Attachment 3 PWROG-15105-NP PA-MSC-1288 PWR RV …Group (PWROG) authorized PA-MSC-1288, Rev. 2, to leverage the data in currently available responses to this cold-work question to

Attachment 3

PWROG-15105-NP

PA-MSC-1288 PWR RV Internals Cold-Work Assessment

L-2017-015 10-CFR 54

WESTINGHOUSE NON-PROPRIETARY CLASS 3

PA-MSC-1288 PWR RV Internals ColdWork Assessment Materials Committee

PAnmMSC ... 1288

WESTINGHOUSE NON-PROPRIETARY CLASS 3

PWROG-15105-NP Revision 0

PAmMSC-1288 PWR RV Internals Cold-Work

Assessment

PA-MSC-1288

Michael R. Ickes* Reactor Internals Aging Management

Verifier:

Michael A. Burke* Materials Center of Excellence

April 2016

Joshua K. McKinley* Reactor Internals Aging Management

Approved: Patricia C. Paesano*, Manager Reactor Internals Aging Management

Approved: James P. Molkenthin*, Program Director PWR Owners Group PMO

*Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive

Cranberry Township, PA 16066, USA

© 2016 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3

LEGAL NOTICE

This report was prepared as an account of work performed by Westinghouse Electric Company LLC. Neither Westinghouse Electric Company LLC, nor any person acting on its behalf:

ii

1. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefulness pf the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this report may not infringe privately owned rights; or

2. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this report.

COPYRIGHT NOTICE

This report has been prepared by Westinghouse Electric Company LLC and bears a Westinghouse Electric Company copyright notice. As a member of the PWR Owners Group, you are permitted to copy and redistribute all or portions of the report within your organization; however all copies made by you must include the copyright notice in all instances.

DISTRIBUTION NOTICE

This report was prepared for the PWR Owners Group. This Distribution Notice is intended to establish guidance for access to this information. This report (including proprietary and non-proprietary versions) is not to be provided to any individual or organization outside of the PWR Owners Group program participants without prior written approval of the PWR Owners Group Program Management Office. However, prior written approval is not required for program participants to provide copies of Class 3 Non-Proprietary reports to third parties that are supporting implementation at their plant, and for submittals to the NRC.

PWROG-15105-NP April 2016 Revision 0


PWR Owners Group United States Member Participation* for PA-MSC-1288

Utility Member Plant Site(s)

Ameren Missouri Callaway (W)

American Electric Power D.C. Cook 1 & 2 (W)

Arizona Public Service Palo Verde Unit 1, 2, & 3 (CE)

Dominion Connecticut Millstone 2 (CE) .

Millstone 3 0/V)

Dominion VA North Anna 1 & 2 (W)

Surry 1 & 2 (W)

Catawba 1 & 2 (W)

Duke Energy Carolinas McGuire 1 & 2 0N)

Oconee 1, 2, & 3 (B&W)

Duke Energy Progress Robinson 2 0/V)

Shearon Harris (W)

Entergy Palisades Palisades (CE)

Entergy Nuclear Northeast Indian Point 2 & 3 (W)

Arkansas 1 (B&W)

Entergy Operations South Arkansas 2 (CE)

Waterford 3 (CE)

Braidwood 1 & 2 (W)

Byron 1 & 2 (W)

Exelon Generation Co. LLC TMI 1 (B&W)

Calvert Cliffs 1 & 2 (CE)

Ginna 0/V)

Beaver Valley 1 & 2 (W) FirstEnergy Nuclear Operating Co.

Davis-Besse (B&W)

St. Lucie 1 & 2 (CE)

Florida Power & Light\ NextEra Turkey Point 3 & 4 0/V)

Seabrook (W)

Pt. Beach 1 & 2 (W)

Luminant Power Comanche Peak 1 & 2 (W)

PWROG-15105-NP

iii

Participant

Yes

x x x x x x x x x x x x x x x x x x x x x x x x x x x x x

No

April 2016 Revision 0

\


PWR Owners Group United States Member Participation* for PA-MSC-1288

Participant (

Utility Member Plant Site(s) Yes

Omaha Public Power District Fort Calhoun (CE) x Pacific Gas & Electric Diablo Canyon 1 & 2 (W) x PSEG - Nuclear Salem 1 & 2 (W) x South Carolina Electric & Gas V.C. Summer (W) x So. Texas Project Nuclear Operating Co. South Texas Project 1 & 2 (W) x

Farley 1 & 2 (W) x Southern Nuclear Operating Co.

x Vogtle 1 & 2 (W)

Sequoyah 1 & 2 (W) x Tennessee Valley Authority

x Watts Bar 1 & 2 (W)

Wolf Creek Nuclear Operating Co. Wolf Creek (W) x Xcel Energy Prairie Island 1 & 2 (W) x * Project participants as of the date the final deliverable was completed. On occasion,

additional members will join a project. Please contact the PWR Owners Group Program

No

. Management Office to verify participation before sending this document to participants not listed above.

iv



PWR Owners Group International Member Participation* for PA-MSC-1288

Participant

Utility Member Plant Site(s) Yes No

Asco 1 & 2 0JV) x Asociaci6n Nuclear Asc6-Vandell6s

Vandellos 2 (W) x AxpoAG Beznau 1 & 2 (W) x Centrales Nucleares Almaraz-Trillo Almaraz 1 & 2 (W) x EDF Energy Sizewell B 0/V) x

Electrabel Dael 1, 2 & 4 0/V) x Tihange 1 & 3 (W) x

Electricite de France 58 Units x Eletronuclear-Eletrobras Angra 1 (W) x Eskom Koeberg 1 & 2 (W) x Hokkaido Tomari 1, 2 & 3 (MHI) x Japan Atomic Power Company Tsuruga 2 (MHI) x

Mihama 1, 2 & 3 (W) x Kansai Electric Co., LTD Ohi 1, 2, 3 & 4 (W & MHI) x

Takahama 1, 2, 3 & 4 (W & MHI) x Kori 1, 2, 3 &4 (W) x Hanbit 1 & 2 0/V) x

Korea Hydro & Nuclear Power Corp. Hanbit 3, 4, 5 & 6 (CE) x

\ Hanul 3, 4 , 5 & 6 (CE) x Genkai 1, 2, 3 & 4 (MHI) x

Kyushu Sendai 1 & 2 (MHI) x

Nuklearna Electrarna KRSKO Krsko (W) x Ringhals AB Ringhals 2, 3 & 4 (W) x Shikoku lkata 1, 2 & 3 (MHI) x Taiwan Power Co. Maanshan 1 & 2 0/V) x * Project participants as of the date the final deliverable was completed. On occasion,

additional members will join a project. Please contact the PWR Owners Group Program Management Office to verify participation before sending this document to participants not listed above.

v


Westinghouse Non-Proprietary Class 3 vi-

TABLE OF CONTENTS

LIST OF TABLES ............................ _ .......................................................................................... vii

ACRONYMS AND ABBREVIATIONS ....................................................................................... viii

ACKNOWLEDGEMENTS .......................................................................................................... ix

1 EXECUTIVE SUMMARY .............................................................................................. 1-1 2 INTRODUCTION .......................................................................................................... 2-1 3 BACKGROUND ............................................................................................................ 3-1 4 APPROACH DESCRIPTION ....................................................................................... .4-1

4.1 EVALUATION OF FABRICATION-RELATED COLD-WORK ........................... .4-1 4.2 EVALUATION OF MATERIALS SPECIFIED FOR RV INTERNALS ................. .4-2

5 RESULTS ............................................. ~ ....................................................................... 5-1 5.1 EVALUATION OF CE AND WESTINGHOUSE PLANT DESIGN

CONFIGURATIONS .......................................................................................... 5-1 5.2 EVALUATION OF CE AND WESTINGHOUSE PLANT VINTAGES ................... 5-3 5.3 EVALUATION OF B&W PLANTS ...................................................................... 5-4

6 CONCLUSIONS ........................................................................................................... 6-1 7 REFERENCES ............................................................................................................. 7-1 APPENDIX A PLANT MATERIALS EVALUATION DETAILS .................................................. A-1 APPENDIX B MATERIALS REVIEWED FOR CE-DESIGNED PLANTS ................................ B-1 APPENDIX C MATERIALS REVIEWED FOR WESTINGHOUSE-DESIGNED PLANTS ........ C-1


Table 5-1

Table 5-2

Table 5-3

TableA-1

Table A-2

Table A-3

Table B-1

Table C-1

Westinghouse Non-Proprietary Class 3 vii

LIST OF TABLES

CE Plants Reviewed for Cold-Work .................................................................. 5-1

Westinghouse Plants Reviewed for Cold-Work ................................................ 5-2

Significant Differences Regarding Cold-work in Editions of the ASME B&PV Code [30] [31] [32] [33] [34] [35] [36] ......................................................................... 5-4

List of Austenitic Stainless Steels from Drawings for Reactor Vessel Internals. A-2

MRP 2013-25 Categorization of Austenitic Stainless Steels and Guidelines for Susceptibility to SCC ....................................................................................... A-3

Stainless Steel Bin Categories by Specification ............................................... A-7

MRP-227-A CE Design Component Materials .................................................. B-1

MRP-227-A Westinghouse Design Component Materials ................................ C-1


_]

AfLAI ASME ASTM B&W B&PV BMI BWR CASS CE CEA GSSS l&E ICI ITH EPRI MRP NRC PWR PWROG RAI RV RVLMS sec scs SE SS UHi

PWROG-15105-NP


ACRONYMS AND ABBREVIATIONS

I

applicant/licensee action item American Society of Mechanical Engineers American Society for Testing and Materials Babcock & Wilcox Boiler and Pressure Vessel bottom mounted instrumentation boiling water reactor cast austenitic stainless steel Combustion Engineering control element assembly guide structure support system inspection and evaluation in-core instrumentation inverted top hat Electric Power Research Institute Materials Reliability Program Nuclear Regulatory Commission pressurized water reactor Pressurized Water Reactor Owner's Group request for additional information reactor vessel reactor vessel level monitoring system stress corrosion cracking secondary core support safety evaluation stainless steel upper head injection

viii


Westinghouse Non-Proprietary Class 3 ix

ACKNOWLEDGEMENTS

The authors would like to thank the team who performed the cold-work asse~sments for the Westinghouse and Combustion Engineering plants, including Tom Hamm, John Long, Mary Ann Walsh, Taylor Terek, Beth Paden, Brad Carpenter, Jessica Tatarczuk, Ty Holderbaum, Luyen Nguyen, and Ben Cramer.

Thank you to the AREVA NP team of Steve Fyfitch, Sarah Davidsaver, and Tammy Natour, for valuable contributions, both in technical discussion and in providing information for B&W plants.

Special thanks are owed to Dan Denis for documenting the technical basis for the Westinghouse and CE cold-work assessments, upon which much of this report is based.

Thanks are also owed to the project team, including Patricia Paesano, Jason Cecchetti, Cheryl Boggess, Brad Grimmel, and Jim Molkenthin for assistance in organizing the project efforts.

PVVROG-15105-NP April 2016 Revision 0

Westinghouse Non-Proprietary-Class 3 1-1

1 EXECUTIVE SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) Safety Evaluation (SE) issued on Materials Reliability Program (MRP) technical report MRP-227 [1] contains eight Applicant/Licensee Action Items (A/LAls). These eight action items must be completed in the implementation of the Inspection and Evaluation (l&E) Guidelines outlined in MRP-227-A [2]. PA-MSC-1288 was developed to provide utilities an efficient method for responding to these A/LAls and subsequent requests for additional information (RAls).

As utilities responded to A/LAls 1 and 2, the NRC issued RAls on the responses. As is discussed in [3], one question common to these RAls was regarding cold-worked material in the reactor vessel (RV) internals:

"Does the plant have non-weld or bolting austenitic stainless steel (SS) components with 20 percent cold-work or greater, and if so, do the affected components have operating stresses greater than 30 ksi? (If both conditions are true, additional components may need to be screened in for stress corrosion cracking, SCC.)" [3]

It is important to note that sec has never been observed in austenitic stainless steel components under normal conditions in the pressurized water reactor (PWR) environment, and that the potential for sec due to cold-work is believed to be a highly remote possibility [4]. While generic guidance for responding to this question was provided in [3], the resulting reviews of individual plants' component fabrication records required to generate responses on this basis have been found to be very time consuming and resource intensive. This process has placed significant burden on the utilities and, presumably on the NRC in conducting reviews of essentially similar plant responses. For this reason, the Pressurized Water Reactor Owner's Group (PWROG) authorized PA-MSC-1288, Rev. 2, to leverage the data in currently available responses to this cold-work question to develop a consistent response that would provide credit for the entire domestic PWR fleet.

For Babcock & Wilcox (B&W) designed plants, cold-worked austenitic stainless steel materials had only been used in crimped locking cups and some fasteners [5].

For Westinghouse and Combustion Engineering (CE) designed plants, individual plant responses to the RAI have been required. Design data, including materials allowables for all internals components, were searched and assessed for potential material of fabrication and inclusion of cold-work to produce assurance of no cold-work on a plant-specific basis. To date, material cold-worked greater than 20 percent has not been identified outside of the previously considered fastener applications. These searches are demonstrated in this report to include a significant fraction of plants (56 percent of the Westinghouse plants and 43 percent of the CE plants) and to effectively cover early, median, and later plant designs.

The plant-specific assessments conducted to date have not discovered any use of materials with cold work greater than 20 percent in non-fastener applications in RV internals. It is therefore concluded that it is reasonable to assume that, going forward, no materials with coldwork greater than 20 percent will be found in non-fastener components in the RV internals of


Westinghouse Non-Proprietary Class 3 1-2

any other plants. On this basis, this report provides an adequate response to the NRC RAI regarding the potential for the use of cold-worked materials in non-fastener components in reactor vessel internals.

The report thereby provides additional assurance that the screening approach applied in developing MRP-227-A remains appropriate for such plants. This report can be used as the technical basis for stating that no non-fastener cold-work greater than 20 percent is present in the RV internals of domestic B&W, CE, and Westinghouse designed PWRs.



2 INTRODUCTION

The MRP developed inspection and evaluation guidelines for managing long-term aging of RV internals components for PWRs in MRP-227-A [2]. In MRP-175 [4], a precursor document to MRP-227-A, the industry identified screening criteria for RV internals component materials for use in determining susceptibility to sec under certain conditions. Cold-Worked austenitic stainless steel components and austenitic stainless steel welds were determined to be potentially susceptible materials if under sufficient stress. The screening criteria for potential sec susceptibility in austenitic stainless steels were set at an operating stress of 30 ksi and cold-work greater than 20 percent or at welded locations [4].

The screening criteria set in MRP-175 [4] were then applied to generic lists of plant components for B&W designed reactors [5] and CE and Westinghouse reactors [6]. The results of the screening and ranking process were used to develop the l&E guidelines set in MRP-227-A [2].

In the NRC Staff's SE on MRP-227-A [2], eight A/LAls were included by the NRC. The intent of these A/LAls was to ensure that the assumptions in MRP-227-A were valid for each plant intending to implement it. As utilities operating Westinghouse and CE designed plants began to respond to A/LAls 1 and 2, the NRC followed these responses with the following question:

"Does the plant have non-weld or bolting austenitic stainless steel (SS) components with 20 percent cold-work or greater, and if so, do the affected components have operating stresses greater than 30 ksi? (If both conditions are true, additional components may need to be screened in for stress corrosion cracking, SCC.)" [3]

One approach to responding to this question was to conduct a detailed review of the plantspecific fabrication and materials specifications for each RV internals component to determine if any such cold-work was present. While this approach provided a firm technical basis for an individual plant response, the effort and expense involved placed a burden on utilities. After several plants completed the cold-work review and determined that no non-fastener cold-work was present, the PWROG authorized PA-MSC-1288, Rev. 2 [7], with the goal of providing reasonable assurance to the NRC that no such cold-work is present in other operating domestic PWRs. This report summarizes the results and conclusions of that program.



3 BACKGROUND

MRP-175, Appendix A [4] contains an overview of sec as applicable to nuclear plant materials. The following four paragraphs contain some of the information from that overview that pertains to the subject of this report.

SCC occurs under a synergistic combination of susceptible material, corrosive environment, and stress. One factor in material susceptibility for SCC is believed to be the material's yield strength, which is increased by cold-work.

The conditions that contribute to sec were described in the scientific literature in 1957 by Williams in support of the Navy's use of austenitic stainless steels in heat transfer equipment [4]. The NRC published Regulatory Guide 1.44 [8] in 1973 describing controls for processing austenitic stainless steel to avoid susceptibility to SCC (primarily from sensitization). Regulatory Guide 1.44 requires that reactor coolant system materials be used in the solution annealed condition, or a condition which has been tested to assure resistance to SCC [8]. Current versions of ~he ASME (American Society of Mechanical Engineers) Code [9] state that sensitization and cold-work render the material susceptible to SCC, and that therefore these materials should be solution annealed and water quenched to mitigate this susceptibility. Therefore, the use of solution annealed material as prescribed in the Regulatory Guide would have precluded the use of cold-worked material.

sec has been observed to affect non-austenitic stainless steel components in the primary coolant environment of PWRs. Examples include dissimilar metal welds and guide tube support pins. Boiling water reactors (BWRs) have experienced stress corrosion cracking

, of the austenitic stainless steel core shroud (similar in size and shape to a PWR core barrel); however BWRs have a greater amount of dissolved oxygen in the coolant than PWRs, which is expected to contribute to the cracking issue.

No SCC has been observed to date in PWR internals fabricated with austenitic stainless steel [4]. However, the MRP-227-A screening process conservatively considered the remote possibility that the potential for SCC could occur in a severely cold-worked component under high levels of stress (greater than the room temperature material yield strength).

In the development of MRP-227-A [2], the precursor document MRP-189 [5] applied the screening ci-iteria developed in MRP-175 [4] to B&W plants. Through this effort (which included a search of manufacturing and fabrication records performed in 2005) it was identified that two items could potentially contain cold work greater than 20 percent: (1) crimped locking cups and (2) hot-headed or shot-peened Alloy A-286 bolts. Therefore, the cold-work question addressed to the CE and Westinghouse plants had already been addressed for B&W plants.

In order to address the cold-work question for CE and Westinghouse plants, many utilities participated in PA-MSC-0983 [1 O], conducting a cold-work assessment in accordance with MRP guidance [3]. During the review of component fabrication records, it was found that:


L --


1. The material of construction was typically solution annealed austenitic stainless steel 2. Material specifications or fabrication drawings often included upper limits on the yield

strength· of the material, effectively limiting the amount of strain hardening or cold-work that could be applied.

3. In the limited cases where cold-work may have been applied to non-fastener material after solution annealing, it was less than 3 percent, well below the 20 percent criterion.

Some fastener components were identified as potentially cold-worked, however this had already been considered in the development of MRP-227-A (in MRP-191 [6]) and so these are excluded from the NRC's cold-work question.

From the review of these data, it was concluded that special care had indeed been taken to exclude non-fastener cold-work from the RV internals. This care and concern was demonstrated in materials specifications, for example, which limit the ultimate strength of materials to below certain criteria. Review of data from Westinghouse and CE plants that have already conducted plant-specific cold-work assessments confirms that no coldworked materials have been found in non-fastener RV internals applications.


. Westinghouse Non-Proprietary Class 3 4-1

4 APPROACH DESCRIPTION

A significant fraction of the domestic CE and Westinghouse PWR fleet has already been reviewed for cold-work as part of PA-MSC-0983 [1 O], which was intended to provide responses to the NRC's plant-specific RAl's. In preparing MRP-189 [5], record searches performed in 2005 for the B&W designed plants addressed the cold-work issue for those plants. Thus, the detailed evaluation of specific plants and predictions based on this experience described in this section is only applicable for Westinghouse and CE plants.

For the Westinghouse and CE plants, fabrication records, including component drawings, material specifications, and fabrication procedures, were reviewed as part of the PA-MSC-0983 effort to determine if any cold-work may have been present in RV internals components. Drawings were examined for component forming processes to determine if any cold-work could have been induced during component fabrication and on-site assembly. Drawings were also examined to identify material call outs and, in comparison with the prevailing materials specifications at the time of construction, to determine if material with greater than 20 percent cold-work could have been used in that plant's construction.

The assessments conducted to date have been performed according to a consistent approach [3] to identify the potential for cold-work in the materials of construction or by incorporation during plant component fabrication. The information collected to date (according to the process described below) demonstrates that no evidence of the use of material with greater than 20 percent cold-work in non-fastener applications has been uncovered in any of the plants considered. These assessments effectively demonstrate that no usage of cold-worked materials has been identified to date. The conclusions can be then compared to categorizations of the remaining plant population in order to determine whether the findings of the previous investigations should be relevant to the remaining plants. On this basis, it should be possible to project whether the potential for the use of cold-worked materials in RV internals non-fastener applications would or would not be expected to be a concern for any of the remaining plants.

4.1 EVALUATION OF FABRICATION-RELATED COLD-WORK

While bending and forming of metals are widely employed in developing metal shapes for nonnuclear structures, because of concerns about the long-term impact of cold-work on materials performance, cold-work has generally been avoided in fabricating nuclear power plant components, especially those found in the reactor vessel internals.

Field fit-up·and auxiliary processes that could introduce cold work are expected to provide only minor increases of cold work and minor increases of potential susceptibility to sec. Additional

. macroscopic strain hardening induced by fit-up would be expected to be small compared to the 20% allowable. The most significant additional cold work induced by these processes would be expected to be quite local and would be considered to primarily affect the surface of the component [3].

The only potential cold-work fabrication concerns are then limited to intentional deformations applied to flat or straight product in order to produce the required component shapes. Such processes were typically avoided in the fabrication of internals for PWR's. The only mechanical

PWROG-15105~NP April 2016 Revision 0

Westinghouse Non-'Proprietary Class 3 4-2

cold forming identified for the RV internals was bending to shape the internals conduit. This conduit is identified as 'In-Core Instrumentation (ICI) - ICI thimble tubes-upper' in Table 4-5 of MRP-191 [6] for CE-designed plants and 'Upper Internals Assembly - Upper Instrumentation Conduit and Supports - Conduit' in Table 4-4 of MRP-191 [6] for Westinghouse-designed plants.

Examination of plant component drawings indicated that in the limited instances where bending was applied, the incremental cold-work introduced was constrained to less than 3 percent by the geometry of the allowed bends. Thus, it is concluded that in all of the plants considered to date, cold-work from part fabrication would not have significantly added to the cold-work level of the utilized material. Therefore, the only concern with regard to the cold-work level of the materials employed in the construction of plant reactor vessel internals is the inherent cold-work in the specified and procured material.

4.2 EVALUATION OF MATERIALS SPECIFIED FOR RV INTERNALS

CE- and Westinghouse-designed plants conducted evaluations of RV internals materials and fabrication following the guidance of [3]. The process consists of reviewing the engineering drawings for each part, determining if the material specified included cold work; determining if the fabrication of the component involved cold-working the component (bending) without subsequent solution annealing, and, based on these determinations, assigning the material to the appropriate category. Per MRP 2013-025, surface grinding was not considered to contribute significantly to sec susceptibility [3].

In some instances, a drawing allowed for the use of an alternate material. In this case, it was assumed for the purposes of the evaluation that the more conservative material type with respect to allowed cold-work was the one that had been used in plant construction. Note that, while the design configuration of the RV internals underwent several evolutions, the material of fabrication for the vast majority of components was consistently specified to be solution annealed austenitic stainless steel. Specific exceptions include martensitic stainless steel for hold-down springs and nickel-based alloys or cold-worked stainless steel for certai11 fasteners. In frequent cases, specifications were found to be augmented by limitations on the material hardness or strength. This effectively corresponds to limitations on allowed cold-work at the 20 percent level. Thus the evidence to date supports the conclusion that no cold worked material was used in the construction of the RV internals for the domestic operating PWR fleet.

Additional details of the evaluation process can be found in Appendix A. The material specifications reviewed and corresponding categorizations can be found in Appendix B for CEdesigned plants and Appendix C for Westinghouse-designed plants.


Westinghouse Non-Proprietary Class 3- 5-1

5 RESULTS

In order to provide a basis for prediction of the potential for cold-worked materials having been used in the construction of RV internals in other CE and Westinghouse plants, the data obtained to date (viz. that no cold-worked materials were found in the materials of non-fastener components of the RV internals) were compared with the potential designs and periods of construction of the other plants that may be under consideration with respect to the potential use of cold-worked materials.

5.1 EVALUATION OF CE AND WESTINGHOUSE PLANT DESIGN CONFIGURATIONS

Table 5-1 and Table 5-2 list the CE- and Westinghouse-designed units, respectively, that have already been reviewed for cold-work. These tables list the major design features of each unit's RV internals. The examined plants represent 56 percent of the Westinghouse designed plants and 43 percent of the CE plants. Moreover, the major design features of the assessed plants can be compared with those expected for other plants that have not already been addressed. No different features are expected in the designs of the plants that have not yet been assessed. These comparisons provide a basis for the determination of whether the already established conclusions regarding the potential for the use of cold-worked materials in non-fastener applications can be applicable to the plants that have not been previously assessed.

Table 5-1 CE Plants Reviewed for Cold-Work

Fuel Type Commercial Operation Plant Design Date

Millstone 2 [11] 800MW 14x14 December 1975

Fort Calhoun f 121 Bolted shroud 14x14 September 1973

Palo Verde 1 [13] System 80 16x16 January 1986

Palo Verde 2 [13] System 80 16x16 August 1986

Palo Verde 3 [13] System 80 16 x 16 January 1988

Waterford 3 [14] 3410 type 16 x 16 September 1985



Table 5-2 Westinghouse Plants Reviewed for Cold-Work

# Upper Internals Lower Internals Commercial Plant Loops Fuel Type Design Design Operation Date

Prairie Island 1 [15] 2 14x14 Inverted Top Hat Flat December 1973

Prairie Island 2 [151 2 14x14 Inverted Top Hat Flat December 197 4

H.B. Robinson [16] 3 15x15 Flat Flat March 1971

Turkey Point 3 [17] 3 15x15 Flat Flat December 1972

Turkey Point 4 f 171 3 15x15 Flat Flat September 1973

Beaver Valley 1 [18] 3 17x17 Flat Flat September 1976

Beaver Valley 2 f 181 3 17x17 Flat Flat November 1987

Callaway f191 4 17x17 Inverted Top Hat Flat April 1985

D.C. Cook 1 [20] 4 15x15 Top Hat Dome August1975

D.C. Cook 2 [20] 4 17x17 Top Hat Dome July 1978

Braidwood 1 f 211 4 17x17 Top Hat Flat July 1988

Braidwood 2 [21] 4 17x17 Top Hat Flat October 1988

Byron 1 f22] 4 17x17 Top Hat Flat September 1985

Byron 2 f22] 4 17x17 Top Hat Flat August 1987

Sequoyah 1 [23] 4 17x17 Inverted Top Hat Dome July 1981

Sequoyah 2 [23] 4 17x17 Inverted Top Hat Dome June 1982

McGuire 1 [241 4 17x17 Inverted Top Hat Flat December 1981

McGuire 2 [24] 4 17x17 Inverted Top Hat Flat March 1984

Catawba 1 f 251 4 17x17 Inverted Top Hat Flat June 1985

Catawba 2 [25] 4 17x17 Inverted Top Hat Flat August 1986

Seabrook 1 [26] 4 17x17 Inverted Top Hat Flat August 1990

Salem 1 [27] 4 17x17 Top Hat Dome June 1977

Salem 2 [27] 4 17x17 Top Hat Dome October 1981

Diablo Canyon 1 f281 4 17x17 Top Hat Dome May 1985

Diablo Canyon 2 f28l 4 17x17 Flat Flat March 1986

South Texas 1 [29] 4XL 17x17 Inverted Top Hat Flat August1988

South Texas 2 [29] 4XL 17x17 Inverted Top Hat Flat June 1989

The designs assessed to date effectively cover all of the CE and Westinghouse designs that were fabricated in the US during the period from 1970 to 1990. Thus, the examined data can be considered to be effectively representative of the possible plant designs that may need to be evaluated during relicensing for the period of extended operations. Conclusions based on the plants considered to date should be valid, therefore, for all of those plant designs. The fact that no cold-worked materials were found in the previously assessed plant designs indicates that no cold-work would be discovered in the designs of any other, heretofore not assessed, plants.



5.2 EVALUATION OF CE AND WESTINGHOUSE PLANT VINTAGES

Table 5-1 and Table 5-2 list the commercial start dates for the previously assessed CE- and Westinghouse-designed units. The plants listed in these two tables represent early, median, and later plant designs providing reasonable assurance that confirmation of no cold-work has been completed over a sufficiently representative portion of the fleet. The majority of the plants listed in Table 5-1 and Table 5-2 began operation well after the implementation of regulatory requirements that would have prohibited cold-work (May 1973 [8]). By comparing component drawings and materials specifications from the time periods before and after this guidance was released, it is clear that the use of solution annealed material was standard practice in the fabrication of: RV internals before it was a regulatory requirement.

The ASME B&PV (Boiler & Pressure Vessel) Code Editions for the various specifications were also compared to determine if any significant changes that could impact the cold-work assessments were made on this basis. Comparisons were also made between the various editions of the ASTM (American Society for Testing and Materials) standards. The results are tabulated in Table 5-3. No significant changes in material specifications reviewed were identified. The reviewed material specifications include specifications as early as 1963 and as late as 1983. Thus, material call outs in plant drawings across this time frame refer to essentially identical materials with respect to cold-work considerations .

• The results of plant-specific cold-work reviews and results of comparison of the materials specifications across time demonstrate that there is no effect of plant vintage on the potential inclusion of cold work. Therefore, the assessments of the potential for the use of cold-worked materials made on the plants examined to date should be reliable predictors of the material

. used in the other operating plants. On this basis, it is reasonable to expect that no cold-work will be identified in the non-fastener components in other operating, domestic, CE and Westinghouse designed PWR internals given that the plants were constructed during the same time period.

I _)



Table 5-3 Significant Differences Regarding Cold-work in Editions of the ASME B&PV Code [30] [31] [32] [33] [34] [35] [36]

ASME B&PV Code Edition

Specification Earlier ASTM · 1971 1974 1977 1980 1983

standard

A182 (SA-182) A 182-65 [37] A182-68 A182-72 A182-75 A182-78 A182-79a No Change No Change No Change No Change No Change No Change

A193 (SA-193) A 193-66 [38] A193-69 A193-71 A193-75 A193-78a A193-79a No Change No Change No Change No Change No Change No Change

- A194-69 A194-71 A194-74 A194-78 A194-80a A194 (SA-194)

No Change No Change No Change No Change No Change

- A213-66 A213-71 A213-76 A213-76a A213-81a A213 (SA-213)


- A240-69 A240-72b A240-75A A214-78a A240-80b A240 (SA-240)


- A249-65 A249-71 A249-75 A249-77 A249-82 A249 (SA-249)


- A479-63 A479-72 A479-75 A479-78 A479-80 A479 (SA-479)


A511 - A511-71 N/A N/A N/A N/A

No Change

5.3 EVALUATION OF B&W PLANTS

As noted above, cold-work assessments have not been required within this project for the B&W plants. Consideration of the potential for cold-work was included and documented in MRP-189 [5]. There were two component items that potentially contain cold-work greater than 20 percent identified to exist in the B&W reactor vessel internals: (1) crimped locking cups and (2) hotheaded or shot-peened Alloy A-286 bolts.



6 CONCLUSIONS

Plant-specific evaluations of RV internals component design drawings have assessed the possibility for the inclusion of cold-worked austenitic stainless steel with the potential for sec susceptibility in a significant fraction of the US domestic operating plants. By examination of the regulatory requirements, of the fabrication practices at the time of the RV internals' construction, and of the detailed specifications of the materials of construction, it is clear that for non-fastener components care was always taken to use material in the non-cold-worked (solution annealed) condition.

Cold-Worked components in B&W-designed units were assessed in MRP-189 [5]. No nonfast~ner components were identified as cold-worked. Therefore there is no need for further assessments of cold-work for the internals of these plants. For Westinghouse and CE-designed units, a representative majority of the domestfc fleet of PWR plants has been reviewed to determine the extent of cold-work present in the RV internals. The reviewed plants effectively represent early, median, and later plant designs that might need to be considered in future plant evaluations. No cold-work greater than 20 percent has been identified for any non-fastener RV internals components in reviews of approximately 50 percent of the installed Westinghouse and CE design fleet. It is therefore reasonably assured that no such cold-work will be identified in the remainder of the domestic PWR fleet going forward. On this basis, no additional components need to be screened-in for potential susceptibility to SCC due to cold-work in the application of MRP-227-A [2].

This evaluation provides a basis for responses to the NRC RAls regarding the potential for the use of cold-worked materials in non-fastener components. It provides additional assurance that the screening approach applied in developing MRP-227-A remains appropriate. This report can be used as the technical basis for stating that no non-fastener cold-work greater than 20 percent is present in the RV internals of domestic B&W, CE, and Westinghouse designed PWRs.



7 REFERENCES

1. Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, (MRP-227 Rev. 0). EPRI, Palo Alto, CA: 2008. 1016596.

2. Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, (MRP-227-A). EPRI, Palo Alto, CA: 2011. 1022863.

7-1

3. MRP Letter 2013-25, "MRP-227-A Applicability Template Guideline," October 14, 2013. 4. Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism

Screening and Threshold Values (MRP-175). EPRI, Palo Alto, CA: 2006. 1012081. 5. Materials Reliability Program: Screening, Categorization, and Ranking of B&W-Designed

PWR Internals Component Items (MRP-189-Rev. 1). EPRI, Palo Alto, CA: 2009.

1018292. 6. Materials Reliability Program: Screening, Categorization, and Ranking of Reactor

Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191). EPRI, Palo Alto, CA: 2006. 1013234.

7. PWROG Project Authorization, PA-MSC-1288, "PWR Materials Assessment", Revision

2." 8. U.S. Atomic Energy Commission Regulatory Guide 1.44, "Control of the Use of

Sensitized Stainless Steel," May 1973. 9. ASME International Boiler & Pressure Vessel Code, Section Ill, Appendix W-2130,

"Materials," 2013 Edition. 10. PWROG Project Authorization, PA-MSC-0983, "Support for Applicant Action Items 1, 2,

and 7 from the Final Safety Evaluation on MRP-227, Revision O." 11. PWROG-140?,-1-P, Rev. 0, "Millstone Unit 2 Summary Report for the Cold-work

Assessment," December 9, 2014. 12. PWROG-14080-P, Rev. 0, "Fort Calhoun Station Summary Report for the Cold-work

Assessment," January 15, 2015. 13. APS Letter, "Palo Verde Nuclear Generating Station Units 1, 2, and 3 Docket Nos. STN

50-528, 529, and 530 Response to Request for Additional Information (RAI) -Pressurized Water Reactor (PWR) Internals Aging Management Program Plan," July 23,

2014. ADAMS Accession Number ML 14205A438. 14. PWROG-15041-P, Rev. 0, "Waterford Unit 3 Summary Report for the Cold Work

Assessment," June 4, 2015. 15. PWROG-14042-P, Rev. 0, "Prairie Island Units 1 and 2 Summary Report for the Cold

Work Assessment," October 6, 2014. 16. PWROG-14030-P, Rev. 0, "H.B. Robinson Unit 2 Summary Report for the Cold Work

Assessment," August 21, 2014. 17. PWROG-14032-P, Rev. 0, "Turkey Point Units 3 and 4 Summary Report for the Cold

Work Assessment," August 21, 2014. 18. PWROG-15029-P, Rev. 0, "Beaver Valley Units 1 & 2 Summary Report for the Cold

Work Assessment," August 6, 2015. 19. Westinghouse Letter LTR-RIAM-14-25, Rev. 0, "PWROG PA-MSC-0983 Revision 1

Task 6 Final Summary Report for Callaway Unit 1," March 27, 2014.


Westing!'louse Non-Proprietary Class 3 7-2

20. PWROG-14044-P, Rev. 1, "D.C. Cook Units 1 and 2 Summary Report for the Cold-work Assessment in Support of RAls Regarding NLAI 1 for MRP-227," January 22, 2015.

21. PWROG-14040-P, Rev. 1, "Braidwood Units 1 and 2 Summary Rep0rt for the Cold Work Assessment," October 17, 2014.

22. PWROG-14039-P, Rev. 2, "Byron Units 1 and 2 Summary Report for the Cold Work Assessment," October 17, 2014.

23. PWROG-14021-P, Rev. 1, "Sequoyah Units 1 and 2 Summary Report for the Cold Work Assessment," August 19, 2014.

24. PWROG-14054-P, Rev. 0, "McGuire Units 1 and 2 Summary Report for the Cold Work Assessment," December 2, 2014.

25. PWROG-14055-P, Rev. 0, "Catawba Units 1 and 2 Summary Report for the Cold Work Assessment," December 2, 2014.

26. PWROG-15042-P, Rev. 0, "NextEra Energy, Seabrook Unit 1 Summary Report for the Cold Work Assessment," May 2015.

27. Westinghouse Letter L TR-RIAM-15-68, Rev. 0, "Salem Units 1 and 2 Summary Report for the Cold Work Assessment - Request for Transmittal," October 1, 2015.

28. Westinghouse Letter L TR-RIAM-15-90, Rev. 0, "Diablo Canyon Units 1 and 2 Summary Report for the Cold Work Assessment - Request for Transmittal," December 14, 2015.

29. PWROG-15027-P, Rev. 0, "South Texas Units 1 and 2 Summary Report for the Cold Work Assessment," July 8, 2015.

30. ASME International Boiler & Pressure Vessel Code, Section II, Part A, "Materials," 1971 Edition.







37. ASTM Standard Specification A 182-65, "Forged or Rolled Alloy-Steel Pipe Flanges, Forged Fittings, and Valves and Parts for High-Temperature Service," 1965.

38. ASTM Standard Specification A 193-66, "Alloy-Steel Bolting Materials for HighTemperature Service," 1966.


Westinghouse Klan-Proprietary Class 3 A-1

APPENDIX A PLANT MATERIALS EVALUATION DETAILS

Table A-1 lists the ASTM and ASME specifications for the materials that were referenced in plant drawings for CE and Westinghouse designed internals. Each of these material specifications corresponds to a specific material called out in the ASME Code (or an ASTM standard). The wording used to designate and call out the materials on the drawings were consistent and, thus, allowed the grouping of the materials into specific categories. In some instances, a drawing allowed for the use of an alternate material. In this case, it was assumed for the purposes of the evaluation that the more conservative material type with respect to allowed cold-work was the one that had been used in plant construction. Note that, while the design configuration of the RV internals 1,mderwent several evolutions, the material of fabrication for the vast majority of components was consistently specified to be solution annealed austenitic stainless steel. Specific exceptions include martensitic stainless steel for hold-down springs and nickel-based alloys or cold-worked stainless steel for certain fasteners. In frequent cases, specifications were found to be augmented by limitations on the material hardness or strength. This effectively corresponds to limitations on allowed cold-work at the 20 percent level.

Determination of the potential for cold-work in the materials purchased for fabrication of plant internals is based upon the allowable materials specified in the plant component drawings. It is reasonable to use the specifications of those materials to identify the potential for cold-work. MRP 2013-25 [3] identifies a procedure for "binning" the austenitic stainless steels of construction of reactor internals into five categories and identifies those categories that need to be considered as potentially having sufficient cold-work (i.e., greater than 20 percent) to be susceptible to sec. Table A-2 lists the five categories of austenitic stainless steel used in construction of internals and provides guidance for evaluating such materials.

MRP-2013-25 [3] notes that all materials in Category 1, 2, and 3 should be considered not susceptible to SCC. These materials, by specification, have less than 20 percent cold-work. Category 4 includes material specifications that may allow more that 20 percent cold-work, but these are fastener applications and, as such, are excluded from consideration in this discussion (as they were conservatively assumed susceptible to sec in MRP-191 [6]). Finally, the materials that correspond to category 5 could have been employed in non-fastener applications and included some cold-work without subsequent solution annealing. In those cases, these category 5 materials were further investigated to determine if the cold-work could have potentially exceeded 20 percent. However, in all cases, component drawing call outs have been found to limit the material strength or hardness such that it could be concluded that the allowed cold-work was limited, or, the cold-work was the result of bending and limited to less than 3 percent. Therefore, the category 5 materials have all been further categorized as containing less than 20 percent cold-work and not susceptible to sec.

PWROG-15105-NP April2016 Revision 0

Westinghouse Nen.:Proprietary-Class 3 A-2

Table A-1 List of Austenitic Stainless Steels from Drawings for Reactor Vessel Internals

ASTM Standard (ASME Specification)

A182 (SA-182)

A193 (SA-193)

A194 (SA-194)

A213 (SA-213)

A240 (SA-240)

A249 (SA-249)

A269

A276

A296

A312 (SA-312)

A336 (SA-336)

A358 (SA-358)

A376 (SA-376)

A451

A473

A479 (SA-479)

A511

PWROG-15105-NP

Description (From Specification Title)

Forged or Rolled Alloy and Stainless Steel Pipe Flanges, Forged Fittings, and Valves and Parts for

High-Temperature Service

Alloy-Steel and Stainless Steel Bolting Materials for High-Temperature Service

Carbon and Alloy Steel Nuts for Bolts for High Pressure or High Temperature Service, or Both

Seamless Ferritic and Austenitic Alloy-Steel Boiler, Superheater, and Heat-Exchanger Tubes

Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels and

for General Applications

Welded Austenitic Steel Boiler, Superheater, Heat-Exchanger, and Condenser Tubes

Standard Specification for Seamless and Welded Austenitic Stainless Steel Tubing for General

Service

Standard Specification for Stainless and Heat-Resisting Steel Bars and Shapes

Tentative Specification for Corrosion-Resistant Iron-Chromium and Iron-Chromium-Nickel Alloy

Castings for General Application

Specification for Seamless and Welded Austenitic Pipes

Specification for Alloy Steel Forgings for Pressure and High-Temperature Parts (Note: Current specification no longer contains austenitic

material)

Specification for Electric-Fusion-Welded Austenitic Chromium-Nickel Alloy Steel Pipe for High-

Temperature Service

Specification for Seamless Austenitic Steel Pipe for High-Temperature Central-Station Service

Standard Specification for Centrifugally Cast Austenitic Steel Pipe for High-

Temperature Service

Standard Specification for Stainless and Heat-Resisting Steel Forgings

Stainless Steel Bars and Shapes for Use in Boilers and other Pressure Vessels

Standard Specification for Seamless Stainless Steel Mechanical Tubing


Table A-2

Category

1

2

3

4


MRP 2013-25 Categorization of Austenitic Stainless Steels and Guidelines for Susceptibility to SCC

A-3

Possible Potentially Susceptible to Material Type Cold-Work

> 20% sec

Cast Austenitic Stainless Steel No No

Hot Formed Austenitic Stainless No No Steel

Annealed Austenitic Stainless No No Steel

Yes Generally No, unless (Assumed Austenitic Steel Fasteners

Yes in specification identifies

MRP-191) possibility of> 20% Cold-Work

Cold Formed Austenitic Stainless 5 Steel without Subsequent Solution Yes Yes, if> 20% Cold-Work

Annealing

The detailed information regarding how the possible materials of construction may be categorized with respect to the cold-work criteria of Table A-2 is found in the individual material specifications. Thus, for a specific plant, the material specified in the component drawing and its characteristics stated in the ASME Code or ASTM requirements determine whether a material would be considered sufficiently cold-worked to be potentially susceptible to SCC as per Table A-2. The key characteristics of the relevant material of construction, as considered in the previously performed plant assessments for cold-work, were identified as follows:

A182: Identified as "ASME SA-182 F 304 Water Quenched Carbon Content 0.04% to 0.08%, Co Content 0.02% Maximum" in plant drawings. The ASME SA-182 specification cites that this material must be furnished in the solution annealed condition. Thus this material is considered to be in the material category Annealed Austenitic Stainless Steel corresponding to MRP 2013-25 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to sec. A193: Identified as "ASME SA-193 Class 2 B8M Co Content 0.25% Maximum Mechanical Properties: Tensile Strength 95 ksi Minimum, Yield Strength 65ksi Minimum to 90 ksi Maximum". This material is a fastener material and to meet mechanical properties would be delivered in the strain hardened condition (The material is to be solution treated prior to strain hardening). This material is limited to a Brinell hardness of 320 and must display 12 to 15 percent remaining (elongation) ductility. These requirements indicate that the as-delivered condition is restricted to less than 20 percent cold-work in the strain hardened condition. Thus this material is considered to be fastener material in Category 4 with less than 20 percent cold-work and is not susceptible to sec. A194: Identified as "ASME SA-194 Type 304 Co Content 0.20% Maximum Fastener Material" in plant drawings; thus this material is considered to be materials type which corresponds to MRP 2013-25 Category 4. The material may be delivered in a strain hardened condition. If the strain


Westinghouse Non-Proprietary Class 3 A-4

hardening is restricted so that the yield strength is below 90 ksi then the materials cold-work is less than 20 percent and it would be considered not susceptible to SCC. However if the yield strength is not specified then strain hardening might be considered to incur cold-work of greater than 20 percent.

A213: Identified as "ASME SA-213 Type 304 Cold Drawn Cobalt Content 0.20% Maximum C Content 0.04 to 0.08%" in plant drawings. The ASTM standard cites that this tubing product shall be formed by cold drawing but delivered in the fully solution annealed condition; thus this material is considered to be a fully annealed material type which corresponds to MRP 2013-25 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to sec. A240: Identified as "ASME SA-240 Type 304 Hot Rolled, Heat Trea.ted and Pickled, Co Content 0.20% Maximum" in plal)t drawings. The ASME specification cites that this material is delivered in the fully solution treated condition; thus this material is considered to be a fully annealed material type which corresponds to MRP 2013-025 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to SCC.

A249: Identified as "ASME SA-249 Grade TP 304 Carbon Content 0.04-0.08 Co Content 0.20%" in plant drawings. The ASTM standard cites that all tubing shall be delivered in the solution annealed condition; thus this material is considered to be a fully annealed material type which corresponds to MRP 2013-25 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to sec A269: Identified as "ASTM A269 Type 304 Welded Tubing" in plant drawings. The ASTM standard cites that all material shall be furnished in the solution annealed condition, corresponding to MRP 2013-025 Category 3. The material is therefore considered to contain less than 20 percent "cold-work and is not susceptible to sec. A276: Identified as "ASTM A276 Type 304 Hot Rolled Pickled Cond A" in plant drawings. The material specification for Condition A allows "hot finished and annealed" and "cold finished and annealed" product forms. "Condition S" of the specification allows a cold-worked product form. The annealed material corresponds to MRP 2013-025 Category 3 while the cold-worked material corresponds to MRP 2013-025 Category 5.

A296: Identified as "ASTM A296 Gr CF8" in plant drawings. This is CF8 cast material and is a cast austenitic stainless steel (CASS), which corresponds to MRP 2013-025 Category 1. A296 also specifies solution annealing after casting. The material is not worked and thus contains less than 20 percent cold-work and is not susceptible to sec. A312: Identified as "ASTM A312 Type 304 Cold Drawn Seamless" in plant drawings. The ASTM standard states that "all pipe shall be furnished in the heat treated condition", corresponding to MRP 2013-025 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to sec. A336: Identified as "ASTM A336 Type F8" in plant drawings. This grade was split from the modern specification (which only contains low alloy steel forgings) but was part of the specification during the time of plant manufacture. Type F8 corresponded to Type 304 stainless steel and Type F8M corresponded to Type 316 stainless steel. The specification states "The austenitic stainless steels shall receive a carbide solution treatment", corresponding to MRP


Westinghouse Non-Proprietary Ciass 3 A-5

2013-025 Category 3. The material is therefore considered to contain less than 20 percent coldwork and is not susceptible to sec. A351: Identified as "A351 ASME SA-351 CF8" in plant drawings. This is CF8 cast material and is a cast austenitic stainless steel (CASS), which corresponds to MRP 2013-025 Category 1. ASME SA-351 also specifies solution annealing after casting. The material is not worked and thus contains less than 20 percent cold-work and is not susceptible to sec. A358: Identified as "ASTM A358 Type 304 Electric-Fusion Welded Pipe" in plant drawings. The ASTM standard states that austenitic material shall be solution annealed to a minimum of 1900°F, corresponding to MRP 2013-025 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to SCC.

A376: Identified as "ASTM A376 Type 304 Cold Finished and Heat Treated" in plant drawings. The ASTM standard states that "all pipe shall be furnished in the heat-treated condition", corresponding to MRP 2013-025 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to SCC.

A451: Identified as "A451 ASME SA-451 CF8" in plant drawings. This is CF8 centrifugally-cast material and is a cast austenitic stainless steel (CASS), which corresponds to MRP 2013-025 Category 1. ASME SA-451 also specifies solution annealing after casting. The material is not worked and thus contains less than 20 percent cold-work and is not susceptible to SCC.

A473: Identified as "ASTM A373 (Type 304A)" in plant drawings. ASTM A473 notes that "the austenitic steel... shall receive a solution heat treatment", corresponding to MRP 2013-025 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to sec. A479: Identified as "ASME SA-479 Type 304 Centerless Ground Hot Finished, qo Content 0.20% Maximum" in plant drawings. This material is supplied in the "Hot Finished" condition and therefore considered to be an MRP 2013-25 Category 2 material. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to SCC. Care should be taken when A479/SA-479 material is used in fastener applications, or when drawings specifically refer to strain hardened material. Strain hardened A479/SA-479 materials may have cold-work greater than 20 percent. Some components required a solution anneal treatment, making those components MRP 2013-025 Category 3. If the application is a fastener, conservatism would cause the component (for the material application) to be assigned to MRP 2013-025 Category 4. If the material is strain hardened but is not a fastener, the component would be assigned to MRP 2013-025 Category 5.

A511: Identified as "A511C01' in plant drawings, corresponding to ASTM A511. ASTM A511 notes that unless specifically called out as temper hardened material, this material would be furnished in the solution annealed condition; thus this material is considered to be an Annealed Austenitic Stainless Steel material which corresponds to MRP 2013-25 Category 3. The material is therefore considered to contain less than 20 percent cold-work and is not susceptible to SCC.

Applying the above definitions to the materials called out on the drawings for each component in the RV internals allows identification of the appropriate materials categories per MRP 2013-025 [3] to be applied to the materials of construction of the plant RV internals as per Table A-3. This process was applied in all of the evaluations of Westinghouse and CE plants conducted to date.


Westinghouse Non-Proprietary Class-3 A-6

The complete results of the materials evaluation are contained in Appendix B for CE plants, and Appendix C for Westinghouse designed plants. In these appendices, the applicable material specifications and MRP 2013-025 [3] categories (as determined during the plant-specific reviews) are defined for each component called out in MRP-191 [6]. The data for Appendix Bis taken from the references listed in Table 5-1, and the data in Appendix C is taken from the references listed in Table 5-2. Note that some components in Table A-1 (CE data, Appendix 8) do not have an associated identified material. This is because many of these components were reviewed for cold-work as part of one specific plant's cold-work assessment, which did not assign specific material specifications to each component. Overall, no non-fastener material with coldwork greater than 20 percent was identified in CE or Westinghouse designed plants.


Westinghouse Non-Proprietary Class 3- " A-7

TableA-3 Stainless Steel Bin Categories by Specification

Specification MRP 2013-025 Potential Cold-Work

Category 1•2 (Yes/No)3

A182 (SA-182) 3 No

A193 (SA-193) 4 Yes

A194 (SA-194) 4 Yes

A213 (SA-213) 3 No 5 Yes

A240 (SA-240) 3 No

A249 (SA-249) 2 No 3 No

A269 3 No

A276 3 No 5 Yes

A296 1 No

A312 3 No

A351 (SA-351) 1 No

SA-358 3 No

A451 (SA-451) 1 No

A473 3 No

2 No A4 79 (SA-4 79) 3 No

4 (for fasteners) Yes

A511 3 No

Note 1: For fastener components, a component may be binned as a fastener even though the material specification does not typically apply to fasteners.

Note 2: For components that are cold-worked subsequent to certification as material (e.g., by bending), components can be binned as category 5 even though the material certification does not apply to cold-worked material.

Note 3: This column indicates the presence of cold-work. More thorough investigation provides assessment of whether the degree of cold-work exceeds the 20 percent criterion.


Westinghouse Non-Proprietary Class 3 B-1

APPENDIX B MATERIALS REVIEWED FOR CE-DESIGNED PLANTS

Detailed data is not provided for all cases listed in Table 5-1. Table B-1 is based on tables in MRP-191 [6], with cold-work categories determined via the approach in [3], with additional data included as appropriate from the references listed in Table 5-1.

Assembly

Upper Internals Assembly

PWROG-15105-NP

Table B-1 MRP-227-A CE Design Component Materials

Component Total Cold- Cold-Work Materials Considered for Work>20%? Category [3] Cold-Work

Upper Guide Structure No 3 A240 Support Plate No 4 A276

Upper Guide Structure No 3 A182 Support Flange - Upper No 3 A240

Upper Guide Structure Support Flange - Lower

Cylindrical Skirt No 3 A240

Grid Plate No 3 A240

No 3 A479

Control Rod Shroud - Grid Ring

Control Rod Shroud - Grid No 3 A240 Beams

Control Rod Shroud - Cross Braces

Control Rod Shroud - Bolts

Guide Structure Support System (GSSS) Guide

Structure Plate

Notes

'



Table B-1 (cont.) MRP-227-A CE Design Component Materials

Total Cold-Cold-Work Materials Considered for

Assembly Component Work Category [3] Cold-Work >20%?

GSSS Support Cylinder

GSSS Studs

GSSS Spherical Washer Sets

Flange Blocks

Flange Block Bolts

Flange Block Shear Pins

Upper Internals Assembly Reactor Vessel Level No 3 A213 Monitoring System (RVLMS)

Support Structure Tubes No 3 A479

Fuel Alignment Plate No 3 A240

Flow Restrictor Plugs No 3 SA479

Fuel Bundle Guide Pins

Fuel Bundle Guide Pin Nuts

Hold-down Ring N/A NIA A182 (AISI 403)

Belleville Washer

PWROG-15105-NP

B-2

Notes

2

April 2016 Revision O

Assembly

Lower Support Structure

PWROG-15105-NP




Component Work Category [3] Cold-Work >20%?

Core Support Plate No 3 A240

Core Support Plate Bolts No 4 A193

Core Support Plate Dowel No 3 A276

Pins No 4 A276

Anchor Block Bolts No 4 A193

No 4 A276 Anchor Block Dowel Pins

No 3 A240

No 3 A479 Fuel Alignment Pins

No 4 A276

No 3 A479 Core Support Columns

No 1 A351

Core Support Beams No 3 A240

Core Support Deep Beams

No 4 A193 Core Support Column Bolts

No 3 A276

Bottom Plate No 3 A240

ICI Support Columns

B-3

Notes


Assembly

Control Element Assembly (CEA) - Shroud Assemblies

PWROG-15105-NP




Component. Work Category [3] Cold-Work >20%?

No 3 A240

CEA Shrouds No 3 A479

No 1 A451 CPF8

No 1 A296

No 3 A240

CEA Shroud Bases No 3 A479

No 1 A296

No 3 A182

CEA Shroud Extension Shaft No 3 A312 Guides No 3 A479

No 3 A240

No 3 A269

Modified CEA Shroud No 1 A351

Extension Shaft Guides No 3 A312

No 3 A182

No 3 A240

No 3 A269

Instrument Tubes No 3 A479

No 3 A240

No 3 A213

No 3 A182

Internal/External Spanner No 4 A182 Nuts

No 3 A240

B-4

Notes


Assembly

CEA - Shroud Assemblies

Core Support Barrel Assembly

PWROG-15105-NP




Component Work Category [3] Cold-Work

>20%?

No 4 AMS 5736-F

CEA Shroud Bolts No 4 AMS 5735

No 3 A479

CEA Shroud Tie Rods

Snubber Blocks

Snubber Shims

Shim Bolts

No 1 A351 (CF8)

Flow Bypass Insert No 3 A240

No 3 A312

No 3 A479

Upper Cylinder No 3 A240

Lower Cylinder No 3 A240

Upper Core Barrel Flange No 3 A182

Lower Core Barrel Flange No 3 A182

No 3 A240

Core Barrel Snubber Lugs No 3 A240

No 3 A182

B-5

Notes

.,,


Assembly

'

Core Support Barrel Assembly

'

PWROG-15105-NP


Table 8-1 (cont.) MRP-227-A CE Design Component Materials

Total Cold- Cold-Work Materials Considered for Component Work

Category [3] Cold-Work >20%?

No 4 A193

Core Barrel Snubber Lug No 4 AMS 5735

Bolts

No 4 A276 (304 SS)

Core Stabilizing Pin N/A N/A SFA5.11 (X-750)

Core Stabilizing Hex. Head N/A N/A A-461 (X-750) Bolt

Core Stabilizing Shims N/A N/A A-461 (X-750)

Alignment Keys No 4 A638

No 3 A240

Alignment Key Dowel Pins No 4 A479

No 4 A276

Core Barrel Outlet Nozzles No 3 A182

No 3 A240

Thermal Shield No 3 A240

Thermal Shield Positioning No 4 A276 Pins

No 4 A479

Thermal Shield Support Pins No 4 A276

B-6

Notes

1

1

1

April2016 Revision 0

Assembly

Core Shroud Assembly

PWROG-15105-NP



Total Cold- Cold-Work Materials Considered for Component Work Category [3] Cold-Work >20%?

Shroud Plates No 3 A240

(welded OR bolted)

Former Plates No 3 A240

(welded OR bolted)

Ribs No 3 A240

Rings

Core Shroud Bolts No 4 A193

Barrel-Core Shroud Bolts No 4 A193

Barrel-Core Shroud Bolts No 4 A276

Core Shroud Tie Rods No 4 A479

Core Shroud Tie Rod Nuts Yes 4 A194

Guide Lugs No 3 A182

No 3 A276

No 4 AMS 5736-F

Guide Lug Insert Bolts No 4 A453

No 3 A479

No 4 A479

No 4 A193

Guide Lug Inserts No 3 A240

No 4 A240

B-7

Notes





Assembly Component Work Category [3] Cold-Work

>20%? ICI Guide Tubes No 5 A269

ICI Nozzle Support Plate

ICI Thimble Support Plate No 3 A240

No 3 A479 In-Core Instrumentation

ICI Thimble Tubes - Upper No 3 A269 (ICI)

No 3 A240

No 3 A479

ICI Thimble Tubes - Lower N/A N/A 8353

N/A N/A 8351

ICI Coupling N/A N/A 8446 UNS N06625 Grade 2

(Alloy625)

1. Not applicable because the material is a nickel-base alloy. 2. Not applicable because the material is a martensitic stainless steel. 3. Not applicable because the material is a zirconium alloy.

PWROG-15105-NP

B-8

Notes

3

3

1


Westinghouse Non-Proprietary Class 3 C-1

APPENDIX C MATERIALS REVIEWED FOR WESTINGHOUSE-DESIGNED PLANTS

Detailed data is not provided for all cases listed in Table 5-2. Table C-1 is based on tables in MRP-191 [6], with cold-work categories determined via the approach in [3], with additional data included as appropriate from the references listed in Table 5-2.

Assembly

Upper Internals

Assembly

PWROG-15105-NP

Table C-1 MRP-227-A Westinghouse Design Component Materials

Sub-Total Cold- Material Materials

Assembly Component Work> 20% Category Considered for (Note 1) [3] Cold-Work

Yes 4 A194

Yes 4 SA-194

Yes 4 SA-479

No 4 SA-479 I

Anti-Rotation studs and nuts No 3 A240

Control Rod Yes 4

10706 FY Guide Tube (AISI 316) Assemblies Yes 4 SA-193

and Flow Downcomers Yes 4 A479

No 4 A479C05 (SA-479)

Yes 4 84800WS

(SA-193/SA-479)

Yes 4 SA-193

Yes 4 SA-479

Bolts No 3 84800WS

(SA-193/SA-4 79)

No 4 70041 EA (AISI 316)

No 4 A193C01

(SA-193/SA-4 79)

Note

5

5

5

5

5


Assembly

Upper Internals

Assembly

PWROG-15105-NP


Table C-1 (cont.) MRP-227-A Westinghouse Design Component Materials

Sub- Total Cold- Material Materials


No 3 SA-249

No 3 SA-213

C tubes No 3 A249

No 3 A554

No 3 A511

Control Rod No 4 A479C05 (SA-479) Guide Tube Assemblies Enclosure pins No 3 A479

and Flow Downcomers No 4 A479

No 4 SA-479

No 3 A240

No 3 SA-240

No 3 SA-213

Upper guide tube enclosures No 3 A358

No 1 A351

No 3 A269

No 3 A213

C-2

Note

5


Assembly

Upper Internals

Assembly

PWROG-15105-NP





Upper guide tube enclosures No 3 A182

No 3 A182

No 2 A479

No 3 A240

Control Rod No 3 A249 Guide Tube Assemblies Flanges - intermediate No 3 SA-240

and Flow Downcomers No 2 SA-479

No 3 SA-479

No 3 A240C05 {SA-240)

No 3 A479C05 {SA-479)

No 1 A351

No 3 A249

No 3 A479

Flanges - lower No 2 SA-479

No 3 A240

No 3 SA-240

C-3

Note

5

5


Assembly

Upper Internals

Assembly

PWROG-15105-NP





Flanges - lower No 3 SA-479

No 1 A351

Flexureless inserts No 2 SA-479

No 3 SA-240

Control Rod No 3 A240 Guide Tube Assemblies No 2 A479

and Flow Down corners No 3 SA-240

No 2 SA-479

Guide plates/cards No 3 SA-479

No 3 A276

No 1 A351

No 3 A182

No 3 A479

No 4 SA-479

Guide tube support p(ns No 4 SA-193

No 4 A193C08 (SA-193)

C-4

Note

5




Sub- Total Cold- Material Materials Assembly Assembly Component Work> 20% Category Considered for

(Note 1) rJ1 Cold-Work

No 4 A193C01

(SA-193/SA-479)

Guide tube support pins N/A N/A AX-750

N/A N/A A637C01

No 3 A240

No 2 SA-479

Control Rod No 3 SA-479 Upper Guide Tube

Internals Assemblies Assembly and Flow Housing plates No 3 SA-240

Down comers

No 1 A351

No 3 A182

No 3 A479

Inserts No 2 A479

Lock bars No 4 A479

Yes 4 AISI Type 304 SS

No 2 SA-249

Sheaths No 2 SA-479

No 3 SA-479

PWROG-15105-NP

C-5

Note

5

2

2,5





(Note 1) [3] Cold-Work

Sheaths No 3 A2.76

Support pin cover plates

Support pin cover plate cap screws

Support pin cover plate lockinq caps and tie straps

Yes 4 SA-479

No 4 A193C08 (SA-193)

Control Rod Yes 4 A193C09 (SA-193) Upper Guide Tube

Internals Assemblies Support pin nuts No 4 SA-193 Assembly and Flow

Downcomers N/A NIA AX-750

N/A N/A B637C02 (SB-637)

N/A N/A A637C01 (SNSB-

637)

Water flow slot ligaments No 3 A2.40

No 3 SA-240

No 1 A351

Mixing Devices Mixing devices No 3 A2.40

No 3 A2.40C05 (SA-240)

PWROG-15105-NP

C-6

Note

5

2

2, 5

2,5

5




Sub- Total Cold- Material Materials Assembly Assembly

Component Work> 20°/o Category Considered for {Note 1) f31 Cold-Work

Yes 4 10706 FY (AISI

316)

No 4 SA-193

Upper core Fuel alignment pins Yes 4 AISI Type 316 plate and fuel alignment pin Yes 4 I SA-193

No 4 A2.76

No 4 A2.76 Upper

Internals No 3 SA-240 Assembly

No 3 SA-479

Upper core plate and fuel Upper core plate No 3 A2.40 alignment pin

No 4 SA-479

No 4 SA-193

Yes 4 A193

Upper Yes 4 SA-193 Instrumentation Bolting Yes 4 SA-479

Conduit and ( Supports No 3 A2.13

No 3 A2.76

PWROG-15105-NP

C-7

Note

5



Table C-1 MRP-227-AWestinghouse Design Component Materials


(Note 1) r31 Cold-Work

No 4 70041 EA (AISI 316)

Yes 4 84800WS

(SA-193/SA-4 79)

No 3 SA-240

No 2 SA-479

No 4 A193

Bolting No 2 A479

Upper Upper No 4 SA-479

Instrumentation Internals

Conduit and Assembly

Supports No 3 A269

No 4 A276

No 4 A213

No 4 A193C01

(SA-193/SA-479)

No 2 SA-479

No 3 A479

Brackets, clamps, terminal No 2 A479

blocks; and conduit straps

No 3 A240

No 3 A276

PWROG-15105-NP

C-8

Note

5

5

5





Assembly Assembly

Component Work> 20% Category Considered for (Note 1) rJ1 Cold-Work

No 1 A351

No 5 A2.76

No 5 A2.69

No 3 SA-479

No 2 A2.40

Brackets, clamps, terminal No 3 SA-240

blocks, and conduit straps

Upper No 5 A2.76 Upper

Instrumentation Internals

Conduit and No 5 A479 Assembly

Supports No 3 A182

No 5 A479C02

No 4 SA-479

Yes 4 Comm. 18-8

No 2 SA-479

Conduit seal assembly -No 5 A2.13

body, tubesheets

No 3 SA-213

No 3 A2.76

PWROG-15105-NP

C-9

Note





(Note 1) rJ1 Cold-Work I

No 3 A249

Conduit seal assembly - No 3 A213C03 tubes

No 3 SA-249

No 3 A276

No 5 A213

No 5 A249

Upper Upper No 5 SA-249

Instrumentation Internals Conduit and Assembly

Supports No 5 A269

No 3 A213

Conduits No 3 A240

No 2 A479

No 3 SA-213

No 5 A276

No 3 SA-249

No 5 SA-213

No 3 A276

PWROG-15105-NP

C-10

Note


Westinghouse Non-Proprietary.Class 3



Assembly Assembly Component Work> 20% Category Considered for (Note 1) [3] Cold-Work

No 3 A240

Flange base No 2 A240

No 3 A213

No 3 SA-213

No 3 SA-240

No 3 SA-479

Upper Upper Locking caps Yes 4 SA-479

Instrumentation Internals Conduit and Assembly Supports

No 4 A276

No 4 A479

No 3 SA-213

Support tubes No 3 A213C06

No 3 A213

UHi (upper head injection) No 1 SA-351

flow column bases

Upper plenum No 3 A479

UHi flow columns No 2 A479

No 3 A376

PWROG-15105-NP

C-11

Note




Sub- Total Cold- Material Materials Assembly

Assembly Component Work> 20% Category Considered for


UHi flow columns No 3 A240

No 3 A213

' No 3 A213

No 2 A479

Adapters No 3 A479

Upper Upper Support No 2 SA-479 Internals Column

Assembly Assemblies No 3 A276

No 4 70041 EA (AISI 316)

Yes 4 SA-479

Bolts No 3 SA-213

No 4 A193

Yes 4 84800WS

(SA-193/SA-479)

No 1 SA-351

Column bases No 1 A351

No 2 A182

No 2 SA-479

PWROG-15105-NP

C-12

Note

5

5


-- ------ --------------------------------




Assembly Assembly Component Work> 20% Category Considered for


No 2 A479

No 3 A213

No 3 A376

No 3 A182

No 3 A479

Column bodies No 3 A276

Upper Upper Support No 3 A511 Internals Column Assembly Assemblies No 3 SA-358

No 3 A554

No 2 SA-479

No 2 A511

No 1 Type 308L SS

No 3 A213

Extension tubes No 3 A376

No· 3 A276

No 3 A479

PWROG-15105-NP

C-13

Note





Assembly Assembly

Component Work> 20% Category Considered for (Note 1) r31 Cold-Work

No 2 A479

Extension tubes No 5 SA-479

No 2 SA-479

No 2 A479

No 3 A213

Flanges No 3 A479

Upper Upper Support No 3 A276 Internals Column

Assembly Assemblies No 2 SA-479

No 3 A182

I Lock keys No 4 A276

Yes 4 AISI Type 304 SS

No 4 A479

No 4 SA-479

Nuts Yes 4 SA-479

Yes 4 A194

Yes 4 AISI Type 302 or

304SS

PWROG-15105-NP

C-14

Note





Assembly Assembly Component Work> 20% Category Considered for (Note 1) [3] Cold-Work

No 4 70041 EA (AISI 316)

Bolts No 4 A193

Yes 4 SA-479

Deep beam ribs No 3 A240

No 3 SA-240

No 3 A479

Upper Upper Support No 2 SA-479

Internals Assembly

Plate Assembly Deep beam stiffeners No 3 A276

No 3 A240

No 3 SA-182

Flange No 3 A182

No 1 A351

No 3 A182

Inverted top hat (ITH) flange No 3 SA-182

No 3 SA-240

No 3 A182

Inverted top hat (ITH) upper No 3 SA-182 suooort olate

PWROG-15105-NP

C-15

Note

5





Assembly Component Work> 20°/o Category Considered for

(Note 1) [3) Cold-Work

Lock keys Yes 4 AISL Type 304 SS

No 4 A2.76

Ribs No 3 A2.40

Upper Upper support No 3 A2.76

Internals Assembly

plate assembly No 3 A182

Upper support plate No 3 SA-182

No 3 A2.40

No 1 A351

No 3 SA-182

Upper support ring or skirt No 3 SA-240

No 3 A2.40

No 1 A351

Yes 4 AISI Type 304

Lower Baffle and No 4 A479 Internals Former

Assembly Assembly Baffle bolting lock bars No 4 A2.76

No 4 SA-479

No 2 SA-479

PWROG-15105-NP

C-16

Note





(Note 1) [3] Cold-Work Baffle-edge bolts No 4 A193

No 4 70041 EA CAISI 316)

No 3 A240

Baffle plates No 3 SA-240

No 3 A276

No 4 A193C01

(SA-193/SA-479)

Lower Baffle and Yes 4 SA-193 Internals former

Assembly assembly No 4 A193

No 4 70041 EA (AISI 316)

Baffle-former bolts No 4 70041 EB (AISI 347)

Yes 4 84800WS

(SA-193/SA-479)

No 4 A193

Barrel-former bolts No 4 70041 EA (AISI 316)

No 4 70041 EB (AISI 347)

PWROG-15105-NP

C-17

Note

5

5

5

5

5

5

5





(Note 1) rJ1 Cold-Work

Yes 4 SA-479

Baffle and Barrel-former bolts Yes 4 SA-193

former 84800WS assembly Yes 4 (SA-193/SA-479)

Former plates No 3 SA-240

No 3 A240

Lower No 2 SA-479 Internals

Assembly No 3 SA-479

Bottom- No 3 A182 Mounted

Instrumentation No 3 SA-182 (BMI) Column Assemblies No 3 A276

BMI column bodies No 3 A213

No 3 A473

No 3 A240

No 3 A312

No 5 A312

Yes 4 Type 304 SS

PWROG-15105-NP

C-18

Note

5





Assembly Component Work> 20% Category Considered for

(Note 1) r31 Cold-Work

No 4 70041 EA (AISI 316)

BMI column bolts Yes 4 SA-193

No 4 A193

Yes 4 84800WS

(SA-193/SA-479)

No 4 A479

Bottom- No 2 A479 Lower Mounted

Internals instrumentation BMI column collars Yes 4 SA-479 Assembly (BMI) Column

Assemblies No 4 SA-479

No 4 A276

No 2 A276

No 1 A296

No 3 A473

BMI column cruciforms No 3 A276

No 3 A240 '

No 3 A213

No 3 A312

PWROG-15105-NP

C-19

Note

5

5

April2016 Revision O ·

Westinghouse Nori-Proprietary Class 3



Assembly Assembly Component Work> 20% Category Considered for


BMI column cruciforms No 1 A351

No 1 SA-351

No 2 SA-479

No 3 A479

BMI column extension bars No 2 A479

Bottom- No 3 A276 Lower Mounted

Internals Instrumentation No 3 A473 Assembly (BMI) Column •

Assemblies No 3 A312

No 3 A213

No 3 A276

No 3 A182

BMI column extension tubes No 3 SA-213

No 1 A371 Type ER308L

No 5 A312

No 3 A312

BMI column lock caps No 4 A276

PWROG-15105-NP

C-20

Note






BMI column lock caps No 4 SA-193

Yes 4 SA-479

Bottom- No 4 A479 Mounted

instrumentation Yes 4 SA-479 (BMI) column assemblies BMI column nuts No 4 SA-479

No 4 A276

Lower No 2 A276 Internals

Assembly No 3 A182

Core barrel flange No 3 SA-182

No 3 SA-479

Core barrel outlet nozzles No 3 A182

Core Barrel No 3 SA-182

No 3 A240

Upper core barrel No 3 SA-240

No 3 A276

No 4 A276

Lower core barrel No 3 A240

PWROG-15105-NP

C-21

Note





(Note 1l rJ1 Cold-Work

Core Barrel Lower core barrel No 3 SA-240

No 3 A276

Diffuser plate Diffuser plate No 3 A240

No 3 SA-479

No 3 SA-213

No 4 SA-479

Flux thimble tube plugs No 3 10730 BP (ER 308)

No 4 10730 BP (ER 308)

Lower Yes 4 10765 FY

Internals Flux thimbles (316 SS)

Assembly (tubes)

N/A NIA lnconel 600

No 3 SS-600-P

(SA-276 Type 316)

No 3 SA-479

No 3 SA-213

Flux thimbles (tubes) No 5 SA-213

No 3 A213

N/A N/A lnconel 600

N/A N/A UNS N06600

PWROG-15105-NP

C-22

Note

2

2

2






No 3 A276 Head cooling

Head cooling spray nozzles No 2 SA-479 spray nozzles

No 2 A479

No 2 A479

No 2 SA-479

No 4 SA-479

Irradiation specimen guide No 3 SA-240

Lower Internals

Yes 4 AISI Type 304 SST

Assembly Irradiation No 3 A479 Specimen

No 3 A276 Guides

No 3 A249

Yes 4 SA-193

Irradiation specimen guide No 4 70041 EA

bolts (AISI 316)

Yes 4 84800WS

(SA-193/SA-479)

Yes 4 SA-479

Irradiation specimen lock No 4 A276

caps

No 4 SA-479

No 4 SA-193

PWROG-15105-NP

C-23

Note

5


!





No 2 SA-479

No 3 A479

No 4 A479

No 4 70041 EA (AISI 316)

Irradiation specimen

Specimen plugs No 3 A276

guides No 3 A240

No 4 A193

Yes 4 A193

Lower No 4 SA-479 Internals 10706 FY

Assembly Yes 4 (AISI 316)

No 4 SA-193

Fuel alignment pins No 3 A276

Lower Core No 4 A276 Plate and Fuel Alignment Pins No 3 SA-240

Fuel alignment pin bolts

Fuel alignment pin lock caps

Lower core plate No 3 A240

PWROG-15105-NP

C-24

Note

5

5




Sub- Total Cold- Material Materials Assembly Assembly

Component Work> 20% Category Considered for lNote 1l f3l Cold-Work

Lower core plate No 3 SA-240

Lower Core Yes 4 Comm. 18-8 Plate and Fuel Alignment Pins XL lower core plate No 3 SA-182

No 3 A240

No 2 SA-479

No 2 A479

Lower No 1 A351 Internals

Assembly No 3 A182

Lower support column No 3 A479 bodies

Lower Support No 1 A296 Column

Assemblies No 3 A276

No 5 A312

No 4 A276

Lower support column bolts No 4 70041 EA (AISI 316)

) Yes 4 SA-193

PWROG-15105-NP

C-25

Note

5






Lower support column bolts Yes 4 84800WS

(SA-193/SA-479)

No 4 A479

No 4 A479

No 4 A213

Lower Support column nuts Yes 4 COML. 18-8

Lower Support Yes 4 SA-479 Column

Lower Assemblies No 4 A276 Internals

Assembly No 4 A269

Yes 4 A269

Lower support column No 3 A213

sleeves

No 3 A312

Lower support casting No 1 A351

Lower Support No 3 A182 Casting or

Forging No 3 A240

Lower suppo_rt forging No 3 SA-240

No 3 SA-182

No 3 A276

PWROG-15105-NP

C-26

Note

5





Assembly Assembly Component Work> 20% Category Considered for (Note 1) £31 Cold-Work

No 4 70041 EA (AISI 316)

Neutron panel bolts Yes 4 84800WS

(SA-193/SA-479)

Yes 4 SA-193

Yes 4 SA-479

Neutron panel lock caps Yes 4 SA-193

No 4 A2.76

Lower Neutron Thermal shield bolts No 4 70041 EA

Internals Panels/ (AISI 316)

Assembly Thermal Shield No 4 A193

No 4 A193

No 4 A2.76

No 4 A479

Thermal shield dowels Yes 4 A2.76

No 3 A2.40

No 4 A2.40

Yes 4 AISI Type 302 or

304

Yes 4 AISI Type 316

PWROG-15105-NP

C-27

Note

5

5

5





(Note 1) f31 Cold-Work

No 3 A2.76

No 4 AISI Type 304 SS

Thermal shield dowels No 1 308L

Yes 4 10706 FY (AISI 316)

Yes 4 A193

Neutron Thermal shield flexures No 3 A182 Panels/

Thermal Shield No 3 A2.40

Lower No 3 A2.40 Internals

Thermal shield or neutron Assembly panels

No 2 SA-240

No 3 SA-240

No 3 A2.76

No 4 70041 EA (AISI 316)

No 4 A193

Radial support key bolts Yes 4 A193

Radial Support Yes 4

84800WS Keys (SA-193/SA-479)

Yes 4 SA-479

Radial support key lock keys No 4 A479

PWROG-15105-NP

C-28

Note

5

5

5






No 4 A2.76

Radial support key lock keys Yes 4 AISI Type 304 SS

No 2 SA-479

Radial Support No 4 SA-479 Keys

No 3 A182

Radial support keys No 3 SA-182

No 3 A182C01 (SA-182)

Lower No 3 A2.40 Internals

Assembly sc.s base plate No 3 SA-240

No 3 A2.40

No 4 A193 Secondary

core support SCS bolts Yes 4 A193 (SCS)

assembly No 4 70041 EA (AISI 316)

Yes 4 84800WS

(SA-193/SA-479)

SCS energy absorber No 3 A182

PWROG-15105-NP

C-29

Note

5

5

5


Assembly

Lower Internals

Assembly

PWROG-15105-NP





No 3 A336

SCS energy absorber No 2 SA-479

No 3 SA-182

No 2 A479

No 3 A479

No 3 A182

SCS guide post No 2 SA-479

Secondary No 3 A276 core support

(SCS) No 3 AISI Type 304 assembly

No 2 A479

No 3 A479

No 3 A336

SCS housing No 2 SA-479

No 2 SA-213

No 3 A276

No 3 AISI Type 304

C-30

Note




Sub-\fotal Cold- Material Materials

Assembly Assembly

Component Work> 20°/o Category Considered for (Note 1) rJ1 Cold-Work

SCS housing No 3 A312

No 2 A479

Lower Secondary Yes 4 AISI Type 304 SS

Internals core support

Assembly (SCS) SGS lock keys No 4 A276

assembly

No 3 A276

No 4 SA-479

N/A N/A 15106 DA

(lnconel X-750)

Clevis insert bolts N/A N/A 70041 EJ

N/A N/A 8637

NIA N/A 84800XA

Interfacing Interfacing N/A N/A 8166

components Components Clevis insert lock keys N/A N/A S8-166

N/A N/A SA-637

N/A N/A S8-166

Clevis inserts N/A N/A Stellite

N/A N/A 8166

Head and vessel alignment 70041 EA pin bolts No 4 (AISI 316)

PWROG-15105-NP

C-31

Note

2, 5

2,5

2,5

2,5

2

2

2

2

4

2

' 5






No 4 A193

Head and vessel alignment Yes 4 A193

pin bolts

Yes 4 84800WS

(SA-193/SA-479)

Yes 4 A479

Head and vessel alignment Yes 4 SA-479

pin lock cups

No 4 A2.76

No 4 A479

Interfacing Interfacing No 4 SA-182

components components

No 4 SA-479

No 2 SA-479

Head and vessel alignment Yes 4 A479 pins

No 4 A182

No 4 A479

No 4 A2.76

Internals hold-down spring N/A N/A 80280 NL

!Modified Tvoe 403)

N/A N/A AISI Type 403 SS

PWROG-15105-NP

C-32

Note

5

3,5

3






Internals hold-down spring N/A N/A 10725 HA (AISI 403)

No 3 A182

No 4 SA-479

Interfacing Interfacing No 4 SA-182

components Components Upper core plate alignment

No 4 A276 pins

No 4 A182

No 4 A479

No 2 SA-479

1. Based on applicable material and fabrication specifications. 2. Not applicable because the material is a nickel-base alloy. 3. Not applicable because the material is a martensitic stainless steel. 4. Not applicable because the material is hard-facing. 5. Westinghouse material specification (Equivalent standard specification noted in parentheses).

PWROG-15105-NP

C-33

Note

3, 5


Documents

Attachment 3 PWROG-15105-NP PA-MSC-1288 PWR RV …Group (PWROG) authorized PA-MSC-1288, Rev. 2, to leverage the data in currently available responses to this cold-work question to