BYRON 2007-0051, Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR)

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Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR)
ML071070447
Person / Time
Site: Byron Constellation icon.png
Issue date: 04/17/2007
From: Hoots D
Exelon Generation Co
To:
Document Control Desk, NRC/NRR/ADRO
References
BYRON 2007-0051
Download: ML071070447 (26)
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Text

Ex&on Generation Company, LLC www.exeloncorpcorn Exekrn,.N Byron Station 4450 North German Church Road Byron, ft 610109794 April 17, 2007 LTR: BYRON 2007-0051 File: 1.10.0101 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF- 66 NRC Docket No. STN 50-455

Subject:

Byron Station Unit 2 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

In accordance with Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR), we are submitting the December 2006 revision to the Unit 2 PTLR. The PTLR was revised to extend the applicability of the heatup and cooldown curves out to 32 Effective Full Power Years.

Should you have any questions concerning this report, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully, David M Hoots Site Vice President Byron Nuclear Generating Station

Attachment:

Byron Station Unit 2 PTLR DMH/JEL/rah

A1TACHM ENT Byron Station Unit 2 Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

(December 2006)

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents Section Page 1.0 Introduction 1 2.0 RCS Pressure and Temperature Limits 1 2.1 RCS Pressure and Temperature (PIT) Limits (LCO 3.4.3) 1 3.0 Low Temperature Over Pressure Protection and Boltup 7 3.1 LTOP System Setpoints (LCO 3.4.12) 7 3.2 LTOP Enable Temperature 7 3.3 Reactor Vessel Boltup Temperature (Non-Technical Specification) 7 4.0 Reactor Vessel Material Surveillance Program 10 5.0 Supplemental Data Tables 12 6.0 References 19

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures Figure Page 2.1 Byron Unit 2 Reactor Coolant System Heatup Limitations (Heatup 3 Rates of 100°F/hr)Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 2.2 Byron Unit 2 Reactor Coolant System Cooldown Limitations 4 (Cooldown Rates of0, 25, 50, and 100°FIhr)Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 3.1 Byron Unit 2 Nominal PORV Setpoints for the Low Temperature 8 Overpressure Protection (LTOP) System Applicable for 32 EFPY (Includes Instrumentation Uncertainty) 11

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Page

2. la Byron Unit 2 Heatup Data Points at 32 EFPY (Without Margins 5 for Instrumentation Errors)
2. lb Byron Unit 2 Cooldown Data Points at 32 EFPY (Without 6 Margins for Instrumentation Errors) 3.1 Data Points forByron Unit 2 Nominal PORV Setpoints for the 9 LTOP System Applicable for 32 EFPY (Includes Instrumentation Uncertainty) 4.1 Byron Unit 2 Capsule Withdrawal Schedule 11 5.1 Byron Unit 2 Calculation of Chemistry Factors Using 13 Surveillance Capsule Data 5.2 Byron Unit 2 Reactor Vessel Material Properties 14 5.3 Summary ofByron Unit 2 Adjusted Reference Temperatures 15 (ARTs) at 1/4T and 3/4T Locations for 32 EFPY 5.4 Byron Unit 2 Calculation of Adjusted Reference Temperatures 16 (ARTs) at 32 EFPY at the Limiting Reactor Vessel Material Nozzle Shell Forging 4P-6 107 5.5 RTpTs Calculation for Byron Unit 2 Beltline Region Materials at 17 EOL (32 EFPY) 5.6 RTPTS Calculation for Byron Unit 2 Beltline Region Materials at 18 Life Extension (48 EFPY) 111

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

This Pressure and Temperature Limits Report (PTLR) for Byron Unit 2 has been prepared in accordance with the requirements of Byron TS-5.6.6 (RCS Pressure and Temperature Limits Report). Revisions to the PTLR shall be provided to the NRC after issuance.

The Technical Specifications addressed in this report are listed below:

TS-LCO 3.4.3 RCS Pressure and Temperature (PIT) Limits; and TS-LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System.

2.0 RCS Pressure and Temperature Limits This section provides the Byron Unit 1 Heatup and Cooldown Limitations.

The PTLR limits for Byron Unit 2 were developed using a methodology specified in the Technical Specifications. The methodology listed in WCAP-l4040-NP-A, Revision 2 (Reference 1) was used with the following exception:

a) Use of ASME Code Section XI, Appendix G, Article G-2000, 1996 Addenda, b) Use of ASME Code Case N-640, Alternative Reference Fracture Toughness for Development of P-T Limit Curves,Section XI, Division 1, c) Use ofASME Code Case N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessels,Section XI, Division 1, and d) Elimination ofthe flange requirements documented in WCAP-16 143-P.

This exception to the methodology in WCAP- 14040-NP-A, Revision 2 has been reviewed and accepted by the NRC in References 8, 10, 11 and 12.

WCAP- 15392, Revision 2 (Reference 7), provides the basis for the Byron Unit 2 PIT curves, along with the best estimate chemical compositions, fluence projections, and adjusted reference temperatures used to determine these limits. The weld metal data integration for Byron and Braidwood Units 1 and 2 is documented in Reference 2.

WCAP- 16 143-P, Reference 13, documents the technical basis for the elimination of the flange requirements.

2.1 RCS Pressure and Temperature (PIT) Limits (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°Fin any 1-hour period,
b. A maximum cooldown of 100°Fin any 1-hour period, and
c. A maximum temperature change ofless than or equal to 10°Fin any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 2.1.2 The RCS PIT limits for heatup, inservice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.la. The RCS PIT limits for cooldown are shown in Figure 2.2 and Table 2. lb. These limits are defined in WCAP-15392, Revision 2 (Reference 7). Consistent with the methodology described in Reference 1, the RCS PIT limits for heatup and cooldown shown in Figures 2.1 and 2.2 are provided without margins for instrument error. These limits were developed using ASME Boiler and Pressure Vessel Code Section XI, Appendix G, Article G-2000, 1996 Addenda. 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 PIT 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°Fhigher than the minimum permissible temperature in the corresponding PIT curve for heatup and cooldown.

2

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD WF-447 & NOZZLE SHELL FORGING LIMITING ART VALUES AT 32 EFPY: 1/4T, 107°F(N-588) & 52°F(96 App. G) 3/4T, 89°F(N-588) & 37°F(96 App. G) 2500 2250 2000 1750 1500 I 1250 1000 750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

Figure 2.1 Byron Unit 2 Reactor Coolant System Heatup Limitations (Heatup rates of 100°FIhr)

Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 3

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD WF-447 & NOZZLE SHELL FORGING LIMITING ART VALUES AT 32 EFPY: 1/4T, 107°F(N-588) & 52°F(96 App. G) 3/4T, 89°F(N-588) & 37°F(96 App. G) 2500 2250 2000 1750 1500 I 1250 1000 750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

Figure 2.2 Byron Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0,25,50 and 100°FIhr)Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 4

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.la Byron Unit 2 Heatup Data Points at 32 EFPY (Without Margins for Instrumentation Errors)

Heatup Curve 100 F Heatup Criticality Leak Test Limit Limit T (°F) P (nsi~ T (°F~ P (nsi~ T (°F~ P (nsi~

60 1030 0 95 2000 65 1078 112 1078 112 2485 70 1128 112 1128 75 1 148 115 1148 80 1 152 120 1 152 85 1 162 125 1 162 90 1 180 130 1 180 95 1205 135 1205 100 1237 1237 105 1276 145 1276 110 1323 50 1323 115 1377 55 1377 120 1440 60 1440 125 1511 165 1511 130 1592 170 1592 135 1682 175 1682 140 1784 180 1784 145 1897 185 1897 150 2023 190 2023 155 2120 195 2120 160 2227 200 2227 165 2347 205 2347 170 2480 210 2480 5

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.lb Byron Unit 2 Cooldown Data Points at 32 EFPY (Without Margins for Instrumentation Errors)

Cooldown Curves Steady State 25 °FCooldown 50 °FCooldown 100 °FCooldown T (°F~ P (nsi~ T (°F~ P (nsi~ T (°F~ P (nsi~ T (°FI P (nsi~

60 0 60 0 60 0 60 0 60 1045 60 1036 60 1033 65 1092 65 1088 70 1143 75 1200 80 1263 85 1332 90 1409 95 1494 00 1587 05 1691 10 1805 115 1932 120 2071 125 2226 130 2396 Note: For each cooldown rate, the steady-state pressure values shall govern the temperature where no allowable pressure values are provided.

6

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT 3.0 Low Temperature Overpressure Protection and Bottup This section provides the Byron Unit 2 power operated relief valve lift settings, low temperature overpressure protection (LTOP) system arming temperature, and minimum reactor vessel boltup temperature.

3.1 LTOP System Setpoints (LCO 3.4.12)

The power operated relief valves (PORVs) shall each have maximum lift settings in accordance with Figure 3.1 and Table 3.1. These limits are based on References 3 and 6.

The LTOP setpoints are based on PIT limits which were established in accordance with 10 CFR 50, Appendix U without allowance for instrumentation error and in accordance with the methodology described in Reference 1. The LTOP PORV nominal lift settings shown in Figure 3.1 and Table 3.1 account for appropriate instrument error.

3.2 LTOP Enable Temperature The required enable temperature for the PORVs shall be 350°FRCS temperature.

(Byron Unit 2 procedures governing the heatup and cooldown of the RCS require the arming of the LTOP System for RCS temperature of 350°Fand below and disarming of LTOP for RCS temperature above 350°F).

Note that the last LTOP PORV segment in Table 3.1 extends to 400°Fwhere the pressure setpoint is 2335 psig. This is intended to prohibit PORV lift for an inadvertent LTOP system arming at power.

3.3 Reactor Vessel Boltup Temperature (Non-Technical Specification)

The minimum boltup temperature for the Reactor Vessel Flange shall be 60°F. Boltup is a condition in which the Reactor Vessel head is installed with tension applied to any stud, and with the RCS vented to atmosphere (Reference 7).

7

Ex&on Generation Company, LLC www.exeloncorpcorn Exekrn,.N Byron Station 4450 North German Church Road Byron, ft 610109794 April 17, 2007 LTR: BYRON 2007-0051 File: 1.10.0101 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Byron Station, Unit 2 Facility Operating License No. NPF- 66 NRC Docket No. STN 50-455

Subject:

Byron Station Unit 2 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

In accordance with Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR), we are submitting the December 2006 revision to the Unit 2 PTLR. The PTLR was revised to extend the applicability of the heatup and cooldown curves out to 32 Effective Full Power Years.

Should you have any questions concerning this report, please contact William Grundmann, Regulatory Assurance Manager, at (815) 406-2800.

Respectfully, David M Hoots Site Vice President Byron Nuclear Generating Station

Attachment:

Byron Station Unit 2 PTLR DMH/JEL/rah

A1TACHM ENT Byron Station Unit 2 Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

(December 2006)

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table of Contents Section Page 1.0 Introduction 1 2.0 RCS Pressure and Temperature Limits 1 2.1 RCS Pressure and Temperature (PIT) Limits (LCO 3.4.3) 1 3.0 Low Temperature Over Pressure Protection and Boltup 7 3.1 LTOP System Setpoints (LCO 3.4.12) 7 3.2 LTOP Enable Temperature 7 3.3 Reactor Vessel Boltup Temperature (Non-Technical Specification) 7 4.0 Reactor Vessel Material Surveillance Program 10 5.0 Supplemental Data Tables 12 6.0 References 19

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT List of Figures Figure Page 2.1 Byron Unit 2 Reactor Coolant System Heatup Limitations (Heatup 3 Rates of 100°F/hr)Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 2.2 Byron Unit 2 Reactor Coolant System Cooldown Limitations 4 (Cooldown Rates of0, 25, 50, and 100°FIhr)Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 3.1 Byron Unit 2 Nominal PORV Setpoints for the Low Temperature 8 Overpressure Protection (LTOP) System Applicable for 32 EFPY (Includes Instrumentation Uncertainty) 11

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Page

2. la Byron Unit 2 Heatup Data Points at 32 EFPY (Without Margins 5 for Instrumentation Errors)
2. lb Byron Unit 2 Cooldown Data Points at 32 EFPY (Without 6 Margins for Instrumentation Errors) 3.1 Data Points forByron Unit 2 Nominal PORV Setpoints for the 9 LTOP System Applicable for 32 EFPY (Includes Instrumentation Uncertainty) 4.1 Byron Unit 2 Capsule Withdrawal Schedule 11 5.1 Byron Unit 2 Calculation of Chemistry Factors Using 13 Surveillance Capsule Data 5.2 Byron Unit 2 Reactor Vessel Material Properties 14 5.3 Summary ofByron Unit 2 Adjusted Reference Temperatures 15 (ARTs) at 1/4T and 3/4T Locations for 32 EFPY 5.4 Byron Unit 2 Calculation of Adjusted Reference Temperatures 16 (ARTs) at 32 EFPY at the Limiting Reactor Vessel Material Nozzle Shell Forging 4P-6 107 5.5 RTpTs Calculation for Byron Unit 2 Beltline Region Materials at 17 EOL (32 EFPY) 5.6 RTPTS Calculation for Byron Unit 2 Beltline Region Materials at 18 Life Extension (48 EFPY) 111

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 1.0 Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)

This Pressure and Temperature Limits Report (PTLR) for Byron Unit 2 has been prepared in accordance with the requirements of Byron TS-5.6.6 (RCS Pressure and Temperature Limits Report). Revisions to the PTLR shall be provided to the NRC after issuance.

The Technical Specifications addressed in this report are listed below:

TS-LCO 3.4.3 RCS Pressure and Temperature (PIT) Limits; and TS-LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System.

2.0 RCS Pressure and Temperature Limits This section provides the Byron Unit 1 Heatup and Cooldown Limitations.

The PTLR limits for Byron Unit 2 were developed using a methodology specified in the Technical Specifications. The methodology listed in WCAP-l4040-NP-A, Revision 2 (Reference 1) was used with the following exception:

a) Use of ASME Code Section XI, Appendix G, Article G-2000, 1996 Addenda, b) Use of ASME Code Case N-640, Alternative Reference Fracture Toughness for Development of P-T Limit Curves,Section XI, Division 1, c) Use ofASME Code Case N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessels,Section XI, Division 1, and d) Elimination ofthe flange requirements documented in WCAP-16 143-P.

This exception to the methodology in WCAP- 14040-NP-A, Revision 2 has been reviewed and accepted by the NRC in References 8, 10, 11 and 12.

WCAP- 15392, Revision 2 (Reference 7), provides the basis for the Byron Unit 2 PIT curves, along with the best estimate chemical compositions, fluence projections, and adjusted reference temperatures used to determine these limits. The weld metal data integration for Byron and Braidwood Units 1 and 2 is documented in Reference 2.

WCAP- 16 143-P, Reference 13, documents the technical basis for the elimination of the flange requirements.

2.1 RCS Pressure and Temperature (PIT) Limits (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°Fin any 1-hour period,
b. A maximum cooldown of 100°Fin any 1-hour period, and
c. A maximum temperature change ofless than or equal to 10°Fin any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 2.1.2 The RCS PIT limits for heatup, inservice hydrostatic and leak testing, and criticality are specified by Figure 2.1 and Table 2.la. The RCS PIT limits for cooldown are shown in Figure 2.2 and Table 2. lb. These limits are defined in WCAP-15392, Revision 2 (Reference 7). Consistent with the methodology described in Reference 1, the RCS PIT limits for heatup and cooldown shown in Figures 2.1 and 2.2 are provided without margins for instrument error. These limits were developed using ASME Boiler and Pressure Vessel Code Section XI, Appendix G, Article G-2000, 1996 Addenda. 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 PIT 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°Fhigher than the minimum permissible temperature in the corresponding PIT curve for heatup and cooldown.

2

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD WF-447 & NOZZLE SHELL FORGING LIMITING ART VALUES AT 32 EFPY: 1/4T, 107°F(N-588) & 52°F(96 App. G) 3/4T, 89°F(N-588) & 37°F(96 App. G) 2500 2250 2000 1750 1500 I 1250 1000 750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

Figure 2.1 Byron Unit 2 Reactor Coolant System Heatup Limitations (Heatup rates of 100°FIhr)

Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 3

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD WF-447 & NOZZLE SHELL FORGING LIMITING ART VALUES AT 32 EFPY: 1/4T, 107°F(N-588) & 52°F(96 App. G) 3/4T, 89°F(N-588) & 37°F(96 App. G) 2500 2250 2000 1750 1500 I 1250 1000 750 500 250 0

0 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (Deg. F)

Figure 2.2 Byron Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates of 0,25,50 and 100°FIhr)Applicable for 32 EFPY (Without Margins for Instrumentation Errors) 4

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.la Byron Unit 2 Heatup Data Points at 32 EFPY (Without Margins for Instrumentation Errors)

Heatup Curve 100 F Heatup Criticality Leak Test Limit Limit T (°F) P (nsi~ T (°F~ P (nsi~ T (°F~ P (nsi~

60 1030 0 95 2000 65 1078 112 1078 112 2485 70 1128 112 1128 75 1 148 115 1148 80 1 152 120 1 152 85 1 162 125 1 162 90 1 180 130 1 180 95 1205 135 1205 100 1237 1237 105 1276 145 1276 110 1323 50 1323 115 1377 55 1377 120 1440 60 1440 125 1511 165 1511 130 1592 170 1592 135 1682 175 1682 140 1784 180 1784 145 1897 185 1897 150 2023 190 2023 155 2120 195 2120 160 2227 200 2227 165 2347 205 2347 170 2480 210 2480 5

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.lb Byron Unit 2 Cooldown Data Points at 32 EFPY (Without Margins for Instrumentation Errors)

Cooldown Curves Steady State 25 °FCooldown 50 °FCooldown 100 °FCooldown T (°F~ P (nsi~ T (°F~ P (nsi~ T (°F~ P (nsi~ T (°FI P (nsi~

60 0 60 0 60 0 60 0 60 1045 60 1036 60 1033 65 1092 65 1088 70 1143 75 1200 80 1263 85 1332 90 1409 95 1494 00 1587 05 1691 10 1805 115 1932 120 2071 125 2226 130 2396 Note: For each cooldown rate, the steady-state pressure values shall govern the temperature where no allowable pressure values are provided.

6

BYRON UNIT 2-PRESSURE AND TEMPERATURE LIMITS REPORT 3.0 Low Temperature Overpressure Protection and Bottup This section provides the Byron Unit 2 power operated relief valve lift settings, low temperature overpressure protection (LTOP) system arming temperature, and minimum reactor vessel boltup temperature.

3.1 LTOP System Setpoints (LCO 3.4.12)

The power operated relief valves (PORVs) shall each have maximum lift settings in accordance with Figure 3.1 and Table 3.1. These limits are based on References 3 and 6.

The LTOP setpoints are based on PIT limits which were established in accordance with 10 CFR 50, Appendix U without allowance for instrumentation error and in accordance with the methodology described in Reference 1. The LTOP PORV nominal lift settings shown in Figure 3.1 and Table 3.1 account for appropriate instrument error.

3.2 LTOP Enable Temperature The required enable temperature for the PORVs shall be 350°FRCS temperature.

(Byron Unit 2 procedures governing the heatup and cooldown of the RCS require the arming of the LTOP System for RCS temperature of 350°Fand below and disarming of LTOP for RCS temperature above 350°F).

Note that the last LTOP PORV segment in Table 3.1 extends to 400°Fwhere the pressure setpoint is 2335 psig. This is intended to prohibit PORV lift for an inadvertent LTOP system arming at power.

3.3 Reactor Vessel Boltup Temperature (Non-Technical Specification)

The minimum boltup temperature for the Reactor Vessel Flange shall be 60°F. Boltup is a condition in which the Reactor Vessel head is installed with tension applied to any stud, and with the RCS vented to atmosphere (Reference 7).

7

BYRON UNIT 2 -

PRESSURE AND TEMPERATURE LIMITS REPORT I

0 0.

C E

0 z

50 100 150 200 250 300 350 400 450 Auctioneered Low RCS Temperature (DEG. F)

Figure 3.1 Byron Unit 2 Nominal PORV Setpoints for the Low Temperature Overpressure Protection (LTOP) System Applicable for the 32 EFPY (Includes Instrumentation Uncertainty) 8

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 3.1 Data Points for Byron Unit 2 Nominal PORV Setpoints for the LTOP System Applicable for 32 EFPY (Includes Instrumentation Uncertainty)

PCV-455A PCV-456 (2TY-04 1 3M) (2TY-04 1 3P)

AUCTIONEERED LOW RCS PRESSURE AUCTIONEERED LOW RCS PRESSURE RCS TEMP. (DEG. F) (PSIG) RCS TEMP. (DEG. F) (PSIG) 50 599 50 639 300 599 300 639 400 2335 400 2335 Note: To determine nominal lift setpoints for RCS Pressure and RCS Temperatures greater than 300°F,linearly interpolate between the 300°Fand 400°Fdata points shown above. (Setpoints extend to 400°Fto prevent PORV liftoff from an inadvertent LTOP system arming while at power.)

9

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 4.0 Reactor Vessel Material Surveillance Program The pressure vessel material surveillance program (Reference 4) is in compliance with Appendix H to 10 CFR 50, Reactor Vessel Radiation Surveillance Program. The material test requirements and the acceptance standard utilize the reference nil-ductility temperature, RT~1,which is determined in accordance with ASME Boiler and Pressure Vessel Code Section ifi, NB-233 1. The empirical relationship between RTNDT 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 E185-82.

The third and final reactor vessel material irradiation surveillance specimens have been removed and analyzed to determine changes in the reactor vessel material properties. The surveillance capsule testing has been completed for the original operating period. Other capsules will be removed to avoid excessive fluence accumulation should they be needed to support life extension. The removal schedule is provided in Table 4.1. The time of specimen withdrawal may be modified to coincide with those refueling outages or reactor shutdowns most closely approaching the withdrawal schedule.

10

BYRON UNIT 2 -

PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.1 Byron Unit 2 Capsule Withdrawal Schedule Capsule Vessel Location Capsule Lead Removal Time~ Estimated Capsule (Degrees) Factor (EFPY) Fluence (nlcm2)

U 58.5° 4.40 1.15 (Removed) 4.05x 1018 W 121.5° 4.25 4.634(Removed) 1.27x 10~

X 238.5° 4.25 8.573 (Removed) 2.30 x 1019 (b)

(d)

Z 301.5° 4.21 B2R11 (c)

-- (d)

V 6 1.0° 3.97 B2R1 1 (c)

Y 24 1.0° 3.97 Standby (c)

~.

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

b) Maximum end of license (32 EFPY) inner vessel wall fluence is estimated to be 2.06 x iO9 nlcm2.

c) Standby capsule to be used for future license renewal (derived from Table 7-1 of WCAP 15176, Reference 9).

d) Capsule has been removed and stored in the spent fuel pool. Since the capsule has not been analyzed the fluence has not been estimated.

11

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 5.0 Supplemental Data Tables 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 PIT limits.

Table 5.1 shows the calculation of the surveillance material chemistry factors using surveillance capsule data.

Table 5.2 provides the reactor vessel material properties table.

Table 5.3 provides a summary of the Byron Unit 2 adjusted reference temperature (ARTs) at the l/4T and 3/4T locations for 32 EFPY.

Table 5.4 shows the calculation of ARTs at 32 EFPY for the limiting Byron Unit 2 reactor vessel material, i.e. weld metal HT # 442002, (Based on Surveillance Capsule Data).

Table 5.5 provides RTpTS values for Byron Unit 2 for 32 EFPY obtained from Reference 5.

Table 5.6 provides RTpTS values for Byron Unit 2 for 48 EFPY obtained from Reference 5.

12

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 5.1 Byron Unit 2 Calculation of Chemistry Factors Using Surveillance Capsule Data (a)

Material Capsule Capsule f ~ FF~ ARTNDT~d) FF*L~RTNDT FF2 Lower Shell Forging U 4,05*1018 0.749 0.0 0 0.561 49D330/49C298-1-l W 1.27*1019 1.067 3.65 3.89 1.138 (Tangential) X 2.30*1019 1.225 15.75 19.29 1.500 Lower Shell U 4.05*1018 0.749 19.76 14.80 0.561 Forging49D33O/ W 1.27*1019 1.067 31.88 34.02 1.138 49C298-l-l X 2.30*1019 1.225 38.91 47.66 1.500 Sum: 119.66 6.398 CFFO~8ifl8= ~(FF ~ RTNDT) ÷ ~( FF~)= (119.66) ÷ (6.398) = 18.7°F Byron 1 Weld U 4.O4xlO8 0.749 11.22 (5.61) (e) 8.40 0.561 Metal WF-336 X 1.57x109 1.125 80.22(40.l1)~ 90,25 1.266 (Heat#442002) W 2.43x1019 1.239 102.68(51.34)~ 127.22 1.535 Byron 2 Weld U 4.05x108 0.749 16.88 (8.44) (e) 12.64 0.561 Metal WF-447 W 1.27 xlO9 1.067 57.76 (28.88) ~ 61.63 1.138 (Heat#442002) X 2.30x l0~ 1.225 108.02 (54.01) (e) 132.32 1.500 SUM: 432.46 6.561 CF = ~(FE

  • ART~1) ÷ ~( FF~)= (432.46) + (6.561) = 65.9°F a) Reference 7, Table 4-8 b) f= Calculated fluence, (x 1019 n/cm2, E> 1.0 MeV) c) FE = fluence factor = f(0.280.1*logf) d) L~RTNDTvalues are the measured 30 ft-lb shift values taken from Ref. 9 e) Adjusted ARTNDT per Ratio Procedure of Regulatory Guide 1.99, Rev, 2. Ratio = 2.0. See Table 4-9 of WCAP 15392, Revision 2. (Reference 7).

13

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT a) Reference 7. Table 5.2 Byron Unit 2 Reactor Vessel Material Properties ~

. . Initial Material Description Cu (%) Ni (%) ~,

RT NDT ( I)

Closure Head Flange 5P7382 / 3P6407 -- 0.71 0 Vessel Flange 124L556VA1 -- 0.70 30 Nozzle Shell Forging 4P-6 107 0.05 0.74 10 Inter. Shell Forging 49D329-l-1/49C297-1-1 0.01 0.70 -20 Lower Shell Forging 49D330-1-1/49C298-l-1 0.06 0.73 -20 Circumferential Weld WF-447 (HT# 442002) 0.04 0.63 10 Upper Circumferential Weld WF-562 (HT# 442011) 0.03 0.67 40 Byron Unit 1 Surveillance Program 002 0 ~69 --

Weld Metal (Heat #442002) ~

Byron Unit 2 Surveillance Program 002

~ 071~ --

Weld Metal (Heat # 442002)

Braidwood Units 1 & 2 Surveillance Program 0.67, 0 03 Weld Metal (Heat #442002) ~ 0.71 b) Initial RTNDT values are based on measured data.

14

BYRON UNIT 2 -

PRESSURE AND TEMPERATURE LIMITS REPORT Table 5.3 Sununary ofByron Unit 2 Adjusted Reference Temperatures (ARTs) at 1/4T and 3/4T Locations for 32 EFPY ~

32EFPY Material Description 1/4T ART(°F) 3/4T ART(°F)

Intermediate Shell Forging 49D329-1/49C297- 1 22 11 (RG_Position_1_(b))

Lower Shell Forging 49D330-l/49C298-l 53 37 (RU_Position_1~)

Using capsule data (RG Position 2~) 17 9 Circumferential Weld WF-447 (HT# 442002) 123 93 (RU_Position_1(b))

Using credible surveillance capsule data 107 89 (RG_Position_2(b))

Nozzle Shell Forging 4P-6107 52(c) 37(C)

(RG_Position_1_(b))

Nozzle Shell to Intermediate Shell Weld WF-562 96 76 (HT #442011)

Using credible surveillance capsule data 75 63 (RU Position 2(b))

1-~ .0 Mev) = 2.06x 10~at 32 EFPY, Reference 7.

(a) Fluence, f, is based upon f~~(E>1 (b) Calculated using a chemistry factor based on Regulatory Guide (RG) 1.99, Positions 1 and 2, as reported in WCAP-15392, Revision 2 (Reference 7).

(c) These ART values were used to generate the Byron Unit 2 Heatup and Cooldown Curves, WCAP-15392 Revision 2 (Reference 7).

15

BYRON UNIT 2 -

PRESSURE AND TEMPERATURE LIMITS REPORT Table 5.4 Byron Unit 2 Calculation of Adjusted Reference Temperatures (ARTs) at 32 EFPY at the Limiting Reactor Vessel Material, Nozzle Shell Forging 4P-6 107 ~

Parameter Values Operating Time 32 EFPY Location~ l/4T ART(°F) 3/4T ART(°F)

Chemistry Factor, CF (°F) 31.0 31.0 Fluence(f), nlcm2 3.13xl08 1.l3xlO8 (E>1.0_Mev)~

Fluence Factor, FF 0.681 0.442 ARTNDT=CFXFF(°F) 21.1 13.7 Initial RTNDT,, I (°F) 10 10 Margin,M(°F) 21.1 13.7 ART= I~f~(CF*FF)+M,°F 52 37 per RG 1.99, Revision 2 (a) WCAP 15392, Revision 2, Reference 7.

(b) The Byron Unit 2 reactor vessel wall thickness is 8.5 inches at the beltline region.

(c) Fluence, f, is based upon f~(E>1.0 Mev) = 2.06x109 at 32 EFPY, Reference 7.

16

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 5.5 RTprs Calculation for Byron Unit 2 Beltline Region Materials at EOL (32 EFPY) ~

Material Fluence FF CF ARTp.~ Margin (°F) RTNDT(U~ RTpi~

(1On/cm2, (°F) (°F) (°F) (°F)

E>1.O MeV)

Intermediate Shell Forging 2.06

  • 10~ 1.20 20 23.8 23.8 -20 28 Lower Shell Forging 2.06
  • 1019 1.20 37 44.0 34 20 58 Lower Shell Forging Using S/C 2.06
  • 1019 1.20 18.7 22.3 17 -20 19 Data~

Nozzle Shell Forging 5.22

  • 1018 0.818 31 25.0 25 10 60 Inter, to Lower Shell Circ. Weld 2.03 * ~ 1,19 54 63.7 56 10 130 Inter, to Lower Shell Circ. Weld 2.03
  • 1019 1.19 65.9 77.8 28 10 116 Using S/C Data~

Nozzle Shell to Inter. Shell Circ. 5.22

  • 1018 0.8 18 41 33.1 33.1 40 106 Weld Nozzle Shell to Inter. Shell Circ. 5.22
  • 1018 0.8 18 16.7 13.5 13.5 40 67 Weld Using S/C Data~ ~

(a) Fluence projections for 32 EFPY from Byron 2 PTS report, WCAP-15 177 (Reference 5)

(b) Limiting RTp~~is5 significantly less than the PTS Screening Criteria of 300 °F.

(c) ART~5 = CF*FF (d) Initial RTNDT values are measured values (See Table 5.2)

(e) RTpTS = RTNDT(u) + ARTPTS + Margin (°F)

(1) Calculated using a CF based on surveillance capsule data per RG 1.99, Position 2.

17

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT Table 5.6 RTprs Calculation for Byron Unit 2 Beltline Region Materials at Life Extension (48 EFPY) ~

Material Fluence FF CF Margin (°F) RTNDT(IJ)(d)

(1019n/cm2, (°F) (°F) (°F) (°F)

E>1.OMeV)

Intermediate Shell Forging 2.98

  • 10~ 1.29 20 25.8 25.8 20 32 Lower Shell Forging 2.98
  • 10~ 1.29 37 47.7 34 20 62 Lower Shell Forging Using S/C 2.98
  • lO~ 1.29 18.7 24.1 17 -20 21 Data~

Nozzle Shell Forging 7,53*1018 0.920 31 28.5 28.5 10 67 Inter. to Lower Shell Circ. Weld 2.93

  • iO9 1.29 54 69.7 56 10 136 Inter, to Lower Shell Circ. Weld 2.93
  • 1019 1.29 65.9 85 28 10 123 Using S/C Data~

Nozzle Shell to Inter. Shell Circ. 753*1018 0.920 41 37,7 37,7 40 115 Weld Nozzle Shell to Inter. Shell Circ. 753* 1018 0.920 16.7 15.4 15.4 40 71 Weld Using S/C Data~~

(a) The fluence for 48 EFPY (Reference 5) did not incorporate the 5% increase. However, this fluence value is greater than the end-of-life fluence (32 EFPY).

(b) Limiting RT~5is significantly less than the PTS Screening Criteria of 300 °F.

(c) ARTpTS = CF*FF (d) Initial RTNDT values are measured values (See Table 5.2)

(e) RT~5= RTNrJT(U) + ARTPTS + Margin (°F)

(1) Calculated using a CF based on surveillance capsule data per RG 1.99, Position 2.

18

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 6.0 References

1. WCAP-14040-NP-A, Revision 2, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, Andrachek, J.D.,

et al., January 1996.

2. WCAP-14824, Revision 2, Byron Unit 1 Heatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration forByron & Braidwood, November 1997 with Westinghouse errata letters CAE-97-220, dated November 26, 1997 and CAE 23 1/CCE-97-3 14 and CAE-97-233/CCE-97-3 16, dated January 6, 1998.
3. Westinghouse Letter to Commonwealth Edison Company, CAE-06-90/CCE-06-86, Transmittal of Byron and Braidwood Units 1 and 2 Revision 1 LTOPS Setpoints Analysis Reports for 22 and 32 EFPY (LTR-SCS-03-87, Revision 1 Attachment A) (LTR-SCS-03-87, Revision 1 Attachment B), August 28, 2006.
4. WCAP-10398, Commonwealth Edison Company, Byron Station Unit 2 Reactor Vessel Radiation Surveillance Program, Singer, L.R., December 1983.
5. WCAP-15 177, Evaluation ofPressurized Thermal Shock for Byron Unit 2, Revision 0, T. J.

Laubham, et al., September 2000.

6. Byron Station Design Information Transmittal DIT-BYR-06-046, Transmittal of Byron Unit 1 and Unit 2 Temperature and Pressure Uncertainties for Low Temperature Overpressure System (LTOPS) Power Operated Relief Valves (PORVS), David Neidich, August 15, 2006.
7. WCAP- 15392, Revision 2, Byron Unit 2 Heatup and Cooldown Limit Curves for Normal Operation, T. J. Laubham, et al., November 2003.
8. NRC Letter from R. A. Capra, NRR, to 0. D. Kingsley, Commonwealth Edison Co., Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, Acceptance for Referencing of Pressure Temperature Limits Report (TAC Numbers M98799, M98800, M98801, and M98802), January 21, 1998.
9. WCAP-l5 176, Revision 0, Analysis of Capsule X from Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program, T. J. Laubham, et al., March 1999.
10. NRC Letter from G. F. Dick, Jr., NRR, to C. Crane, Exelon Generation Company, LLC, Issuance of Amendments: Revised Pressure-Temperature Limits Methodology; Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, dated October 4, 2004.
11. NRC Letter from M. Chawla to O.D. Kingsley, Exelon Generation Company, LLC, Issuance of exemption from the Requirements of 10 CFR 50 Part 60 and Appendix U for Byron Station, Units 1 and 2, and Braidwood Stations, Units 1 and 2, dated August 8, 2001.

19

BYRON UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

12. NRC Letter from R. F. Kuntz, NRR, to C. M. Crane, Exelon Generation Company, LLC, Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Unit Nos. 1 and 2 Issuance of Amendments Re: Reactor Coolant System Pressure and Temperature Limits Report (TAC Nos. MC8693, MC8694, MC8695, and MC8696), November 27, 2006.
13. WCAP-16143-P, Revision 0, Reactor Vessel Closure HeadlVessel Flange Requirements Evaluation for ByronIBraidwood Units 1 and 2, W. Bamford, et al., November 2003.

20

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