 1.99, Revision 2 (a) Fluence, f, is based upon f,r (Fil.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 Rev. 2 Appendix B: Weld Metai Irnegration for Braidwood Units I and 2 (Reference 2).

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BRAIDWOOD-UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.5 RTns Values for liraidwood Unit I for 32 EFPY M

RTmn(u)

ARTns RTns CF p.)

ppo Material

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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"8 Intermediate Shell Forging 31.0 2.239 1.218 34.0 30 37.77 41.8 24 2 Circumferential Weld 41.0 2.239 1.213 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")

3 (a) 2.239x10" n/cm (F>l.0 Mev) for 32 EFFY from liraidwood 1 PTS report, WCAP 14242 (Reference 8).

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(b) FF (fluence Factor) = i (c) Calculated with CF based on surveillance capsule data per RO 1.99, Position 2 (Reference 1I).

-16

BRAll) WOOD - UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.6 RTm Values for 13raidwood Unit I for 48 EFPY M

RTNm(u)

ARTns RTns j

CF p.)

ppm Material

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Lower Shell Forging 26.0 3.358 1.317 34.0 20 34.25 48.3 i

MK 24 3 Using Surveillance 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

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Metal WF562 Using Surveillance 16.7 3.358 1.317 21.99 40 21.99 84.0 l

Capsule Data")

2 (a) 3.358x10 n/cm (I>l.0 Mev) for 48 EFPY from 11raidwood 1 PTS report, WCAP 14242 (Reference 8).

(b) FF (Fluence Factor) = fn2 mos o (c) Calculated with CF based on surveillance capsule data per RG 1.99. Position 2 (Reference 11).

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llRAIDWOOD - UNIT I PRESSURE AND TEMPERATURE LIMITS REPORT 5.0 References 1.

Andrachek, J.D., et al., WCAP 14040 NP A,"hiethodology used to Develop Cold Overpressure hiitigating System Setpoints and RCS lleatup and Cooldown Limit Curves," Revision 2. January 1996.

2.

Laubham, T.A. et al., WCAP 14824,"Ilyron Unit 1 Ileatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Hyron &

Iltaldwood," Revision 2 November 1997 and Errata Sheets (Westinghouse Letter CAE.

97 220, CCE 97 304 and Westinghouse Letter CAE 97 233, CCE 97 316).

3.

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

March 1995.

4.

Terek, E., et al., WCAP 12685," Analysis of Capsule U from the Commonwealth Edison Company Braidwood Unit i Reactor Vessel Radiation Surveillance Program,"

August 1990.

5.

Westinghouse Letter to Commonwealth Edison Company, CCE 95186,"Braidwood Unit i LTOPS Setpoints Based on 16 EFPY P/T Limits," June 5,1995.

6.

Yanichko, S.E., et al., WCAP 9807," Commonwealth Edison Company, Braidwood Station Unit i Reactor Vessel Surveillance Program," February 1981.

7.

Peter, P.A., WCAP 14243,"Braidwood Unit i IIcatup and Cooldcwn Limit Curves for Normal Operation," March 1995.

8.

Peter, P.A., WCAP 14242," Evaluation of Pressurized Thennal Shock for Braidwood Unit 1," March 1995.

9.

Lippencott, E.P., WCAP-14044," Westinghouse Surveillance Capsule Neutron Fluence Reevaluation," April 1994.

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

I1. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99," Radiation Embrittlement of Reactor Vessel Materials," Revision 2, May 1988.

12. Laubham, T. J., WCAP-14970,"Braidwood Unit 2 IIcatup and Cooldmvn Limit Curves for Nomtal Operation," October 1997 and Errata Sheets (Westinghouse Letter CAE 97-210. CCE-97 289 and Westinghouse Letter CAE-97-232, CCE-97 315).

18 w

HRAIDWOOD-UNIT I PRESSURE AND TEMPERATURE I.lMITS REPORT i-References (Continued) f

13. Comed Calculation llRW 96 9061/llYR % 293," Channel Accuracy for Power Operated Relief

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Valve (PORV) Setpoints and Wide Range RCS Temperature Indication (Unit i Original Steam l

Oenerators and Replacement Steam Generators)," Revision 0.

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

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15. Westinghouse 1.ctter to Commonwealth Edison Company. CAE 97 211. CCE 97 290,

" Comed Ilyron and liraldwood Units I and 2 ATmetal Evaluation for Commonwealth I

Edison," November 7,1997.

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NORMAL OPERATION AND SURVEll, LANCE WELD METAL INTEGRATION FOR HYRON AND HRAII)WOOI)

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