materials apc (mapc) - amazon s3...materials apc (mapc) date: august 24, 2016 ... 8:00 am welcome...

© 2016 Electric Power Research Institute, Inc. All rights reserved.

Scot Greenlee, Exelon, Technical Chair

Kurt Edsinger, EPRI

Wednesday, August 31, 2016

Materials APC (MAPC)

Date: August 24, 2016

2© 2016 Electric Power Research Institute, Inc. All rights reserved.

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Morning AgendaTime Topic Lead

8:00 am Welcome and Introductions, Agenda Review S. Greenlee, Exelon

8:10 am

MAPC Operations

Action Items

Taking a Step on “Ease of Doing Business”

Cross Comparison of Program Research Focus Areas (RFAs)

Other

K. Edsinger, EPRI

8:30 am Summary from Issue Program Self-Assessment D. Odell, Exelon

9:00 am Lessons learned from MRP-227 – Discussion on Implications for EPRI Guidelines D. Czufin, TVA

9:30 am Summary of Topical Screening ProcessD. Czufin, TVA

T. Hanley, Exelon

10:00 am Morning Break All

10:15 am Member Satisfaction Survey TBD, EPRI

10:30 amRegulatory / Code Update

Update on Readiness for Second License Renewal (summary status from BWRVIP and PMMP meetings)R. Dyle, EPRI

11:00 am

BWRVIP EOC Report-out

Key Points from BWRVIP EOC Meeting

BWRVIP Program Summary (Key 2016/2017 Products & Challenges)

T. Hanley, Exelon D. Odell, Exelon

A. McGehee, EPRI

11:20 am

PMMP EC Report-out

Key Points from PMMP EC Meeting

MRP Program Summary (Key 2016/2017 Products & Challenges)

SGMP Program Summary (Key 2016/2017 Products & Challenges)

D. Czufin, TVAB. Rudell, ExelonA. Demma, EPRI J. Stevens, LuminantH. Cothron, EPRI

11:40 am PWROG MSC Program Summary (Key 2016/2017 Products & Challenges)H. Malikowski, Exelon

J. Molkenthin, PWROG

12:00 pm Lunch - Crescent City Ballroom (Mezzanine Level) All


Afternoon AgendaTime Topic Lead

1:00 pm

Progress on Knowledge Transfer / Training

Tribal Knowledge Approach

Recent examples from MRP

Concept from BWRVIP

D. Czufin, TVA

A. Demma, EPRI

A. McGehee, EPRI

1:45 pm Update from Institute of Nuclear Power Operations (INPO) C. Larsen, INPO

2:15 pm Chemistry Program Summary (Key 2016/2017 Products & Challenges)J. Goldstein, Entergy

D. Wells, EPRI

2:30 pm

PSCR Program Summary

Key 2016/2017 Products & Challenges

Strategy & Strategic Challenges

J. Cirilli, Exelon

TG Lian, EPRI

2:45 pm NDE Program Summary (Key 2016/2017 Products & Challenges)K. Hacker, Dominion

S. Swilley, EPRI

3:00 pm Afternoon Break All

3:15 pm

WRTC Program Summary

Key 2016/2017 Products & Challenges

Strategy & Strategic Challenges

D. Patten, FENOC

G. Frederick, EPRI

3:30 pm Summary of Demonstration Strategy for KOH Keith Fruzzetti, EPRI

3:45 pm

Environmentally Assisted Fatigue

Overall Approach

Analytical Effort and Regulatory Progress

Testing Plans

D. Steininger, EPRI

N. Palm, EPRI

4:30 pm

Wrap-up Develop Messages for NPC Executive Committee

Collect Action ItemsAll

4:45 pm Adjourn


Strategic Focus

Typical focus for January meeting is on financial performance

and products delivered over the past year, as well as budgets

proposed for year N+1. Typical focus for the August meeting is

on overall strategic direction and emerging needs.


Materials Action Plan Committee (MAPC)

Source: EPRI Operations Protocol

“Beginning January 1, 2010, the EPRI Materials Degradation and

Aging Action Plan Committee has the principal role for overseeing

industry activities related to primary system materials and the

continuing commitment to the Industry Materials Initiative (NEI 03-

08).

It will accomplish this through a combination of direct governance

over those key programs for which it is directly responsible and

coordination with those working subject to the initiative, but not

under the Materials APC.”


PMMP Executive Committee (EC)

Nuclear Power Council

Materials & Aging Action Plan Committee (MAPC)

Executive Chair:

CNO Level Executive

Technical Chair:

VP/Director Level Executive

BWR Vessel Internals Program (BWRVIP)

Materials Reliability Program (MRP)

Steam Generator Mgmt Project (SGMP)

Primary System Corrosion Research

(PSCR)

BWRVIP Executive Committee

NDE Action Plan Committee*

Other APCs not shown

PWR Owners Group Materials Committee (PWROG MC)**

PMMP (EOC)

Welding & Repair Technology Center

(WRTC)

BWRVIP EOC

Water Chemistry Action Plan Committee

Long Term Operations

*NDE APC coordinates with Materials APC and PWR Owners Group **Materials Committee has a representative on Materials APC

Materials Advisory Structure


Materials Advisory Structure (cont’d)

Action Plan Committee

Executive Chair: Bill Pitesa, Duke

Technical Chair: Scot Greenlee, Exelon

EPRI: Kurt Edsinger

BWRVIPBWR Vessel &

Internals Program

Exec Chair

Tim Hanley

Exelon

IC Chair

Drew Odell

Exelon

Andy McGehee

EPRI PM

MRPPWR Materials

Reliability Program

IC Chair

Bernie Rudell

Exelon

Anne Demma

EPRI PM

WRTCWelding & Repair

Technology Center

Exec Chair

Bill Pitesa

Duke

IC Chair

Dan Patten

FENOC

Greg Frederick

EPRI PM

SGMPSteam Generator

Mgmt Program

IC Chair

Jim Stevens

Luminant

Helen Cothron

EPRI PM

PSCRPrimary Systems

Corrosion Research

Exec Chair

Bill Pitesa

Duke

IC Chair

Jim Cirilli, Exelon

Armson, Rolls Royce,

Technical Chair

TG Lian

EPRI PM

PWR Materials Management Program (PMMP)

Exec Chair: David Czufin, TVA

EPRI PM: Robin Dyle

Exec Sponsor

Tom McCaffrey

Entergy

Exec Sponsor

Brad Adams

Southern Nuclear

Exec Sponsor

Richard Bologna

First Energy


Other Attachments

NEI 03-08 Document List

Handling EPRI Proprietary Information

Anti-Trust Guidelines for EPRI Meetings and

Conferences

Minutes From Last Meeting

MAPC Committee List

Additional Program Materials – PSCR

Additional Program Materials – WRTC

Additional Program Materials – BWRVIP

Additional Program Materials – SGMP

Additional Program Materials – MRP

Additional Program Materials – PWROG MC

Additional Program Materials – Chemistry

Additional Program Materials – NDE

Other attachments are in a separate PDF file and can be downloaded via the app


Together…Shaping the Future of Electricity


Kurt Edsinger

Director

Materials Degradation/Aging APC Meeting


MAPC Operations



Topic

Action Items


Cross Comparison of Program Research Focus Areas

(RFAs)

Other


Action Items


Action Items (1 of 3) – Info from July Coordination Call – Update with August

# Action Responsible Due Date Status / Summary of Closure

75

Issue programs to track identified gaps in training, include

in research plans, and report to their executive committees

annually on progress (i.e., as Graybook / strategic plans

are endorsed). Coordination with the Advanced Training

Initiative should be part of the overall approach where there

is a synergy (Note: This is the remaining part of the gap for

the Materials Programs from Action #41). Edsinger 1-Jul-16

Changed date to reflecting the estimated arrival of

the "training matrix", which will organize the training

that we have and help with the assessment of gaps /

priorities.

67

Knowledge Transfer: Looking for something to capture /

convey the "tribal knowledge". Description of final product

being sought not clear / still under discussion. Action is to

come back to MAPC with some suggestions or a

recommendation on what should be considered or where

we might start.

Czufin /

Dyle 1-Sep-16

Czufin made a proposal at the Atlanta meeting that

appeared to be widely supported. It was essentially

to create program training using key EPRI and

industry experts; video with voice-overs as

appropriate to make it flow better and to fill any gaps

identified when the package is assembled. The one

to start with, in terms of applying the voice-over

approach, might be the existing NEI 03-08 video for

the training at Exelon.

78

Develop screening process for regulatory approval of EPRI

products

Czufin /

Hanley 1-Sep-16

Currently drafting a screening process to determine

which products need regulatory approval. This

process would then be endorsed by NRC. 1st draft of

a procedure was isssued this week for folks to review

and comment on.

79

Develop strategy for working with Code with anticipated

decrease in engagement by NRC Dyle 1-Sep-16


Action Items (2 of 3)# Action Responsible Due Date Status / Summary of Closure

80

Define approach for improving ease of doing business (quicker to

identify, quicker to address, simpler to implement through better

use of technology, sharing more clearly, etc.). Edsinger 1-Sep-16

81

Make meaningful progress on use of "one-pagers" (overviews of

the key information for any given subject) and leverage graphic

where possible. Edsinger 1-Sep-16

Coming from the "International Perspectives"

session and follow-on discussion

82

SGMP to respond to the foreign material issue described by

INPO (eliminating/removing loose parts versus analyzing why

they can be left in place). Cothron 1-Sep-16

Jim Benson will give a presentation at the

PMMP on the foreign object project and this

will be summarized as part of the SGMP

report out to MAPC.

83

BWRVIP to respond to the INPO challenge regarding dry tube

replacement (why it is a business decision and not a safety

decision). McGehee 1-Sep-16

Plan to close action #83 during the BWRVIP

report out at MAPC.

85

Discuss status of xLPR applications group on MAPC calls to

ensure there are a sufficient number of participants. Demma 1-Sep-16

59

SLR/LTO: We know where the technical gaps are (there are not

many), but need a plan on what products need to be updated for

SLR that can be referenced in the GALL revision process. The

plan should assess which products are OK as-is, which are

already expected to be revised in time for SLR and which need

to be expedited. For the latter, they need to be incorporated into

the plans of the Issue Programs. Provide update to MAPC ~

every 2 months. Reach out to Bernhoft / Gallagher to ensure

coordination. (Note: #20 from Chicago Meeting minutes.) Dyle

extended to

31-Dec-16

Roadmap has been developed and provide

to LTO for inclusion with the overall roadmap

for SLR. Also planning to provide an update

on SLR at the August MAPC meeting.


Action Items (3 of 3)

# Action Responsible Due Date Status / Summary of Closure

84

Chemistry to provide update on the PAA/steam project at

the next MAPC Meeting Fruzzetti 1-Feb-17

Team ran into some complications in the testing

which forced testing to be halt while to assessing

the complications / determining a revised path.

Shifted action out by 6 months to provide update at

January meeting.

62

Question related to BTP 5-3: How do owners manage

loss of margin related to the issue, even if the license is

not impacted? (Will be able to better address after the

NRC reviews & accepts / comments on MRP-

401/BWRVIP-287.) Hardin 15-Feb-17

NRC position still pending (no answer at January

meeting). Note that if the EPRI position is accepted,

then the loss of margin has been managed. The

industry (PWRPG & MRP) effort to transition to use

of direct fracture toughness (Master Curve) for RPV

integrity evaluation will also recoup any margin lost

from the BTP issue, but that is a longer term (~8

year) effort. Revised due date to reflect the fact that

NRC told us on the April quarterly call that they are

doing PFM work to evaluate the industry reports and

would finish near the end of the year.


Ease of Doing Business



It was suggested from the International Session that one page descriptions of key topic areas would be helpful

Examples could include RPV, PWR Internals, BWR Internals, Jet Pumps, Alloy 600, Foreign Objects, Primary Chemistry, etc.

The one-pager could adopt a format like the following:i. Describe the issue

ii. Summarize the key gaps, focus areas of current research

iii. List the guidance documents available

iv. List key technical references available

v. List the training available

vi. Provide a contact name for further inquiries

The one pagers could then go on the cockpits and act as a launch points for the topics


Example One-Pager

Needed strategy for managing degradation on the

secondary side of steam generator tubing

– Efficient method for foreign object inspections

– Quantitative method for prioritizing foreign object

removal efforts

– Eliminating buildup of deposits that can

accelerate corrosion, reduce heat transfer

efficiency, disrupt thermal hydraulic conditions

ECT Technique Qualifications for

Foreign Object Inspection

epriq.com

Foreign Object Removal

Prioritization

1019039

1020989

SG Integrity Assessment

Guidelines

3002007571

Foreign Object Handbook 3002007578

Causes and Mitigation of TTS

Denting

3002002197

Characterization of SG Deposits 3002002794

Deposit Removal Strategies 3002005090

Dispersant Application

Sourcebook

1025317

PWR Secondary Side Water

Chemistry Guidelines

1016555

Sludge Management Workshop 3002002756

Secondary Side Management

Conference

Every two years

EPRI Technical Contacts: Brent Capell, James Benson


Research Focus Areas


Cross Comparison of Program Research Focus Areas

There are benefits of having a consistent naming and

numbering convention for RFAs

Discussed on several occasions, including the Self-

Assessment

It’s possible and probably the right thing to do


Research Focus Areas (RFA) Proposal

Use unique RFA # index for EPRI Materials R&D

#RFA.#PROJECT.#TASK

Limit number of RFA’s (perhaps 15-20 across entire group)

RFA’s can incorporate all key elements of “Roadmaps”

– Ensure that all EPRI R&D programs (i.e., internal to EPRI )

collaborations are incorporated into RFA’s

– Ensure that collaborations external to EPRI are incorporated into

RFA’s

Ultimately need the Programs to work together and identify the optimal approach


Research Focus Areas (possible approach)

RFA DESCRIPTION 41.01.01 - PSCR 41.01.02 - SGMP 41.01.03 - BWR 41.01.04 - MRP 41.01.05 - WRTC

1Reactor Internals

Management

BWR Inspection & , RCS Piping

and Components Inspection

Technologies, NDE Technology

Reactor Vessel Internals

Assessment, Modeling and

Inspection

2Irradiated

Materials

IASCC mechanistic models /

correlations, IASCC

mechanism, De-tensioning of X-

750 annulus spacers as a result

of irradiation-induced creep and

void swelling, The effects of

irradiation aging or synergetic

aging on fracture toughness

Thermal and Irradiation Effects

on Stainless Steel Reactor

Internals


Irradiated Materials Testing

3Nickel Base

Materials

PWSCC degradation in Alloy

600/82/182 components

(especially DMW)

Managing Corrosion

Mechanisms Affecting SGs,

Overall significance of ODSCC

and PbSCC on steam generator

tubes, Sherlock

Alloy 600/690 Management,

Mitigation, and Inspection

4Probabilistic

Analysis MethodsLBB (xLPR)

5Stainless Steel

Materials

Degradation mechanism for Ti-

stabilized stainless steels,

Factors that lead to the cracking

of VVER steam generator

collect or welds

BWR-Related Corrosion

Research

Stainless Steel Degradation

Mechanism Studies, Reliability

of CASS Pressure Boundary

Components

6Thermal and

Vibration FatigueFatigue Management (Dryer)

Fatigue Management (Thermal

and Vibration Fatigue)

7Replacement

Materials

Development of irradiation

resistant alloys and IASCC

mitigation strategy

Management of High Strength

Alloys

Replacement Materials Testing

(Alloy 690/52/152)

8

Pressure Vessel

and Low Alloy

Steel Materials

RPV embrittlement, The

vulnerability of SCC crack

propagation in low alloy steels

Reactor Pressure Vessel

Integrity

Assessment for RPV Integrity,

Boric Acid Corrosion


Research Focus Areas (possible approach)

RFA DESCRIPTION 41.01.01 - PSCR 41.01.02 - SGMP 41.01.03 - BWR 41.01.04 - MRP 41.01.05 - WRTC

9Environmentally

Assisted FatigueEAF mechanisms EAF EAF

10 WearUnderstanding Wear

Mechanisms in SG Tubing

11 MitigationEffectiveness of HWC

mitigation to IASCCMitigation of BWR Material

DegradationPeening of 600/82/182

Thermal spray, Coatings, and

Hardfacing Applications

12 Weld RepairWelding of irradiated

materials+D9

BWR Irradiated Materials

Welding

Irradiated Materials Welding

Solutions, Small Bore Piping

Asset Repair Solutions, Buried

Pipe Asset Management /

Repair Solutions, Repair

Solutions for Structures:

Containment, Fuel Pool Asset

Management, Spent Fuel

Storage

13Welding

Fabrication

Optimized Joining, Fabrication,

and Repair Processes

(including WRS), Identify,

Research, Develop, and Mature

Advanced Welding Processes

Development

14Optimized Weld

Materials

Nickel-Base Filler Metal

Weldability and New Alloy

development

15 Flow PhenomenaMechanism of cracking in

CANDU primary heat transfer

(PHT) feeder pipe bend

Development of State of the Art

Software for Analyzing Steam

Generator Flow Conditions

Management of Jet Pump Flow-

Induced VibrationCFD for thermal fatigue

16Steam Generator

Inspection

Development and Employment

of Eddy Current Technology

Improvements, Foreign Object

Inspection Technologies,

Sherlock


Other


Expanded Mission and Scope for PSCR

This program will have the overall responsibility for materials testing,

characterization, and modeling within the Materials Programs. It will

directly support the other Programs and its scope will be completely

integrated with their strategic plans. The Program will also support

other areas of EPRI with materials expertise (e.g., FRP, Used Fuel,

etc.), and will act as a focal point for materials-related TI scope.

Additionally, the program will provide the key engagement point for

Base members that do not participate in the other programs (e.g.,

those with other reactor designs).


PSCR Leadership

TAC Chair: Jim Cirilli, Exelon

– Vice Chair: open

Technical Chair: Ian Armson, Rolls Royce

EPRI Program Manager: Anne Demma

TG Lian assigned to support EPRI engagement in Europe


Materials Organizational Chart – August 2016

Al Ahluwalia

Kyle Amberge

Brian Burgos

Paul Crooker

Tim Hardin

Craig Harrington

Mike McDevitt

Peter Chou

Gabriel Ilevbare

Raj Pathania

Cem Topbasi

Jean Smith

David Steininger

Jim Benson

Brent Capell

Rich Guill

Sean Kil

Rick Williams

Bob Carter

John Hosler

Wayne Lunceford

Amardeep Mehat

Nathan Palm

Chuck Wirtz

Dana Couch

Steve McCracken

Nick Mohr

Artie Peterson

Ben Sutton

Jon Tatman

Stacey Wells

Kurt EdsingerMaterials

Open

MRP

Helen Cothron

SGMPAnne Demma

PSCR

Andy McGehee

BWRVIPGreg Frederick

WRTC

Anna Deshon

Robin Dyle

David Gandy

Jennifer Ma

Chuck Welty


Drew Odell

Exelon – BWRVIP Integration Chair

Nuclear Power Council Advisory Meeting


NEI 03-08 - 2016 Self

Assessment Report



NEI 03-08 - 2016 Self Assessment Report

NEI 03-08 requires Materials Issue Programs to perform a self assessment every 3 years.

Self Assessment performed week of July 25th in Charlotte.

All representatives were present including: EPRI Materials Director, EPRI Project Managers, Issue Program IC Chairs, INPO Asset Management representative, Duke Energy Utility Participant and various EPRI personnel.

IP’s in attendance were: BWRVIP, Chemistry, MRP and SGMP.

All IPs were found to be meeting the intent and main objectives of NEI 03-08.


NEI 03-08 - 2016 Self Assessment Recommendations

A revision to NEI 03-08 is needed to align with how the Issue Programs (IPs) have evolved.

IPs should fully assess the implications of all materials related “safety communications” from OEMs. (Tech Bulletins, NSAL, SC, SIL etc.)

IPs should ensure “issues” have visibility in the Issue Management Tables (IMTs) or IP project lists. There was no IMT gap for Baffle Former Bolts (BFB).

IPs (members and vendors) improve flow of restricted or proprietary information to ensure analysis includes a complete picture. (e.g. – RCA from D.C. Cook, subsequent analyses and potential impact from Cook)


NEI 03-08 - 2016 Self Assessment Recommendations (cont.)

IPs consider how trending of inspection data or OE could

provide early indicators.

IPs consider collecting data from limiting plants. IPs could

sponsor industry surveillance programs to collect and share

data.

Improve IP administrative procedures

– Document a common Emergent Issues Protocol

– Document Research Focus Areas

– Consider a more formal OE determination process of “Emergent

Issues”


NEI 03-08 - 2016 Self Assessment Next Steps

Complete Self Assessment report – September 2016.

Obtain reviews, concurrence and approval of Self

Assessment report – October 2016.

Enter all recommendations into EPRI Corrective Action

Process – October 2016.


Lessons Learned from MRP-227

“Presentation Placeholder”*Materials will be added after August 31, 2016


David Czufin (TVA), PMMP Executive Chair

Tim Hanley (Exelon), BWRVIP Executive Chair



Summary of Topical

Screening Process



Background

This is an action item from the January 2016 MAPC meeting that later became a Deliver on the Nuclear Promise (DNP) initiative

EPRI NEI 03-08 issue programs have drafted a document screening process to be used in conjunction with the existing topical report review and approval process currently used by BWRVIP and MRP

Analogous to 50.59 process

Initial application focus on BWRVIP documents

– BWRVIP has majority of documents with implementation contingent on NRC approval

– There are clear examples of difficulty in obtaining NRC support in reasonable and timely reviews of optimized BWRVIP I&E guidance

Proposed process includes initial “applicability evaluation” and more detailed “screening evaluation”


Key Elements (1 of 2)

Applicability Evaluation– Used to determine when further

document screening is applicable

– Document screening only applicable for reports containing EPRI IP controlled aging management guidance associated with prior NRC review and approval

– Excludes NRC review for documents not previously approved by NRC or without explicit commitments to NRC

– As drafted, does no harm to existing processes not currently dependent on topical report approval

(1c)

Prior guidance approved by NRC

via SE or is credited to meet a

specific IP commitment to NRC?

(1a)

Topical report revision /

replacement or new topical report

contains implementable aging

management guidance?

(1d)

Does the guidance represent a

technical change to NEI 03-08

Mandatory or Needed elements?

(1e)

Could implementation of the

guidance result in a change to

aging management elements

other than the inclusion of new

elements?

Perform screening evaluation of

new / revised aging management

guidance.

[Go to Fig. 2, box (2a)]

YES

YES

No EPRI IP controlled

implementation elements.

Screening not applicable.

Document may be generically

released by the IP for

implementation without NRC

approval.

NO

NO

YES

(1b)

Implementable aging

management guidance elements

are applicable to safety-related

SSCs or to nonsafety-related

SSCs generically subject to aging

management for license renewal?

YES

YES

Guidance relevant to asset

preservation only and may be

generically released for

implementation without NRC

approval.

NO

NO

NO

DRAFT “APPLICABILITY EVALUATION” PROCESS


Key Elements (2 of 2)

Screening Evaluation would allow implementation without NRC SE for:– Revisions consistent with NRC

precedent / prior NRC approval

– Determinations based on qualitative risk-based evaluation, using methods consistent with those previously approved by NRC

– Determinations based on quantitative risk-based analysis with results meeting criteria accepted by NRC

DRAFT “SCREENING EVALUATION” PROCESS

(2c) – Prior Acceptance of Similar Methodologies

Direct Precedent:

Are the guidance changes consistent with either direct NRC

precedent associated with analogous applications?

OR

Analysis Method Precedent:

Are guidance changes directly supported through application of

improved analytical methods that use inputs, evaluation methods, and

margins on acceptance criteria essentially the same as those

previously approved by NRC for similar applications?

NRC approval of change(s) required prior

to generic release for implementation.

(2e)

Are the evaluation results sensitive to new OE or R&D results?

Release change(s) for generic implementation without NRC approval.

(2a) – Component Safety Function(s)

Is the proposed change predicated on conclusions based on revised

component safety function or consequence of failure assessment(s)?

(2b) – Impact on Availability of Future OE

Does the proposed change recommend complete elimination of future

examinations for any distinct component location previously subject to

periodic inspection?

NO

(2d) – Change in Risk

Qualitative Risk Assessment:

Are the changes directly and clearly supported by a generic qualitative

assessment of risk (e.g., FMEA) that concludes the proposed

changes are, as a minimum, risk-neutral?

OR

Quantitative Risk Assessment:

Are the changes directly and clearly supported by generic risk-based

analyses that demonstrate the proposed changes have a negligible

impact on level of safety using bases previously accepted by NRC?

NO

NO

YES

NO

(2f)

Can bases for reevaluation to address new

data be established and included as a

condition of release for implementation?

NO

YES

YES

NO

YES

YES

YES


Schedule, Status & Impact

Schedule as defined by MAPC– Aug 2016 – Development of proposed screening process (COMPLETE)

– Aug 2016 – Executive leadership presents approach to NRC (COMPLETE)

– Aug 2016 to May 2017 Executive leadership works to obtain NRC acceptance (in progress)

– May 2017 – If process approved AND SE not received on optimized version of BWRVIP-41, withdraw from NRC review and implement based on document screening process

– Present – Feb 2017 MAPC meeting – Identify schedule for revision of cost beneficial NEI 03-08 documents (in progress)

Feedback from NRC @ August technical exchange meeting is that NRC is attempting to determine an appropriate process for review (also will need to assign a primary POC)

BWRVIP impact– Accelerated implementation of: BWRVIP-41 Rev. 4 (Optimized Jet Pump I&E Guidance)

BWRVIP-76 Rev. 2 (Core Shroud I&E Guidance)

– Could also result in acceleration of I&E guidance optimization by the BWRVIP for other components (should a success path via screening be identified)

– Screening directly benefits U.S. utilities operating under NEI 03-08 initiative. However, concept and principles could be beneficial for international utilities in interacting with regulators


2016 Nuclear Sector

Member Satisfaction



Member Satisfaction - Background

EPRI has captured member satisfaction

feedback in various forms for many years

Current member satisfaction survey

adopted by Board in 2006

Results reviewed regularly with Board

– one of Corporate Performance Indices (CPIs)

Member feedback used to drive

continuous improvement across EPRI

Helps prioritize efforts

– focus on areas with greatest impact on

satisfaction


Nuclear Member Satisfaction Survey Results

Overall Performance

Ease of Doing Business

Technical Program Value

Overall Satisfaction

2015 Results

2010-2015 Trend

92.3%

Overall

PerformanceEase of Doing

BusinessTechnical

Program Value

86.1%

93.2%

92.4%

75%

80%

85%

90%

95%

100%

2010 2011 2012 2013 2014 2015

• Impact of research on improving my business

• The program's strategic priorities and directions

• Quality of research results

• Relevance of research carried out by the program

• Technical staff expertise

Top ranked aspects of EPRI Experience

Who completed the Survey


Category Initiative Timeframe

Research and

Development

• Research Focus Areas

• Project Overview Forms

• Quality Management ProgramImplemented 2016

Tech Transfer

• Executive Summary

• Onsite EPRI updates/regional meetings

• International workshops

• International NPC

• Digital Strategy (ongoing)

Implemented 2016

Simplification

• On-line Pricing

• Invoice Review

• New Pricing Model

Implemented 2016

Website• New Search Engine

• Member Center ImprovementsImplemented 2016

Improvement Initiatives

Listening and Responding to the Feedback of our Members


Digital Delivery Enhancements

Becomes


Becomes

Digital Delivery Enhancements


New Search Engine

The search engine gets smarter over

time based on use.

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Survey instrument

Key components …

1. Who you arewithout a name and organization, we can’t

count your input!

2. Number of years you have been an Advisor

3. How we’re doing

4. How you assess EPRI value

5. Key improvement in ease of doing business

6. Value you have received from this Program


Survey instrument

Key components

7. Rate each statement based on how

satisfied you are

8. Rank the top 5 statements as

indicated in the instructions

9. Would you recommend EPRI

10.If you are not satisfied with us in any

area, please tell us why

9

10

7

8


2015 Nuclear Member Satisfaction Scores, By Area≤86% 87%-90% ≥91%

Program AreaSurveyed

Co's% Response

Overall

Performance

Technical

Program Value

Ease of Doing

Business

Overall

SatisfactionTotal

Nuclear Sector Council 19/39 48.7% 94.4% 96.6% 81.1% 93.3% 91.3%

Materials Degradation / Aging 18/40 45.0% 91.5% 92.1% 84.2% 92.1% 90.0%

Fuel Reliability 15/40 37.5% 89.5% 91.4% 89.5% 89.5% 90.0%

Used Fuel and High-Level Waste Management 16/40 40.0% 96.8% 96.0% 90.5% 97.8% 95.3%

Nondestructive Evaluation 13/40 32.5% 90.0% 92.7% 81.8% 90.0% 88.6%

Equipment Reliability 30/40 75.0% 91.0% 91.2% 83.8% 90.7% 89.2%

Risk and Safety Management 16/40 40.0% 92.2% 94.4% 91.1% 91.1% 92.2%

Strategic Initiatives (ANT and LTO) 20/40 50.0% 95.0% 95.7% 90.7% 95.7% 94.2%

Chemistry, Low-Level Waste and Radiation

Management15/40 37.5% 94.4% 94.4% 88.8% 95.8% 93.3%

Total 92.3% 93.2% 86.1% 92.4% 91.0%


Robin Dyle

Senior Technical Executive


August 31, 2016

Regulatory / Code Update

on Readiness for Second

License Renewal



Topics

SLR issues– Actions/meetings to date

– Successes

– Items to appeal

– Support for lead plants

– VIP/MRP work

NRC– Tech mtg

– Mgmt mtg

Code– Status of code cases

– NRC changes


Overview of SLR

Effective January 2016 the SLR support work by BWRVIP

and MRP became part of the routine program work.

Follow-up meetings held with lead plants

Project plans are done

Work is underway


EPRI Lead:

Wayne Lunceford

[email protected]

BWRVIP Activities to

Address SLR

mailto:[email protected]


Status & Schedule

Working multiple technical areas in parallel to accelerate completion schedule– Reactor internals fluence study

– Generic BWR internals aging management review technical bases

– RPV circumferential and axial weld probabilistic fracture mechanics (PFM) evaluations

– RPV equivalent margins analysis screening

– EAF database development

– 80-Yr Integrated Surveillance Program

Engaged with lead plant to ensure appropriate work prioritization(most recent meeting in July 2016)

Most of the technical work anticipated to be complete by the end of 2017


Reactor Internals Fluence Study Goals

– Provide comprehensive dataset of BWR/3-6 internals fluence

– Classify and categorize internal components according to material of construction and EOL fluence

– Identify any locations for which existing aging management guidance may not adequately consider / address EOL fluence for SLR

Approach

– Create a consolidated fluence database from existing data

– Project service times when component locations may exceed target fluence values

Database will include all classes of U.S. BWRs except:

– BWR/3 with 724 assemblies (Dresden, Quad)

– BWR/6 with 800 assemblies (Grand Gulf)

Results feed into updated AMR for BWR internals addressing LTO

Unit TypeRTP

(MWth)

Fuel

Assy

RPV ID

(in)

SHR OD

(in)RPV Data

Internals

Data

Monticello BWR/3 2004 484 205 167 X

Hope Creek BWR/4 3840 764 251 207 X X

Limerick 1 BWR/4 3515 764 251 207 X X

Limerick 2 BWR/4 3515 764 251 207 X X

Susquehanna 1 BWR/4 3952 764 251 207 X X

Susquehanna 2 BWR/4 3952 764 251 207 X X

Browns Ferry 2 BWR/4 3458 764 251 207 X

Cooper BWR/4 2419 548 218 177.5 X X

Duane Arnold BWR/4 1912 368 183 145 X X

FitzPatrick BWR/4 2536 560 218 177.5 X X

Hatch 1 BWR/4 2804 560 218 177.5 X X

Hatch 2 BWR/4 2804 560 218 177.5 X X

Peach Bottom 2 BWR/4 3951 764 251 207 X X

Peach Bottom 3 BWR/4 3951 764 251 207 X X

LaSalle 1 BWR/5 3546 764 251 207 X X

LaSalle 2 BWR/5 3546 764 251 207 X X

Clinton BWR/6 3473 624 218 185.5 X X

Perry BWR/6 3758 748 238 202 X X


BWR Internals Aging Management – Talking Points

NRC license renewal staff have expressed concern about development of “80-year” BWRVIP I&E Guidelines– Represents a fundamental disconnect in aging management approach

– BWRVIP guidance applicable so long as conditions placed on the engineering evaluations remain satisfied (e.g., accumulated neutron fluence, number of fatigue cycles)

– Not tied to any single licensed operating period

– Significant variation in plant design – some plants can apply “bounding” 60-year analyses for 80-years or more of operation

AMR document addressing SLR for BWR internals being developed to address this disconnect– Analogous to BWRVIP-74-A

1but addressing BWR internals LTO

– Revisits technical basis evaluations that support inspection intervals to reevaluate suitability of existing inspection intervals for operation beyond 60 years (e.g., generic flaw tolerance calculations)

– Addresses SLR SRP-SLR further evaluation items related to IASCC, Loss of Preload

– Assessment consolidated in a single report in lieu of including “SLR evaluation” content multiple inspection & evaluation guidelines

1 BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal (BWRVIP-74-A) 1008872

https://membercenter.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000000001008872


RPV Weld Probabilistic Fracture Mechanics (PFM)

Issue:– Many BWRs will need updated probabilistic

analyses as a technical basis for RPV weld ISI exemptions and relief

– Recent work by U.S. NRC and ORNL indicated significant conservatism in BWRVIP-05 approach

– Use of the FAVOR Code can address limitations associated with both RPV circumferential and axial welds for initial LR and SLR (and beyond)

Status of BWRVIP Work:– Initial assessments performed by BWRVIP

using the currently available beta version of FAVOR indicate possible resolution path

– Work temporarily on hold pending issue of revised FAVOR Code by ORNL / NRC(revised code completion promised Sept 2016)

Adjusted Reference Temperature (F)

Cond

itio

nal P

rob

ab

ility

of F

ailu

re

Source: PVP2015-45836, “Analysis of Circumferential

Welds in BWRs for Life Beyond 60”


Screening to Assess RPV Equivalent Margins Analyses

for SLR

Generic EMAs provided for initial license renewal in Appendix B of BWRVIP-74-A1

Many materials likely remain bounded by this generic EMA through SLR

Perform initial screening assessment to identify SLR needs– Project reductions in USE values for all available

plate, and weld materials using 80-year fluence estimates

– Identify those plants that are not projected to remain acceptable for SLR

For plants not projected to pass the initial screen, perform a second screen using method proposed by NRC as a replacement to the 10 CFR 50 Appendix G 50 ft-lb acceptance criteria

SMAW Materials (BWRVIP-74-A, Fig. B-5)

1 BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines for License Renewal (BWRVIP-74-A) 1008872



Screening to Assess Environmentally-Assisted Fatigue

(EAF) Margins

Screening approach similar to that taken for RPV EMA being taken for EAF– Anticipated that a majority of BWR component locations either can pass for

SLR using existing analysis or with additional analyses using accepted methods

Database of U.S. BWR EAF status under development– Results will identify scope of component locations requiring alternative / more

advanced analyses, as well as the magnitude of the issue for SLR

– Preliminary results indicate that only a small percentage of BWR locations exceed CUFen of 1.0 with environmental effects for 80-year operation

Results should identify any substantial difficulties anticipated for BWRs with regard to EAF TLAAs

Data obtained will be applied to inform future EAF work


80-Yr Integrated Surveillance Program Development

Status Overview Initial assessment of options complete

– Some data applicable for 80 years may be available from:

4th or reconstituted capsules in ISP host plants

High lead factor SSP capsules

– No single option is most favorable in all areas of feasibility

– Optimal approach would maintain the critical elements of the ISP to the greatest extent possible, provide additional higher fluence data for the entire set of ISP materials, and be characterized as an extension to the existing ISP

Feasibility evaluation report published as BWRVIP-2951

Work in progress to gather data and perform investigations recommended in BWRVIP-2951

Draft report providing results of investigations will be completed in late 2016

Meeting with NRC targeted for Late 2016 to provide briefing on planned 80-year approach and obtain feedback

1 Boiling Water Reactor Vessel and Internals Project, Reactor Vessel Material Surveillance for U.S. BWRs During the Second License Renewal: Feasibility Evaluation (BWRVIP-295) 3002007041



EPRI Lead:

Kyle Amberge

[email protected]

MRP Activities to

Address SLR

mailto:[email protected]


Lead Plant Activity Update PWR Component List

• Surry implement MRP-227-A1 A/LAI 1 & 2 and update lead

plant RVI component list as necessary for SLR

• This was not done for 1st LR since Surry was pre-GALL

• Confirm no Surry-specific component replacements or plant

modifications since first license renewal appl.

• Provide Surry input to industry’s MRP-1912 component and

material update for SLR applicability evaluations

1 Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A) 1022863

2 Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191) 1013234

http://membercenter.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000000001022863



MRP Update Mechanism Screening Criteria

• Simultaneous activity with lead plant RVI component list

update actions

• Review MRP-1751 materials aging screening criteria and

identify criteria that could change

• Update of screening criteria as necessary

• Included as part of planned MRP-1912update

• NRC Staff briefing and follow-up technical discussions

planned for first half of 2017

1 Materials Reliability Program: PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values (MRP-175) 1012081

2 Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191) 1013234




Joint (MRP and Surry) Component Screening / Evaluation

• Based on lead PWR RVI updated component list and MRP

updated screening criteria

• Identify components with “new/changed” degradation

mechanism

• Identify any previously identified “non-susceptible”

component where extended operations would cause aging

effect to become credible

• Provide these components for FMECA evaluation

• Provide updated list of susceptible components for update of

MRP-1911 list of applicable components1 Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191) 1013234



Joint Component Screening and Evaluation (Cont.)

• Develop re-screening and FMECA analysis of susceptible components and identify revised primary and expansion inspection components, if needed

• Issue MRP-1911 update for SLR once screening inputs and inspection aging management strategies are complete

• Identify components where extended operation (80-100 years) could affect applicability of prior functionality analysis results (updates to MRP-2302/2323)

• Define and issue any interim guidance to lead PWR for any needed changes to Primary, Expansion and Existing components tables of MRP-227 Revision 14

• Brief NRC Staff and continue to engage with NRC in follow-up technical discussions in 2018-2019 time-frame

1 Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191) 10132342 Materials Reliability Program: Functionality Analysis for Westinghouse and Combustion Engineering Representative PWR Internals (MRP- 230, Revision 2) 10210263 Materials Reliability Program: Aging Management Strategies for Westinghouse and Combustion Engineering PWR Internals (MRP-232) 10165934 Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1) 3002005349






Additional Activities

Multiple calls with NRC Research and the Division of License Renewal including “deep-dive” Q&A calls

Multiple meetings with NRC on GALL-SLR– NRC has accepted many recommendations

– Now keeping MRP-227-A1 as a reference for reactor internals AMP

– Dropped the need for a BWR feedwater nozzle AMP

– Expects new surveillance capsules to be inserted

– All PWRs to perform volumetric examination on BMNs

Coordinated with LTO revising IAEA’s IGALL– 1st meeting in April 2016

– No US participants involved on PWR IGALL work

– Providing edits and updated references for AMPs and TLAAs




Aging Management Roadmap


Enhancement and Modernization Technology Roadmap


For Reference - Summary of the SLR Approach & Communication PlanKey Elements (owner) Current Status

1Continue the initial look at funding and potential budget flexibility

(BWRVIP and MRP)

• EPRI identified $1M in additional funding for this effort through the "Strategic Gap Funding" process. MRP and BWRVIP each

allocated $500k to their proposed 2016 work plan.

• Estimate up to ~$500k/year additional from MRP could be applied towards PWR updates.

2Discuss specific needs with Peach Bottom and Surry (BWRVIP and

MRP)

• Meetings involving both planned lead plants have occurred.

• BWRVIP representatives met with Peach Bottom personnel and made an initial assessment. After several follow-up discussions,

BWRVIP has what it needs for initial prioritization of their work. Where lead plant needs are not defined, the prioritization and

updates will be developed based on generic fleet needs.

• MRP and NSSS vendors met with Surry representatives to assess needs and begin prioritization. The current position is that only

core internals need to be addressed (i.e., only MRP-227 and various technical support documents). A plan was outlined for core

internals. Proposals from Westinghouse and AREVA are now in-hand. The follow-up meeting with Surry occurred January 12,

2016.

3Develop matrix of actual barriers to operation for the 26 identified

products (BWRVIP and MRP)

• BWRVIP and MRP to work this in parallel, factoring in the learnings from item 2.

• The current assessment from BWRVIP is that most inspection & evaluation documents related to reactor internals with apparent

time limitations include sufficient details regarding the underlying assumptions to the EOL conditions (e.g., neutron fluence, fatigue

usage, hot operating time) to establish limitations associated with guidance applicability. It is anticipated that a standalone SLR

aging management document could be produced to clarify these limits without the need to revise multiple guidelines on an

accelerated schedule.

• MRP will attempt to follow a similar approach, but it is recognized that some of the data limits will be substantially more

challenging and will require significant analysis (and time) to address.

4 Provide heads-up to NRC about our approach (Greenlee, Dyle)Discussions ongoing: RIC (Mar 8-10)and LRTF (Mar 11); at EPRI-NRC-RES coordination meeting (Taylor, Edsinger, Miller, Thomas). Additional meetings between LRTF and multiple meetings on GALL-SLR.

5

Develop and maintain overall communication plan for use with NEI

Licensing Renewal Task Force (Bernhoft), SLR Working Group

(Taylor), and NSIAC (Edsinger)

• Tina Taylor to presented summary to SLR Working Group 11/6/2015.

• Bill Pitesa provided update to NSIAC on 3/7/16.

6Draft a work plan (with insights from item 2) and reconcile with current

scope and budget (BWRVIP and MRP)• Complete plans were formally endorsed during NPC week (February 9-10, 2016). Handoff made to Materials Programs.

7Draft a roadmap showing overall timing and coordination (primary

system materials, but also concrete, cables, etc.) (Bernhoft)• Roadmaps have been updated for materials, cables and concrete, etc. and presented to MAPC 8/30/16

8Support detailed discussion with NRC using insights from items 6 and

7 (Pitesa+Greenlee+Dyle+Bernhoft)

• Mike Gallagher (Exelon), Paul Aitkin (Dominion) , Jerud Hanson (NEI) and Sherry Bernhoft (EPRI) had a drop in visit with Chris

Miller and others from DLR on 12/10/15. DLR was supportive of working with the industry to connect the 03-08 approach for

aging management to SLR. Follow up mtg with NRC on 1/19/16 where industry further discussed use of MRP-227 in GALL-SLR

• SLR Executive Working Group including Bill Pitesa met with NRC 4/13/16. Routine interactions with NRC and LRTF as late as

7/28/16. Also plans to meet at technical levels as work for lead plants progresses.


Code and NRC


NRC Interactions, 1 of 3

02/17/19 – NRC/ACRS overview of GALL-SLR

02/19/16 – Initial discussion on MRP-227-A1 not referenced in GALL-SLR

03/02/16 – PWROG plan to transition to Master Curve

03/11/16 – License Renewal Task Force (LRTF)

04/12/16 – Annual NRC RES / EPRI management coordination meeting

04/13/16 – Quarterly tech call with materials leads

04/26/16 – GALL-SLR discussion– NRC update on process of addressing 300 pages of public comments

– Expressed willingness to find a solution for MRP-227

– NRC requested input on RPV issues

– Unwilling to move on BMN inspections and BWR feedwater nozzle AMP

05/05/16 – PWROG met on CASS and internals cold work




NRC Interactions, 2 of 3

06/01/16 – GALL-SLR

– Industry offering options/challenges to GALL-SLR positions

– NRC agreed to reconsider BMNs UT and BWR feedwater nozzle issues

– NRC asked for additional clarification on several RPV issues

06/23/16 - Quarterly tech call with materials leads

06/26/16 – GALL-SLR

– NRC agreed to drop BWR feedwater nozzle AMP

– NRC reiterated need for BMN baseline UT

– NRC offered weak proposal on the need for additional RPV capsule

06/30/16 – Updated NRC on current environmental fatigue program elements and testing

07/19/16 – Baffle Former Bolt (BFB) meeting

– BFB OE history

– Safety Assessments

– BFB focus group structure and plans


Recent Interactions, 3 of 3

07/28/16 – Materials executives and NRC management– Industry executives, NRC directors and branch chiefs

– Key topics included as part of program overviews

NDE Overview – Calvert Cliffs OE, DMW treated by MSIP

GALL-SLR

– Good progress on MRP-227 and gap analysis

– Concern over BMNs and additional RPV surveillance capsule

Need for NRC to resolve current RPV and CASS issues (BWR closed)

Need for NRC to release FAVOR Code and positions on use of PFM

NRC pleased with BFB response – wants frequent communication

NRC will continue interaction on use of document screening tool

Nuclear Promise and NRC budget (NRR restructuring)

08/04/16 – Annual NRC / Materials program tech exchange

08/17/16 – Steam Generator Task Force meeting

08/22/16 – NRC public meeting on Code limitations

08/23/16 – Drop-in on SLR issues - BMNs and RPV surveillance capsule


ASME Code Update

Code meetings in May and August 2016

NRC participation in flux – numbers reduced and personnel uncertain

Code Case N-853 approved - ½ nozzle repairs for branch connections

Code case on excavate and weld repair (EWR) – One negative by NRC

– Changes to N-770-4 to account for these repairs under consideration.

Revision to N-770 to match words in approved Version of N-729 received

NRC negative

N-770-4 to provide inspection credit for peening of piping approved by ASME

Other changes in progress for N-770

– Dissimilar metal weld branch connections (Pending PWROG analysis)

– Revise cold led inspection requirements

– OWOL examination frequency changes


BWRVIP EOC Program Summary

“Presentation Placeholder”*Materials will be added after August 31, 2016


Bernie RudellMRP Chairman, Exelon

Anne DemmaProgram Manager, EPRI

MAPC MeetingWednesday, August 31, 2016

Materials Reliability

Program



Presentation Topics

2016 Key Products

Industry Challenges


2016 Key Deliverables

Topical Report for PWSCC Mitigation by Surface Stress Improvement (MRP-335

Rev. 3)

Basis for ASME Section XI Code Case N-838—Flaw Tolerance Evaluation of

Cast Austenitic Stainless Steel (CASS) Piping Components (MRP-362 Rev. 1)

Effect of Lithium Concentration on IASCC Initiation in Irradiated Stainless Steel

(MRP-413)

Management of Thermal Fatigue in Normally Stagnant Non-Isolable RCS Branch

Lines (MRP-146, Rev. 2)

PWR Supplemental Surveillance Program (PSSP) Capsule Fabrication Report

(MRP-412)


Industry Challenges

Quasi-Laminar Flaws / Hydrogen Flaking Issue (Doel 3 RPV issue)

– MRP participated in the meeting organized by the Belgium regulator on this subject in January 2016

– MRP is assessing the impact of the new information on the previous probabilistic analysis (MRP-367) and will update report as needed

Potential Non-conservatism of Branch Technical Position 5-3 Methods to Estimate Initial Toughness of RPV Steels

– NRC agrees with MRP-401/ BWRVIP-287 that issue is not immediate safety concern but is performing analyses to determine if BTP must be revised

BMN Volumetric Examination

– Agreement reached with NRC in 2013 to pursue Code Case to incentivize but not require volumetric exams, however eventually tabled

Reactor Vessel Internals: Baffle-Former-Bolt Cracking

– During spring 2016 outages, Indian Point 2 and Salem 1 found large quantities of degraded baffle-former-bolts that required replacement, resulting in extended outages

– The findings raised concern regarding industry preparedness to respond when such degradation is discovered and the impact on the rest of the fleet


Industry Issue: Quasi-Laminar Flaws in RPV Forgings In 2012 UT ISI, quasi-laminar flaws were found at 2 Belgian PWRs (Doel 3, Tihange

2) in base metal areas of the forged beltline rings not usually inspected

– Root cause: Hydrogen flaking, a fabrication defect

– ~7,200 flaws in one forged ring at Doel 3

In 2014, reinspection of that ring using greater UT sensitivity identified ~13,000 flaws

– Licensee demonstrated acceptability of flaws and both plants restarted in late 2015

In 2013 MRP assessed relevance of this Operating Experience by postulating the

same [2012] condition in the limiting forged-ring PWR in the U.S. (MRP-367)

– A probabilistic fracture mechanics (PFM) analysis was conducted for a vessel with 60 year

fluence and subjected to a severe pressurized thermal shock (PTS) transient

– Through-wall cracking frequency = ~ 10-7 /year (met safety criterion of 10-6 /year)

NRC requested MRP-367 for information and cited MRP analyses as justification

for not requiring special vessel inspections

– NRC has requested ORNL to review MRP-367 (in progress); RAIs possible

MRP to update MRP-367 analyses for (1) higher number of flaws from 2014

inspection and (2) 80 years of operation


Industry Issue: NUREG-0800 Branch Technical Position 5-3

Fracture toughness reference temperature, RTNDT, is used to evaluate RPV integrity per 10CFR50, Appendix G – Approximately 46 PWR vessels were fabricated before the ASME Code began

requiring, in 1973, the mechanical tests necessary to determine Initial RTNDT

– In those cases, NUREG-0800 Branch Technical Position (BTP) 5-3 provides acceptable alternatives for estimating RTNDT from other available test data

In early 2014, some BTP 5-3 guidelines were identified as potentially non-conservative

MRP conducted joint project with BWRVIP to assess impact– PFM analyses showed the fleet can continue to use existing BTP guidance

though 60 years of operation with negligible increase in failure risk

– Based on review of MRP-401/BWRVIP-287 and a PWROG report (PWROG-15003-NP, Rev. 0), NRC agrees there is no immediate safety concern but is performing analyses to determine if BTP must be revised to address operation to 80 years

– NRC analyses to be completed by end of 2016


A600 BMNs susceptible to PWSCC; challenging to mitigate, repair, or replace; some significant inspection challenges exist

MRP safety assessments conclude routine visual exams are both necessary and sufficient for plant safety– Periodic volumetric exam is not necessary

– Volumetric exam important for Extent of Condition determinations if a leak is detected

– Effective volumetric exam not presently possible for B&W unit BMNs

MRP ongoing BMN projects seek to– Ensure PWR fleet has the necessary tools available to assure safety and

address potential BMN degradation issues

– Inspection methods and coverage requirements are available to satisfy routine and issue-driven needs

Industry Issue: Bottom Mounted Nozzles (BMN) Volumetric

Examination


Spring Baffle Former Bolts Issue: Industry Response

The Industry Baffle-Former Bolt Focus Group (BFB FG) was formed

in May 2016 to support an integrated approach among industry

organizations to address recent operating experience

- AREVA

- EPRI

- PWROG

- Utility Staff

- Westinghouse

- Others

Six focus areas with key

actions defined


Near Term Industry BFB FG Actions Completed

Supported presentation to NSIAC on 5/23/2016– Westinghouse Technical Bulletin TB-12-5 remains valid

Provided Industry Alert Letter from the PMMP Chairman to PWR site VPs on 6/1/2016– Expect that NEI 03-08 Interim Guidance will require the 4-loop plants

identified in the Westinghouse TB-12-5 bulletin to perform UT inspections of all the BFBs or replace an acceptable pattern of bolts at their next outage.

– Consideration should also be given to proceeding with procurement of replacement bolts prior to issuance of interim guidance due to potentially long manufacturing lead times.

Westinghouse NSAL 16-01 issued 07/05/16

AREVA CSB issued 07/14/16


Near Term Industry BFB FG Actions Completed

Issued NEI 03-08 “Needed” Interim Guidance on 7/25/2016 regarding

BFB inspections for Tier 1 plants as identified in Westinghouse NSAL

16-01

Assessed Fall 2016 and Spring 2017 outage seasons for developing

a contingency plan for tooling and BFB material needs

– Fall 2016: 3 planned MRP-227 UT inspections (1 of 3 is a Tier 1a plant) and 1

VT-3 inspection (Tier 1b plant)

– Spring 2017: 2 planned MRP-227 UT inspections (both Tier 1a plants), 1

planned UT inspection (non MRP-227 but a Tier 1a plant), and 1 VT-3

inspection (Tier 1b plant)

Initiated Hot Cell Post Irradiation Examinations of Indian Point 2 BFBs– Microscopic examinations have begun and are currently underway; may be done by 11/1/2016


Planned BFB FG Activities through Mid-2017

Finalize BFB OE database by adding international data and UT inspection results from 2016-2017 exams

Continue with Hot Cell PIE work for IP2 and SAL1Potential additional NEI 03-08 Interim Guidance for remainder

of U.S. PWR fleet (2-loop and 3-loop plants) later in Fall 2016 or early 2017

Establish fundamental understanding of BFB failure mechanism(s) and develop potential changes to MRP-227 inspection guidance as needed– Re-inspection frequency for UT exams

– Allowance for proactive BFB replacement to manage aging


Jim StevensSGMP Chairman, Luminant

Helen Cothron

Program Manager, EPRI

MAPC Meeting


Steam Generator

Management Program



2016/2017 Key Products

Generic Elements of U-Bend Tube Vibration Induced Fatigue

Analysis for Westinghouse Model D5, Model 44F, and Model 51F

Steam Generators

Triton Steam Generator Thermal-Hydraulics Code, Version 1.0

Steam Generator Examination Guidelines, Revision 8

Steam Generator Integrity Assessment Guidelines, Revision 4

Steam Generator In Situ Pressure Test Guidelines, Revision 5


2016+ Challenges

Assuring High Performance of Single Party Auto Analysis Systems

Foreign Object Wear

– Detection of FOs

– Inspection Scope

– Estimating Wear rates from FOs

Cracking in Alloy 600TT Steam Generator Tubes

Wear in Replacement Steam Generators

Need for a State of the Art Thermal Hydraulic Code


Regulatory Issues

NRC has accepted SGMP Research Conclusions Regarding Divider

Plate Crack Propagation

– Staff Interim Guidance Letter

NRC will review published guidelines in 2016 to ensure all their

technical issues have been resolved

– Most of the technical issues have been incorporated into the guidelines;

however, not all of them are requirements

Single pass auto analysis

Site-specific equivalency of generic eddy current technique

qualifications

In plane fluid elastic instability


Operating Experience Update

South Texas identified a 0.09 volt volumetric indication in

Alloy 690TT tubing during a steam generator inspection in

2015

Utility has completed the apparent cause and determined

that if the indication is not a false call, the degradation is

most likely pitting corrosion

They will be taking action in the future to address pitting

corrosion in their hard sludge pile

SGMP will be conducting research 2017/2018 to investigate

pitting corrosion in Alloy 690TT tubing

P R E S S U R I Z E D W A T E R R E A C T O R O W N E R S G R O U P

Global Expertise • One Voice

Bernie Rudell, MRP IC Chair (Exelon)

August 31, 2016

New Orleans, LA

PWROG Materials Committee Summary

Materials Degradation and Aging Action Plan Committee

Meeting


Agenda Overview

• Significant Activities Since Last MAPC Meeting

• Areas of Coordination & Strategic Planning with EPRI

MRP

• 2016/2017 Products – Key Programs

• 2016/2017 Challenges/Initiatives

• Key Contacts

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Significant Activities Since Last MAPC Meeting

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Generic Projects

• Final SE received in May 2016 for WCAP-17096, “Reactor Internals Acceptance Criteria

Methodology”. Working to issue the “A” version of the report.

• Issued final report PWROG-15032-NP, Revision 0, “Statistical Assessment of PWR RV

Internals CASS Materials” (November 2015). The NRC made a formal request for the

report for information only. Report was submitted in January 2016. Meeting held with the

Staff on May 5, 2016. During the August 4th industry exchange meeting the NRC indicated

that the RAIs discussed at the May 5th meeting were resolved and the Staff indicated they

are finalizing their safety assessment.

• Issued final report PWROG-15105-NP, Revision 0, “PWR RV Internals Cold-Work

Assessment” (April 2016). The NRC made a formal request for the report for information

only and the report was provided in June 2016. Working to set up meeting with NRC.


Significant Activities Since Last MAPC Meeting –

Cont’d

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Generic Projects – Cont’d

• Issued draft report PWROG-15089-P, Revision 0-A, “Plan for Transitioning RPV Integrity to Direct Fracture Toughness” for review and comment in late January. The PWROG MSC and the program technical team met with the NRC in early March 2016 to present the plan.

• Issued final report PWROG-16025-NP, Revision 0 “Qualification/Refinement of Fluence Determination in Non-Traditional Reactor Vessel Beltline Locations for review and comment in March 2016.

• Issued draft report PWROG-15109-P, Revision 0-A “PWR Reactor Pressure Vessel Nozzle Appendix G Evaluation” for review and comment in July 2016.



Cont’d

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Generic Projects – Cont’d

• Issued draft report PWROG-16026-NP, Revision 0-A "Implementation of Phase 2 Recommendations for Three Representative Plants (PA-MSC-0551R2 Phase 3a)“ for review and comment in March 2016.



Cont’d

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Cafeteria Projects

• Issued additional draft and final reports under MSC-1283 “Evaluation of Applicable Dissimilar Metal Welds Joining Alloy 600 Branch Connection Nozzle to Primary Loop Piping (B&W and Palisades only)” and MSC-1294 “Development of Contingency Weld Repair Design for Applicable Dissimilar Metal Welds Joining Alloy 600 Branch Connection Nozzles to Primary Loop Piping (B&W & Palisades Plants Only).

• Issued additional site specific reports under PA-MSC-0983 – “Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0.

• Issued final report PWROG-16003-P, Revision 0, “Evaluation of Potential Thermal Sleeve Flange Wear” (PA-MSC-1286).


Areas of Coordination & Strategic Planning with

EPRI MRP

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• Reactor Vessel Integrity

Providing funding to defray costs associated with installation of PWR

Supplemental Surveillance Capsules at two plants

Working to demonstrate generically that nozzles are never bounding for P-T limits

Developed plan to transition industry and regulation to Direct Fracture Toughness

(Master Curve)

o Meeting held on March 2, 2016 to present the overall plan


Areas of Coordination & Strategic Planning with

EPRI MRP – Cont’d

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• Reactor Internals

Coordinating with the EPRI MRP on the Baffle-Former Bolt Inspection Findings

o Supported NSAL-16-1 and AREVA CSB 16-02 issuance and the 7/19 public

meeting

Coordinating with EPRI MRP on MRP-227 LAI/RAI responses

Supporting utilities in plant-specific applicability determinations, including MRP-191,

fluence, and cold worked stainless

Working with MRP and NRC on a statistical approach for assessing CASS material in

PWR reactor internals

• Stainless Steel Degradation Working with the EPRI MRP on the development of I&E guidance for ID and OD

initiated SCC of PWR SS pressure boundary components


2016/2017 Products – Key Programs

• Programs to Support MRP-227-A - Reactor Internals PA-MSC-1403 - Scale and Impact of Uncertainty in Fluence Determinations for


PA-MSC-1299 – Guide Card Wear RAI Support

PA-MSC-1288 – PWR Materials Assessment

PA-MSC-1103 - Functionality Analysis: Westinghouse Lower Support Columns

PA-MSC-0983 - Support for Applicant Action Items 1, 2, and 7 from the Final Safety Evaluation on MRP-227, Revision 0 (Working on plant specific requests)

PA-MSC-0473 - Reactor Internals Acceptance Criteria Methodology & Data Requirements (working to complete A-version of report)

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• Programs to Support Reactor Vessel Integrity PA-MSC-1392 - Qualification/Refinement of Fluence Determination in Non-

Traditional Reactor Vessel Beltline Locations

PA-MSC-1207 – Proactively Drive Changes in Reactor Vessel Embrittlement Regulations

PA-MSC-1200 - B&W Fabricated Reactor Vessel Materials and Surveillance Data Information

PA-MSC-1189 - Funding to Defray Costs Associated with Installation of Two PWR Supplemental Surveillance Capsules

PA-MSC-1182 - Revision to BAW-1543 for Master Integrated Reactor Vessel Program

PA-MSC-1091 – Demonstrate Excessive Appendix G Margins for PWR RPV Nozzles

PA-MSC-0783 - Archival of Westinghouse and CE Unirradiated Reactor Vessel Materials



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• Programs to Support Pressure Boundary Activities PA-MSC-1390 - Bottom Mounted Instrument Nozzle MNSA Repair Planning for

PWR Fleet – Task 1 only

PA-MSC-1300 – PWROG Subsequent License Renewal

PA-MSC-1294 - Development of Contingency Weld Repair Design for Applicable Dissimilar Metal Welds Joining Alloy 600 Branch Connection Nozzles to Primary Loop Piping

PA-MSC-1283 - Evaluation of Applicable Dissimilar Metal Welds Joining Alloy 600 Branch Connection Nozzle to Primary Loop Piping (B&W and Palisades only)

PA-MSC-0551 - Development of Generic Recommendations to Address ID-Initiated and OD-Initiated SCC of PWR Stainless Steel Pressure Boundary Components (Phase 3a: Apply Phase 2 Recommendations to One B&W, One Westinghouse, and One CE Unit)


2016/2017 Challenges/Initiatives

• Resolving the NRC concerns with the MRP-227-A Guidance

– Addressing and incorporating OE and Revision 1 impacts to existing OG products

– Addressing A/LAI’s and recurring RAI’s

• Developing plan to transition industry and regulation to Direct Fracture Toughness (Master Curve)

• Working to address Baffle-to-Former Bolt inspection findings. Near term and longer term guidance being looked into.

• Supporting the Nuclear Promise

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MSC PWROG Core/Planning Team Organization

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Materials CommitteeHeather Malikowski, Exelon (Chair)

(610) 765-5864

Chris Wax, APS (Vice-Chair)(623) 393-6871

Reactor Internals Industry Planning TeamGlenn Gardner(860) 440-0373

Reactor Vessel Integrity Core TeamJim Nurrenbern, Ameren

(314) 225-1908

Pressure Boundary Core TeamSteve Petro, AEP

(269) 697-5048

Jim MolkenthinPWROG PMO(860) 731-6727

Tammy NatourAREVA

(434) 832-2763


Questions?

The Materials Committee is established to provide a forum

for the identification and resolution of materials issues

including their development, modification and

implementation to enhance the safe, efficient operation of

PWR plants.

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