Text

DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR)
	ML20160A461
Person / Time
Site:	Fermi
Issue date:	06/08/2020
From:	Peter Dietrich; DTE Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML20160A460	List: NRC-20-0009, DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR);
References
	NRC-20-0009 NEDO-33915, Rev. 1
	Download: ML20160A461 (66)
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Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4153 Fax: 734.586.1431 Email: peter.dietrich@dteenergy.com contains Proprietary Information - Withhold Under 10 CFR 2.390.

When separated from Enclosure 2, this document is decontrolled.

Proprietary Information - Withhold Under 10 CFR 2.390 TS 5.6.8 June 8, 2020 NRC-20-0009 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR)

References:

1) NRC Letter to DTE, Fermi 2 - Issuance of Amendment Re: Relocation of Pressure and Temperature Curves to a Pressure Temperature Limits Report (TAC No. MF0446), License Amendment 195, dated February 4, 2014 (ML13346B067)

2) NEDC-33178P-A, GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves, Revision 1, dated June 2009

3) DTE Letter to NRC, License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle, NRC-19-0054, dated November 8, 2019 (ML19312A110)

In Reference 1, the Fermi 2 Technical Specifications (TS) were revised to relocate pressure and temperature limit curves to a Pressure and Temperature Limits Report (PTLR). Requirements for control of the PTLR were added to the Fermi 2 TS in Section 5.6.8. In accordance with TS 5.6.8.c, DTE Electric Company (DTE) transmits a revision of the PTLR to the NRC. The revised PTLR is based on the methodology in Reference 2, as required by TS 5.6.8.b. The PTLR was revised in support of GNF3 new fuel introduction for operating cycle 21 and planned future use of 24-month fuel cycles as requested in Reference 3. The revised PTLR is provided in.

DTE

USNRC NRC-20-0009 Page 2 contains proprietary information as defined by 10 CFR 2.390. GE-Hitachi (GEH) and Electric Power Research Institute (EPRI), as the owners of the proprietary information, have executed the affidavits in Enclosure 1, which identify that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. A non-proprietary version of the documentation in Enclosure 2 is provided in Enclosure 3.

No new commitments are made in this letter.

Should you have any questions or require additional information, please contact Ms. Margaret Offerle, Manager - Nuclear Licensing, at (734) 586-5076.

Sincerely, Senior Vice President and Chief Nuclear Officer

Enclosures:

1) GEH and EPRI Affidavits for NEDC-33915P cc:

2) NEDC-33915P, Revision 1 -PROPRIETARY

3) NEDO-33915, Revision 1 -NON-PROPRIETARY NRC Project Manager NRC Resident Office Regional Administrator, Region III

to NRC-20-0009 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 GEH and EPRI Affidavits for NEDC-33915P

GE-Hitachi Nuclear Energy Americas LLC NEDC-33915P Revision 1 Affidavit Page 1 of 3 AFFIDAVIT I, Michelle P. Catts, state as follows:

(1) I am the Senior Vice President of Regulatory Affairs, GE-Hitachi Nuclear Energy Americas LLC (GEH), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in GEH proprietary report NEDC-33915P, DTE Energy/Enrico Fermi Power Plant Unit 2 Pressure and Temperature Limits Report (PTLR) up to 52 Effective Full-Power Years, Revision 1, dated May 2020.

GEH proprietary information in NEDC-33915P Revision 1 is identified by a dotted underline inside double square brackets. ((This sentence is an example.{3})). GEH proprietary information in figures and large objects is identified by double square brackets before and after the object. In each case, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 U.S.C. §552(b)(4), and the Trade Secrets Act, 18 U.S.C.

§1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).

(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:

a.

Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without a license from GEH constitutes a competitive economic advantage over other companies;

b.

Information that, if used by a competitor, would reduce its expenditure of resources or improve its competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;

c.

Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH;

d.

Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.

GE-Hitachi Nuclear Energy Americas LLC NEDC-33915P Revision 1 Affidavit Page 2 of 3 (5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions for proprietary or confidentiality agreements or both that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary and/or confidentiality agreements.

(8) The information identified in paragraph (2) is classified as proprietary because it contains the detailed GEH methodology for pressure-temperature curve analysis for the GEH Boiling Water Reactor (BWR). These methods, techniques, and data along with their application to the design, modification, and analyses associated with the pressure-temperature curves were achieved at a significant cost to GEH.

The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience databases that constitute a major GEH asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

GE-Hitachi Nuclear Energy Americas LLC NEDC-33915P Revision 1 Affidavit Page 3 of 3 The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without there having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on this 14th day of May 2020.

Michelle P. Catts Senior Vice President of Regulatory Affairs GE-Hitachi Nuclear Energy Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 michelle.catts@ge.com

E ~121 1 ELECTRIC POWER RESEARCH INSTITUTE AFFIDAVIT RE:

Request for Withholding of the Following Proprietary Information Included In:

DTE Energy/Enrico Fermi Power Plant Unit 2, Pressure and Temperature Limits Report (PTLR) up to 52 Effective Full Power Years (EFPY),

NEDC-33915, Revision 1 I, Neil Wilmshurst, being duly sworn, depose and state as follows:

I am the Vice President and Chief Nuclear Officer at Electric Power Research Institute, Inc. whose principal office is located at 3420 Hillview Avenue, Palo Alto, California ("EPRI") and I have been specifically delegated responsibility for the above-listed Report which contains EPRI Proprietary Information that is sought under this Affidavit to be withheld "Proprietary Information". I am authorized to apply to the U.S.

Nuclear Regulatory Commission ("NRC") for the withholding of the Proprietary Information on behalf of EPRI.

EPRI Proprietary Information is identified in the above referenced report with text inside double brackets. Examples of such identification is as follows:

((This sentence is an example{El]l Tables containing EPRI Proprietary Information are identified with double brackets before and after the object. In each case the superscript notation {El refers to this affidavit and all the bases included below, which provide the reasons for the proprietary determination.

EPRI requests that the Proprietary Information be withheld from the public on the following bases:

Withholding Based Upon Privileged And Confidential Trade Secrets Or Commercial Or Financial Information (see e.g. 10 C.F.R. §2.390(a)(4))::

a.

The Proprietary Information is owned by EPRI and has been held in confidence by EPRI. All entities accepting copies of the Proprietary Information do so subject to written agreements imposing an obligation upon the recipient to maintain the confidentiality of the Proprietary Information. The Proprietary Information is disclosed only to parties who agree, in writing, to preserve the confidentiality thereof.

b.

EPRI considers the Proprietary Information contained therein to constitute trade secrets of EPRI. As such, EPRI holds the information in confidence and disclosure thereof is strictly limited to individuals and entities who have agreed, in writing, to maintain the confidentiality of the Information.

c.

The information sought to be withheld is considered to be proprietary for the following reasons. EPRI made a substantial economic investment to develop the Proprietary Information and, by prohibiting public disclosure, EPRI derives an economic benefit in the form of licensing royalties and other additional fees from the confidential nature of the Proprietary Information. If the Proprietary Information were publicly available to consultants and/or other businesses providing services in the electric and/or nuclear power industry, they would be able to use the Proprietary Information for their own commercial benefit and profit and without expending the substantial economic resources required of EPRI to develop the Proprietary Information.

d.

EPRl's classification of the Proprietary Information as trade secrets is justified by the Uniform Trade Secrets Act which California adopted in 1984 and a version of which has been adopted by over forty states. The California Uniform Trade Secrets Act, California Civil Code §§3426 - 3426.11, defines a "trade secret" as follows:

"'Trade secret' means information, including a formula, pattern, compilation, program device, method, technique, or process, that:

( 1) Derives independent economic value, actual or potential, from not being generally known to the public or to other persons who can obtain economic value from its disclosure or use; and (2) Is the subject of efforts that are reasonable under the circumstances to maintain its secrecy."

e.

The Proprietary Information contained therein are not generally known or available to the public. EPRI developed the Information only after making a determination that the Proprietary Information was not available from public sources. EPRI made a substantial investment of both money and employee hours in the development of the Propretary Information. EPRI was required to devote these resources and effort to derive the Proprietary Information. As a result of such effort and cost, both in terms of dollars spent and dedicated employee time, the Proprietary Information is highly valuable to EPRI.

f.

A public disclosure of the Proprietary Information would be highly likely to cause substantial harm to EPRl's competitive position and the ability of EPRI to license the Proprietary Information both domestically and internationally. The Proprietary Information and Report can only be acquired and/or duplicated by others using an equivalent investment of time and effort.

I have read the foregoing and the matters stated herein are true and correct to the best of my knowledge, information and belief. I make this affidavit under penalty of perjury under the laws of the United States of America and under the laws of the State of North Carolina.

Executed at 1300 W WT Harris Blvd, Charlotte, NC being the premises and place of business of Electric Power Research Institute, Inc.

Date: f\\ S -

11 - )o 2--c -

~IJL wr~

Neil Wilmshurst

(State of North Carolina)

(County of Mecklenburg)

to NRC-20-0009 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 NEDO-33915, Revision 1 - NON-PROPRIETARY DTE Energy/Enrico Fermi Power Plant Unit 2 Pressure and Temperature Limits Report (PTLR) up to 52 Effective Full-Power Years

GE Hitachi Nuclear Energy NEDO-33915 Revision 1 May 2020 Non - Proprietary Information DTE Energy/Enrico Fermi Power Plant Unit 2 Pressure and Temperature Limits Report (PTLR) up to 52 Effective Full-Power Years Copyright 2020 GE-Hitachi Nuclear Energy Americas LLC All Rights Reserved

HITACHI

NEDO-33915 Revision 1 Non-Proprietary Information ii

INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33915P, Revision 1, which has the proprietary information removed. Portions of the document that have been removed are indicated by open and closed brackets as shown here (( )).

IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The design, engineering, and other information contained in this document are furnished for the purpose of supporting the Enrico Fermi Power Plant Unit 2 project in proceedings before the United States (US) Nuclear Regulatory Commission (NRC). The only undertakings of GEH with respect to the information in this document are contained in the contract between Detroit Edison Company (DTE) and GEH, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than DTE, or for any purpose other than that for which it is furnished by GEH is not authorized; and with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.

NEDO-33915 Revision 1 Non - Proprietary Information iii Revision Summary Revision Description 0

Initial Issue 1

The ART for the N16 WLI nozzles was revised. The Fermi Unit 2 PTLR has been updated to incorporate the new ART. All changes are identified by revision bars in the right margin. References 6 and 7 are no longer applicable and have been removed. Any instances of N12 were corrected to N16 for the WLI nozzle. Updated reference pointers.

NEDO-33915 Revision 1 Non - Proprietary Information iv Table of Contents Section Page ACRONYMS.............................................................................................................................. vi 1.0 Purpose...................................................................................................................1 2.0 Applicability...........................................................................................................1 3.0 Methodology..........................................................................................................1 4.0 Operating Limits..................................................................................................10 5.0 Discussion............................................................................................................11 6.0 References............................................................................................................12 Appendix A Reactor Vessel Material Surveillance Program...................................................24 Appendix B Fermi 2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information...........................................................................................................25 Appendix C Fermi 2 Reactor Pressure Vessel P-T Curve Checklist........................................37 Appendix D Sample P-T Curve Calculations..........................................................................42 List of Tables Table 1 Fermi 2 Tabulation of Curves - 52 EFPY........................................................... 16 Table B-1 Fermi 2 Initial RTNDT Values for RPV Plate and Flange Materials................. 27 Table B-2 Fermi 2 Initial RTNDT Values for RPV Nozzle Materials................................ 28 Table B-3 Fermi 2 Initial RTNDT Values for RPV Weld Materials...................................... 29 Table B-4 Fermi 2 Initial RTNDT Values for RPV Appurtenance and Bolting Materials.. 31 Table B-5 Fermi 2 Adjusted Reference Temperatures for up to 52 EFPY.......................... 32 Table B-6 Fermi 2 RPV Beltline P-T Curve Input Values for 52 EFPY............................. 35 Table B-7 Fermi 2 Definition of RPV Beltline Region(1)................................................... 36 Table C-1 Fermi 2 Checklist................................................................................................ 38

NEDO-33915 Revision 1 Non - Proprietary Information v

List of Figures Figure 1 - Fermi 2 Composite Curve A (Pressure Test P-T Curves)

Effective for up to 52 EFPY........................................................................................ 13 Figure 2 - Fermi 2 Composite Curve B (Core Not Critical P-T Curves)

Effective for up to 52 EFPY........................................................................................ 14 Figure 3 - Fermi 2 Limiting Curve C (Core Critical P-T Curve)

Effective for up to 52 EFPY........................................................................................ 15 Figure B Schematic of the Fermi 2 RPV Showing Arrangement of Vessel Plates and Welds.................................................................... 26

NEDO-33915 Revision 1 Non - Proprietary Information vi

ACRONYMS Acronym Definition

%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 ASME American Society of Mechanical Engineers BAF Bottom of Active Fuel BTP Branch Technical Position 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 Curve A P-T Curves Applicable to Hydrotest (or Pressure Test) Operation Curve B P-T Curves Applicable to Core Not Critical Operation Curve C P-T Curves Applicable to Core Critical Operation

°F Degree Fahrenheit T

Temperature

NEDO-33915 Revision 1 Non - Proprietary Information vii

Acronym Definition EFPY Effective Full Power Years EPRI Electric Power Research Institute Fermi 2 Enrico Fermi Power Plant 2 FW Feedwater GE General Electric Company GEH GE Hitachi Nuclear Energy GNF3 Global Nuclear Fuel 3 ID Inside Diameter ISP Integrated Surveillance Program KI Stress Intensity Factor KIr Allowable Fracture Toughness LTR Licensing Topical Report MTEB Materials Engineering Branch N16 Water Level Instrumentation Nozzle NFI New Fuel Introduction n/cm2 neutrons per square centimeter (measure of fluence)

NRC (or USNRC)

United States Nuclear Regulatory Commission P/T Pressure/Temperature P-T Pressure-Temperature PTLR Pressure and Temperature Limits Report PVP Pressure Vessels and Piping

NEDO-33915 Revision 1 Non - Proprietary Information viii

Acronym Definition PVRC Pressure Vessel Research Council RCPB Reactor Coolant Pressure Boundary RCS Reactor Coolant System RFO Refueling Outage RG 1.190 Regulatory Guide 1.190 RG 1.99 Regulatory Guide 1.99, Revision 2 RPV Reactor Pressure Vessel RTNDT Reference Temperature of Nil Ductility Transition RVID Reactor Vessel Integrity Database (by NRC) i Standard Deviation on Initial RTNDT Shell #

RPV Shell Ring Number (see Figure B-1)

SSP Supplemental Surveillance Program T

Temperature TAF Top of Active Fuel TS Technical Specification UFSAR Updated Final Safety Analysis Report US United States WLI Water Level Instrumentation WRC Welding Research Council

NEDO-33915 Revision 1 Non - Proprietary Information 1

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 delta temperature (T) requirements during Recirculation Pump startups;

4. RPV bottom head coolant temperature to RPV coolant temperature T 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 52 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 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 1.

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

This PTLR incorporates the following items and changes:

Initial issuance of the PTLR for Global Nuclear Fuel 3 (GNF3) New Fuel Introduction (NFI) and 24-month cycle extension for Fermi 2

NEDO-33915 Revision 1 Non - Proprietary Information 2

Application of GEH Topical Report for Fermi 2 Pressure-Temperature (P-T) Curves Incorporation of new fluence results for 52 EFPY Application of the Integrated Surveillance Program (ISP) testing and analysis results that are applicable to Fermi 2 P-T curves Application of Materials Engineering Branch (MTEB) 5-2 (currently Branch Technical Position (BTP) 5-3) resolution to the N16 water level instrumentation (WLI) forging material 3.1 Chemistry The vessel beltline copper and nickel values were obtained from Fermi 2 plant-specific vessel purchase order records, Certified Material Test Reports (CMTR), or are values previously approved by the NRC, and remain unchanged from previous submittals (Reference 5). Surveillance materials are evaluated using the adjusted chemistry factors obtained from BWRVIP-135 (Reference 3). Best estimate chemistries for other beltline materials were also considered from Reference 3 and however, none were applicable to Fermi 2.

The chemistry factors (CF) for all materials are calculated based upon the requirements of Regulatory Guide 1.99, Revision 2 (RG 1.99, Reference 10).

3.2 Fluence The peak RPV inside diameter (ID) fluence at metal interface between the cladding and the RPV base metal used in the P-T curve evaluation for Fermi 2 at 52 EFPY is 9.92e17 n/cm2. This value was calculated using methods that comply with the guidelines of Regulatory Guide 1.190 (RG 1.190) (Reference 11) as discussed in Reference 1. This fluence applies to the lower-intermediate shell (Shell #2) plates and longitudinal axial (vertical) welds. The fluence at the elevation of girth weld between the lower shell (Shell #1) plate and lower-intermediate shell (Shell #2) is 5.74e17 n/cm2. This fluence also applies to the lower shell plates and longitudinal axial welds. The peak fluence at the bottom of N16 WLI nozzle is 3.59e17 n/cm2.

3.3 Initial Reference Temperature of Nil Ductility Transition (RTNDT)

The method for determining the Initial Reference Temperature of Nil-Ductility Transition (RTNDT) for all vessel materials is that defined in Section 4.1.2 of Reference 2. Initial RTNDT values for all vessel materials considered in developing the P-T curves are presented in tables in Appendix B.

The N16 WLI nozzle is evaluated for ART. As the WLI weld material is Inconel, for which fracture toughness evaluations are not required, only the WLI forging material is evaluated.

The determination of initial RTNDT for WLI forging material which was already submitted

NEDO-33915 Revision 1 Non - Proprietary Information 3

to NRC is summarized as follows. The Combustion Engineering (CE) purchase specification for this material demonstrates a required test temperature of ((` ` ` ` ` ` ` ` )),

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 WLI forging material. Testing for one N16 WLI forging material was performed at ((` ` ` ` ` ` ` ` )), with a minimum result of ((` ` ` ` ` ` ` ` ` ` ` ` ` )) and where the maximum results is ((` ` ` ` ` ` ` ` ` ` ` ` ` ))

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 ((` ` ` ` ` ` ` ` )). Testing for the second N16 material was performed at ((` ` ` ` ` ` ` ` )), but dropweight was not reported. The dropweight was considered to be ((` ` ` ` ` ` ` ` )), consistent with MTEB 5-2 guidance.

Therefore, the initial RTNDT for this heat is the greater of the dropweight (((` ` ` ` ` ` ` ` ))) and

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), shown in Table B-2. The resulting initial RTNDT for this material is ((` ` ` ` ` ` ` ` )).

3.4 Adjusted Reference Temperature (ART)

The ART values for 52 EFPY included in Appendix B are developed considering the latest BWRVIP Integrated Surveillance Program (ISP) published surveillance data available that is representative of the applicable materials in the Fermi 2 RPV (Reference 3). As the ISP plate material, heat C4114-2, is not identical to the target vessel material, the ISP data is not considered in the development of P-T curves. The ISP weld material, heat CE-2 (WM)

(Heat 13253/12008), is identical to the target vessel material (13253/12008). Therefore, the ISP weld data is considered in the development of P-T curves. The CF value for weld is updated with ISP data and used for the determination of ART. This ART is not limiting with respect to the ART.

3.5 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 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 4.

BWRVIP-135 (Reference 3) provides the representative surveillance data considered in determining the chemistry and any fitted or adjusted CFs for the beltline materials for Fermi 2.

Excerpt from Reference 3:

NEDO-33915 Revision 1 Non - Proprietary Information 4

As seen above, the ISP representative plate, heat C4114-2, is not identical to any Fermi 2 vessel beltline plate. Therefore, this ISP data is not used in the development of P-T curves.

For Fermi 2, the ISP representative weld, heat CE-2 (WM) (13253/12008), is the identical heat as the Fermi 2 lower shell axial weld heat (13253/12008). This heat was contained in two (2) BWR Supplemental Surveillance Program (SSP) capsules that have been tested and analyzed. It is noted that the maximum scatter in the fitted data falls within the 1-sigma value of 28°F from RG 1.99. BWRVIP-135 also provides best estimate chemistries that are used in the ART evaluation. The best estimate chemistry for ISP weld heat is defined as 0.21% Cu and 0.86% Ni. The CF from RG 1.99 is 206.6°F (Table CFSurvChem in Equation 1) and the fitted CF is ((323.68°F {E})) (CFFittedData in Equation 1). The Fermi 2 limiting vessel chemistry for this material is 0.26% Cu and 0.87% Ni, from plant-specific CMTRs. Using RG 1.99, the CF is 224.0°F (Table CFVesselChem in Equation 1). As the ISP weld material is identical to the vessel target material, the ART table evaluates the ISP weld material using an adjusted CF and is therefore permitted to reduce the margin term as defined in RG 1.99, Position 2.1.

The CF for a weld material that has more than two (2) data points is determined by calculating an adjusted CF in accordance with RG 1.99. The adjusted CF is determined using the following equation:

(1)

For Fermi 2, the adjusted CF = (224.0°F / 206.6°F) * ((323.68°F = 351°F {E})).

As ((351°F {E}))is greater than 224°F, and the surveillance data is credible, the adjusted CF of ((351°F {E}))is used in the ART evaluation. This material was considered in determining the limiting ART for the P-T curves.

Target Vessel Materials and ISP Representative Materials for Fermi Target Vessel Materials ISP Representative Materials Weld 13253/12008 CE-2(WM) [Heat 13253/12008]

Plate C4554-1, C4568-2 C4114-2 T.., Shift Results for Weld Heat CE-2(WM)

Capsule Cu Ni Fluence

,H..,(°F)

(wt%)

(10" n/cm', E > 1 MeV)

SSP E 17.572 192.7 0.21 0.86 SSP G 19.503 164.9

NEDO-33915 Revision 1 Non - Proprietary Information 5

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 Reference3.

3.6 Beltline Weld Flaw Indications Three (3) flaw indications have been evaluated for the Fermi 2 vessel, occurring at weld 15-308 (axial weld) in the lower-intermediate shell (Shell #2). Flaw #124 requirements bound those of Flaw #127 and Flaw #128. In addition, two (2) welding flaws were detected at weld 1-308 (axial weld) of upper shell (Shell #4) and were determined acceptable as they met the construction code acceptance criteria of ASME Code Section III NB-2500 and NB-5300.

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 52 EFPY, the leak test temperature is calculated to be ((` ` ` ` ` ` ` ` ` ` ` ` ` ` )) at ((` ` ` ` ` ` ` ` ` `

` ` ` )) from Table 1. For these conditions, the allowable fracture toughness (KIr) is ((` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` )) and ((` ` ` ` ` ` ` ` ` ` )) the calculated value of stress intensity factor (KI), which is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). For the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), KIr is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` `

)) and ((` ` ` ` ` ` ` ` ` ` )) the calculated value of KI, which is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). Therefore, the P-T curves bound the calculated values of KI; so, no additional shift of P-T curves is required. Because the calculated values of KI are less than the allowable fracture toughness (KIr), the indication is not expected to become a surface indication during future operation and the indication is acceptable in the as-is condition for operation over 52 EFPY (60 years) considering GNF3 NFI and 24-month cycle extension operating conditions.

3.7 Thickness Discontinuities For Fermi 2, there are four (4) thickness discontinuities in the RPV as follows:

between the bottom head upper and lower torus between the bottom head torus and the support skirt attachment between the bottom head torus and Shell #1 between Shell #1 and Shell #2.

There is also a thickness discontinuity between the top head dollar plate and torus; the P-T limits for the top head are determined considering this continuity in order to ensure that the vessel is adequately protected, or bounded.

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An evaluation was performed for the vessel wall thickness transition discontinuities identified above. The Fermi 2 P-T curves bound the requirements due to the flaws discussed in Section 3.6, and the beltline thickness discontinuities discussed in this Section.

3.8 Pressure-Temperature (P-T) Curves The Fermi 2 P-T curves presented in this PTLR are based upon the GEH methodology accepted by the NRC in Reference 2. Selected explanations are presented below, and Appendix D includes sample calculations demonstrating P-T curve methodology.

The pressure head for the beltline hydrostatic test curve (Curve A) for Fermi 2 is ((` ` ` ` ` ` `

` ` ` ` ` ` )). This is determined using the height of the vessel and the elevation of the bottom of active fuel. The full vessel pressure head is ((` ` ` ` ` ` ` ` ` ` ` )). The pressure combining the internal pressure and pressure head is used for determining KI for the bottom head curve as discussed in Sections 4.3.2.1.1 and 4.3.2.1.2 of Reference 2.

In Reference 2, the P-T curves for the non-beltline region were developed for a ((` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) vessel with a nominal inside diameter of ((` ` ` ` `

` ` ` ` ` ` ` ` ` )). Because the Fermi 2 RPV bottom head geometry is different from a ((` ` ` ` ` ` `

` ` )), it is necessary to confirm that the generic analysis of the ((` ` ` ` ` ` ` ` ` )) applies to Fermi

2. The applicability of generic analysis data to Fermi 2 is shown as follows.

The P-T curve is dependent on the calculated KI value which is proportional to the stress ()

and the crack depth (a) as shown below:

Ka (2)

The stress is proportional to R/t (R = bottom head radius and t = bottom head thickness) and, for the P-T curves, crack depth, a, is t/4. Thus, KI is proportional to R/t. The generic curve value of R/t, based on the generic BWR/6 bottom head dimensions, is:

Generic:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

The Fermi 2-specific bottom head dimensions are R = 127.38 inches and t = 7.38 inches minimum, resulting in:

Fermi 2-specific: R/t 127.38/ 7.38 47in Because the generic value of R/t is ((` ` ` ` ` ` ` ` ` ` )), the generic P-T curve ((` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` )) when applied to the Fermi 2 bottom head.

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

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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 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 temperature 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°F/hr 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. The P-T limits and corresponding heatup/cooldown rates of either Curve A or Curve B may be applied while achieving or recovering from hydrostatic pressure and leak test conditions. Curve A may be used for the hydrostatic pressure and leak test if a coolant heatup and cooldown rate of 20°F/hr is maintained. Otherwise, the limits of Curve B apply when performing the hydrostatic pressure and leak test.

The Fermi 2 P-T curves are based upon an initial RTNDT of ((` ` ` ` ` ` ` ` )) for the bottom head,

((` ` ` ` ` ` ` ` )) for the upper vessel, an ART of ((` ` ` ` ` ` ` ` ` ` )) for the plates and welds, and ((`

` ` ` ` ` ` ` ` ` ` ` ` )) for the N16 WLI nozzle. For Curve B, the N16 WLI nozzle requirements

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) on the beltline limited curves.

For Fermi 2, the N16 WLI nozzle is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) for the beltline region for 52 EFPY. The WLI nozzle is evaluated using the appropriate stresses for the nozzle and shifting the baseline curve by the ART. Using the fluence discussed earlier, the P-T curves are beltline weld limited at all pressures ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) for Curve A. For Curve B, the N16 nozzle requirements are bounding ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

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 2 for the non-beltline and beltline regions, respectively, are applied.

In order to determine how much to shift the baseline non-beltline P-T curves, an evaluation is performed using Tables 4-4a and 4-5a from Reference 2. These tables define ((` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). Each component listed in these tables is evaluated using its plant-specific initial RTNDT. The required temperature is then determined by ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), thereby resulting in the required T for the curve. As the upper vessel curve is initially based on the non-shifted

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), all resulting T values are compared to the ((` ` ` ` ` ` ` `

` ` ` ` ` ` ` )). The difference between the maximum T and ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) is used to shift the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). The same method is applied for the ((` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). In this manner, it is assured that each curve bounds the maximum discontinuity that is represented.

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For the Fermi 2 upper vessel curve, the maximum T value for pressure equal to ((` ` ` ` ` ` ` ` `

` ` ` ` )) from the method described above is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

)). The initial required T-RTNDT for the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )); this is then adjusted by the Fermi 2 specific maximum FW nozzle initial RTNDT of ((` ` ` ` ` ` ` ` )),

resulting in ((` ` ` ` ` ` ` ` ` )). Comparing this to the other components bounded by the upper vessel curve, the limiting value is for the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). The required T-RTNDT for the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), which is added to the limiting ((` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). It is seen that the resulting T required for the ((` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). As ((` ` ` ` ` ` ` ` ` ` ))is limiting, the Fermi 2 upper vessel curve is based on an RTNDT of ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). As noted above, this calculation was performed for each component shown in Table 4-4a of the Reference 2; only the limiting cases are discussed here.

For the Fermi 2 bottom head or CRD hydrotest and core critical curves (Curves A and C, respectively), the maximum T value from the method described above is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). The required T-RTNDT for the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` )); this is adjusted by the Fermi 2 specific maximum ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), resulting in ((` ` ` ` ` ` ` ` ` )). Comparing this to the remaining components represented by the bottom head curve, the required T-RTNDT is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` )), which is added to the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). It is seen that the resulting T required for the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). As ((` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), the Fermi 2 bottom head (CRD) curve is based on an ((` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` )). As noted above, this calculation was performed for each component shown in Table 4-5a of Reference 2; only the limiting case is presented here.

Appendix H of Reference 2 contains the details of an analysis performed to determine the baseline requirement (non-shifted) for the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). It can be seen in Section H.5 of Appendix H of Reference 2 that the stresses developed in this finite element analysis demonstrated that the ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), resulting in a baseline non-shifted required T-RTNDT of

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). Therefore, considering the determination of the required shift from the paragraph above for ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )), calculations for all components listed in Table 4-5a of Reference 2 were compared to the CRD T, which is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` )) (where ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` )) materials). Therefore, the shift for the bottom head ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

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The ART of the limiting beltline material is used to adjust the beltline P-T curves to account for the effects of irradiation. RG 1.99 provides the methods for determining the ART.

Appendix J of Reference 2 provides detailed results of an analysis performed for the WLI nozzle that provides the required stresses for the drill hole in the shell plate. These stresses were used to generate a specific curve applicable for the WLI nozzle to ensure that this location is bounded in the P-T curves. For Fermi 2, the N16 WLI nozzle is the ((` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` )) for the beltline region for 52 EFPY. The Fermi 2 P-T curves are N16 WLI nozzle requirements are bounding Curve A ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) and Curve B above

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

The Fermi 2 N16 WLI nozzle is a partial penetration design similar to that shown in Figure 1 in Appendix J of Reference 2, fabricated with a ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

Therefore, the evaluation is performed, consistent with the statement in Appendix J, by using the material properties and ART of the limiting forging material.

3.9 Reactor Coolant Pressure Boundary (RCPB)

ASME Code Section III, NB-2332(b) states:

Pressure retaining material, other than bolting, with nominal wall thickness over 2-1/2 in. for piping (pipe and tubes) and material for pumps, valves, and fittings with any pipe connections of nominal wall thickness greater than 2-1/2 in. shall meet the requirements of NB-2331. The lowest service temperature shall not be lower than RTNDT + 100°F unless a lower temperature is justified by following methods similar to those contained in Appendix G.

All Fermi 2 ferritic reactor coolant pressure boundary (RCPB) piping have wall thicknesses less than 2.5 inches. The lowest service temperature may be less than RTNDT + 100°F, however the methods of Appendix G have been followed to justify lower temperatures.

Therefore, the requirements of NB-2332 have been met, and there are no ferritic RCPB piping components that require consideration in the Fermi 2 P-T curves.

With respect to the concern regarding irradiation effects on RCPB piping, the N16 WLI beltline nozzles were assessed. As can be seen in Table B-5, the WLI nozzle exceeds 1.0e17 n/cm2 at the 1/4T location. It is further noted that the WLI piping have a thickness less than 2.5 inches and are fabricated from ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). Therefore, this piping meets the conditions identified in ASME NB-2332(b) and does not require evaluation for fracture toughness.

3.10 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

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methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance (Reference 2).

4.0 Operating Limits The pressure-temperature (P-T) curves provided in this PTLR represent steam dome pressure versus minimum vessel metal temperature and incorporate the appropriate non-beltline limits and irradiation embrittlement effects in the beltline region. Note that the P-T curves were developed without allowance or margin for instrument uncertainty or errors.

The operating limits for pressure and temperature are required for three categories of operation:

1.

Curve A: Pressure Test (Hydrostatic Pressure Tests and Leak Tests)

Curve A may be used during pressure tests at times when the coolant temperature heatup or cooldown rate is 20°F/hr during a hydrotest and when the core is not critical.

2.

Curve B: Non-Nuclear Heatup/Cooldown Curve B must be used whenever Curve A or Curve C do not apply. In other words, this curve must be followed during times when the coolant heatup or cooldown rate is greater than 20°F/hr during a pressure test and when the core is not critical.

Additionally, when performing low-power physics testing, Curve B must be followed. The heatup and cooldown rate is limited to 100°F/hr when using Curve B.

3.

Curve C: Core Critical Operation This curve must be used when the core is critical with the exception as noted in Item 2 above, during low-power physics testing activities. The heatup and cooldown rate is limited to 100°F/hr when using Curve C.

Complete P-T curves were developed for 52 EFPY. The P-T curves are provided in Figures 1 through 3, and a tabulation of the curves is included in Table 1.

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

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

20F/hour.

Normal Operating Heatup and Cooldown rate limit: 100 F/hour.

RPV bottom head coolant temperature to RPV coolant temperature T limit during Recirculation Pump startup: 145 F.

Recirculation loop coolant temperature to RPV coolant temperature T limit during Recirculation Pump startup: 50 F.

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RPV flange and adjacent shell temperature limit: 72 F.

5.0 Discussion The procedures described in References 1 and 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 2. Initial RTNDT values for all vessel materials considered are presented in tables in Appendix B.

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

However, from Table B-5, the limiting material is N16 WLI nozzle forging whose ART is

((` ` ` ` ` ` ` ` ` ` ` )). This ART was used for the generation of P-T curves.

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

The P-T curves for the non-beltline region were conservatively developed for ((` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) vessel with nominal inside diameter of ((` ` ` ` ` `

` ` ` ` ` ` ` ` )). The analysis is considered appropriate for Fermi 2 because the plant-specific geometric values ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) by the generic analysis for the large ((` ` ` ` ` ` ` ` ` )). The generic value ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) to the conditions at Fermi 2 using plant-specific RTNDT values for the reactor pressure vessel.

For Fermi 2, the N16 WLI nozzle forging material is the limiting material for the beltline region for 52 EFPY whose initial RTNDT and ART are 30°F and ((` ` ` ` ` ` ` ` ` ` ` )), respectively.

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 ((` ` ` ` ` ` ` ` ` )) for 52 EFPY. Using the fluence discussed above, the P-T curves are ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) for Curves A, B, and C. Curve A is ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )); Curve B and Curve C are ((` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

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 2 for the non-beltline and beltline regions, respectively, are applied.

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6.0 References

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.

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.

3.

BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations, BWRVIP-135, Revision 3, EPRI, Palo Alto, CA: December 2014, 3002003144 (including BWRVIP Correspondence 2017-111 Final BWRVIP Integrated Surveillance Program (ISP) Data Application to Fermi Unit 2, EPRI, September 2017). (EPRI Proprietary)

4.

BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan, BWRVIP-86, Revision 1-A, EPRI, Palo Alto, CA:

October 2012, 1025144. (EPRI Proprietary)

5.

DTE Energy/Enrico Fermi Power Plant 2 Pressure and Temperature Limits Report Up to 24 And 32 Effective Full-Power Years, NEDC-33785P, Revision 1, June 2013. (GEH Proprietary Information)

6.

Not used.

7.

Not used.

8.

PCRC Recommendations on Toughness Requirements for Ferritic Materials, Welding Research Council Bulletin 175, August 1972.

9.

Mehta, H.S., Stevens, G.L., Sommerville, D.V., Benson, M., Kirk, M., Griesbach, T.J., and Kusnick, J., Treatment of Stresses Exceeding Material Yield Strength in ASME Code Section XI Appendix G Fracture Toughness Evaluations, 2014 ASME Pressure Vessels and Piping Conference, PVP2014-28397, July 2014.

10.

Radiation Embrittlement of Reactor Vessel Materials, USNRC Regulatory Guide 1.99, Revision 2, May 1988.

11.

Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, USNRC Regulatory Guide 1.190, March 2001.

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Figure 1 - Fermi 2 Composite Curve A (Pressure Test P-T Curves) Effective for up to 52 EFPY

1400 1300 1200 1100 C)

]: 1000 j

I I

I 0

i.5

c:

900

0.

0 I-

...J 800 UJ I

c,,

UJ >

0::

700 0 I-u i.5 600 0::

z I-

E 500

J UJ 0::

BOTTO~

HEAD 6S*F 400 c,,

c,,

UJ 0::

0. 300 131 2 PSIGI 200 FLA GE REGIO 100 72°F 0

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

INITIAL RT NOT VALUES ARE

-44°F FOR BEL TUNE AND 30°F FOR WU, 25°F FOR UPPER VESSEL, AND 30°F FOR BOTTOM HEAD BEL TUNE CURVES ADJUSTED AS SHOWN:

EFPY SHIFT (°F) 52 116 52 54 (WU)

HEATUP/COOLDOWN RA TE OF COOLANT

~ 20°F/HR UPPER VESSEL AND BELTLINE LIMITS

* BOTTOM HEAD CURVE

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Figure 2 - Fermi 2 Composite Curve B (Core Not Critical P-T Curves) Effective for up to 52 EFPY

1400 I

I I

1300 I

I I

I 1200 I

I I

1100 I

I I

Cl I

I

! 1000 I

I,'

C c(

w I

I I

I

c:

900

a.

I i

E I

I I

...J 800 w

I I

Cl)

Cl) w I

0::

700 E

I I

I u

c(

w 600 0::

I I

z I

I i

500

J w

0::

I j

I 400 Cl)

Cl) w BOTTOM 0::

a.

300 200 HEAD 68°F

/

I FLANGE 100 I

REGION 72°F 0

I 0

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

NITIAL RTNDT VALUES ARE

-44°F FOR BEL TUNE, AND 30°F FOR WU, 25°F FOR UPPER VESSEL, AND 44.6°F FOR BOTTOM HEAD BEL TUNE CURVES ADJUSTED AS SHOWN:

EFPY SHIFT (°F) 52 116 52 54 (WU)

HEATUP/COOLDOWN RA TE OF COOLANT

~ 100°F/HR UPPER VESSEL AND BEL TLINE LIMITS

BOTTOM HEAD CURVE

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Figure 3 - Fermi 2 Limiting Curve C (Core Critical P-T Curve) Effective for up to 52 EFPY

1400 1300 1200 1100 ci

'[ 1000 C

~

r:

900 Q. g

..J 800 w

V)

V) w 0::

700 0

I-0

<( w 600 0::

z I-500 w

I I

0::

400 V)

V) w 0::

Q.

300 200

,, V I

100 0

,/

Minimum Vessel I~ __...

Temperature 72°F I

0 25 50 75 100 125 150 175 200 225 250 275 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)

INITIAL RT Nor VALUES ARE

-44°F FOR BEL TUNE AND 30°F FOR WU, 25°F FOR UPPER VESSEL, AND 30°F FOR BOTTOM HEAD BEL TUNE CURVE ADJUSTED AS SHOWN:

EFPY SHIFT (°F) 52 116 52 54 (WU)

HEATUP/COOLDOWN RA TE OF COOLANT

.:5 100°F/HR BEL TUNE AND NON-BEL TUNE LIMITS

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Table 1 Fermi 2 Tabulation of Curves - 52 EFPY

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 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

NEDO-33915 Revision 1 Non - Proprietary Information 17

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 190 68.0 72.0 68.0 75.2 115.2 200 68.0 72.0 68.0 77.3 117.3.0 210 68.0 72.0 68.0 80.4 120.4 220 68.0 72.0 68.0 85.5 125.3 230 68.0 72.0 68.0 89.8 129.8 240 68.0 72.0 68.0 93.8 133.8 250 68.0 72.0 68.0 97.3 137.3 260 68.0 72.0 68.0 100.7 140.7 270 68.0 72.0 68.0 103.8 143.8 280 68.0 72.0 68.0 106.7 146.7 290 68.0 72.0 68.0 109.4 149.4 300 68.0 72.0 68.0 111.9 151.9 310 68.0 72.0 68.0 114.2 154.2 312.5 68.0 72.0 68.0 114.8 154.8 312.5 68.0 102.0 68.0 132.0 172.0 320 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

NEDO-33915 Revision 1 Non - Proprietary Information 18

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 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 68.0 132.6 172.6 420 68.0 102.0 68.0 134.0 174.0 430 68.0 102.0 68.0 135.5 175.5 440 68.0 102.0 68.0 136.8 176.8 450 68.0 102.0 68.0 138.1 178.1 460 68.0 102.0 68.0 139.4 179.4 470 68.0 102.0 68.0 140.6 180.6 480 68.0 102.0 68.0 141.8 181.8 490 68.0 102.0 68.0 143.0 183.0 500 68.0 102.0 68.0 144.1 184.1 510 68.0 102.0 68.0 145.2 185.2 520 68.0 102.0 68.0 146.3 186.3 530 68.0 102.0 68.0 147.3 187.3 540 68.0 102.0 68.0 148.4 188.4 550 68.0 102.0 69.5 149.3 189.3 560 68.0 102.0 71.3 150.3 190.3

NEDO-33915 Revision 1 Non - Proprietary Information 19

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 570 68.0 102.0 73.0 151.3 191.3 580 68.0 102.0 74.6 152.2 192.2 590 68.0 102.0 76.2 153.1 193.1 600 68.0 102.0 77.8 153.9 193.9 610 68.0 102.0 79.3 154.3 194.3 620 68.0 102.0 80.7 154.7 194.7 630 68.0 102.0 82.1 155.1 195.1 640 68.0 102.0 83.5 155.4 195.4 650 68.0 102.0 84.8 155.8 195.8 660 68.0 102.0 86.1 156.2 196.2 670 68.0 102.0 87.4 156.6 196.6 680 68.0 102.0 88.7 156.9 196.9 690 68.0 102.0 89.9 157.3 197.3 700 68.0 102.0 91.0 157.7 197.7 710 68.0 102.0 92.2 158.0 198.0 720 68.0 102.0 93.3 158.4 198.4 730 68.0 102.0 94.4 158.8 198.8 740 68.0 102.0 95.5 159.1 199.1 750 68.0 102.0 96.6 159.5 199.5 760 68.0 102.0 97.6 159.8 199.8

NEDO-33915 Revision 1 Non - Proprietary Information 20

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 770 68.0 102.0 98.6 160.2 200.2 780 68.0 102.0 99.6 160.5 200.5 790 68.0 102.0 100.6 160.9 200.9 800 68.0 102.8 101.5 161.2 201.2 810 68.0 104.1 102.5 161.6 201.6 820 68.0 105.4 103.4 161.9 201.9 830 68.0 106.6 104.3 162.3 202.3 840 68.0 107.9 105.2 162.6 202.6 850 68.6 109.0 106.0 162.9 202.9 860 69.6 110.2 106.9 163.3 203.3 870 70.6 111.4 107.7 163.6 203.6 880 71.5 112.5 108.6 163.9 203.9 890 72.5 113.6 109.4 164.3 204.3 900 73.4 114.6 110.2 164.6 204.6 910 74.4 115.7 111.0 164.9 204.9 920 75.3 116.7 111.7 165.2 205.2 930 76.1 117.7 112.5 165.6 205.6 940 77.0 118.7 113.3 165.9 205.9 950 77.9 119.7 114.0 166.2 206.2 960 78.7 120.6 114.7 166.5 206.5

NEDO-33915 Revision 1 Non - Proprietary Information 21

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 970 79.6 121.5 115.5 166.8 206.8 980 80.4 122.4 116.2 167.1 207.1 990 81.2 123.3 116.9 167.5 207.5 1000 82.0 124.2 117.6 167.8 207.8 1010 82.7 125.1 118.2 168.1 208.1 1020 83.5 125.9 118.9 168.4 208.4 1030 84.3 126.8 119.6 168.7 208.7 1035 84.6 127.2 119.9 168.8 208.8 1040 85.0 127.6 120.2 169.0 209.0 1050 85.7 128.4 120.9 169.3 209.3 1055 86.1 128.8 121.2 169.4 209.4 1060 86.4 129.2 121.5 169.6 209.6 1070 87.2 130.0 122.1 169.9 209.9 1080 87.9 130.8 122.8 170.2 210.2 1090 88.6 131.5 123.4 170.5 210.5 1100 89.2 132.3 124.0 170.8 210.8 1105 89.6 132.6 124.3 170.9 210.9 1110 89.9 133.0 124.6 171.1 211.1 1120 90.6 133.7 125.2 171.4 211.4 1130 91.2 134.5 125.8 171.6 211.6

NEDO-33915 Revision 1 Non - Proprietary Information 22

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 1140 91.9 135.2 126.3 171.9 211.9 1150 92.5 135.9 126.9 172.2 212.2 1160 93.1 136.5 127.5 172.5 212.5 1170 93.8 137.2 128.0 172.8 212.8 1180 94.4 137.9 128.6 173.1 213.1 1190 95.0 138.5 129.1 173.4 213.4 1200 95.6 139.2 129.7 173.6 213.6 1210 96.2 139.8 130.2 173.9 213.9 1220 96.8 140.5 130.8 174.2 214.2 1230 97.3 141.1 131.3 174.5 214.5 1240 97.9 141.7 131.8 174.8 214.8 1250 98.5 142.3 132.3 175.0 215.0 1260 99.0 142.9 132.8 175.3 215.3 1270 99.6 143.5 133.3 175.6 215.6 1280 100.1 144.1 133.8 175.8 215.8 1290 100.7 144.7 134.3 176.1 216.1 1300 101.2 145.3 134.8 176.4 216.4 1310 101.7 145.8 135.3 176.7 216.7 1320 102.3 146.4 135.8 176.9 216.9 1330 102.8 147.0 136.2 177.2 217.2

NEDO-33915 Revision 1 Non - Proprietary Information 23

BOTTOM UPPERRPV&

HEAD BELTLINEAT HEAD BELTLINEAT LIMITING

52EFPY

52EFPY 52EFPY PRESSURE CURVEA CURVEA CURVEB CURVEB CURVEC (PSIG)

(°F)

(°F) 1340 103.3 147.5 136.7 177.5 217.5 1350 103.8 148.1 137.2 177.7 217.7 1360 104.3 148.6 137.6 178.0 218.0 1370 104.8 149.1 138.1 178.2 218.2 1380 105.3 149.7 138.5 178.5 218.5 1390 105.8 150.2 139.0 178.8 218.8 1400 106.3 150.7 139.4 179.0 219.0

NEDO-33915 Revision 1 Non - Proprietary Information 24

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 5.2.4.4, Surveillance Programs for the Reactor Pressure Vessel, the BWR Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (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 ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). Per the BWRVIP ISP, Fermi 2

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )); all surveillance capsules are classified as Deferred.

NEDO-33915 Revision 1 Non - Proprietary Information 25

Appendix B Fermi 2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information

NEDO-33915 Revision 1 Non - Proprietary Information 26

Figure B Schematic of the Fermi 2 RPV Showing Arrangement of Vessel Plates and Welds TOP OF ACTIVE FUEL (TAF) 366.3" ---1 BOTTOM OF ACTIVE FUEL (BAF) 216.3" ---1 WllT.H7ll.TJ',

AXIAL WELDS

--- TOP HEAD TOP HEAD FLANGE SHELL FLANGE SHELL #4 SHELL #3 SHELL #2 SHELL #1 BOTTOM HEAD

~-- SUPPORT SKIRT

NEDO-33915 Revision 1 Non - Proprietary Information 27

Table B-1 Fermi 2 Initial RTNDT Values for RPV Plate and Flange Materials

Note:MinimumCharpyvaluesareprovidedforallmaterials.

Component Heat Test Temp

(°F)

Charpy Energy (ft-lb)

(T50T-60)

(°F)

Drop Weight NDT

(°F)

RTNDT

(°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 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 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

NEDO-33915 Revision 1 Non - Proprietary Information 28

Table B-2 Fermi 2 Initial RTNDT Values for RPV Nozzle Materials

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 30°F.

Component Heat or Heat / Flux / Lot Test Temp

(°F)

(T50T-60)

(°F)

Drop Weight NDT

(°F)

RTNDT

(°F)

Recirculation Outlet Nozzle G3717-1 AJF 181 10 77 96 59

-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 G3719-2 EV-9806 8L-9211B 10 99 124 105

-20

-20 CRD HYD Return Nozzle G3716 AV3138 8L-9104 10 42 40 48 0

10 10 Core P 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 High Pressure Leak Detector Nozzle G4546 10 [1]

Drain Nozzle G3739 Q1Q1VW 738T 10 39 25 32 30 40 40 CRD Stub Tubes G3736-1 through -5 Alloy 600

[2]

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

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

Charpy Energy (ft-lb)

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

NEDO-33915 Revision 1 Non - Proprietary Information 29

Table B-3 Fermi 2 Initial RTNDT Values for RPV Weld Materials Component Heat or Heat / Flux / Lot Test Temp

(°F)

Charpy Energy (ft-lb)

(T50T-60)

(°F)

Drop Weight NDT

(°F)

RTNDT

(°F)

Beltline - Axial Lower Shell 2-307 A, B, C 13253 Linde 1092 Lot 3833 10 79 79 82

-50

-50 12008 Linde 1092 Lot 3833 10 62 47 62

-44

-44 Lower-Intermediate Shell 15-308 A, B, C, D 33A277 Linde 124 Lot 3878 10 83 94 87

-50

-50 Beltline - Girth Lower-Intermediate Shell to Lower Shell 1-313 10137 Linde 0091 Lot 3999 10 101 108 107

-50

-50 Non-Beltline - Axial Upper-Intermediate Shell 2-308 A through C 20291 & 12008 Linde 1092 Lot 3833 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 4-308-A 305424 Linde 1092 Lot 3889 10 82 87 92

-50

-50 Upper-Intermediate Shell to Lower-Intermediate Shell 4-308-B 1P3571 Linde 1092 Lot 3958 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 3-306, 5-306, 6-306 1P2809 Linde 1092 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

NEDO-33915 Revision 1 Non - Proprietary Information 30

Table B-3:

Fermi 2 Initial RTNDT Values for RPV Weld Materials (continued)

Note: Minimum Charpy values are provided for all materials.

Component Heat or Heat / Flux / Lot Test Temp

(°F)

Charpy Energy (ft-lb)

(T50T-60)

(°F)

Drop Weight NDT

(°F)

RTNDT

(°F)

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 P 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 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

NEDO-33915 Revision 1 Non - Proprietary Information 31

Table B-4 Fermi 2 Initial RTNDT Values for RPV Appurtenance and Bolting Materials

Note:MinimumCharpyvaluesareprovidedforallmaterials.

Component Heat Test Temp

(°F)

Charpy Energy (ft-lb)

(T50T-60)

(°F)

Drop Weight NDT

(°F)

RTNDT (°F)

Misc Appurtenances:

Support Skirt Forging S8530 AHC 178 10 81 100 102

-20 30 30 Shroud Support Alloy 600 G3726 580608-1X (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 (1)

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)

G3819 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)

Component Heat Test Temp

(°F)

Charpy Energy (ft-lb)

Min Lat Exp (mils)

LST

(°F)

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 (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.

NEDO-33915 Revision 1 Non - Proprietary Information 32

Table B-5 Fermi 2 Adjusted Reference Temperatures for up to 52 EFPY Lower-Intermediate Shell Plates, Axial Welds Thickness in inches = 6.125 52 EFPY Peak I.D. fluence = 9.92E+17 n/cm2 52 EFPY Peak 1/4 T fluence = 6.87E+17 n/cm2 Water Level Instrumentation Nozzle Thickness in inches = 6.125 52 EFPY Peak I.D. fluence = 3.59E+17 n/cm2 52 EFPY Peak 1/4 T fluence = 2.49E+17 n/cm2 Lower Shell Plates and Axial Welds & Lower to Lower-Intermediate Girth Weld Thickness in inches = 7.125 52 EFPY Peak I.D. fluence = 5.74E+17 n/cm2 52 EFPY Peak 1/4 T fluence = 3.74E+17 n/cm2 COMPONENT HEAT OR HEAT/LOT

%Cu

%Ni CF Adjusted CF [1]

Initial RTNDT °F 1/4 T Fluence n/cm2 52 EFPY RTNDT° F

I Margin

°F 52 EFPY Shift

°F 52 EFPY ART °F PLANT SPECIFIC CHEMISTRIES PLATES:

Lower Shell G3706-1 G3706-2 G3706-3 Lower-Intermediate Shell G3703-5 G3705-1 G3705-2 G3705-3 C4540-2 C4560-1 C4554-1 C4564-1 B8614-1 C4574-2 C4568-2 0.08 0.11 0.12 0.09 0.12 0.10 0.12 0.62 0.57 0.56 0.55 0.61 0.55 0.61 51 74 82 58 83 65 83

-10

-20

-16

-12 3.74E+17 3.74E+17 3.74E+17 6.87E+17 6.87E+17 6.87E+17 6.87E+17 13 18 21 20 29 22 29 0

0 0

6 9

10 10 14 11 14 13 18 21 20 29 22 29 25 37 41 40 58 45 58 15 27 31 30 38 29 46

NEDO-33915 Revision 1 Non - Proprietary Information 33

Table B-5 Fermi 2 Adjusted Reference Temperatures for up to 52 EFPY (continued)

COMPONENT HEAT OR HEAT/LOT

%Cu

%Ni CF Adjusted CF (1)

Initial RTNDT °F 1/4 T Fluence n/cm2 52 EFPY RTNDT°F I

Margin

°F 52 EFPY Shift

°F 52 EFPY ART °F WELDS:

Lower Shell Axial 2-307 A, B, C Lower-Intermediate Shell Axial 15-308 A, B, C, D Lower to Lower-Intermediate Girth 1-313 Tandem 13253, 12008 1092 Lot 3833 33A277, 124 Lot 3878 10137, 0091 Lot 3999 0.26 0.32 0.23 0.87 0.50 1.00 224 188.5 236

-44

-50

-50 3.74E+17 6.87E+17 3.74E+17 56 65 59 0

0 0

28 28 28 56 56 56 112 121 115 68 71 65 NOZZLES:

N16 (Water Level Instrumentation) 2127273 0.272 0.214 136 30 2.49E+17 27 0

13 27 54 84 N16 (Water Level Instrumentation) 6397860 0.272 0.214 136 30 2.49E+17 27 0

13 27 54 84 N16 Weld Inconel (2)

NEDO-33915 Revision 1 Non - Proprietary Information 34

Table B-5 Fermi 2 Adjusted Reference Temperatures for up to 52 EFPY (continued)

COMPONENT HEAT OR HEAT/LOT

%Cu

%Ni CF Adjusted CF (1)

Initial RTNDT °F 1/4 T Fluence n/cm2 52 EFPY RTNDT°F I

Margin

°F 52 EFPY Shift °F 52 EFPY ART °F Best Estimate Chemistries (6)

None None INTEGRATED SURVEILLANCE PROGRAM (3):

BWRVIP-135 R3 Plate (4)

Weld (5)

C4114-2 CE-2 (WM)

(13253,12008) 0.12 0.21 0.70 0.86 84.5 207

((351 {E}))

-12

-44 6.87E+17 3.74E+17 29 88 0

0 15 28 29 28 58 116 46 72

1. Adjusted CF calculated per RG 1.99 Position 2.1.

2. ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

3. Procedures defined in RG 1.99 are applied to determine the ART considering the Integrated Surveillance Program.

4. This ISP plate heat number is not identical to target (any plant specific) plate heat number. It is presented using the ISP chemistry, RG 1.99 R2 CF, the limiting Fermi 2 plate (Heat C4568-2) fluence and its initial RTNDT. This is not applicable to development of P-T curves and is provided for information only.

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.

is presented as calculated but is multiplied by 0.5 for the Margin calculation as defined in RG 1.99, Position 2.1.

6. None of the plate and weld heats had different best estimate chemistries.

NEDO-33915 Revision 1 Non - Proprietary Information 35

Table B-6 Fermi 2 RPV Beltline P-T Curve Input Values for 52 EFPY Adjusted RTNDT = Initial RTNDT + Shift A = ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) (limiting value for ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )))

A = ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) (limiting value for ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )))

(Based on ART values in Table B-5; no additional adjustment is required to protect the existing flaw discussed in Section 3.5.)

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

NEDO-33915 Revision 1 Non - Proprietary Information 36

Table B-7 Fermi 2 Definition of RPV Beltline Region (1)

Component Elevation (inches from RPV 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 381.6 Shell # 1 - Bottom of Extended Beltline Region 208.5 Circumferential Weld Between Shell #1 and Shell #2 244.6 Circumferential Weld Between Shell #2 and Shell #3 415.6 Centerline of Recirculation Outlet Nozzle N1 in Shell # 1 161.5 Top of Recirculation Outlet Nozzle N1 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 N16 in Shell # 2 366.0 Bottom of Water Level Instrumentation Nozzle N16 in Shell # 2 (2) 364.2

1. The extended beltline region is defined as any location where the peak neutron fluence is expected to exceed or equal 1.0e17 n/cm2.

2. Elevation considering the WLI weld for the bounding fluence value at the WLI nozzle.

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.

NEDO-33915 Revision 1 Non - Proprietary Information 37

Appendix C Fermi 2 Reactor Pressure Vessel P-T Curve Checklist 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 Licensing Topical Report (LTR) (Reference 2), and includes comments, resolutions, and clarifications as necessary.

NEDO-33915 Revision 1 Non - Proprietary Information 38

Table C-1 Fermi 2 Checklist Parameter Completed Comments/Resolutions/Clarifications Initial RTNDT Initial RTNDT has been determined for Fermi 2 for all vessel materials including plates, flanges, forgings, studs, nuts, bolts, welds.

Include explanation (including methods/sources) of any exceptions, resolution of discrepant data (e.g., deviation from originally reported values).

The N16 water level instrumentation nozzle is considered within the beltline region. This forging was fabricated from ((` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )). Additional details regarding this material and its properties are provided in Section 3.0 of this PTLR.

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 information (e.g., ISP, comparison to other plant) been used?

Plate heat C4114-2 information was obtained from the ISP database. This 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 process occurred, sufficient supporting information has been included (e.g., Charpy V-Notch data used to determine an Initial RTNDT).

Details regarding the determination of the initial RTNDT of the N16 nozzle are provided in Section 3.0 of this PTLR.

No other deviations from the P-T curve LTR process.

All previously published Initial RTNDT values from sources such as the GL88-01, Reactor Vessel Integrity Database (RVID), UFSAR, etc., have been reviewed.

RVID was reviewed for the beltline materials; all initial RTNDT values agree; no further review was performed.

~

NEDO-33915 Revision 1 Non - Proprietary Information 39

Table C-1: Fermi 2 Checklist (continued)

Parameter Completed Comments/Resolutions/Clarifications Adjusted Reference Temperature (ART)

Sigma I (I, standard deviation for Initial RTNDT) is 0°F unless the RTNDT was obtained from a source other than CMTRs. If I is not equal to 0, reference/basis has been provided.

Sigma I is equal to 0 for all materials.

Sigma (, standard deviation for RTNDT) is determined per RG 1.99, Revision 2.

Chemistry has been determined for all vessel beltline materials including plates, forgings (if applicable), and welds for Fermi 2.

Include explanation (including methods/sources) of any exceptions, resolution of discrepant data (e.g., deviation from originally reported values).

Sufficient information was not available to determine the chemistry content for the N16 water level instrumentation nozzle materials. ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` )). More information is provided in Section 3.0.

No deviations from previously reported values.

Non-Fermi 2 chemistry information (e.g., ISP, comparison to other plant) used has been adequately defined and described.

Plate heat C4114-2 and weld heat CE-2 (WM) 13253/12008 have been evaluated using best estimate chemistry from the ISP.

For any deviation from the P-T curve LTR

process, sufficient information has been included.

No deviations from the P-T curve LTR process.

~

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Table C-1: Fermi 2 Checklist (continued)

Parameter Completed Comments/Resolutions/Clarifications All previously published chemistry values from sources such as the GL88-01, Reactor Vessel Integrity Database (RVID), UFSAR, etc., have been reviewed.

RVID was reviewed; all initial RTNDT values agree; no further review was performed The fluence used for determination of ART and any extended beltline region was obtained using an NRC-approved methodology.

One (1)

NRC-approved methodology (Reference 1) was used for the entire plant license.

The fluence calculation provides an axial distribution to allow determination of the vessel elevations that experience fluence of 1.0e17 n/cm2 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 1.0e17 n/cm2 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.

There are no deviations.

~

NEDO-33915 Revision 1 Non - Proprietary Information 41

Table C-1: Fermi 2 Checklist (continued)

Parameter Completed Comments/Resolutions/Clarifications 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 describes the process for considering a thickness discontinuity, both beltline and non-beltline. If there is a discontinuity in the Fermi 2 vessel that requires such an evaluation, the evaluation was performed. The affected curve was adjusted to bound the discontinuity, if required.

The thickness discontinuity evaluation demonstrated that ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )); the curves ((` ` ` ` ` ` ` ` ` ))

the discontinuity stresses.

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 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.

~

NEDO-33915 Revision 1 Non - Proprietary Information 42

Appendix D Sample P-T Curve Calculations Beltline Water Level Instrumentation Nozzle Pressure Test (Curve A) for 52 EFPY KI for the discontinuity is determined considering the KI obtained from Table 7 of Appendix J of Reference.2 (for hydrotest). For 1055 psig, this KI is scaled by pressure as follows:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

T-RTNDT is calculated in the following manner:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

The ART is added to T-RTNDT to obtain the required T:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

This temperature can be found from Table 1 as it bounds the temperature requirements for upper RPV and beltline region.

Core Not Critical (Curve B) for 52 EFPY KI for the discontinuity is determined considering the KI obtained from Table 5 of Appendix J of Reference 2.

KI(pressure)

=

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

KI(thermal)

=

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

The transient used for the WLI nozzle, defined in Appendix J, is used in determination of KI.

The total KI is therefore:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

T-RTNDT is calculated in the following manner:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

The ART is added to T-RTNDT to obtain the required T:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

This temperature can be found from Table 1 as it ((` ` ` ` ` ` ` ` ` ` )) the temperature requirements for

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

NEDO-33915 Revision 1 Non - Proprietary Information 43

Correction Factor The total stress for the WLI nozzle exceeds the yield stress; therefore, the correction factor, R, is calculated to consider the nonlinear effects in the plastic region. The R factor adjustment for the WLI nozzle is based on the assumptions and recommendation of Welding Research Council (WRC)

Bulletin 175 (Reference 8) that provides the technical background for Appendix G (Fracture Toughness Criteria for Protection Against Failure) of ASME Boiler & Pressure Vessel Code Section XI. WRC Bulletin 175 proposes the methodology how to estimate the stresses when the secondary and peak stresses calculated on an elastic basis exceed the yield stress. This is to consider the nonlinear effects in the local plastic region. However, for the application to WLI nozzle, ((` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) The technical detail for this method is described in Section 5.C.3 of WRC Bulletin 175. The applicability of this procedure to pressure vessel was studied in a Pressure Vessels & Piping (PVP) Conference paper (Reference 9). For example, the R factor under the pressure of 1055 psig is calculated below in accordance with the Equation 4-7 of Reference 2.

R

=

[ys - pm + ((total - ys)/30)]/(total - pm)

Applied to the WLI nozzle:

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ))

R factor values for WLI nozzle over the entire pressure range are shown as follows.

((` ` ` ` ` ` ` ` ` ` ` ` `

` `

` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` `

`

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

` ` `

` ` ` `

` ` ` ` `

NEDO-33915 Revision 1 Non - Proprietary Information 44

((` ` ` ` ` ` ` ` ` ` ` ` `

` `

` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` `

```

````

`````

```

````

`````

````

`````

````

`````

````

`````

````

`````

````

`````

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

Beltline Calculations Excluding Nozzles Pressure Test (Curve A) at 1055 psig for 52 EFPY A sample calculation for the beltline material, not including the N16 WLI nozzle, for Curve A is provided for 1055 psig as follows.

The ART applied to the beltline P-T curves is ((` ` ` ` ` ` ` ` ` ` )), for ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

)).

Pressure is calculated to include hydrostatic pressure for a full vessel:

P

=

1055 psig + (H - B)

0.0361 psi/inch (H = vessel height; B = elevation of bottom of active fuel)

=

1055 + (861.6 - 216.3)

0.0361

=

1078 psig Pressure Stress:

=

PR/t (P = pressure; R = vessel radius; t = vessel thickness)

=

1.078

127 / 6.125

=

22.35 ksi

NEDO-33915 Revision 1 Non - Proprietary Information 45

Mm

=

0.926

t (for 2 t 3.464)

=

0.926

6.125

=

2.29 The stress intensity factor, KIt, is calculated as described in Section 4.3.2.2.4 of Reference 2, except that G is 20°F/hr instead of 100°F/hr.

Mt

=

0.2942, from ASME Appendix G, Figure G-2214-1 T

=

GC2 / 2 G = coolant heatup/cooldown rate of 20°F/hr C = minimum vessel thickness including clad = 6.4375 = 0.5365 ft

= thermal diffusivity at 550°F = 0.354 ft2/hr

=

(20 * (0.5365)2) / (2

0.354)

=

8.13°F KIt

=

Mt

T

=

0.2942

8.13

=

2.39 KIm

=

Mm

=

22.35

2.29

=

51.2 T-RTNDT

=

ln[(1.5

KIm + KIt - 33.2) / 20.734] / 0.02

=

ln[(1.5

51.2 + 2.39 - 33.2) / 20.734] / 0.02

=

39.8°F T is calculated by adding the ART:

T

=

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

=

((` ` ` ` ` ` ` ` ` ` ` ))

for P = 1055 psig at 52 EFPY This temperature is not obvious from the P-T curves as it ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

Core Not Critical (Curve B) at 1055 psig for 52 EFPY As discussed above and shown in Table B-5, the ART applied to the beltline Curve B is ((` ` ` ` ` ` ` `

` ` )) for the lower shell axial weld.

NEDO-33915 Revision 1 Non - Proprietary Information 46

The T term is calculated as shown above for the Pressure Test case, but the temperature rate change is 100°F/hr instead of 20°F/hr. Therefore, T equals 40.65°F.

P

=

1055 psig + (H - B)

0.0361 psi/inch (H = vessel height; B = elevation of bottom of active fuel)

=

1055 + (861.6 - 216.3)

0.0361

=

1078 psig Pressure Stress:

=

PR/t (P = pressure; R = vessel radius; t = vessel thickness)

=

1.078

127 / 6.125

=

22.35 ksi KIm

=

Mm

=

22.35

2.29

=

51.2 KIt

=

Mt

T (for the 100°F/hr case)

=

0.2942

40.65

=

11.96 T-RTNDT

=

ln [(2.0

KIm + KIt - 33.2) / 20.734] / 0.02

=

ln [(2.0

51.2 + 11.96 - 33.2) / 20.734] / 0.02

=

68.2°F T is calculated by adding the ART:

T

=

((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ))

=

((` ` ` ` ` ` ` ` ` ` ` ))

for P = 1055 psig at 52 EFPY This temperature is not obvious from the P-T curves as it ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )).

NEDO-33915 Revision 1 Non - Proprietary Information 47

Feedwater Nozzle Calculations An evaluation was performed for the feedwater nozzle as described in Section 4.3.2.1.3 of the Reference 2. The first part of the evaluation is as described earlier, where it is assured that the limiting component that is represented by the upper vessel curve is bounded by the ((` ` ` ` ` ` ` ` ` ` ` `

` ` ` ` ` ` ` ` ` ` ` ` ` )). A second evaluation was performed using the Fermi 2-specific feedwater nozzle dimensions; this evaluation is shown below to demonstrate that the baseline curve is applicable to Fermi 2:

Vessel radius to base metal, Rv

((

Vessel thickness, tv Vessel pressure, Pv Pressure stress = PR/t = ((

))

Dead Weight + Thermal Restricted Free End stress Total Stress = ((

))

The factor F(a/rn) from Figure A5-1 of PVRC Recommendations on Toughness Requirements for Ferritic Materials, WRC-175 is determined where:

a = 1/4 * (tn2 + tv2) 1/2

((

tn = thickness of nozzle tv = thickness of vessel rn = apparent radius of nozzle = ri + 0.29*rc ri = actual inner radius of nozzle rc = nozzle radius (nozzle corner radius)

))

Therefore, a/rn = ((

)). The value F(a/rn), taken from Figure A5-1 of WRC-175 for an ((

)). Including the safety factor of 1.5, the stress intensity factor, KI, is 1.5 (a)1/2

F(a/rn):

Fermi 2 Plant-Specific Nominal KI = 1.5 * ((

))

NEDO-33915 Revision 1 Non - Proprietary Information 48

A detailed upper vessel example calculation for core not critical conditions is provided in Section 4.3.2.1.4 of the Reference 2. Section 4.3.2.1.3 of the Reference 2 defines the baseline nominal KI to be ((` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` ` )) for the FW nozzle evaluation upon which the baseline non-shifted upper vessel P-T curve is based. It can be seen that the nominal KI from this Fermi 2 evaluation is ((

` ` ` )). Therefore, it has been shown that the nominal KI for the Fermi 2-specific FW nozzle is less than the baseline K1, demonstrating applicability of the FW nozzle curve for Fermi

2.

\\

NRC-20-0009, DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR)

Text

Subject:

References:

Enclosures:

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