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Enclosure 5 to NRC-12-0037, NEDO-33785, Rev 0, DTE Energy/Enrico Fermi Power Plant 2 Pressure and Temperature Limits Report Up to 24 and 32 Effective Full-Power Years.
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Enclosure 5 to NRC-12-0037 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report Fermi 2 Pressure Temperature Limits Report

GE Hitachi Nuclear Energy

(-) HITACHI NEDO-33785 Revision 0 DRF Section 0000-0153-5712 RO October 2012 GEHNon-ProprietaryInformation - Class I (Public)

NEDO-33785 Revision 0 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document is furnished for the purposes of supporting the Detroit Edison Energy license amendment request for pressure-temperature curves at Enrico Fermi Power Plant 2 in proceedings before the U.S. Nuclear Regulatory Commission (NRC). The only undertakings of GEH with respect to information in this document are contained in the contracts between GEH and its customers or participating utilities, and nothing contained in this document shall be construed as changing that contract.

The use of this information by anyone for any purpose other than that for which it is intended is not authorized; and with respect to any unauthorized use, GEH makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.

No use of or right to copy any of this information contained in this document, other than by the NRC and its contractors in support of GEH's application, is authorized except by contract with GEH, as noted above. The information provided in this document is part of and dependent upon a larger set of knowledge, technology, and intellectual property rights pertaining to the design of standardized, nuclear powered, electric generating facilities. Without access and a GEH grant of rights to that larger set of knowledge, technology, and intellectual property rights, this document is not practically or rightfully usable by others, except by the NRC or through contractual agreements with Detroit Edison Energy, as set forth in the previous paragraph.

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NEDO-33785 Revision 0 Table of Contents ABBREVIATIONS & ACRONYMS ................................................................................................. iv 1.0 P urp o se ....................................................................................................................................... 1 2 .0 A pp licab ility ............................................................................................................................. 1 3 .0 M eth odology ............................................................................................................................. 1 3 .1 C h em istry .............................................................................................................................. 2 3.2 Initial Reference Temperature of Nil Ductility Transition (RTNDT) ..................................... 2 3.3 Adjusted Reference Temperature ...................................................................................... 2 3.4 Surveillance Program ...................................................................................................... 2 3.5 Beltline Weld Flaw Indications ........................................................................................ 3 3.6 Future C hanges ............................................................................................................... 3 4.0 O perating Lim its .............................................................................................................. 3 5 .0 D iscu ssion ................................................................................................................................. 4 6 .0 R eferen ces ................................................................................................................................. 6 Appendix A Reactor Vessel Material Surveillance Program ................................................... A-1 Appendix B Fermi 2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information. B-1 Appendix C Fermi 2 Reactor Pressure Vessel P-T Curve Checklist .......................................... C-1 Table of Tables Table 1 Fermi 2 Tabulation of Curves - 24 EFPY ......................................................................... 13 Table 2 Fermi 2 Tabulation of Curves - 32 EFPY ......................................................................... 18 Table B-1 Fermi 2 Initial RTNDT Values for RPV Plate and Flange Materials ................................. B-3 Table B-2 Fermi 2 Initial RTNDT Values for RPV Nozzle Materials ................................................. B-4 Table B-3 Fermi 2 Initial RTNDT Values for RPV Weld Materials ................................................... B-6 Table B-4 Fermi 2 Initial RTNDT Values for RPV Appurtenance and Bolting Materials .................. B-9 Table B-5 Fermi 2 Adjusted Reference Temperatures for up to 24 EFPY ................................. B- 1I Table B-6 Fermi 2 Adjusted Reference Temperatures for up to 32 EFPY ................................. B-13 Table B-7 Fermi 2 RPV Beltline P-T Curve Input Values for 32 EFPY ................................... B-15 Table B-8 Fermi 2 Definition of RPV Beltline Region ................................................................... B-16 T able C-1 Ferm i 2 Checklist .............................................................................................................. C -2 Table of Figures Figure 1 Fermi 2 Composite Curve A Pressure Test P-T Curves Effective for up to 24 EFPY ........ 7 Figure 2 Fermi 2 Composite Curve B Core Not Critical P-T Curves Effective for up to24 EFPY ...... 8 Figure 3 Fermi 2 Limiting Curve C Core Critical P-T Curve Effective for up to 24 EFPY ............. 9 Figure 4 Fermi 2 Composite Curve A Pressure Test P-T Curves Effective for up to 32 EFPY ..... 10 Figure 5 Fermi 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 32 EFPY ... 11 Figure 6 Fermi 2 Limiting Curve C Core Critical P-T Curve Effective for up to 32 EFPY ........... 12 Figure B-1 Fermi 2 Reactor Pressure Vessel ...................................................................................... B-2 iii

NEDO-33785 Revision 0 ABBREVIATIONS & ACRONYMS STerm Description

%Cu Weight percent Copper

%Ni Weight percent Nickel 1/4T 1/4 depth into the vessel wall from the inside diameter 3/4T 3/4 depth into the vessel wall from the inside diameter ART Adjusted Reference Temperature BAF Bottom of Active Fuel BWR Boiling Water Reactor BWR/6 BWR Product Line 6 BWRVIP BWR Vessel and Internals Project CE Combustion Engineering CF Chemistry Factor CMTR Certified Material Test Report CRD Control Rod Drive EFPY Effective Full Power Years EPU Extended Power Uprate FSAR Final Safety Analysis Report GEH GE Hitachi Nuclear Energy ID Inside Diameter ISP Integrated Surveillance Program LTR Licensing Topical Report MUR Measurement Uncertainty Recovery MWt Megawatt Thermal NDT Nil Ductility Transition n/cm 2 neutrons per square centimeter (measure of fluence)

NRC Nuclear Regulatory Commission P/T Pressure/Temperature P-T Pressure-Temperature PTLR Pressure and Temperature Limits Report RCS Reactor Coolant System RFO Refueling Outage RG Regulatory Guide RPV Reactor Pressure Vessel RTNDT Reference Temperature of Nil Ductility Transition RVID Reactor Vessel Integrity Database (by NRC)

SSP Supplemental Surveillance Program T Temperature TAF Top of Active Fuel TPO Thermal Power Optimization TS Technical Specification UFSAR Updated Final Safety Analysis Report US United States WLI Water Level Instrumentation iv

NEDO-33785 Revision 0 1.0 Purpose The purpose of the Enrico Fermi Power Plant 2 (Fermi 2) Pressure and Temperature Limits Report (PTLR) is to present operating limits relating to:

1. Reactor coolant system (RCS) Pressure versus temperature limits during heatup, cooldown and hydrostatic/class 1 leak testing;

2. RCS heatup and cooldown rates;

3. Reactor pressure vessel (RPV) to RCS coolant AT requirements during Recirculation Pump startups;

4. RPV bottom head coolant temperature to RPV coolant temperature AT requirements during recirculation pump startups;

5. RPV head flange bolt-up temperature limits.

This report has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.8, "Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)".

2.0 Applicability This report is applicable to the Fermi 2 RPV for up to 24 and 32 Effective Full Power Years (EFPY).

The following TS is affected by the information contained in this report:

TS 3.4.10 RCS Pressure and Temperature (P/T) Limits 3.0 Methodology The limits in this report were derived from the Nuclear Regulatory Commission (NRC)-approved methods listed in TS 5.6.8, using the specific revisions listed below:

1. The neutron fluence was calculated per Licensing Topical Report, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation, NEDC-32983P-A, Revision 2, January 2006, approved in Reference 6.1.

2. The pressure and temperature limits were calculated per GE Hitachi Nuclear Energy Methodologyfor Development of Reactor Pressure Vessel Pressure-TemperatureCurves, NEDC-33178P-A, Revision 1, June 2009, approved in Reference 6.2.

3. This revision of the pressure and temperature limits is to incorporate the following changes:

Initial issuance of the PTLR

Application of GEH licensing topical report (LTR) for pressure-temperature (P-T) curves

Thermal power optimization (TPO) at 3486 MWt 1

NEDO-33785 Revision 0

. The water level instrumentation (WLI) nozzle that occurs in the beltline region was fabricated from carbon steel and has been considered in the adjusted reference temperature (ART) evaluation. The fluence at this location is based on a less conservative power history that excludes EPU and considers TPO after RFO16.

The fluence used considers operation at 3293 MWt for 3.228 EFPY, 3430 MWt for 16.35 EFPY, and 3486 MWt (TPO) for 10.59 EFPY.

3.1 Chemistry The N16 WLI nozzle is defined as being within the beltline region, and is evaluated for ART.

Insufficient information was located to determine the copper and nickel content for these SA508 Class 1 forging materials. All available boiling water reactor (BWR) fleet SA508 Class 1 forging information was reviewed; fourteen (14) copper and thirty-five (35) nickel data points were obtained. The copper and nickel content was determined using the Mean + 1 , resulting in 0.272 %Cu and 0.214 %Ni.

3.2 Initial Reference Temperature of Nil Ductility Transition (RTNDT)

The N16 WLI nozzle is evaluated for ART. The Combustion Engineering (CE) purchase specification for this material demonstrates a required test temperature of 10°F, consistent with the N16 certified material test reports (CMTR). However, insufficient information is available to determine the initial RTNDT. NRC MTEB 5-2, paragraph B.1.1(4) defines the method for determining initial RTNDT where limited Charpy V-Notch tests were performed at a single temperature, as is the case for the N16 material. Testing for one N16 material was performed at 10F, with a minimum results of 30 ft-lbs and where the maximum results is less than 45 ft-lbs.

Therefore, MTEB 5-2 states that the RTNDT may be calculated as 20'F above the test temperature; hence, the initial RTNDT is determined to be 30 0 F. Testing for the second N16 material was performed at 10'F, but dropweight was not reported. The dropweight was considered to be 30'F, consistent with MTEB 5-2 guidance. Therefore, the initial RTNDT for this heat is the greater of the dropweight and TSoT - 60'F. The resulting initial RTNDT for this material is 30'F.

3.3 Adjusted Reference Temperature The ART values for 24 and 32 EFPY included in Appendix B are developed considering the latest BWR Vessel and Internals Project (BWRVIP) integrated surveillance program (ISP) published surveillance data available that is representative of the applicable materials in the Fermi 2 RPV (Reference 6.3). The surveillance data used in the Fermi 2 ART calculations is not obtained from actual Fermi 2 RPV test specimens. The ISP plate materials did not have the limiting ART. The ISP weld material has the limiting ART; this value is considered in the development of the P-T curves because the ISP material is the identical heat to the material in the Fermi 2 RPV.

3.4 Surveillance Program As discussed in Appendix A, Fermi 2 participates in the ISP. Two of the surveillance capsules, installed at plant startup, remain in the vessel, while the third capsule was removed at 2

NEDO-33785 Revision 0 approximately 8 EFPY, but was not tested. As Fermi 2 is not a host plant, the three (3) surveillance capsules have an ISP status designation of deferred (standby) per Reference 6.4.

Should actual surveillance capsules be withdrawn and tested from the Fermi 2 RPV (e.g., status change to be an ISP host plant under the BWRVIP ISP), compliance with 10 CFR 50 Appendix H requirements on reporting test results and evaluations on the effects to plant operations parameters (e.g., P-T limits, hydrostatic and leak test conditions) will be in accordance with Section 3 of Reference 6.3.

3.5 Beltline Weld Flaw Indications Three (3) flaw indications have been evaluated for the Fermi 2 vessel, occurring in Shell Ring #2, in weld 15-308 (axial weld). Flaw #124 requirements bound those of Flaw #127 and Flaw #128.

A fracture mechanics evaluation was conducted using techniques consistent with the philosophy of Section XI of the ASME Code. The indication, Flaw #124, was modeled with length equal to 4.24 inches (along the weld thickness direction) and width equal to 2 inches. The long end of the indication is located 0.7 inches from the inside diameter (ID) surface, which includes a clad thickness of 0.3125 inches.

At 32 EFPY, the hydrotest temperature is calculated to be 114.9°F at 1030 psig. For these conditions, the allowable value of K, is 34.0 ksi-inl/ 2 and does not bound the calculated value of K1, which is 35.7 ksi-in" 2 . Therefore, the beltline hydrotest P-T curve must be shifted to the right in order to increase the allowable value of KI, resulting in a calculated value of K, that is bounded by the allowable value of K1. For the 32 EFPY curve, an adjustment of 5°F was applied such that Curve A requires a temperature of 119.9°F at 1030 psig. Similarly, an adjustment of 13'F was applied for 24 EFPY.

For the limiting leak test condition at 32 EFPY, the highest calculated value of applied stress intensity factor was 35.7 ksi-in1/ 2 and the allowable value of KI was calculated to be 35.9 ksi-in" 2 . Because the calculated value of K, is less than the allowable value of K1, the indication is not expected to become a surface indication during future operation. The indication is acceptable in the as-is condition for operation up to 32 EFPY, including TPO/ measurement uncertainty recovery (MUR).

3.6 Future Changes Changes to the curves, limits, or parameters within this PTLR, based upon new irradiation fluence data of the RPV, or other plant design assumptions in the updated final safety analysis report (UFSAR), can be made pursuant to 10 CFR 50.59, provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance.

4.0 Operating Limits The pressure-temperature (P-T) curves provided in this report represent steam dome pressure versus minimum vessel metal temperature and incorporate the appropriate non-beltline limits and irradiation embrittlement effects in the beltline region.

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NEDO-33785 Revision 0 The operating limits for pressure and temperature are required for three categories of operation:

(a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatup/cooldown (core not critical), referred to as Curve B; and (c) core critical operation, referred to as Curve C.

Complete P-T curves were developed for 24 and 32 EFPY. The P-T curves are provided in Figures 1 through 6, and a tabulation of the curves is included in Table 1 (24 EFPY) and Table 2 (32 EFPY).

Other temperature limits applicable to the RPV and controlled by the TS are:

Heatup and cooldown rate limit during Hydrostatic and Class 1 Leak Testing:

< 20 °F/hour.

Normal operating heatup and cooldown rate limit: *100°F/hour.

RPV bottom head coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: <145°F.

Recirculation loop coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: <50°F.

RPV flange and adjacent shell temperature limit: >72°F.

5.0 Discussion The procedures described in References 6.1 and 6.2 were used in the development of the P-T curves for Fermi 2.

The method for determining the initial reference temperature of nil-ductility transition (RTNDT) for all vessel materials is defined in Section 4.1.2 of Reference 6.2. Initial RTNDT values for all vessel materials considered are presented in tables in Appendix B of this report.

For Fermi 2, the limiting surveillance material, weld heat 13253/12008, was considered using Procedure 1 as defined in Appendix I of Reference 6.2. This procedure was used because the target vessel material and the surveillance material are identical heats.

For Fermi 2, there are four (4) thickness discontinuities in the vessel: (1) between the bottom head upper and lower torus, (2) between the bottom head torus and the support skirt attachment, (3) between the bottom head torus and Shell Ring #1, and (4) between Shell Ring #1 and Shell Ring #2. The P-T curves defined in Section 4.3 of Reference 6.2 are based upon an RTNDT of 30'F for the bottom head Curves A and C, 44.6°F for the bottom head Curve B, and 25°F for the upper vessel. The 24 EFPY beltline curves are based on an ART of 75°F, and the 32 EFPY beltline curves are based on an ART of 82°F. Curves based on these temperatures bound the requirements due to the flaws discussed in Section 3.5, and the beltline thickness discontinuities.

The ART of the limiting beltline material is used to adjust the beltline P-T curves to account for irradiation effects. Regulatory Guide (RG) 1.99, Revision 2, provides the methods for determining the ART. The RG 1.99 methods for determining the limiting material and adjusting the P-T curves using ART are discussed in this section.

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NEDO-33785 Revision 0 The vessel beltline copper and nickel values, with the exception of the N16 WLI nozzle, were obtained from plant-specific vessel purchase order records, CMTRs. The N16 nozzle is fabricated from SA508 Class 1 material; there is insufficient plant-specific chemistry information for these nozzles. Therefore, chemistry values using BWR fleet data and Mean + IC have been considered. The copper (Cu) and nickel (Ni) values were used with Tables 1 and 2 of RG 1.99, to determine a chemistry factor (CF) per paragraph 1.1 of RG 1.99 for welds and plates, respectively. ART values for 24 and 32 EFPY are presented in Appendix B. The ART tables also include plant-specific materials considering best estimate chemistry values obtained from Reference 6.3.

The P-T curves for the non-beltline region were conservatively developed for a BWR product line 6 (BWR/6) with nominal ID of 251 inches. The analysis is considered appropriate for Fermi 2 because the plant-specific geometric values are bounded by the generic analysis for the large BWR/6. The generic value was adapted to the conditions at Fermi 2 using plant-specific RTNDT values for the reactor pressure vessel.

The peak RPV ID fluence used in the P-T curve evaluation for Fermi 2 at 24 EFPY is 7.26e17 n/cm 2 and at 32 EFPY is 9.68e17 n/cm 2 . These values were calculated using methods that comply with the guidelines of RG 1.190, (as discussed in Reference 6.1). This fluence applies to the lower-intermediate shell plates and longitudinal welds. The fluence is adjusted for the lower plates, associated longitudinal welds, and the girth weld based upon the axial fluence distribution calculated as part of the fluence evaluation; hence, the peak ID surface fluence for these components is 4.67e17 n/cm 2 for 24 EFPY and 6.23e17 n/cm 2 for 32 EFPY. Similarly, the fluence is adjusted for the N16 nozzle based upon the axial fluence distribution; hence the peak ID surface fluence used for this component is 1.24e17 n/cm 2 for 24 EFPY and 1.65e17 n/cm 2 for 32 EFPY. It is also noted that the fluence used for the N16 nozzle is based on a less conservative power history as noted in Section 3.0.

The P-T curves for the heatup and cooldown operating conditions at a given EFPY apply for both the 1/4T and 3/4T locations. When combining pressure and thermal stresses, it is usually necessary to evaluate stresses at the 1/4T location (inside surface flaw) and the 3/4T location (outside surface flaw). This is because the thermal gradient tensile stress of interest is in the inner wall during cooldown and the outer wall during heatup. However, as a conservative simplification, the thermal gradient stress at the 1/4T location is assumed to be tensile for both heatup and cooldown. This results in the approach of applying the maximum tensile stress at the 1/4T location. This approach is conservative because irradiation effects cause the allowable toughness, KIr, at 1/4T to be less than that at 3/4T for a given metal temperature. This approach causes no operational difficulties, because the BWR is at steam saturation conditions during normal operation, well above the heatup/cooldown curve limits.

For the core not critical curve (Curve B) and the core critical curve (Curve C), the P-T curves specify a coolant heatup and cooldown temperature rate of < 100°Fihr for which the curves are applicable. However, the core not critical and the core critical curves were also developed to bound transients defined on the RPV thermal cycle diagram and the nozzle thermal cycle diagrams. For the hydrostatic pressure and leak test curve (Curve A), a coolant heatup and 5

NEDO-33785 Revision 0 cooldown temperature rate of < 20°F/hr must be maintained. The P-T limits and corresponding heatup/cooldown rates of either Curve A or B may be applied while achieving or recovering from test conditions. Curve A applies during pressure testing and when the limits of Curve B cannot be maintained.

For Fermi 2, weld heat 13253/12008 is the limiting material for the beltline region for 24 and 32 EFPY. The initial RTNDT for weld heat 13253/12008 material is -44'F. The generic pressure test P-T curve is applied to the Fermi 2 beltline curve by shifting the P vs. (T - RTNDT) values to reflect the ART value of 75°F for 24 EFPY and 82°F for 32 EFPY. Using the fluence discussed above, the P-T curves are beltline limited for Curves A, B, or C, for 24 or 32 EFPY. For 24 EFPY, Curve A is beltline limited above 900 psig; Curve B and Curve C are beltline limited above 730 psig. For 32 EFPY, Curve A is beltline limited above 840 psig; Curve B and Curve C are beltline limited above 600 psig.

In order to ensure that the limiting vessel discontinuity has been considered in the development of the P-T curves, the methods in Sections 4.3.2.1 and 4.3.2.2 of Reference 6.2 for the non-beltline and beltline regions, respectively, are applied.

6.0 References 6.1 Final Safety Evaluation Regarding Removal of Methodology Limitations for NEDC-32983P-A, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation (TAC NO. MC3788), November 17, 2005.

6.2 Final Safety Evaluation for Boiling Water Reactors Owners' Group Licensing Topical Report NEDC-33178P, General Electric Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves (TAC NO. MD2693), April 27, 2009.

6.3 BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations, BWRVIP-135, Revision 2, EPRI, Palo Alto, CA, October 2009.

6.4 BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP)

Implementation Plan, BWRVIP-86, Revision 1, EPRI, Palo Alto, CA: September 2008.

1016575.

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NEDO-33785 Revision 0 1400 - - - - - -

1300 'INITIAL RTNDT VALUES ARE 1200 -44*F FOR BELTLINE, 25°F FOR UPPER VESSEL, 10 AND 1100 i 30'F FOR BOTTOM HEAD 1000 0/ BELTLINE CURVES

, ADJUSTED AS SHOWN:

EFPY SHIFT (-F)

/ 24 119 0

o-w CO)800 w

IX 700 _

0I-., HEATUP/COOLDOWN 0 *RATE OF COOLANT W 600 < 20°F/HR z

S50BOTTOM HEAD UJ 68"F 400 LU

(.. 300 FLANGE - UPPER VESSEL 200 200 i / 72*F REGION AND BELTLINE FLIMITS

BOTTOM HEAD 100 CURVE 0

0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 1 Fermi 2 Composite Curve A Pressure Test P-T Curves Effective for up to 24 EFPY 7

NEDO-33785 Revision 0 1400 1300 INITIAL RTNDT VALUES 1200 ARE

-44°F FOR BELTLINE, 25°F FOR UPPER VESSEL, 1100 AND 44.6°F FOR BOTTOM HEAD

.S:1000 BELTLINE CURVES ADJUSTED AS SHOWN:

w

= 900 EFPY SHIFT (°F) a- ; 24 106 0

uj 800 U)

U)

W 700 0

HEATUP/COOLDOWN I-D RATE OF COOLANT

< 100°F/HR Z

500 LU 68*F D 400 U)

U, 0:

HEAD 1312 PSIGI ouU FLNG

___ ___ ___ UPPER VESSEL 200 AND BELTLINE LIMITS HEAO -- BOTTOM HEAD 100 CURVE 01 0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 2 Fermi 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 24 EFPY 8

NEDO-33785 Revision 0 1400 INITIAL RTNDT VALUES ARE 1300 44°F FOR BELTLINE, 25°F FOR UPPER VESSEL, AND 1200 30'F FOR BOTTOM HEAD 1100 U. 1000 BELTLINE CURVE ADJUSTED AS SHOWN:

EFPY SHIFT (°F)

"' 24 106

= 900 0

I-

-,I

,, 800 8HEATUP/COOLDOWN LRATE OF COOLANT

> < 100*F/HR W 700 _ -

I-

"' 600 I-500 LU

=)400 cn U/)

LU w 312 PSIG 300 200 /

- BELTLINE AND NON-BELTLINE LIMI TS 100 Minimum Vessel LIMITS i *...*Temperature 72°F 0

0 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (-F)

Figure 3 Fermi 2 Limiting Curve C Core Critical P-T Curve Effective for up to 24 EFPY 9

NEDO-33785 Revision 0 1400 1300 INITIAL RTNDT VALUES ARE 1200 -44°F FOR BELTLINE, 25°F FOR UPPER VESSEL,

/' AND 1100 30'F FOR BOTTOM HEAD 100 BELTLINE CURVES

/ ADJUSTED AS SHOWN:

900 EFPY SHIFT (-F) 900 32 126 0

I-w 800 co W 700 1-I,- HEATUP/COOLDOWN

- IRATE OF COOLANT U 600 <20°F/HR I-5500

- BOTTOM M HEAD 68*F 400 1,1, w

.. 300 FLANGE -UPPER VESSEL 200 REGION AND BELTLINE 72*F LIMITS

- BOTTOM HEAD 100 CURVE 0 -

0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 4 Fermi 2 Composite Curve A Pressure Test P-T Curves Effective for up to 32 EFPY 10

NEDO-33785 Revision 0 1400 1I NITIAL RTNDT VALUES ARE 1200 10 -44°F FOR BELTLINE, 25"F FOR UPPER VESSEL, 1100 AND 1100 44.6°F FOR S BOTTOM HEAD 100 BELTLINE CURVES

ADJUSTED AS SHOWN

X 900 ;EFPY SHIFT (°F)

/L 32 121 i-

, 800 co w

0, 700 /

I-o* / HEATUP/COOLDOWN 600 / -"' RATE OF COOLANT 60<100°F/HR I--

_ 500 U.'

400 _

WL BOTTOM I-IL 300 HEAD 300 68-F 200 ___UPPER VESSEL AND BELTLINE FLANGE LMT LIMITS 100 i 10REGION 72"F -----BOTTOM URV HEAD CURVE 0

0 25 50 75 100 125 150 175 200 MINIMUM REACTOR VESSEL METAL TEMPERATURE ("F)

Figure 5 Fermi 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 32 EFPY 11

NEDO-33785 Revision 0 1400 INITIAL RTNDT VALUES ARE 1300 44°F FOR BELTLINE, 25°F FOR UPPER VESSEL, AND 1200 30'F FOR BOTTOM HEAD 1100 __

. 10BELTLINE CURVE 10 ADJUSTED AS SHOWN:

EFPY SHIFT (°F)

L 32 121 (L

900 0

I--

,-J LuO 800 HEATUP/COOLDOWN U) wRATE OF COOLANT

> < 100°F/HR W 700 0

I-

"U 600 500 LU Cj) 400 cn, LU w 312 PSIG 200 /

2- BELTLINE AND NON-BELTLINE 100 i *Temp Minimum Vessel erature 72°F LIMITS LMT 0 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 6 Fermi 2 Limiting Curve C Core Critical P-T Curve Effective for up to 32 EFPY 12

NEDO-33785 Revision 0 Table I Fermi 2 Tabulation of Curves - 24 EFPY BOTTOM UPPER RPV & BOTTOM UPPER RPV & LIMITING

,em~svl24 PRESSURE HEAD- EFPYn~a BELTLINE AT HEAD 24:

BELTLINE AT EEFPY 24 EFPY (PSIG) CURVE0A 2EPY CURVE 0 B 2EPY CURVE C

( F) CURVE A FII CURVE B (j~

(OF) (OF) 0 68.0 72.0 68.0 72.0 72.0 10 68.0 72.0 68.0 72.0 72.0 20 68.0 72.0 68.0 72.0 72.0 30 68.0 72.0 68.0 72.0 72.0 40 68.0 72.0 68.0 72.0 72.0 50 68.0 72.0 68.0 72.0 72.0 60 68.0 72.0 68.0 72.0 72.0 70 68.0 72.0 68.0 72.0 72.2 80 68.0 72.0 68.0 72.0 78.2 90 68.0 72.0 68.0 72.0 83.3 100 68.0 72.0 68.0 72.0 87.8 110 68.0 72.0 68.0 72.0 91.9 120 68.0 72.0 68.0 72.0 95.7 130 68.0 72.0 68.0 72.0 99.2 140 68.0 72.0 68.0 72.0 102.4 150 68.0 72.0 68.0 72.0 105.2 160 68.0 72.0 68.0 72.0 107.9 170 68.0 72.0 68.0 72.0 110.5 180 68.0 72.0 68.0 72.9 112.9 190 68.0 72.0 68.0 75.2 115.2 200 68.0 72.0 68.0 77.3 117.3 210 68.0 72.0 68.0 79.3 119.3 220 68.0 72.0 68.0 81.3 121.3 230 68.0 72.0 68.0 83.1 123.1 240 68.0 72.0 68.0 84.9 124.9 250 68.0 72.0 68.0 86.6 126.6 260 68.0 72.0 68.0 88.2 128.2 270 68.0 72.0 68.0 89.8 129.8 280 68.0 72.0 68.0 91.3 131.3 290 68.0 72.0 68.0 92.8 132.8 300 68.0 72.0 68.0 94.2 134.2 310 68.0 72.0 68.0 95.5 135.5 312.5 68.0 72.0 68.0 95.9 135.9 312.5 68.0 102.0 68.0 132.0 172.0 320 68.0 102.0 68.0 132.0 172.0 13

NEDO-33785 Revision 0 UPPER RPV & UPPER RP\

BOTTOM. BOTTOM A LIMITING BELTLINE AT BELTLINE PRESSURE HEAD HEAD 24EFPY 24 EFPY 24 EFPY

'(PSIG) CURVE A CURVE B CURVE C CURVE A' CURVE I (OF) (OF) ('F)

(,IF) (OF) 330 68.0 102.0 68.0 132.0 172.0 340 68.0 102.0 68.0 132.0 172.0 350 68.0 102.0 68.0 132.0 172.0 360 68.0 102.0 68.0 132.0 172.0 370 68.0 102.0 68.0 132.0 172.0 380 68.0 102.0 68.0 132.0 172.0 390 68.0 102.0 68.0 132.0 172.0 400 68.0 102.0 68.0 132.0 172.0 410 68.0 102.0 68.0 132.0 172.0 420 68.0 102.0 68.0 132.0 172.0 430 68.0 102.0 68.0 132.0 172.0 440 68.0 102.0 68.0 132.0 172.0 450 68.0 102.0 68.0 132.0 172.0 460 68.0 102.0 68.0 132.0 172.0 470 68.0 102.0 68.0 132.0 172.0 480 68.0 102.0 68.0 132.0 172.0 490 68.0 102.0 68.0 132.0 172.0 500 68.0 102.0 68.0 132.0 172.0 510 68.0 102.0 68.0 132.0 172.0 520 68.0 102.0 68.0 132.0 172.0 530 68.0 102.0 68.0 132.0 172.0 540 68.0 102.0 68.0 132.0 172.0 550 68.0 102.0 69.5 132.0 172.0 560 68.0 102.0 71.3 132.0 172.0 570 68.0 102.0 73.0 132.0 172.0 580 68.0 102.0 74.6 132.0 172.0 590 68.0 102.0 76.2 132.0 172.0 600 68.0 102.0 77.8 132.0 172.0 610 68.0 102.0 79.3 132.0 172.0 620 68.0 102.0 80.7 132.0 172.0 630 68.0 102.0 82.1 132.0 172.0 640 68.0 102.0 83.5 132.0 172.0 650 68.0 102.0 84.8 132.0 172.0 660 68.0 102.0 86.1 132.0 172.0 670 68.0 102.0 87.4 132.0 172.0 680 68.0 102.0 88.7 132.0 172.0 14

NEDO-33785 Revision 0 UJPPER RPV & UPPER RPV &

BOTTOM BOTTOM LIMITING 3ELTLINE AT BELTLINE AT PRESSURE HEAD HEAD 24 EFPY 24 EFPY 24 EFPY (PSIG) CURVE A CURVE B CURVE C CURVE A CURVE B

('F) (OF) (OF)

(OF) 690 68.0 102.0 89.9 132.0 172.0 700 68.0 102.0 91.0 132.0 172.0 710 68.0 102.0 92.2 132.0 172.0 720 68.0 102.0 93.3 132.0 172.0 730 68.0 102.0 94.4 132.0 172.0 740 68.0 102.0 95.5 132.1 172.1 750 68.0 102.0 96.6 132.5 172.5 760 68.0 102.0 97.6 132.8 172.8 770 68.0 102.0 98.6 133.2 173.2 780 68.0 102.0 99.6 133.5 173.5 790 68.0 102.0 100.6 133.9 173.9 800 68.0 102.0 101.5 134.2 174.2 810 68.0 102.0 102.5 134.6 174.6 820 68.0 102.0 103.4 134.9 174.9 830 68.0 102.0 104.3 135.3 175.3 840 68.0 102.0 105.2 135.6 175.6 850 68.6 102.0 106.0 135.9 175.9 860 69.6 102.0 106.9 136.3 176.3 870 70.6 102.0 107.7 136.6 176.6 880 71.5 102.0 108.6 136.9 176.9 890 72.5 102.0 109.4 137.3 177.3 900 73.4 102.0 110.2 137.6 177.6 910 74.4 102.2 111.0 137.9 177.9 920 75.3 103.2 111.7 138.2 178.2 930 76.1 104.1 112.5 138.6 178.6 940 77.0 105.1 113.3 138.9 178.9 950 77.9 106.0 114.0 139.2 179.2 960 78.7 106.9 114.7 139.5 179.5 970 79.6 107.8 115.5 139.8 179.8 980 80.4 108.7 116.2 140.1 180.1 990 81.2 109.6 116.9 140.5 180.5 1000 82.0 110.4 117.6 140.8 180.8 1010 82.7 111.3 118.2 141.1 181.1 1020 .83.5 112.1 118.9 141.4 181.4 1030 84.3 112.9 119.6 141.7 181.7 1035 84.6 113.3 119.9 141.8 181.8 15

NEDO-33785 Revision 0 UPPER RPV & UPPER RPV S BOTTOM BOTTOM LIMITING BELTLINE AT BELTLINE A]

PRESSURE HEAD) HEAD 24 EFPY 24 EFPY 24 EFPY (PSIG) ~CURVE A CURVE A CURVE B CURVE B CURVE C (OF) (OF) (OF)

(OF) (OF) 1040 85.0 113.7 120.2 142.0 182.0 1050 85.7 114.5 120.9 142.3 182.3 1055 86.1 114.9 121.2 142.4 182.4 1060 86.4 115.3 121.5 142.6 182.6 1070 87.2 116.0 122.1 142.9 182.9 1080 87.9 116.8 122.8 143.2 183.2 1090 88.6 117.5 123.4 143.5 183.5 1100 89.2 118.3 124.0 143.8 183.8 1105 89.6 118.6 124.3 143.9 183.9 1110 89.9 119.0 124.6 144.1 184.1 1120 90.6 119.7 125.2 144.4 184.4 1130 91.2 120.4 125.8 144.6 184.6 1140 91.9 121.1 126.3 144.9 184.9 1150 92.5 121.8 126.9 145.2 185.2 1160 93.1 122.4 127.5 145.5 185.5 1170 93.8 123.1 128.0 145.8 185.8 1180 94.4 123.7 128.6 146.1 186.1 1190 95.0 124.4 129.1 146.4 186.4 1200 95.6 125.0 129.7 146.6 186.6 1210 96.2 125.7 130.2 146.9 186.9 1220 96.8 126.3 130.8 147.2 187.2 1230 97.3 126.9 131.3 147.5 187.5 1240 97.9 127.5 131.8 147.8 187.8 1250 98.5 128.1 132.3 148.0 188.0 1260 99.0 128.7 132.8 148.3 188.3 1270 99.6 129.3 133.3 148.6 188.6 1280 100.1 129.8 133.8 148.8 188.8 1290 100.7 130.4 134.3 149.1 189.1 1300 101.2 131.0 134.8 149.4 189.4 1310 101.7 131.5 135.3 149.7 189.7 1320 102.3 132.1 135.8 149.9 189.9 1330 102.8 132.6 136.2 150.2 190.2 1340 103.3 133.2 136.7 150.5 190.5 1350 103.8 133.7 137.2 150.7 190.7 1360 104.3 134.2 137.6 151.0 191.0 1370 104.8 134.8 138.1 151.2 191.2 16

NEDO-33785 Revision 0 UPPER RPV & UPPER RPV &

BOTTOM- BOTTOM LIMITING PRESSURE HEAD BELTLINE AT BELTLINEyAT HEAD 24 EFPY 24 EFPY~ 24 EFPY (PSIG) CURVE A CURVEB CURVE C CURVE A CURVE B (OF) (OF) (OF) 4(OF) (OF) 1380 105.3 135.3 138.5 151.5 191.5 1390 105.8 135.8 139.0 151.8 191.8 1400 106.3 136.3 139.4 152.0 192.0 17

NEDO-33785 Revision 0 Table 2 Fermi 2 Tabulation of Curves - 32 EFPY UPPER RPV & UPPER RPV &

BE.T...E.AT LIMITING BOTTOM BOTTOM>

BOTTOM BELTLINE AT D BELTLINE AT PRESSURE HEAD HEAD 32EFPV 32 EFPY CURE2 CREPB (PSIG) CURVE A CURVE A CURVE C (OF (F) (OF (F) (OF) 0 68.0 72.0 68.0 72.0 72.0 10 68.0 72.0 68.0 72.0 72.0 20 68.0 72.0 68.0 72.0 72.0 30 68.0 72.0 68.0 72.0 72.0 40 68.0 72.0 68.0 72.0 72.0 50 68.0 72.0 68.0 72.0 72.0 60 68.0 72.0 68.0 72.0 72.0 70 68.0 72.0 68.0 72.0 72.2 80 68.0 72.0 68.0 72.0 78.2 90 68.0 72.0 68.0 72.0 83.3 100 68.0 72.0 68.0 72.0 87.8 110 68.0 72.0 68.0 72.0 91.9 120 68.0 72.0 68.0 72.0 95.7 130 68.0 72.0 68.0 72.0 99.2 140 68.0 72.0 68.0 72.0 102.4 150 68.0 72.0 68.0 72.0 105.2 160 68.0 72.0 68.0 72.0 107.9 170 68.0 72.0 68.0 72.0 110.5 180 68.0 72.0 68.0 72.9 112.9 190 68.0 72.0 68.0 75.2 115.2 200 68.0 72.0 68.0 77.3 117.3 210 68.0 72.0 68.0 79.3 119.3 220 68.0 72.0 68.0 81.3 121.3 230 68.0 72.0 68.0 83.1 123.1 240 68.0 72.0 68.0 84.9 124.9 250 68.0 72.0 68.0 86.6 126.6 260 68.0 72.0 68.0 88.2 128.2 270 68.0 72.0 68.0 89.8 129.8 280 68.0 72.0 68.0 91.3 131.3 290 68.0 72.0 68.0 92.8 132.8 300 68.0 72.0 68.0 94.2 134.2 310 68.0 72.0 68.0 95.5 135.5 312.5 68.0 72.0 68.0 95.9 135.9 312.5 68.0 102.0 68.0 132.0 172.0 18

NEDO-33785 Revision 0 UPPER RPV & UP~PER RPV &

BOTTOM BLLNAT BOTTOM BL INAT LIMITING PRESSURE HEAD B 2ELTINYA HEAD B 2ELTINYA 32 EFPY (PSIG) CURVE A ~,CREA CREBCURVEB CURVEC 320 68.0 102.0 68.0 132.0 172.0 330 68.0 102.0 68.0 132.0 172.0 340 68.0 102.0 68.0 132.0 172.0 350 68.0 102.0 68.0 132.0 172.0 360 68.0 102.0 68.0 132.0 172.0 370 68.0 102.0 68.0 132.0 172.0 380 68.0 102.0 68.0 132.0 172.0 390 68.0 102.0 68.0 132.0 172.0 400 68.0 102.0 68.0 132.0 172.0 410 68.0 102.0 68.0 132.0 172.0 420 68.0 102.0 68.0 132.0 172.0 430 68.0 102.0 68.0 132.0 172.0 440 68.0 102.0 68.0 132.0 172.0 450 68.0 102.0 68.0 132.0 172.0 460 68.0 102.0 68.0 132.0 172.0 470 68.0 102.0 68.0 132.0 172.0 480 68.0 102.0 68.0 132.0 172.0 490 68.0 102.0 68.0 132.0 172.0 500 68.0 102.0 68.0 132.0 172.0 510 68.0 102.0 68.0 132.0 172.0 520 68.0 102.0 68.0 132.0 172.0 530 68.0 102.0 68.0 132.0 172.0 540 68.0 102.0 68.0 132.0 172.0 550 68.0 102.0 69.5 132.0 172.0 560 68.0 102.0 71.3 132.0 172.0 570 68.0 102.0 73.0 132.0 172.0 580 68.0 102.0 74.6 132.0 172.0 590 68.0 102.0 76.2 132.1 172.1 600 68.0 102.0 77.8 132.9 172.9 610 68.0 102.0 79.3 133.3 173.3 620 68.0 102.0 80.7 133.7 173.7 630 68.0 102.0 82.1 134.1 174.1 640 68.0 102.0 83.5 134.4 174.4 650 68.0 102.0 84.8 134.8 174.8 660 68.0 102.0 86.1 135.2 175.2 670 68.0 102.0 87.4 135.6 175.6 19

NEDO-33785 Revision 0

- i ;BOT*TOM UPPER RPV &

.. :"*: BOTTOM', UPPER ':'RPV & LIVI ITI.....NU PRESURE EAD BELTLINE AT BELTLINE AT 32EP (PSIG) CURVE A CURVE B...EFPY CURVE C CURVE A CURVE B (...

(*F) (F) (OF) 680 68.0 102.0 88.7 135.9 175.9 690 68.0 102.0 89.9 136.3 176.3 700 68.0 102.0 91.0 136.7 176.7 710 68.0 102.0 92.2 137.0 177.0 720 68.0 102.0 93.3 137.4 177.4 730 68.0 102.0 94.4 137.8 177.8 740 68.0 102.0 95.5 138.1 178.1 750 68.0 102.0 96.6 138.5 178.5 760 68.0 102.0 97.6 138.8 178.8 770 68.0 102.0 98.6 139.2 179.2 780 68.0 102.0 99.6 139.5 179.5 790 68.0 102.0 100.6 139.9 179.9 800 68.0 102.0 101.5 140.2 180.2 810 68.0 102.0 102.5 140.6 180.6 820 68.0 102.0 103.4 140.9 180.9 830 68.0 102.0 104.3 141.3 181.3 840 68.0 102.0 105.2 141.6 181.6 850 68.6 102.8 106.0 141.9 181.9 860 69.6 103.9 106.9 142.3 182.3 870 70.6 105.0 107.7 142.6 182.6 880 71.5 106.1 108.6 142.9 182.9 890 72.5 107.2 109.4 143.3 183.3 900 73.4 108.2 110.2 143.6 183.6 910 74.4 109.2 111.0 143.9 183.9 920 75.3 110.2 111.7 144.2 184.2 930 76.1 111.1 112.5 144.6 184.6 940 77.0 112.1 113.3 144.9 184.9 950 77.9 113.0 114.0 145.2 185.2 960 78.7 113.9 114.7 145.5 185.5 970 79.6 114.8 115.5 145.8 185.8 980 80.4 115.7 116.2 146.1 186.1 990 81.2 116.6 116.9 146.5 186.5 1000 82.0 117.4 117.6 146.8 186.8 1010 82.7 118.3 118.2 147.1 187.1 1020 83.5 119.1 118.9 147.4 187.4 1030 84.3 119.9 119.6 147.7 187.7 20

NEDO-33785 Revision 0 UPPER RPV & UPPER RPV &

BOTTOM BOTTOM LIMITING BELTLINE AT BELTLINE AT PRESSURE HEAD HEAD 32 EFPY 32 EFPY 32EFPY (PSIG) CURVE A CURVE B CURVE C CURVE A (OF), CURVE B

("F)

(OF) (OF) 1035 84.6 120.3 119.9 147.8 187.8 1040 85.0 120.7 120.2 148.0 188.0 1050 85.7 121.5 120.9 148.3 188.3 1055 86.1 121.9 121.2 148.4 188.4 1060 86.4 122.3 121.5 148.6 188.6 1070 87.2 123.0 122.1 148.9 188.9 1080 87.9 123.8 122.8 149.2 189.2 1090 88.6 124.5 123.4 149.5 189.5 1100 89.2 125.3 124.0 149.8 189.8 1105 89.6 125.6 124.3 149.9 189.9 1110 89.9 126.0 124.6 150.1 190.1 1120 90.6 126.7 125.2 150.4 190.4 1130 91.2 127.4 125.8 150.6 190.6 1140 91.9 128.1 126.3 150.9 190.9 1150 92.5 128.8 126.9 151.2 191.2 1160 93.1 129.4 127.5 151.5 191.5 1170 93.8 130.1 128.0 151.8 191.8 1180 94.4 130.7 128.6 152.1 192.1 1190 95.0 131.4 129.1 152.6 192.6 1200 95.6 132.0 129.7 153.1 193.1 1210 96.2 132.7 130.2 153.6 193.6 1220 96.8 133.3 130.8 154.1 194.1 1230 97.3 133.9 131.3 154.6 194.6 1240 97.9 134.5 131.8 155.1 195.1 1250 98.5 135.1 132.3 155.6 195.6 1260 99.0 135.7 132.8 156.0 196.0 1270 99.6 136.3 133.3 156.5 196.5 1280 100.1 136.8 133.8 157.0 197.0 1290 100.7 137.4 134.3 157.4 197.4 1300 101.2 138.0 134.8 157.9 197.9 1310 101.7 138.5 135.3 158.3 198.3 1320 102.3 139.1 135.8 158.8 198.8 1330 102.8 139.6 136.2 159.2 199.2 1340 103.3 140.2 136.7 159.7 199.7 1350 103.8 140.7 137.2 160.1 200.1 1360 104.3 141.2 137.6 160.5 200.5 21

NEDO-33785 Revision 0 BOTTOM uPPER RPV &

BOTTOM UPPL~R RPV &

RV&UPPER LIMITING LINE AT HEAD

~RI~I.1'LD4 ATBELTLINE AT 32 EFPY PRESSURE > HEAD 32 EFPY EFPY32 EFPY (PSIG), CURVE A C RVE A CURVE B CURVE C

~RVE ACURVE B (OF) C (OF)

(0D (OF) (OF) 1370 104.8 141.8 138.1 161.0 201.0 1380 105.3 142.3 138.5 161.4 201.4 1390 105.8 142.8 139.0 161.8 201.8 1400 106.3 143.3 139.4 162.2 202.2 22

NEDO-33785 Revision 0 Appendix A Reactor Vessel Material Surveillance Program In accordance with 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, the first surveillance capsule was removed from the Fermi 2 reactor vessel after Cycle 7, during refueling outage (RFO) 7 in April 2000. This capsule was placed in the Spent Fuel Pool and has not been tested. The surveillance capsule contains flux wires for neutron fluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel materials within the core beltline region.

As described in the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Section 4.2.6, Inspection and Testing, the BWRVIP ISP will determine the removal schedule for the remaining Fermi 2 surveillance capsules. The Fermi 2 material surveillance program is administered in accordance with the BWRVIP ISP. The ISP combines the US BWR surveillance programs into a single integrated program. This program uses similar heats of materials in the surveillance programs of BWRs to represent the limiting materials in other vessels. It also adds data from the BWR Supplemental Surveillance Program (SSP). Per the BWRVIP ISP, Fermi 2 is not a host plant; all surveillance capsules are classified as "Deferred".

A-1

NEDO-33785 Revision 0 Appendix B Fermi 2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information B-1

NEDO-33785 Revision 0 TOP HEAD TOP HEAD FLANGE

_I SHELL FLANGE SHELL '94 SHELL 403 TOP OF SHELL #2 ACTIVE iýU~L - ~ AXIAL WELDS (TAF) 366.3" SGIRTH WELD BOTTOM OF SHELL *#

ACTIVE FUEL (BAF) 216.3" BOTTOM HEAD SUPPORT SKIRT

- III - i Figure B-1 Fermi 2 Reactor Pressure Vessel B-2

NEDO-33785 Revision 0 Table B-1 Fermi 2 Initial RTNDT Values for RPV Plate and Flange Materials Test Drop Component Heat Temp Charpy Energy (TsoT- 60) Weight RTNDT (OF) (ft-lb) (OF) NDT (OF)

()(F)

Top Head & Flange Shell Flange G3701 AWH 113 2V-708 10 89 89 90 -20 10 10 Top Head Flange G3702 ACR 108 10 196 191 101 -20 10 10 Top Head Dollar C3732 C5445-1 10 79 86 79 -20 -10 -10 Top Head Lower Torus Plates G3731-1 C5445-2 10 95 91 97 -20 -10 -10 G3731-2 C5445-2 10 97 96 101 -20 -10 -10 Top Head Upper Torus Plates G3730 C5445-1 10 107 85 102 -20 -10 -10 Shell Courses Upper Shell Plates G3703-1 C4568-1 40 68 65 56 10 -10 10 G3703-2 C4564-2 40 64 49 54 12 -10 12 G3703-3 C4560-2 10 53 63 52 -20 -10 -10 G3703-4 C4554-2 40 74 75 87 10 -10 10 Upper Intermediate Plates G3704-1 C4574-1 10 70 68 66 -20 -10 -10 G3704-2 C4578-2 10 59 45 52 -10 -10 -10 G3704-3 C4578-1 10 44 56 68 -8 -10 -8 Lower Intermediate Plates G3703-5 C4564-1 10 60 45 59 -10 -20 -10 G3705-1 B8614-1 10 62 64 56 -20 -20 -20 G3705-2 C4574-2 10 48 49 60 -16 -30 -16 G3705-3 C4568-2 10 46 67 63 -12 -30 -12 Lower Shell Plates G3706-1 C4540-2 10 64 76 74 -20 -10 -10 G3706-2 C4560-1 10 85 79 99 -20 -10 -10 G3706-3 C4554-1 10 59 65 68 -20 -10 -10 Bottom Head Bottom Head Dollar G3708 C3424-1 10 41 48 57 -2 -10 -2 Bottom Head Upper Torus Plates G3711-1 C4526-1 -40 57 60 55 -70 -10 -10 G3712-1 C4504-3 -40 70 64 56 -70 -10 -10 Bottom Head Lower Torus Plates C3709-1 C5050-2 10 58 70 83 -20 -10 -10 C3710-1 C4504-1 10 74 70 74 -20 -10 -10 C3710-2 C4504-2 40 40 48 42 30 10 30 Note: Minimum Charpy values are provided for all materials.

B-3

NEDO-33785 Revision 0 Table B-2 Fermi 2 Initial RTNDT Values for RPV Nozzle Materials Test Drop Heat or Charpy Energy (T5 0T-60) Weight RTNDT Component Heat/Flux/Lot Temp (ft-lb) (OF) NDT (OF)

(OF)

Recirculation Outlet Nozzle G3717-1 AJF 181 10 77 96 59 -20 -20 -20 G3717-2 AJF 193 10 91.5 89 85 -20 -30 -20 Recirculation Inlet Nozzle G3718-1 AV3505 9A-9239 10 54 45 38 4 0 4 G3718-2 AV3505 9A-9240 10 34 32 36 16 -10 16 G3718-3 AV3502 9A-9365 10 35 32 36 16 20 20 G3718-5 AV3503 9A-9368 10 42 36 60 8 -30 8 G3718-6 AV3503 9A-9369 10 49 40 49 0 -30 0 G3718-7 AV3504 9A-9371 10 58 28 37 24 -40 24 G3718-8 AV3857 9D-9407 10 48 32 46 16 20 20 G3718-9 AV3857 9D-9406 10 47 64 58 -14 10 10 G3718-10 AV3857 9D-9408 10 82 46 55 -12 10 10 G5218-4 AV3934 9E-9011 10 47 60 88 -14 40 40 Steam Outlet Nozzle G3714-1 AV3496 9A-9234 10 66 36 85 8 10 10 G3714-2 AV3507 9A-9235 10 74 75 36 8 0 8 G3714-3 AV3510 9A-9236 10 36 34 32 16 10 16 G3714-4 AV3511 9A-9237 10 52 32 42 16 10 16 Feedwater Nozzle G3715-1 AV3508 9A-9228 10 82 91 58 -20 0 0 G3715-2 AV3508 9A-9229 10 68 58 50 -20 0 0 G3715-3 AV3508 9A-9230 10 62 67 76 -20 -30 -20 G3715-4 AV3509 9A-9232 10 60 42 64 -4 -10 -4 G3715-5 AV3509 9A-9231 10 38 54 50 4 0 4 G3715-6 AV3504 9B-9202 10 39 46 34 12 -10 12 Core Spray Nozzle G3720-1 AV2997 9A-9363 10 67 52 96 -20 -10 -10 G3720-2 AV2997 9A-9364 10 70 99 84 -20 -10 -10 Instrumentation Nozzle G3811-1 Q2Q14W 969C-1 10 54 59 73 -20 10 10 G3811-2 Q2Q14W 969C-2 10 54 59 73 -20 10 10 Top Head Vent Nozzle G3810 Q2Q6W 986C 10 92 95 88 -20 10 10 Jet Pump Nozzle G3719-1 EV-9806 8L-9211A 10 99 124 105 -20 -20 -20 G3719-2 EV-9806 8L-9211B 10 99 124 105 -20 -20 -20 CRD HYD Return Nozzle G3716 AV3138 8L-9104 10 42 40 48 0 10 10 Core AP Nozzle Alloy 600 G3738 NX9492 [2]

Replacement Instrument Nozzle [3]

G3806 2127273 10 36 43 30 20 30 30 G3806R 6397860 10 250 230 247 -20 30 30 B-4

NEDO-33785 Revision 0 High Pressure Leak Detector Nozzle G4546 10 [1]

Drain Nozzle G3739 Q1Q1VW 738T 10 39 25 32 30 40 40 CRD Stub Tube G3736-1 through -5 Alloy 600 [21 (1) Information for this heat is not available; the purchase specification requirement are used for evaluation of this component.

(2) Alloy 600 components do not require fracture toughness evaluation.

(3) Dropweight data was not available; therefore NRC MTEB 5-2 was applied for the determination of dropweight.

Notes: Minimum Charpy values are provided for all materials.

The Replacement Instrument nozzle material data was reviewed; it was found that the previously reported value of 40'F was unnecessarily conservative, and has been reduced to a maximum of 307F.

B-5

NEDO-33785 Revision 0 Table B-3 Fermi 2 Initial RTNDT Values for RPV Weld Materials Test Drop Charpy Energy, TS0T-60) Weight RTNDT Component Heat or Heat/Flux/Lot

' ... Temp * ... (ft-lb) (OF) N.

NDT (OF)

(OF) (OF)-

Beltline-Axial Lower Shell 13253 Linde 1092 2-307 A, B, C Lot3833 10 79 79 82 -50 -50 12008 Linde 1092 Lot3878 10 62 47 62 -44 -44 Lower-Intermediate Shell 33A277 Linde 124 15-308 A, B, C, D Lot 3878 10 83 94 87 -50 -50 Beltline-Girth Lower-Intermediate Shell 10137 Linde 0091 1-313 Lot 3999 10 101 108 107 -50 -50 Non-Beltline-Axial Upper-Intermediate Shell 20291 & 12008 Linde 1092 2-308 A through C Lot3833 10 62 47 62 -44 - -44 HADH 10 112 110 114 -50 - -50 EOAG 10 173 133 135 -50 - -50 Upper Shell 1-308 A through D 34B009 Linde 124 Lot 3687 10 55 65 57 -50 - -50 34B009 Linde 124 Lot 3688 10 69 70 63 -50 - -50 Bottom Head Upper Torus Meridional Welds 1-306 A through K HADH 10 112 110 114 -50 - -50 Bottom Head Lower Torus Meridional Welds 2-306 A through G LACH-2 10 125 119 119 -50 - -50 HADH 10 112 110 114 -50 - -50 Top Head Upper Torus Meridional Welds 2-319 A through E EOEJ 10 136 170 150 -50 - -50 Top Head Lower Torus Meridional Welds 1-319 A through H DOAJ 10 166 146 158 -50 - -50 AOFJ 10 112 105 115 -50 - -50 EOEJ 10 136 170 150 -50 - -50 Non-Beltline-Girth Top Head Assembly 3-319, 4-319, 5-319 33A277 Linde 0091 Lot 3977 10 111 106 113 -50 - -50 90099 Linde 0091 Lot 3977 10 56 30 52 -10 - -10 Shell Flange to Upper Shell 13-308 21935 Linde 1092 Lot 3889 10 51 70 74 -50 - -50 Upper Shell to Upper-Intermediate Shell 305424 Linde 1092 4-308-A Lot 3889 10 82 87 92 -50 -50 B-6

NEDO-33785 Revision 0 Drop Test Charpy Energy Tý 5oT60) Weight RTNDT Component Heat or Heat/Flux/Lot Temp (f5-Il) (0 F) NDT (0 F)

(OF) OF DT (oF)) (F

((OF)

Upper-Intermediate Shell to Lower-Intermediate Shell 1P3571 Linde 1092 Lot 3958 4-308-B Tandem 10 79 68 64 -50 - -50 1P3571 Linde 1092 Lot 3958 Single 10 40 46 46 -30 - -30 Lower Shell to Bottom Head 9-307 90099 Linde 0091 Lot 3977 10 56 30 52 -10 - -10 90136 Linde 0091 Lot 3998 10 110 109 107 -50 - -50 Bottom Head Assembly 1P2809 Linde 1092 3-306, 5-306, 6-306 Lot 3854 10 102 102 103 50 - -50 Support Skirt to Bottom Head 4-309 21935 Linde 1092 Lot 3869 10 62 59 60 -50 - -50 Nozzle Welds Recirculation Outlet LOBI 10 123 104 115 -50 - -50 5-314 A & B CBAI 10 GBAI 10 120 105 128 -50 - -50 Recirculation Inlet 13-314 A through K LOEH 10 113 123 140 -50 - -50 13-314D (Replacement) BBAI 10 97 100 77 -50 - -50 LACH 10 125 119 119 -50 - -50 HOGI 10 91 93 94 -50 - -50 IAGI 10 142 157 170 -50 - -50 Steam Outlet FAGI 10 135 121 136 -50 - -50 8-316 A through D LACH 10 125 119 119 -50 - -50 Feedwater Nozzle FACI 10 4-316 A through F HOGI 10 91 93 94 -50 - -50 LOEH 10 113 123 140 -50 - -50 COFI 10 96 97 89 -50 - -50 Core Spray Nozzles IAGI 10 142 157 170 -50 - -50 14-316 A & B BBAI 10 97 100 77 -50 - -50 Top Head Instrument Nozzle 14-318 A & B ABEA 10 BOIA 10 99 110 113 -50 - -50 Top Head Vent Nozzle ABEA 10 2-318 BOIA 10 99 110 113 -50 - -50 Jet Pump Nozzle LACH 10 125 119 119 -50 - -50 19-314 A & B LOEH 10 113 123 140 -50 - -50 CRD HYD Return Nozzle 15-315 IAGI 10 142 157 170 -50 - -50 Core AP Nozzle 9-315 Inconel 182 Instrument Nozzles 4-315 A through F Inconel 182 Drain Nozzle 17-315 CAFJ 10 85 101 108 -50 -50 Stub Tubes 1-310 Inconel 182 B-7

NEDO-33785 Revision 0 Test Drop, CmoetHeat~ or Heat/Flux/Lot Temp Charpy Energy T5o1-60) Weight RTNDT Compne) (ft-lb) (OF) NDT (OF)

(OF)

Appurtenance Welds Stabilizer Brackets ICJJ 10 121 120 128 -50 - -50 10-324 A through H DBIJ 10 129 117 122 -50 - -50 HOCJ 10 165 174 140 -50 - -50 GBCJ 10 126 143 121 -50 - -50 Steam Dryer Hold Down Brackets to Top Head 10-319 KAHJ 10 108 116 107 -50 - -50 Basin Seal Skirt 6-324 A through D IBEJ 10 160 151 145 -50 - -50 LOAJ 10 152 125 104 -50 - -50 7-324 A through D; 8-324 HOKJ 10 110 177 154 -50 - -50 KACJ 10 102 81 108 -50 - -50 Thermocouple Pads 1-325 GBJJ 10 203 160 239 -50 - -50 2-325 COEJ 10 129 95 81 -50 - -50 3-325; 4-325; 6-325 FCJJ 10 180 224 171 -50 - -50 BBJJ 10 107 102 53 -50 - -50 COCA 10 120 139 137 -50 - -50 HOKJ 10 110 177 154 -50 - -50 FOIA 10 182 224 218 -50 - -50 7-325; 8-325 BOLH 10 159 138 123 -50 - -50 Top Head Lifting Lugs GBCJ 10 126 143 121 -50 - -50 8-319 A through D DBIJ 10 129 117 122 -50 - -50 Note: Minimum Charpy values are provided for all materials.

B-8

NEDO-33785 Revision 0 Table B-4 Fermi 2 Initial RTNDT Values for RPV Appurtenance and Bolting Materials Drop Test (T50r-60) Weight RTNDT Components : Heat (*F Temp Charpy:: Energy

' (ft-lb) ;:*: ( (OF) 0

6) " NDT NDt : RTND (OF)

(OF)OF Misc Appurtences Support Skirt Forging S8530 AHC 178 10 81 100 102 -20 30 30 Shroud Support Alloy 600 G3726 580608-IX (1)

Stabilizer Brackets C-6-1 A4516-1 40 58 49 53 12 10 12 C-6-2 C5313-2 10 57 45 52 -10 -30 -10 Guide Rod Brackets G3772 Stainless Steel (1)

Steam Dryer Support Lugs G3775 Stainless Steel Steam Dryer Hold Down Brackets G4871 C2588-2D 10 122 129 107 -20 -20 D5591 C6195-4 10 83 69 61 -20 -20 Core Spray Brackets G3774 Stainless Steel (1)

Basin Seal Skirt G3818 C2588-2B 10(2)

C3819 22A459 10(2)

Surveillance Specimen Brackets G3776 Stainless Steel (1)

G3777 Stainless Steel (1)

Feedwater Sparger Brackets G3773 Stainless Steel (1)

Top Head Lifting Lugs G3732 40 (2)

Test Min Lat LST Components Heat Temp Charpy Energy (ft-lb)

(OF) Exp (mils) (OF)

Closure Studs G3778-1 14677 10 50 50 52 - 70 G3778-2 67156 10 55 54 55 - 70 G3778-3 -3 10 - - - - 70 Closure Nuts G3779-1 48192 10 58 59 54 - 70 G3779-2 (3) 10 - - - - 70 Closure Washers Closure Washers G5252 (3) 10 - 70 Bushings G4853 (3) 10 70 B-9

NEDO-33785 Revision 0 (1) Information for this heat is not available; the purchase specification requirements are used for evaluation of this component.

(2) Alloy 600 and Stainless Steel components do not require fracture toughness evaluation.

(3) Information for this component is not available; ASME code requirements are applied.

Note: Minimum Charpy values are provided for all materials.

B-10

NEDO-33785 Revision 0 Table B-5 Fermi 2 Adjusted Reference Temperatures for up to 24 EFPY Lower-Intermediate Shell Plates, Axial Welds Thickness in inches= 6.125 32 EFPY Peak I.D. fluence= 9.68E+17 n/cm 2 24 EFPY Peak I.D. fluence= 7.26E+17 n/cm 2 2

24 EFPY Peak % T fluence= 5.03E+17 n/cm Water Level Instrumentation Nozzle (o Thickness in inches= 6.125 32 EFPY Peak I.D. fluence= 1.65E+ 17 n/cm2 24 EFPY Peak I.D. fluence= 1.24E+17 n/cm 2 24 EFPY Peak 1/4 T fluence= 8.57E+16 n/cm2 Lower Shell Plates and Axial Welds & Lower to Lower-Intermediate Girth Weld 2 Thickness in inches= 7.125 Axial Distribution Factor at Elevation of Girth Weld= 0.64 32 EFPY Peak I.D. fluence= 6.23E+17 n/cm 24 EFPY Peak I.D. fluence= 4.67E+17 n/cm 2 24 EFPY Peak % T fluence= 3.05E+17 n/cm2 Initial 24 EFPY 24 EFPY 24 EFPY Adjusted 1/4T Fluence Margin n/em 2 0 Component Heat or Heat/Lot %Cu %Ni CF Adjusted ARTNDF , A Margin F Shift A.RT CF.(1) (OF) V FF oF F ýF Plant Specific Chemistries Plates:

Lower Shell G3706-1 C4540-2 0.08 0.62 51 -10 3.05E+17 11 0 6 11 23 13 G3706-2 C4560-1 0.11 0.57 74 -10 3.05E+17 16 0 8 16 33 23 G3706-3 C4554-1 0.12 0.56 82 -10 3.05E+17 18 0 9 18 36 26 Lower-Intermediate Shell G3703-5 C4564-1 0.09 0.55 58 -10 5.03E+17 17 0 9 17 34 24 G3705-1 B8614-1 0.12 0.61 83 -20 5.03E+17 24 0 12 24 49 29 G3705-2 C4574-2 0.10 0.55 65 -16 5.03E+17 19 0 10 19 38 22 G3705-3 C4568-2 0.12 0.61 83 -12 5.03E+17 24 0 12 24 49 37 WELDS:

Lower Shell Axial Tandem 13253, 12008 1092 2-307 A, B, C Lot 3833 0.26 0.87 224 -44 3.05E+17 50 0 25 50 99 55 Lower-Intermediate Shell Axial 15-308 A, B, C, D 33A277, 124 Lot 3878 0.32 0.50 188.5 -50 5.03E+17 55 0 28 55 111 61 Lower to Lower-Intermediate Girth 1-313 10137, 0091 Lot 3999 0.23 1.00 236 -50 3.05E+17 52 0 26 52 105 55 NOZZLES:

N16 (Water Level Instrumentation) 2127273 0.272 0.214 136 30 8.57E+16 13 0 7 13 27 57 N16 (Water Level Instrumentation) 6397860 0.272 0.214 136 30 8.57E+16 13 0 7 13 27 57 B-11

NEDO-33785 Revision 0 N16 Weld Inconel (2)

INTEGRATED SURVEILLANCE PROGRAM ():

BWRVIP-135 R1 Plate (4) C4114-2 0.12 0.69 84 -12 5.03E+17 25 0 12 25 49 37 Weld (5) CE-2(WM)(13253, 12008) 0.21 0.86 207 351 -44 3.05E+17 78 0 28 28 106 62 (1) Adjusted CF calculated per RG 1.99 Position 2.1.

(2) Non-ferritic materials such as Inconel do not require fracture toughness evaluation.

(3) Procedures defined in RG 1.99 are applied to determine the ART considering the ISP.

(4) The ISP plate is not the identical heat and is presented using the ISP chemistry and CF and applied to the limiting Fermi 2 plate, which is Heat C4568-2.

ISP indicates that C4554-1 is also a limiting plate, however due to the reduced fluence at the lower shell, this material is no longer limiting.

(5) The ISP weld is the identical heat and is presented using the ISP chemistry and adjusted CF with the vessel weld Initial RTNDT and fluence. cA is presented as calculated, but multiplied by 0.5 for the Margin calculation as defined in RG 1.99, Position 2.1.

(6) Fluence for this nozzle considers TPO beyond RFOI16, and does not include operation at EPU conditions.

B-12

NEDO-33785 Revision 0 Table B-6 Fermi 2 Adjusted Reference Temperatures for up to 32 EFPY Lower-Intermediate Shell Plates, Axial Welds 2

32 EFPY Peak I.D. fluence= 9.68E+17 n/cm Thickness in inches= 6.125 2 32 EFPY Peak 1/4 T fluence= 6.70E+17 n/cm Water Level Instrumentation Nozzle (6) 2 32 EFPY Peak I.D. fluence= 1.65E+17 n/cm Thickness in inches= 6.125 2

32 EFPY Peak 1/4 T fluence= 1.14E+17 n/cm Lower Shell Plates and Axial Welds & Lower to Lower-Intermediate Girth Weld 2

Thickness in inches= 7.125 Axial Distribution Factor at Elevation of Girth Weld= 0.64 32 EFPY Peak I.D. fluence= 6.23E+17 n/cm 2

32 EFPY Peak 1/4 T fluence= 4.06E+17 n/cm Adjusted T Fluence 1/4nta 32EFPY in 32 EFPY' 32 EFPY Heat or Heat/Lot, . %Cu %Ni CF RTNDT n/m ARTNOT Gj Mr 0 gs Shift ART Component ..... CF(1) : n/m :: 0 F

('F) F I: O OF OF Plant Specific Chemistries Plates:

Lower Shell G3706-1 C4540-2 0.08 0.62 51 -10 4.06E+17 13 0 7 13 27 17 G3706-2 C4540-1 0.11 0.57 74 -10 4.06E+17 19 0 10 19 38 28 G3706-3 C4554-1 0.12 0.56 82 -10 4.06E+17 21 0 11 21 43 33 Lower-Intermediate Shell G3703-5 C4564-1 0.09 0.55 58 -10 6.70E+17 20 0 10 20 40 30 G3705-1 B8614-1 0.12 0.61 83 -20 6.70E+17 28 0 14 28 57 37 G3705-2 C4574-2 0.10 0.55 65 -16 6.70E+17 22 0 11 22 44 28 G3705-3 C4568-2 0.12 0.61 83 -12 6.70E+17 28 0 14 28 57 45 WELDS:

Lower Shell Axial Tandem 13253, 12008 1092 2-307 A, B, C Lot3833 0.26 0.87 224 -44 4.06E+17 59 0 28 56 115 71 Lower-Intermediate Shell Axial 15-308 A, B, C, D 33A277, 124 Lot 3878 0.32 0.50 188.5 -50 6.70E+17 64 0 28 56 120 70 Lower to Lower-Intermediate Girth 1-313 10137, 0091 Lot 3999 0.23 1.00 236 -50 4.06E+17 62 0 28 56 118 68 NOZZLES:

N16 (Water Level Instrumentation) 2127273 0.272 0.214 136 30 1.14E+17 16 0 8 16 33 63 N16 (Water Level Instrumentation) 6397860 0.272 0.214 136 30 1.14E+17 16 0 8 16 33 63 N16 Weld Inconel (2)

INTEGRATED SURVEILLANCE PROGRAM (3):

B-13

NEDO-33785 Revision 0 BWRVIP-135 RI 4

Plate o C4114-2 0.12 0.69 84 -12 6.70E+17 29 0 14 29 57 45 Weld (5 CE-2(WM)(13253, 12008) 0.21 0.86 207 351 -44 4.06E+17 92 0 28 28 120 76 (1) Adjusted CF calculated per RG 1.99 Position 2.1.

(2) Non-ferritic materials such as Inconel do not require fracture toughness evaluation.

(3) Procedures defined in RG 1.99 are applied to determine the ART considering the ISP.

(4) The ISP plate is not the identical heat and is presented using the ISP chemistry and CF and applied to the limiting Fermi 2 plate, which is Heat C4568-2.

ISP indicates that C4554-1 is also a limiting plate, however due to the reduced fluence at the lower shell, this material is no longer limiting.

(5) The ISP weld is the identical heat and is presented using the ISP chemistry and adjusted CF with the vessel weld Initial RTNDT and fluence. aA is presented as calculated, but multiplied by 0.5 for the Margin calculation as defined in RG 1.99, Position 2.1.

(6) Fluence for this nozzle considers TPO beyond RFO 16, and does not include operation at EPU conditions.

B-14

NEDO-33785 Revision 0 Table B-7 Fermi 2 RPV Beltline P-T Curve Input Values for 32 EFPY A =-44 +121+/-+5=82"F.

(Based on ART value, .which -is

- - ' - - conservative by 1PF, ind an adjustment Adjusted RTNoT Initial RTNDT + Shift of' 5F t u tectio of the existing Flaw #124 in the axial weld of Shell Ring #2; see Section: 3.0 for details.)

Vessel Height H = 861.6 inches Bottom of Active Fuel Height B = 216.3 inches Vessel Radius (to base metal) R = 127 inches Minimum Vessel Thickness (without clad) t = 6.125 inches Note: The ART for 24 EFPY is 62°F as shown in Table B-5. Flaw #124 is protected by adjusting the ART value by 13'F as noted in Section 3.0.

B-15

NEDO-33785 Revision 0 1

Table B-8 Fermi 2 Definition of RPV Beltline RegionO)

Elevation Component (inches from

___________________________________________ R-PV "0")

Shell # 2 - Top of Active Fuel (TAF) 366.3 Shell # 1 - Bottom of Active Fuel (BAF) 216.3 Shell # 2 - Top of Extended Beltline Region (32 EFPY) 374.7 Shell # 1 - Bottom of Extended Beltline Region (32 EFPY) 210.5 Circumferential Weld Between Shell #1 and Shell #2 244.5 Centerline of Recirculation Outlet Nozzle in Shell # 1 161.5 Top of Recirculation Outlet Nozzle NI in Shell # 1 193.7 Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0 Top of Recirculation Inlet Nozzle N2 in Shell # 1 197.5 Centerline of Water Level Instrumentation Nozzle in Shell # 2 366.0 Bottom of Water Level Instrumentation Nozzle in Shell # 2 364.8 (1) The beltline region is defined as any location where the peak neutron fluence is expected to exceed or equal 1.0el7 n/cm 2 .

Based on the above, it is concluded that none of the Fermi 2 reactor vessel plates, nozzles, or welds, other than those included in the Adjusted Reference Temperature Table, are in the beltline region.

B-16

NEDO-33785 Revision 0 Appendix C Fermi 2 Reactor Pressure Vessel P-T Curve Checklist C-I

NEDO-33785 Revision 0 Table C-1 provides a checklist that defines pertinent points of interest regarding the methods and information used in developing the Fermi 2 Pressure-Temperature Limits Report. This table demonstrates that all important parameters have been addressed in accordance with the P-T curve LTR (Reference 6.2), and includes comments, resolutions, and clarifications as necessary.

Table C-1 Fermi 2 Checklist Parameter Completed Comments/Resolutions/Clarifications Initial RTNDT Initial RTNDT has been determined for Z The N 16 water level instrumentation Fermi 2 for all vessel materials including nozzle is considered within the beltline plates, flanges, forgings, studs, nuts, bolts, region. This forging was fabricated welds. from SA508 Class 1 carbon steel.

Additional details regarding this material Include explanation (including and its properties are provided in Section methods/sources) of any exceptions, 3.0 of this PTLR.

resolution of discrepant data (e.g.,

deviation from originally reported values). All other information remains unchanged from previous submittals.

Appendix B contains tables of all Initial RTNDT values for Fermi 2.

Has any non-Fermi 2 initial RTNDT Plate heat C4114-2 information was information (e.g., ISP, comparison to other obtained from the ISP database. This plant) been used? material is not the identical heat to the target vessel plate material and, in accordance with the ISP guidance; this data was not used in determining the limiting ART.

If deviation from the P-T curve LTR Details regarding the determination of process occurred, sufficient supporting the initial RTNDT of the N 16 nozzle is information has been included (e.g., provided in Section 3.0 of this PTLR.

Charpy V-Notch data used to determine an Initial RTNDT). No other deviations from the P-T curve LTR process.

C-2

NEDO-33785 Revision 0 Table C-1 Fermi 2 Checklist, Continued Parameter Completed Comments/Resolutions/Clarifications All previously published Initial RTNDT RVID was reviewed for the beltline values from sources such as the GL88-01, materials; all initial RTNDT values agree; Reactor Vessel Integrity Database (RVID), no further review was performed FSAR, etc., have been reviewed.

Adjusted Reference Temperature (ART)

Sigma I (al, standard deviation for Initial Z Sigma I is equal to 0 for all materials.

RTNDT) is 0°F unless the RTNDT was obtained from a source other than CMTRs.

If al is not equal to 0, reference/basis has been provided.

Sigma A (aA, standard deviation for [

ARTNDT) is determined per RG 1.99, Rev. 2 Chemistry has been determined for all Z Sufficient information was not available vessel beltline materials including plates, to determine the chemistry content for forgings (if applicable), and welds for the N 16 water level instrumentation Fermi 2. nozzle materials. BWR fleet data was obtained and %Cu and %Ni were Include explanation (including determined using Mean + l. More methods/sources) of any exceptions, information is provided in Section 3.0 of resolution of discrepant data (e.g., this PTLR.

deviation from originally reported values).

No deviations from previously reported values.

Non-Fermi 2 chemistry information (e.g., Z Plate heat C4114-2 and weld heat ISP, comparison to other plant) used has 13253/12008 have been evaluated using been adequately defined and described. best estimate chemistry from the ISP.

For any deviation from the P-T curve LTR Z No deviations from the P-T curve LTR process, sufficient information has been process.

included.

All previously published chemistry values Z RVID was reviewed; all initial RTNDT from sources such as the GL88-01, Reactor values agree; no further review was Vessel Integrity Database (RVID), FSAR, performed etc., have been reviewed.

The fluence used for determination of ART Z and any extended beltline region was obtained using an NRC-approved methodology.

C-3

NEDO-33785 Revision 0 Table C-1 Fermi 2 Checklist, Continued

:: :,:* Param eter . : : : ::** ...

P eCompleted CommentsfResolutions/Clarifications The fluence calculation provides an axial distribution to allow determination of the vessel elevations that experience fluence of 1.0e17 n/cm 2 both above and below active fuel.

The fluence calculation provides an axial distribution to allow determination of the fluence for intermediate locations such as the beltline girth weld (if applicable) or for any nozzles within the beltline region.

All materials within the elevation range where the vessel experiences a fluence

>l.0el7 n/cm 2 have been included in the ART calculation. All initial RTNDT and chemistry information is available or explained.

Discontinuities The discontinuity comparison has been performed as described in Section 4.3.2.1 of the P-T curve LTR. Any deviations have been explained.

Discontinuities requiring additional components (such as nozzles) to be considered part of the beltline have been adequately described. It is clear which curve is used to bound each discontinuity.

Appendix G of the P-T curve LTR The thickness discontinuity evaluation describes the process for considering a demonstrated that no additional thickness discontinuity, both beltline and adjustment is required; the curves bound non-beltline. If there is a discontinuity in the discontinuity stresses.

the Fermi 2 vessel that requires such an evaluation, the evaluation was performed.

The affected curve was adjusted to bound the discontinuity, if required.

C-4

NEDO-33785 Revision 0 Appendix H of the P-T curve LTR defines the basis for the CRD Penetration curve discontinuity and the appropriate transient application. The Fermi 2 evaluation bounds the requirements of Appendix H.

Appendix J of the P-T curve LTR defines the basis for the Water Level Instrumentation Nozzle curve discontinuity and the appropriate transient application.

The Fermi 2 evaluation bounds the requirements of Appendix J.

C-5

ML13004A135

Text

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