industry and nrc coordination meeting on pwr and bwr ...pwr owners group industry and nrc...

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Industry and NRC Coordination Meeting on PWR and BWR Materials Issues

PWR Reactor Internals

James Cirilli - PWROG MSC Chair, Exelon

May 25-26, 2010

PWR Owners GroupIndustry and NRC Coordination Meeting

on PWR and BWR Materials Issues PWROG MSC Reactor Internals Core Team

The Charter for the Reactor Internals Core Team is to develop and manage a Reactor Internals Strategic Plan/Roadmap that assures coordination of PWROG actions with ongoing industry wide activities by:

– Identifying issues of concern for the reactor internals components.– Developing action plans to resolve the issues.– Collaborating and communicating regularly with industry stakeholders as issues are

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Collaborating and communicating regularly with industry stakeholders as issues are identified, information becomes available or resolutions are determined.

The Core Team includes utility personnel from the PWROG MSC and the EPRI MRP along with AREVA and Westinghouse personnel.

The Reactor Internals Core Team has:– Developed a Reactor Internals Strategic Plan/Roadmap that identifies issues of

concern and an initial action plan to resolve the issues.– Collaborated with the EPRI MRP to integrate strategic plans– Started activities to support resolution of identified industry needs.


on PWR and BWR Materials IssuesReactor Internals Roadmap – MSC Role

1. Keep Executives informed and coordinate PWROG MSC activities with the MRP. 2. Define and Implement the Role of the PWROG Materials Subcommittee in the

resolution of RV Internals degradation issues. – Identify and assess emerging operating issues– Develop flaw evaluation guidelines and acceptance criteria

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p g p– Assure tools to support plant-specific Aging Management Programs are available– Interface with MRP to effectively coordinate monitoring and surveillance programs– Processing data from inspection, monitoring and surveillance programs that is collected by MRP

and shared with the PWROG– Provide regulatory and licensing support for implementation of the I&E Guidelines

3. Leverage Existing Vendor Data, Information and Expertise in the development and implementation of plant-specific RV Internals Aging Management Programs.

– Perform design-specific structural and functional analysis– Compile design or plant-specific data required for plant-specific Aging Management Programs– Address design-specific issues in plant Aging Management Programs


on PWR and BWR Materials IssuesPWROG Reactor Internals Programs

Current Project AuthorizationsMSC-0651: RV Internals Integrity Industry Support and Strategic Plan

MSC-0568: RI Operating Experience Review, Risk Ranking and Response Planning

MSC-0572: RV Internals Baseline Information to Support Aging Management Programs

MSC-0573: Review of B&W PWR Internals Fabrication Records for Developing MRP-227 Aging

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Management Program

MSC-0163: Measurement of Westinghouse Upper Internals Guide Card Wear

MSC-0688: Upper Internals Guide Tube Card Wear-Fleet Wide Operational Projections

MSC-0473: Reactor Internals Acceptance Criteria Methodology and Data Requirements

Proposed Project AuthorizationsMSC-0692: B&W Internals MRP-227 Phase II Functionality Criteria Core Barrel Assembly

Modeling (June 2010)

MSC-0562: Implementation Manual & Workshop

Additional Support: Westinghouse Clevis Insert Bolts

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RV Internals Integrity Industry Support and Strategic Plan (PA-MSC-0651)


May 25-26, 2010


on PWR and BWR Materials IssuesIndustry Support and Strategic Plan (PA-MSC-0651)

Purpose:

Provide Westinghouse and AREVA support for PWROG participation in technical meetings and industry forums

• Develop PWR Internals Roadmap

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– Establish strategic objectives

– Facilitate establishment of PWR Internals Core Team

• Support preparation of industry I&E Guidelines

– Assure continuity of effort between MRP and PWROG

– Identify implementation issues requiring PWROG attention• Provide PWROG support at industry meetings in coordination

with MRP– Early identification of emerging issues – Update PWROG on recent developments

Long Term Plan: MRP/PWROG Coordinated RoadmapIndustry Support for Utility Programs

Overview of Reactor Internals Roadmap

MR

P

*Refine/benchmark functionality analysis*Assess/update material models*Conduct Irradiated Materials Testing

Issue MRP-227Rev. 1

IncorporateNRC SER into

MRP-227-A

Issue MRP-227 & 228 andDevelop submittal

templates.

Support NRC Reviewof MRP-227

*Evaluate Inspection Results*Assess impact of LTC*Assess impact of revised material model

20152009 2011 20132010 2012 20162014

AMP Plan Development

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PW

RO

GU

tiliti

es 2nd InspectionPlanning and

Implementation

Plan for Inspectionand Aging

ManagementMRP-227 Revision

(See Figure 1).

RVI Operating Experience, RiskRanking and Response Planning

Monitoring of OperatingExperience

(See Figure 1)

Industry Coordination

Evaluate, Repair,Replace or Mitigate

as required.(See Figure 3)

Acceptance Evaluation Data Requirementsand Methodologies

Component Inspection and Evaluation Supporte.g., Guide Cards, B&W Core Barrel Assemblies

Baseline Information& Fabrication Records

Emerging IssuesNRC Support

Implementation Manual & Workshop

InspectionPlanning and

Implementation

(See Figure 2)

(MRP-227 requirement)(See Figure 1)

Pre-Inspection Engineering(See Figure 2)

Identify Repair/Replace/Mitigate Options(See Figure 3)

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Reactor Internals Operating Experience Review, Risk Ranking and Response Planning (PA-MSC-568)


May 25-26, 2010


on PWR and BWR Materials IssuesReactor Internals Operating Experience Review, Risk

Ranking and Response Planning (PA-MSC-0568)

• Purpose:– To provide an operating experience database, risk ranking and investigation of

contingency planning options for the aging management of reactor internals

• Will focus on the Primary and Expansion components defined in MRP-227• Evaluate component specific inspection risks and identify risk

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• Evaluate component specific inspection risks and identify risk management opportunities

• Aid individual units in applying MRP-227 to develop and implement their reactor vessel internals aging management programs (AMP)

• Benefits:– Will aid individual utilities in generating and implementing their AMP

• Readily accessible operating experience in one database• Consistent approach to ranking the risk of failure for each component• Proper and consistent establishment of mitigation options for detected aging effects

– Will help determine the actions and options for implementation of AMPs

I. Contact informationII. Basic Plant information


on PWR and BWR Materials IssuesReactor Internals Operating Experience Review, Risk

Ranking and Response Planning (PA-MSC-0568)Operating Experience Survey

Issued 5/1/2010

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− Plant name, designer, age …III. Generic Aging Lessons Learned Report and Construction Code of RecordIV. MRP-227 Reactor internals components present in the plantV. Inspections conducted on each component

– Number of times inspected – For each inspection

• Refueling Outage, • Inspection Method, • Recordable Indications, • Supplemental Exams, • Comments

VI. Additional Internals Related Plant History VII. Comments


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RV Internals Baseline Information to Support Aging Management Programs (MSC-0572)

Review of B&W PWR Internals Fabrication Records for Developing MRP-227 Aging Management Program (MSC-0573)


May 25-26, 2010

RV Internals Baseline Information to Support Aging Management Programs (MSC-0572)

Review of B&W PWR Internals Fabrication Records for Developing MRP-227 Aging Management Program (MSC-0573)

Purpose:PA-MSC-0572: Provide participating Westinghouse and CE plants with baseline information on RI components to support implementation of MRP-227 Guidelines.

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PA-MSC-0573: Search the B&W fabrication records for the primary and expansion items, including a review of past operating history and potential failure locations.

Benefits:• Support plant utility implementation of MRP-227 and GALL Guidelines.• Provide information to support creation of a plant specific reactor internals

Aging Management Program (AMP). • Provide basis for unit-specific technical justifications (TJ) in accordance

with ASME Section V, Article 14 for NDE system qualification.

I d d NRC C di i M i PWR

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Reactor Internals Acceptance Criteria Methodology and Data Requirements

(PA-MSC-0473) James Cirilli - PWROG MSC Chair, Exelon

May 25-26, 2010


on PWR and BWR Materials IssuesReactor Internals Acceptance Criteria Methodology and Data

Requirements (PA-MSC-0473)

Purpose:

Identify consistent, industry-wide analytical methodologies and data requirements for developing:

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1. Acceptance Criteria for the Primary and Expansion Components identified in the MRP Reactor Internals Inspection and Evaluation (I&E) Guidelines (MRP-227 Rev. 0).

2. Evaluation Procedures for utilities to assess potential safety and functional impacts of degradation in components with observed relevant conditions.

– Establishment of these criteria and procedures supports the review and implementation of the I&E Guidelines.


on PWR and BWR Materials IssuesAcceptance Criteria Goals for PA-MSC-0473

Information Provided in MRP-227 • Screening of degradation mechanism• Functional impacts of degradation• Inspection recommendations supporting license extension

– What to look for

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– What to look for– Inspection method– Timeframe for initial and subsequent inspections– Defines Initial Inspection Expectation Relevant Condition– Evaluation Guidance

• Provides general high level recommendations for developing acceptance evaluations

Information Provided in WCAP-17096• Methodologies for developing Acceptance Criteria• Data requirements for Acceptance Criteria

– Quantitative Acceptance Criteria expected to be plant-specific

Acceptance Criteria Methodology and Data Requirements W-ID: 1 Component Category: Primary/Expansion Applicability: All plants? Degradation Effect:

Expansion Link: Function: . ________________________________________________________________I ti Wh t i b i l k d f ?

Acceptance Criteria Methodologies Development Process

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Inspection - What is being looked for? Method: .

Coverage: Observable Effect:

________________________________________________________________ Failure - Possible Failure Outcomes Failure Mechanism: Failure Effect: Failure Criteria: ____________________________________________________

Methodology – Methodology / Documentation Goal:

Data Requirements:

Analysis:

Acceptance Criteria: Approach : Generic / Plant Specific


on PWR and BWR Materials Issues

What to Expect in WCAP-17096

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WCAP Prepared Jointly by Westinghouse and AREVA

What to Expect in WCAP-17096Report Table of Contents

1 OBJECTIVE 2 BACKGROUND3 ANALYSIS PROCESS

3.1 PHYSICAL MEASUREMENTS3.2 GENERAL CONDITION3.3 ULTRASONIC TESTING (BOLTS)3.4 VISUAL CRACKING 3.5 VISUAL OTHER

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3.6 FATIGUE (QUALIFY BY TIME-LIMITED AGING ANALYSIS [TLAA])3.7 RESOLUTION BY ANALYSIS

4 RECOMMENDATION FORMAT4.1 IDENTIFICATION AND EXAMINATION RECOMMENDATIONS4.2 COMPONENT FUNCTION4.3 INSPECTION OUTCOMES4.4 METHODOLOGY AND DATA REQUIREMENTS4.5 RECOMMENDED APPROACH

5 B&W PLANT DESIGN RESULTS5.1 METHODOLOGIES5.2 GENERIC ACCEPTANCE CRITERIA

6 COMBUSTION ENGINEERING AND WESTINGHOUSE PLANT DESIGN RESULTS6.1 METHODOLOGIES6.2 GENERIC ACCEPTANCE CRITERIA

7 REFERENCES


on PWR and BWR Materials IssuesActual Recommendations Provided in Appendices

APPENDIX A: B&W DESIGN PRIMARY AND EXPANSION COMPONENT ITEM ACCEPTANCE CRITERIA METHODOLOGY AND DATA REQUIREMENTS

APPENDIX B: ACCEPTANCE CRITERIA FLOWCHARTS FOR B&W-DESIGNED COMPONENTS INCLUDED IN MRP 227

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COMPONENTS INCLUDED IN MRP-227

APPENDIX C: ACCEPTANCE CRITERIA METHODOLOGY AND DATA REQUIREMENTS FOR COMBUSTION ENGINEERING COMPONENTS INCLUDED IN MRP-227

APPENDIX D : FLOW CHARTS OF ILLUSTRATING EVALUATION METHODOLOGIES FOR COMBUSTION ENGINEERING-DESIGNED PLANTS

APPENDIX E ACCEPTANCE CRITERIA METHODOLOGY AND DATA REQUIREMENTS; FOR WESTINGHOUSE COMPONENTS INCLUDED IN MRP-227

APPENDIX F: FLOW CHARTS OF ILLUSTRATING EVALUATION METHODOLOGIES FOR WESTINGHOUSE-DESIGNED PLANTS


on PWR and BWR Materials IssuesFormat for Appendices A,C,E

IDENTIFICATION AND EXAMINATION RECOMMENDATIONS– AREVA provided MRP-227 Table– Westinghouse Reduced MRP-227 Data to Form

COMPONENT FUNCTION– Brief Summary – Details in MRP-156

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Details in MRP 156INSPECTION OUTCOMES

– AREVA: “Observable Effects” and “Possible Outcomes”– Westinghouse: “Observable Effect,” “Failure Mechanism,” “Failure Effect,” and

“Failure Criteria”METHODOLOGY AND DATA REQUIREMENTS

– AREVA: “Methodology and Data Requirements”– Westinghouse: “Goal,” “Data Requirements,” “Analysis,” and “Acceptance

Criteria”RECOMMENDED APPROACH

– Generic Programs / Plant Specific Actions

Thermal Shield FlexuresAppendix F

Thermal Shield FlexuresAppendix E

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PWR Owners Group Industry and NRC Coordination Meeting

on PWR and BWR Materials Issues Reactor Internals Acceptance Criteria Program

Project Schedule

• Draft Methodologies and Data Requirements Currently Reviewed by MSC.

• Report to be transmitted to Staff to Support the MRP-227 Review

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Report to be transmitted to Staff to Support the MRP 227 Review.

Industry and NRC Coordination Meeting on PWR and

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B&W Internals MRP-227 Phase II Functionality Criteria Core Barrel Assembly Modeling (PA-MSC-0692)


May 25-26, 2010

• Purpose:

– Evaluate RV internals items in MRP-227 (Rev. 0) to determine a basis for functionality acceptance criteria and loading conditions that may exist during operation

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on PWR and BWR Materials IssuesB&W Internals MRP-227 Phase II Functionality Criteria

Core Barrel Assembly Modeling (PA-MSC-0692)

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• Excludes upper and lower core barrel bolts and bolt locking devices (completed)– Existing core barrel assembly supermodel will be modified for unit-specific differences

• This will provide unit-specific tools to analyze condition of core barrel assembly – Preparation of safety assessment of consequence of failed core barrel-to-former bolts, baffle-to-

baffle bolts and associated locking devices

• Quantitative and qualitative assessments will performed

• Coolable geometry, bypass flow, safe shutdown, and loose-parts will be evaluated based on existing analyses

industry and nrc coordination meeting on pwr and bwr ...pwr owners group industry and nrc...

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