ML20141K024

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Pressure & Temp Limits Rept
ML20141K024
Person / Time
Site: Byron  Constellation icon.png
Issue date: 05/21/1997
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20141J982 List:
References
NUDOCS 9705280289
Download: ML20141K024 (23)
v • d • e


Text

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BYRON UNIT 2 s  !

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PRESSURE AND TEMPERATURE LIMITS REPORT I s

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. 4 BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT l l

Table of Contents l

Section Page j 1

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 l 2.3 LTOP Enable Temperature 2 i 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 l 5.0 References 18 Attachment

WCAP-14824, " Byron Unit 1 Heatup and Cooldown Limit Curves for Normal Operation and l Surveillance Weld Metal Integration for Byron and Braidwood," Revision 1, April 1997, I

i

BYRON - UNIT 2 l \

PRESSURE AND TEMPERATURE LIMITS REPORT

  • t
l. .

List of Figures Figure Page 2.1 Byron Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to 4 100 F/hr) Applicable for the First 16 EFPY (Without Margins for Instrumentation Errors) '

2.2 Byron Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 5  ;

100 F/hr) Applicable for the First 16 EFPY(Without Margins for Instrumentation

~

Errors) 2.3 Byron Unit 2 Maximum Allowable Nominal PORV Setpoints for the Low 7 Temperature Overpressure Protection (LTOP) System Applicable for the ,

First 16 EFPY i

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b t

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4

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT List of Tables Table Page 2.1 Byron Unit 2 Heatup and Cooldown Data Points at 16 EFPY 6 l (Without Margins for Instrumentation Errors) '

2.2 Data Points from Byron Urdt 2 PORV Setpoints for the LTOP System 8 3.1 Byron Unit 2 Capsule Withdrawal Schedule 10 i 4.1 Byron Unit 2 Calculation of Chemistry Factors Using Surveillance Capsule Data 12 4.2 Byron Unit 2 Reactor Vessel Material Properties '3 l 4.3 Summary ofByron Unit 2 Adjusted Reference Temperatures (ARTS) at the 1/4T 14 l and 3/4T Locations for 16 EFPY l 1

4.4 Byron Unit 2 Calculation of Adjusted Reference Temperatures (ARTS) at 15 16 EFPY at the Limiting Reactor Vessel Material Weld Metal (Based l

on Surveillance Capsule Data) '

4.5 RTns Values for Byron Unit 2 for 32 EFPY 16 4.6 RTns Values for Byron Unit 2 for 48 EFPY 17 iii

o t

l BYRON - UNIT 2 i i.

L

'. PRESSURE AND TEMPERATURE LIMITS REPORT i

l 1.0 ' Introduction l Reference to Technical Specifications (TS) numbers are given in both the Byron Station current  !

Technical Specifications (CTS) and Improved Technical Specifications (ITS). The CTS number l

l is presented first, followed by the ITS number in brackets [ ].  !

This PTLR for Unit I has been prepared in accordance with the. requirements of l

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

l The Technical Specifications addressed in this repon 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 (P/f) Limits; and  !

LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System).

2.0 Operating Limits I i

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:

l

a. Use of ENDF/B-IV neutron transpon 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 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, j b. A maximum cooldown of 100*F in any 1-hour period, and i
c. A maximum temperature change ofless than or equal to 10 F in any 1-hour period during inservice hydrostatic and leak testing operatians above the heatup and cooldown limit curves.

1

! . . l BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT I i

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/T 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 l determining compliance with Figures 2.1 and 2.2 and Table 2.1, instrument uncertainties l

need not be 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 corresponding P/T curve for heatup and cooldown. i l

2.2 Low Temperature Overpres's ure Protection (LTOP) System Setpoints (L'CO 3.4.9.3/  !

[lTS-LCO 3.4.12]).

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

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

2.3 LTOP Enable Temperature The as-analyzed LTOP enable temperature is 185 F (Reference 5).

The TS required enable temperature for the PORVs shall be 2 350 F RCS temperature. l (Byron Unit 2 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 j pressure setpoint is 2350 psig. This is intended to prohibit PORV lift for an inadvertent LTOP system arming at power.

I I

2

BYRON - UNIT 2 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 applied to any stud, and with the RCS vented to atmosphere (Reference 2).

~

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.

9 3

1 l

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT MAWRIAL PROPERTY B ASIS LIMITING MATERIAL: WELD METAL LIMITING ART VALUES AT 16 EFPY: 1/4-t, 43.5'F 3/4-t, 33.2*F 2500 ,

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Figure 2.1 Byron Unit 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to 100 F/hr)

Applicable for the First 16 EFPY* (Without Margins for Instrumentation Errors)

  • Applicability date has been reduced per evaluation in WCAP-14824 Appendix A (Reference 2). ,

t A new applicability date will be determined and the results to be documented in WCAP-14881.

4

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT MATERIAL PROPERTY BASIS LIMITING MATERIAL WELD METAL LIMTHNG ART VALUES AT 16 EFPY: 1/4-t, 43.5'F 3/4-t, 33.2*F 2500 , . ,

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Figure 2.2 Byron Unit 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100 F/hr)

Applicable for the First 16 EFPY* (Without Margins for Instrumentation Errors)

  • Applicability date has been reduced per evaluation in WCAP-14824, Appendix A (Reference 2).

A new applicability date will be determined and the results to be documented in WCAP-14881.

5

a -m -

BYRON - UNIT 2 1

PRESSURE AND TEMPERATURE LIMITS REPORT Table 2.1 Byron Unit 2 Heatup :nd Cooldown" Data Points at 16* *" EFPY (Without Marcin

" for Instrumentation Errors) m,--c 3 , , - - , ~

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= 3ai2At Applicability date has been reduced per evaluation in WCAP-14824, Appendix A (Reference 2). A new applicability date will be determined and the results to be documented in WCAP-14881.

Heatup and Cooldown data include vessel flange requirements of 150 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 pressure values are provided.

6

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

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AUCTidbEREdYOW RNkEMPdAiruRdf8Eo. rP Figure 2.3 Byron Unit 2 Maximum Allowable Nominal PORV Setpoints for the Low Temperature Overpressure Protection (LTOP) System Applicable for the First 16 EFPY'

' Applicability date has been reduced per evaluation in WCAP-14824, Appendix A (Reference 2).

A new applicability date will be determined and the results to be documented in WCAP-14881.

7

BYRON - UNIT 2 i

PRESSURE AND TEMPERATURE LIMITS REPORT -

Table 2.2 Data Points for Byron Unit 2 Maximum Allowable PORV Setpoints for the LTOP System Applicable for the First 16 EFPY' PCV-455A POV-456 (2TY-0413M) (2TY-0413P)

AUCTIONEERED LOW RCS PRESSURE AUCTIONEERED LOW RCS PRESSURE RCS TEMP. (DEG. F) (PSIG) RCS TEMP. (DEG. F) (PSIG) 50 497 50 514 70 497 70 514 100 497 100 514 120 446 120 463 150 446 150 463 200 446 200 463 250 587 250 604 300 587 300 604 350 587 350 604 450 2350 450 2350 Note: To determine maximum allowable lift setpoints for RCS Pressure and RCS Temperatares greater than 350 F, linearly interpolate between the 350 F and 450 F data points shown above.

  • Applicability date has been reduced per evaluation in WCAP-14824, Appendix A (Reference 2).

A new applicability date will be determined and the results to be documented in WCAP-14881.

8

1 4

BYRON - UNIT 2 I

PRESSURE AND TEMPERATURE LIMI1S REPORT 3.0 Reactor Vessel Msterial 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. Also, the results of these analyses shall be used to update Figures 2.1 and 2.2, and Tables 2.1. The 4

time of specimen withdrawal may be modified to coincide with those refueling outages or reactor shutdowns mest closely approaching the withdrawal schedule.

The pressure vessel material surveillance program (Reference 6)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, RTer, which is determined in accordance with ASTM E208. The empirical relationship between RTer and the fracture toughness of the reactor vessel steelis 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. l l

1 1

l 1

9

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT

! Table 3.1 I

l Byron Unit 2 Capsule Withdrawal Schedule

- Capsule Vessel Location Capsule Lead Removal Time (" Estimated Capsule (Degrees) Factor (EFPY) 2 Fluence (n/cm )

U -58.5 3.96 1.15 (Removed) 3.996 x 10  ;

W -121.5 3.89 4.634 (Removed) 1.211 x 10

{

X 233.5 3.89 8.23 (EOL Wall) 2.192 x 10*)

12.34(1.5 EOL Z 301.5 3.89 Wall (d) 3.288 x 10

V 61.0' 3.64 Standby ---

Y 241.0' 3.64 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-2 of WCAP-14824, (Reference 2, which is the Attachment to this report). j i

l l'

i i

10 l

l

- )

BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT '

4.0 Supplemental Data Tables i

The following tables provide supplemental information on reactor vessel material properties and i 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 l

capsule data.

l Table 4.2 provides the reactor vessel material properties table.

l Table 4.3 provides a summary of the Byron Unit 2 adjusted reference temperature (ARTS) at the 1/4T and 3/4T locations for 16 EFPY.

Table 4.4 shows the calculation of ARTS at 16 EFPY for the limiting Byron Unit 2 reactor vessel material weld metal (Based on Surveillance Capsule Data).

1 Table 4.5 provides RTers values for Byron Unit 2 for 32 EFPY.

Table 4.6 provides RTrrsvalues for Byron Unit 2 for 48 EFPY.

l 1

I 1I

BYRON - UNIT 2 )

l l PRESSURE AND TEMPERATURE LIMITS REPORT

{

i i

Table 4.1 1 J

Calculation of Chemistry Factors Using Surveillance Capsule Data i Fluence  ;

Material Capsule (n/cm2 , pp<.) Measured FF*A.RTmr (FF)2 E>l .0 ARTer Mev), f I Byron 1 Weld Metal *) l U 3.72x 10 O.727 0 0 0.00 0.529 X 1.39x10" 1.091 35 105(*) 114.56 1.190 Byron 2 Weld I Metal (') U 3.996x10 ' O.746 0 0 0 0.557 W l .21'l x 10" 1.053 30 90) 94.77 1.110  ;

i Sum: 209.33 3.386

{

3 Chemistry Factor * = 209.33+3.386= 61.8'F

)

(a) FF = Fluence Factor = fe2:4i ioso v were obtained from the surveillance Capsule X analysis (b) Byron Unit 1 ARTmr alues (WCAP-13880, Reference 10). The Byron Unit I capsule fluence values were recalculated using  ;

the ENDF/B-V scattering cross sections in 1994 and are documented in WCAP-14044 (Reference i 8).

(c) Byron Unit 2 capsule fluence, FF, and ARTer alues v were obtained from the surveillance Capsule 1 W analysis of WCAP-14064 (Reference 3) using the ENDF/B-V scattering cross sections.

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

(e) Adjusted ARTmr per Ratio Procedure of 10 CFR 50.61 (Reference 11). Ratio = 3.0. See Table 2 of WCAP 14824, (Reference 2).

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~

BYRON - UNIT 2 l PRESSURE AND TEMPERATURE LIMITS REPORT

. Table 4.2

  • 1 4

)

Byron Unit 2 Reactor Vessel Material Properties  :

Chemistry Initial Material Cu (%)") Ni (%)") Factor") RT mr (*F)*) ,

2 Description Closure Head --

0.74 --

0")

Flange l

Vessel Flange -- 0.70 --

30")

l Lower Shell 0.052 0.720 32.2 -20 l Forging MK 24-3 l i

Inter. Shell Forging 0.007 0.703 20.0 -20 MK 24-2 Weld Metal 0.024 0.709 32.6 10 (a) Chemistry Factors are calculated from Cu and Ni values per Regulatory l

. Guide 1.99, Position 1 (Reference 12).

(b) Initial RTer aluesv are measured, WCAP-14063 (Reference 7)

! (c) Closure head and vessel flange Initial RTer aluesv are used for' considering

. flange requirements for the heatup/cooldown curves, WCAP-14063.

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\

BYRON - UNIT 2 ,

PRESSURE AND TEMPERATURE LIMITS REPORT Table 4.3 -

Summary of Byron Unit 2 Adjusted Reference Temperatures (ARTS) at 1/4T and 3/4T Locations for 16 EFPY')

i 16 EFPY') -

Material Description 1/4T ART ( F) 3/4T ART ( F)

Lower Shell Forging MK 36.8 19.4 24-3 Using credible surveillance capsule data 14.5 4.2 (RG Position 2))

Inter. Shell Forging 15.3 4.4 t MK 24-2 (RG Position l))

Weld Metal 67.6 49.8 Using credible surveillance capsule data 43.5* 33.2*)

(RG Position 2('))

(a) Calculated using a chemistry factor based on Regulatory Guide (RG) 1.99, Positions 1 and 2 (Reference 12).

(b) These ART values were used to generate the Byron Unit 2 heatup and cooldown curves, WCAP-14063 (Reference 7).

(c) Applicability date has been reduced per evaluation in WCAP-14824, Appendix A: Weld MetalIntegration for Byron Units 1 and 2 (Reference 2).

A new applicability date will be determined and the results to be documented in WCAP-14881, " Byron Unit 2 Heatup and Cooldown Curves for Normal Operation."

l 1

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, BYRON - UNIT 2 r PRESSURE AND TEMPERATURE LIMITS REPORT <

l Table 4.4  !

Byron Unit 2 Calculation of Adjusted Reference Temperatures (ARTS) at 16 EFPY*)at the Limiting Reactor Vessel Material l Weld Metal (Based on Surveillance Capsule Data) l 1 Parameter Values Operating Time 16 EFPY*) l Location (*) 1/4T ART 3/4T ART l Chemistry Factor, CF ( F) 19.0 19.0 l

2 Fluence (f), n/cm 6.58x10 2.37x10 .

(E>l.0 Mev)(') j Fluence Factor, FF 0.883 0.611 1 l

ARTun= CFxFF( F) 16.77 11.61 I I

Initial RT mvr., I( F) 10 10 l l

Margin, M ( F) 16.77 11.61 ART = I+(CF*FF)+M, F 43.5 33.2 per RG 1.99, Revision 2 I

(a) Fluence, f, is based upon f.e(E>1.0 Mev) = 1.096x10 at 16 EFPY, WCAP-14063 )

(Reference 7.). j (b) Based on evaluation of WCAP-14063; however, applicability date has been reduced l l per evaluation in WCAP-14824, Appendix A: Weld Metal Integration for Byron '

i Units 1 and 2. A new applicability date will be determined and the results to be i documented in WCAP-14881," Byron Unit 2 Heatup and Cooldown Curves for I Normal Operation."

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

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A BYRON - UNIT 2

e Table 4.5 l <

i l RTns Values for Byron Unit 2 for 32 EFPY CF po pp> M RTmnv3 ARTns RTns Material ( F) ( F) (F) ( F) ( F) i Lower Shell Forging 32.2 2.192 1.213 34.0 -20 39.1 53.1 MK 24-3 Using Surveillance 19.8- 2.192 1.213 17.0 -20 24.0 21.0 Capsule Data")

Intermediate Shell Forging 20.0 2.192 1.213 24.3 -20 24.3 28.6 MK 24-2 l Circumference Weld 82.0 2.192 1.213 56.0 10 99.5 165.5 Metal WF447 Using Surveillance 61.8 2,192 1.213 28.0 10 75.0 113.0

  • Capsule Data 2

(a) 2.192x10* n/cm (E>l.0 Mev) for 32 EFPY from Byron 2 PTS report, WCAP-14054 (Reference 9).

(b) FF (Fluence Factor) = f .2:4:o ios o  ;

(c) Calculated using a CF based on surveillance capsule data per RG 1.99, Position 2 (Reference 12). j i

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16

BYRON - UNIT 2 4

PRESSURE AND TEMPERATURE LIMITS REPORT '

l l

Table 4.6 RTns Values for Byron Unit 2 for 48 EFPY i

CF p.> ppu M RTenu) ARTns RTvrs Material (F) l

( F) ( F) (F) ( F)

Lower Shell Forging 32.2 3.288 1.312 34.0 -20 42.2 56.2 MK 24-3 Using Surveillance 19.8 3.288 1.312 17.0 -20 26.0 23.0 Capsule Data N Intermediate Shell Forging 20.0 3.288 1.312 26.2 -20 26.2 32.4 I MK 24-2 Circumference Weld 82.0 3.288 1.312 56.0 10 107.6 173.6 Metal WF447 {

Using Surveillance 61.8 3.288 1.312 28.0 10 81.1 119.1 Capsule Data 2

(a) 2.192x10 n/cm (E>l.0 Mev) for 32 EFPY from Byron 2 PTS report, WCAP-14054 (Reference 9). The following calculation provides the 48 EFPY fluence value:

2 2.192x10 + ((2.192x 10 -3.174x10)/32-4.6'34 EFPY)) * (48-32EFPY) = 3.288x10 n/cm (b) FF (Fluence Factor) = fg2:4:o ios o (c) Calculated using a CF based on surveillance capsule data per RG 1.99, Position 2 (Reference 12).

i l

17

f

. BYRON - UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT 5.0 References i 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 Curves," Revision 2, January 1996.

2. Grendys, P. A., WCAP-14824, " Byron Unit i Heatup and Cooldown Limit Cunes for Normal Operation and Surveillance Weld Metal Integration for Byron & Braidwood,"  !

Revision 1, April 1997. l

3. Malone, M.J., et al., WCAP-14064, " Analysis of Capsule W from the Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program,"

July 1994.

4. Terek, E., et al., WCAP-12431, " Analysis of Capsule U from the Commonwealth Edison Company Byron Unit 2 Reactor Vessel Radiation Surveillance Program," October 1989.
5. Westinghouse Letter to Commonwealth Edison Company, CAE-96-106, " Byron Unit I and 2 LTOPS Setpoints Based on 10 and 12 EFPY P/T Limits," January 17,1996.
6. Singer, L.R., WCAP-10398, " Commonwealth Edison Company, Byron Station Unit 2 Reactor Vessel Radiation Surveillance Program," December 1983.
7. Peter, P. A., WCAP-14063," Commonwealth Edison Company, Byron Unit 2 Heatup and Cooldown Limit Curves for Normal Operation," November 1994.
8. Lippencott, E.P., WCAP-14044, " Westinghouse Surveillance Capsule Neutron Fluence  !

Reevaluation," April 1994. '

9. Peter, P. A., WCAP-14054, " Evaluation of Pressurized Thermal Shock for Byron Unit 2,"

August 1994.

10. Peter, P.A., et al., WCAP-13880," Analysis of Capsule X from the Commonwealth Edison Company Byron Unit 1 Reactor Vessel Radiation Surveillance Program,"

January 1994. l

' l

11. 10 CFR 50.61, " Fracture Toughness Requirements for Protection Against Pressurized  !

l Thermal Shock Events," (PTS Rule) May 15,1991,1995.

l

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

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4 BYRON - UNIT 2  !

PRESSURE AND TEMPERATURE LIMITS REPORT  !

l References (Continued)

13. Comed Calculation BRW-96-9071/BYR 96-294, " Channel Accuracy for Power Operated Relief Valve (PORV) Setpoints and Wide Range RCS Temperature Indication (Unit 2 Original Steam Generators)" Revision 0.

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