babcock & wilcox nuclear energybabcock & wilcox nuclear energy P 109 ramsey place P lynchburg, va...

babcock & wilcox nuclear energyP 109 ramsey place P lynchburg, va 24501 0 phone 434.316.7592

0 fax 434.316.7534 * www.babcock.com

November 3, 2010 BW-JAH-2010-233

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockville PikeRockville, MD 20852-2738

Babcock & Wilcox Nuclear Energy, Inc.Docket Number-PROJO776Project Number-776

Subject: Submittal of Babcock & Wilcox Nuclear Energy, Inc. (B&W NE) Control Rod DriveMechanism (CRDM) Design Details and Development Plan Technical Report (NP)

On October 28, 2010, a proprietary version of the subject report was sent to the NRC. This letterprovides a redacted, non-proprietary version of that report to be placed in our project file.

Questions concerning this submittal may be directed to T. J. Kim at 434-382-9791 (email:tikimCbabcock.com ) or to J. A. Halfinger at 434-316-7507 (email: iahalfinqer~babcock.com).

JAH/msc

cc: Joelle L. Starefos, NRC, TWFN 9-F-27Stewart L. Magruder, Jr., NRC, TWFN 9-F-27

u-Dbabcock & wilcox nuclear energy, inc., a Babcock & Wilcox company

Document No. Title:R0003-96-002506 (NP) B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

Redacted Non-Proprietary Version

B1W babcock & wilcox nuclear energy

B&W mPowerTM Reactor

CONTROL ROD DRIVE MECHANISM DESIGNDETAILS AND DEVELOPMENT PLAN

TECHNICAL REPORTR0003-96-002506 (NP)

October 2010

generation

B&W mPower Reactor ProgramBabcock & Wilcox Nuclear Energy, Inc.

109 Ramsey PlaceLynchburg, VA 24501

Confidential Commercial Information Is Enclosed in Sauare Brackets: and Reasons for Withholding theIdentified CCI from Public Disclosure Are Provided in an Accompanying Affidavit

@2010 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved.

NP-00590-02Babcock & WHcox Nuclear Power Generation Group, Inc.

a Bbcock a VAM €aW,

NUCLEAR EXTERNAL DOCUMENT REVIEW FORM

B&W NPG Contract No.:Document Source: E- Customer 0 Supplier Q Subcontractor 0 Other

Document Originator: Paul DeSantisContact Name: Paul DeSantisfThad LyonsCompany Name: B&W NOG- EuclidAddress: 24703 Euclid Ave. Cleveland. Ohio 44117-1714Phone: 216) 912-3372Email: Paul K DeSantis (pkdesantlsebabcock.com)Document Title:Control Rod Drive Mechanism Design Details and Development Plan Technical ReportOriginator Document No.: TR-213 Revision No.: 0

NPG Document Status:0 For Information Only [I Accepted 0 Accepted with Exceptions Noted [] Not AcceptedNPG Exceptions/ Comments: [] Exceptions [I Deficiencies 0 Comments(Use attachments as needed)No comments-this document Is for Informational purposes only to allow for technical discussions between B&W NEand the Nuclear Regulatory Commission.

Signatre.

Reviewed By: Matthew W. Ales I.-- . A /2/,o

Printed Name Signature Date

Reviewed By: Paul D. BryantPrinted Name Signature Date

Reviewed 13y: Scott J. Shargots o/zslioPrinted Name Signature/ . Date

Approved By. Michael T. Childerson sg ww ,0 so/4 /rfoPrinted Name ignature Date

B&W NPG Number Assigned NPG Document Number: R0003-98-002506ED Yes C] No

0 2009 BABCOCK & WILCOX NUCLEAR POWER GENERATION GROUP, INC. ALL RIGHTS RESERVED. THIS DOCUMENT IS THEPROPERTY OF BABCOCK & WILCOX NUCLEAR POWER GENERATION GROUP, INC. AND CONTAINS CONFIDENTIAL ANDPROPRIETARY INFORMATION OWNED BY BABCOCK & WILCOX NUCLEAR POWER GENERATION GROUP, INC. ANY COPYING,USE, OR DISCLOSURE OF THIS DOCUMENT WITHOUT THE WRITTEN PERMISSION OF BABCOCK & WILCOX NUCLEAR POWERGENERATION GROUP, INC. IS STRICTLY PROHIBITED. THIS MATERIAL IS PROTECTED UNDER TRADE SECRET AND UNFAIRCOMPETITION LAWS AND THE EXPRESSION OF THE INFORMATION CONTAINED THEREIN IS PROTECTED UNDER FEDERALCOPYRIGHT LAWS.

Technical Report: TR-213

Redacted, Non-Prowpietary Version

B:W babcock & wilcox nuclear operations group

TR-213

B&W mPowerTm Reactor

CONTROL ROD DRIVE MECHANISMDESIGN DETAILS AND DEVELOPMENT

PLAN TECHNICAL REPORT

October 2010

1W a progressive energy solution

B&W mPowerTM Reactor ProgramBabcock & Wilcox Nuclear Operations Group, Inc.

Euclid Operation24703 Euclid Avenue

Cleveland, Ohio 44117

Confidential Commercial Information Is Enclosed in Sauare Brackets: and Reasons for Withholdini theIdentified CCI from Public Disclosure Are Provided in an Accomoanying Affidavit

© 2010 BABCOCK & WILCOX NUCLEAR OPERATIONS GROUP, INC. ALL RIGHTS RESERVED.

I

Technical ReportTR-213

Title:B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

Babcock & Wilcox Nuclear Operations Group, Inc.

B&W mPowerTm ReactorControl Rod Drive Mechanism

Design Details and Development Plan Technical Report

SIGNATURES IPrepared Paul K. DeSantisBy: Manager of Design Engineering

Prepared Edward S. RobitzBy: Advisory Engineer

Prepared Brett T. GoodyearBy: Test Engineer

Reviewed Allan R. MackovjakBy: Senior Engineer

Approved James F. FillBy: Department Manager of Engineering •

02010 Babcock & Wilcox Nuclear Operations Group, Inc. All rights reserved.Page 2 of 69

Technical Report Title:TR-213 TB&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

RECORD OF REVISION

Revision Section(s) or Page(s) Descripton of Changes

0 N/A Initial Issue


i Information withhold per Affidavit 4(a) - 4(d1)

Technical Report: Title:TR-213 B&W mPowerT" Reactor- CRDM Design Details and Development Plan Technical Report

Table of Contents,

1. .OVERVIEW . .. .. ... ....... ....... ...... .........2.2 MECHANISMFUNCTION AND DESIGN. ...... ,............... .... . -6......6

21 KeyDesignC.iteria .......... ....................2.1 I:: es~ i gti n- o ft ra .C D e i n .•,; .: :...... :. ..... ............... .......;...,.......... :..,...,....:......... .682;2 Desction of CRDM Desin ...... ;... ............ ........ .28

.2.2.3 [ ......... I ... 3...2 ........ 2............ .. ..... 132.2.4 [ . ............... . .................. .,..-...... 238

,2.2.5 ....... ............. . 422 .• ...... ...... . .. .. .O. 0 . .. . .. ... ..... 38.

2 2 6 [....................... ......... :...... ...... ..... ;.42

2.2.7 [ ' [CCI per Affidavit 4(a) -4%d)151

2.3 Identification of Safety-Related and, Nn-Safety-Related Features and Functions ...... 54

-.3. DESCRIPTION OF DESIGN CRITERIAWAND MATERIAL SELECTION . ..... ........... 56

3.1 CRDM Component Design Critera. .................. ................. i ...... ...... . .............. :56

3.2 CRDM Material Selection ....... ........... ....... .... .. ................ ..................... .. 57

4. MECHANISM TEST PLAN ...... ...................... ................... ........... 6!4ý 1: Decripti0n of Planned Sub-Astembly Tests and Objectives ...... ý ................. 61:

4.2 Description of Planned. Lfe Tests and Objectives 66

5. CONCLUSION- AND. SUBSEQUENT ACTIONS'.-.............. ..................... ...... 68

-6. REFERENCES. .................... .... ................ ....... ........ 69

@2010 Babcock & Wilcox Nuclear Operations Group, Inc. All rights reserved.Page 4 of 69

Technical Report: Title:TR-21 3 B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

1. OVERVIEW

The B&W mPowerTm reactor is a simplified, passive, modular, light-water-cooled, pressurizedwater nuclear reactor. It has a rated power output of approximately 125 MWe. The reactoruses an integral arrangement in which the reactor core, steam generator, pressurizer, controlrod drive mechanisms (CRDMs) and reactor coolant pumps are combined into a commonpressure vessel. Reactor power is controlled by the CRDMs, which also provide a failsafesafety control rod axe man (SCRAM) capability.

The B&W mPower reactor uses a common, unique and simple CRDM design that is bothdifferent from, and has significantly fewer parts than, conventional light-water reactor CRDMs.This is in part due to the fact that the system and its components are located entirely within thereactor pressure vessel and do not serve as a boundary for reactor coolant. This has certaininherent safety advantages as well as presenting certain challenges, primarily of materialschoices for components.

This report provides a detailed description of the B&W mPower reactor CRDM design,functionality and operating characteristics. The report also discusses the application of theAmerican Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code(References 1 and 2) to the design and structural evaluation of the CRDM, and to the materialselection process. Areas where current regulatory guidance poses a challenge in application tothe CRDM design are identified, along with proposed courses of action. Additionally, the reportdescribes the CRDM test plan to demonstrate and verify the proper CRDM functionality undernormal operational and emergency conditions.

©2010 Babcock & Wilcox Nuclear Operations Group, Inc. All rights reserved.Page 5 of 69

Information Withheld per Affidavit 4(a) - 4(d)

Technical Report: Title:TR-2133 B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

2. MECHANISM FUNCTION AND DESIGN

This section of the report presents a detailed description of the design and function of the B&WmPower CRDM, along with operating characteristics and special features. It also identifies keydesign criteria that serve as the basis for the design and identifies the safety-related andnon-safety-related features and functions of the CRDM.

The function of the CRDM is to control reactivity during power operation, to provide a failsafeSCRAM capability and to provide shutdown other than SCRAM. Specifically, during routineoperation, the CRDM positions a control rod assembly in response to an electrical signal. Uponreceipt of a SCRAM signal or loss of power, the CRDM releases the control rod assembly forfree-fall insertion into the fuel assembly.

The CRDM is designed to operate inside the reactor vessel in [

] [CCI per Affidavit 4(a)-4(d)]

2.1 Key Design Criteria

The B&W mPower reactor CRDM is designed to operate inside the reactor vessel in primarycoolant water conditions. [


InformaUon Withheld per Affidavit 4(a) - 4(d)

Technical Report: Title:TR-213 B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report

[CCI per Affidavit 4(a)-4(d)]



Technical Report Title:TR-213 B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

2.2 Description of CRDM Design






Technical Report: Title:TR-213 B&W mPower Tm Reactor- CRDM Design Details and Development Plan Technical Report








Figure 2.2-1 - Overall CRDM Mechanism, Fully Inserted




Technical Report Title:TR-213 B&W mPower Tm Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2-2 - Overall CRDM Mechanism, Fully Withdrawn





2.2.1 [



Technical Report: Title:TR-213 B&W mPowertT Reactor- CRDM Design Details and Development Plan Technical Report



Technical Report Title:TR-213I B&W mPowerT" Reactor- CRDM Design Details and Development Plan Technical Report


Information Withheld per Affidavit 41a) - 4(d)



Information Withheld per Affidavft 4(a) - 4(d)

Technical Report: Title:TR-213 B&W mPowert M Reactor- CRDM Design Details and Development Plan Technical Report




I[CCI per Affidavit 4(a)-4(d)]



Technical Report: Title:TR-213 B&W mPowerl Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.1-1 - [



Information Withheld per Affidav!t 4(a) - 4(d)


Figure 2.2.1-2 - [




Technical Report Title:TR-213 I B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.1-3 - [





Figure 2.2.1-4-[



Information Withhold per Affidavit 4(a) - 4(d)


Figure 2.2.1-5- [

3 [CCI per Affidavit 4(a)-4(d)]

0§2010 Babcock & Wilcox Nuclear Operations Group, Inc. All rights reserved.Page 24 of 69



Figure 2.2.1-6 - [





Figure 2.2.1-7 - [

] [CC] per Affidavit 4(a)-4(d)]




Figure 2.2.1-8 - [





Figure 2.2.1-9 - [


©2010 Babcock & Wilcox Nuclear Operations Group, Inc. All rights reserved.Page 28 of 69


I Technical Report: Tite: ITR-213 B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

2.2.2 [




Technical Report: Title:TR-213 B&W mPowerT" Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.2-1 - [


O2010 Babcock & Wilcox Nuclear Operations Group, Inc. All rights reserved.Page 30 of 69



Figure 2.2.2-2 - [



Infonnation Withheld per Affidavit 4(a) - 4(d)

Technical Report Title:TR-213 B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report_

2.2.3 [







Technical Report: Tide:TR-213 B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.3-1 - [





Figure 2.2.3-2 - [



Information Withheld per Affidavit 4(a) - 4(d).


Figure 2.2.3-3 - [





Figure 2.2.3-4- [

] [CCl per Affidavit 4(a)-4(d)]




2.2.4 [








Figure 2.2.4-1 - [




Technical Report: Trile:TR-213 B&W mPowerT" Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.4-2- [

] [CCI per Affidavit 4(a)-4(d))




2.2.5 [

J [CCI per Affidavit 4(a)-4(d)]




Figure 2.2.5-1 - [





Figure 2.2.5-2 - [



Information Withheld per Affidavit 4(a) -_4(d)

Technical Report: Title:

TR-21 3 B&W mPower~m Reactor- CRDMV Design Details and Development Plan Technical Report

Figure 2.2.5-3 - [




Technical Report Title:TR-213 B&W mPowerT' Reactor- CRDM Design Details and Development Plan Technical Report

2.2.6 [




][CCI per Affidavit 4(a)-4(d)]


Information Withhold per Affidavit 4(a) - 4(d)

Technical Report Title:TR-213 B&W mPowerM Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.6-1 - [





Figure 2.2.6-2 - [Connecting Rod Assembly, Upper End




Technical Report: Trile:TR-213 B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.6-3 - [Connecting Rod Assembly, Lower End





2.2.7 [

] [CCI per Affidavit4(a)-4(d)]




Figure 2.2.7-1 - [




Technical Report: Title:TR-213 B&W mPowerT ' Reactor- CRDM Design Details and Development Plan Technical Report

Figure 2.2.7-2 - [



Technical Report: Title:TR-213 B&W mPowerTI Reactor- CRDM Design Details and Development Plan Technical Report

2.3 Identification of Safety-Related and Non-Safety-Related Features and Functions

This section summarizes the safety-related (SR) and non-safety-related (NSR) features andfunctions of the B&W mPower reactor CRDM. Although the safety aspects of the CRDM werepreviously discussed as part of the overall description given in Section 2.2, they are restatedhere for completeness. The summary, which is provided in Table 2.3-1, includes thecomponent/assembly definition, the safety designation (SR) or (NSR) and a brief description ofthe rational for the designation.



Technical Report: Title:TR-213 B&W mPower"A Reactor- CRDM Design Details and Development Plan Technical Report

Table 2.3-1 - Identification of Safety-Related and Non-Safety-Related Attributes of CRDM[

[ [CCI per Affidavit 4(a)-4(d)]




Title:B&W mPower"A Reactor- CRDM Design Details and Development Plan Technical Report

3. DESCRIPTION OF DESIGN CRITERIA AND MATERIAL SELECTION

This section of the report discusses the application of the ASME Code (Reference 1) to thespecific component design criteria and to the structural evaluation of the B&W mPower reactorCRDM. Also included is a discussion of the material selection process.

3.1 CRDM Component Design Criteria

Footnote 9 of 10CFR50.55a states that guidance for quality group classifications of componentsmay be found in NRC Regulatory Guide 1.26 and in Section 3.2.2 of NUREG-0800 "StandardReview Plan for Review of Safety Analysis Reports for Nuclear Power Plants." RegulatoryGuide 1.26 provides guidance for "water-, steam-, and radioactive-waste-containingcomponents" but does not provide guidance for supports or core support structures. Table3.2.2-1 of NUREG-0800 includes guidance for components such as supports, metalcontainment components and core support structures.

The CRDM is totally contained within the reactor pressure vessel and is



Technical Report Title:

TR-213 B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report

3.2 CRDM Material Selection

For the majority of the mechanism, and wherever possible, B&W mPower reactor CRDMmaterials are selected from those listed in Tables 2A, 2B, and 4, of the ASME Code, Section II,Part D (Reference 2). In some cases, the technical requirements of the CRDM have madenecessary the use of materials other than those listed in the tables. The materials not listed in atable in the Code, or in a Code Case, are addressed as follows:

Non-Listed ASME Structural Materials for Safety-Related Components

Table 3.2-1 identifies the non-listed materials for the safety-related components. It alsoprovides a rationale for their selection and any confirmatory testing that is being considered.The functional performance of the selected CRDM materials will be confirmed duringperformance verification testing as discussed in Section 4 of this report.

Non-Listed ASME Structural Materials Selected for Non-Safety-Related Components

Table 3.2-2 identifies the non-listed materials for non-safety-related components. It alsoprovides a rationale for their selection, and any confirmatory testing that is being considered.The functional performance of the selected materials will be confirmed during CRDMperformance verification testing as discussed in Section 4 of this report.




Table 3.2-1 - Non-Listed ASME Materials Selected for Safety-Related Components




I Technical Report: Title:TR-213 B&W mPowerTM Reactor- CRDM Design Details and Development Plan Technical Report

Table 3.2-2 - Non-Listed ASME Materials Selected for Non-Safety-Related Components[



[



Table 3.2-2 - Non-Listed ASME Materials Selected for Non-Safety-Related Components(Continued)





4. MECHANISM TEST PLAN

CRDM testing will be performed [

[CCI perAffidavit 4(a)-4(d)]

4.1

[

Description of Planned Sub-Assembly Tests and Objectives



Technical Report: Tite:TR-213 B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report

02010 Babcock & Wilcox Nuudear Operations Group, Inc. All rights reserved.Page 62 of 69






Technical Report: Title:TR-213 B&W mPowerT' Reactor- CRDM Design Details and Development Plan Technical Report

Table 4.11-1 -[


Table 4.1-2-[




Technical Report Title:TR-213 B&W mPower Tm Reactor- CRDM Design Details and Development Plan Technical Report

Table 4.1-3 - [





4.2 Description of Planned Life Tests and Objectives




Technical Report: Tite:TR-213 B&W mPowerTm Reactor- CRDM Design Details and Development Plan Technical Report

Table 4.2-1 - CRDM Life Tests





Title:B&W mPower Tm Reactor- CRDM Design Details and Development Plan Technical Report

5. CONCLUSION AND SUBSEQUENT ACTIONS

All design functionality, material selection, and test plans discussed in this document are subjectto change as analysis and test results become available. It is B&W's intention to complete asmuch of the testing as possible prior to the Design Certification Application submittal butsub-component and CRDM life testing will continue beyond the submittal date. Table 5-1identifies a high level schedule for performance of planned tests. At this time it is uncertain howmany years beyond DCD submittal that the motor tests and CRDM life tests will continue.

Table 6-1: CRDM High Level Test Schedule



Technical Report:TR-213

Title:B&W mPoWerTM Reactor- CRDM Design Details and Development Plan Technical Report

6. REFERENCES

1. ASME Boiler and Pressure Vessel Code, Section III, Division 1, "Rules for Construction ofNuclear Facility Components", Subsection NG, 2007 Edition, 2008 Addenda.

2. ASME Boiler and Pressure Vessel Code, Section II, Part D, "Materials", 2007 Edition, 2008Addenda.

3. Stein, A.A., and Gennaro, M.S., "Material Specification for Alloy X-750 in LWRInternal Components"', EPRI NP-6202, Project 2181-4, January 1989.

4. Gorman, J., "Materials Handbook for Nuclear Plant Pressure BoundaryApplications", EPRI, Palo Alto, CA: 2002. 1002792.


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