Materials Degradation/Aging Action Plan Committee (MAPC). · – See following slides for an update...

Bill Pitesa (Duke), MAPC Executive Chair Scot Greenlee (Exelon), MAPC Technical Chair Kurt Edsinger (EPRI), MAPC Program Manager

Robin Dyle (EPRI), Technical Executive

Industry/NRC Executive Meeting on Materials Program June 25, 2014

Materials Degradation / Aging Action Plan Committee (MAPC)

2 © 2013 Electric Power Research Institute, Inc. All rights reserved.

Outline

• Program Organization • Research Update for other EPRI Programs

– Primary Systems Corrosion Research (PSCR) – No Chemistry or WRTC this meeting

• Technical Issues Update – CASS – BTP 5-3

• Proposal for Prioritizing Research • Contact Information


Programs to Manage Materials Issues

• EPRI Materials Programs – BWR Materials (BWRVIP) – PWR Materials (MRP) – Steam Generator (SGMP) – Primary Systems Corrosion Research (PSCR) – Welding & Repair Technology Center (WRTC)

• Other Coordinated EPRI Programs – NDE – Water Chemistry Control

• PWR Owners Group – Materials Subcommittee (MSC)


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).


Materials Organizational Structure

PMMP Executive Committee (EC)

Nuclear Power Council

Materials & Aging Action Plan Committee

(MAPC)

Executive Chair: Bill Pitesa, Duke

Technical Chair: Scot Greenlee, Exelon

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 Subcommittee (PWROG MSC)**

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 Subcommittee has a representative on Materials APC


EPRI IASCC Crack Growth Report–Status • Database includes over 1600 test segments (cyclic data excluded)

ranked by expert panel • Fluence range 0.21– 43.5 dpa • Draft report on the IASCC database and low ECP (PWR and BWR-

HWC) and high ECP (BWR-NWC) IASCC models is complete • Next draft for industry review to be issued in August for PSCR, MRP

and BWRVIP committees review • Resolve industry comments, revise report and publish by end of 2014 • The report will provide the technical basis for crack growth disposition

curves for irradiated BWR and PWR stainless steel internals for renewal term and subsequent license renewal

• Expect to provide report to NRC for review in 2015


CASS in Reactor Internals • Issue affects BWRs (BWRVIP-234) and PWRs (MRP-227-A) • MRP and BWRVIP met with NRC staff 2/18/2014 to understand issues

related to thermal and irradiation embrittlement of CASS – NRC concerns were use of perceived non-conservative values for

CASS chemical compositions (FN), and fluences for onset of irradiation embrittlement (e.g., Grimes letter versus MRP-175)

• NRC has issued RAIs to PWRs with a proposed new position – NRC tech basis shared with Industry early June

• MRP / BWRVIP CASS joint working group established technical position for screening CASS reactor internals – Unified industry position for CASS internals – Applicable to BWRs and PWRs – Provided to NRC May 23

• Next Steps: – Industry meeting with staff 7/15/2014 – Quick resolution of technical issues needed


BTP 5-3 Summary and Background of Issue • In 1972/73 ASME Code adopted RTNDT-based evaluation of RPV integrity • NRC revised 10 CFR 50 Appendix G to require all plants to comply • Because RPVs ordered before August 15, 1973 may not have those

tests, NRC provided methods to convert pre-1973 test data into parameters needed (then MTEB 5-2, now BTP 5-3) – Technical basis for NRC guidance in BTP 5-3 is unknown – Older plants used BTP 5-3, which NRC reviewed and approved

• Many older PWRs and BWRs have used these licensed values for 40 years to show compliance with RPV integrity regulations

• 2013 research by AREVA suggested potential non-conservatism of one of the BTP 5-3 methods

• In an evaluation of the AREVA results, it was found that NRC had contracted with EG&G Idaho (INEL) in 1983 to review and evaluate BTP 5-3 (MTEB 5-2) – INEL report noted 3 of 5 methods found to be potentially non-

conservative – No record of NRC disposition of report found – BTP 5-3 was not revised


Outline of MRP/BWRVIP BTP 5-3 Project Plan • Industry decided to perform its own data review and evaluation • Identify possible, viable alternatives to the guidance in BTP 5-3

paragraphs B.1.1(3), B.1.1(4), or B.1.2 if they are found to be potentially non-conservative

• Assess extent of condition – To verify the scope of materials potentially affected, a survey was

sent to all BWRS and PWRs; responses by July 25, 2014 • Assemble enhanced materials database of USE and TNDT measurements

and evaluate the BTP 5-3 procedures (independent of current on-going NRC evaluation)

• Where necessary, recommend revised procedures • Draft report due mid-November • Industry suggests a public meeting to discuss BTP 5-3 (and other RPV

issues) in the Fall – e.g., late October 2014


Prioritizing Materials Work and Research

Background • A number of research projects have been driven by a regulatory need,

whether perceived or communicated, rather than a defined issue or a safety challenge

• Examples: – SG divider plate cracking – Plant specific RAIs on use of MRP-227 – P-T limits (small flaws vs. operational constraints) – BWR steam dryer evaluation methodology – RAIs for previously approved BWRVIP guidance

• In many cases, the initial look was appropriate, but we are not good at stopping when we know enough to stop


Proposal for Prioritizing Research (cont’d) Approach • Develop a template to discuss and compare research priorities • Focused on upfront discussion (i.e., as issue begins to emerge), but

also need the ability to check and adjust • Start with NEI cumulative impact assessment • Potential filters might include:

– Impact on safety – Breadth of impact – Reopening approved issues absent OE or new data – Support for ongoing review – Realistic versus hypothetical issue – Public Perception


MAPC Key Contact Information • MAPC Executive Chairman Bill Pitesa, Duke, Senior Vice President and Chief Nuclear Officer

– Phone: 704-382-7258 – E-Mail: [email protected]

• MAPC Technical Chairman Scot Greenlee, Exelon, Senior Vice President, Engineering & Technical Services

– Phone: 630-657-3723 – Email: [email protected]

• MAPC Program Manager Kurt Edsinger, EPRI, Director of Materials

– Phone: 650-855-2271 – Email: [email protected]

• Robin Dyle, EPRI, Technical Executive – Phone: 205-426-5371 – Email: [email protected]

mailto:[email protected]�





Together…Shaping the Future of Electricity


Materials Roadmaps

1. BWR and PWR Irradiated Materials Testing and Degradation Models 2. Steam Generator Foreign Object Management 3. Steam Generator Degradation Prediction and Mitigation 4. Management of Jet Pump Flow-Induced Vibration 5. Ensuring Reactor Pressure Vessel Integrity Through Eighty Years of

Operation 6. PWR reactor internals aging management 7. Welding of Irradiated Materials for PWR and BWR Internals 8. Alloy 52 Nickel-Base Filler Metal Weldability Solution 9. High Chromium Weld Metal Development and Cracking Mechanisms


Materials Roadmaps (cont’d)

10. Aging Management of Alloy 600 and Alloy 82/182 in the Steam Generator Channel Head Assembly

11. Mitigation of Boiling Water Reactor Materials Degradation 12. Fatigue Management in Boiling and Pressurized Water Reactor

Coolant Systems 13. Pipe Rupture Probability Re-Assessment (XLPR) 14. Primary Water Stress Corrosion Cracking Characterization of Alloy

690 and Weld Metals 15. Advance Welding Process development in the Nuclear Power

Industry 16. Incorporation of Fabrication, Repair and Joining Technologies in

Nuclear Codes and Standards 17. Steam Generator Tube Integrity Assessment 18. Understanding of Environmental Effects on Fracture Properties

BWR Vessel & Internals Project (BWRVIP)

Tim Hanley, Exelon BWRVIP Executive Committee Chairman

Drew Odell, Exelon BWRVIP Integration Committee Chairman

Andy McGehee BWRVIP Program Manager

Robin Dyle EPRI Technical Executive

Industry/NRC Executive Meeting on Materials Program June 25, 2014


Overview Outline

• Current Members and Organization

• 2014 BWRVIP Major Tasks

• Status of Key Topics with NRC

• Contact Information


Current Members and Organization


2014 BWRVIP Member Utilities

U. S. • Constellation • DTE Energy • Duke Energy

• Energy Northwest • Entergy • Exelon

• FirstEnergy • NextEra Energy

• NPPD • PPL

• PSEG Nuclear • Southern Nuclear Company • Tennessee Valley Authority

• Xcel Energy

Non-US • BKW FMB Energie AG – Switzerland

• Chubu Electric Power Company – Japan • Chugoku Electric Power Company – Japan • Comision Federal de Electricidad – Mexico

• Forsmarks Kraftgrupp AB – Sweden • Iberdrola Generation – Spain

• Kernkraftwerk Leibstadt – Switzerland • Nuclenor – Spain

• OKG Aktiebolag – Sweden • Ringhals AB – Sweden

• Taiwan Power Company – Taiwan • Tokyo Electric Power Company – Japan


2014 BWRVIP Organization

Assessment Committee Ron DiSabatino, Exelon (Technical Chairman)

Steve Richter, Energy Northwest (Technical Vice Chair)

Bob Carter, EPRI (Task Manager)

Mitigation Committee Dan Miller, PPL (Technical Chairman)

David Willer, DTE (Technical Vice Chair)

Raj Pathania, (EPRI Task Manager)

Integration Committee Drew Odell, Exelon Vacant

Chairman Vice Chairman

Andy McGehee

EPRI Program Manager

Repair Focus Group Denver Atwood, Southern Nuclear (Chairman)

Wynter McGruder, Xcel (Vice Chairman)

Ken Wolfe, EPRI (Task Manager)

Inspection Focus Group Dave Potter, Xcel (Chairman)

Christian McKean, Exelon (Vice Chairman)

Jeff Landrum, EPRI (Task Manager)

Executive Committee Tim Hanley, Exelon Vacant

Chairman Vice-Chairman

Andy McGehee

EPRI Program Manager Executive Oversight Committee Ken Knaide, PSEG (AC Exec Sponsor),

Joe Frisco, Duke (Mitigation Exec Sponsor),

Dennis Madison, Southern (BWROG Chair),

Dave Czufin, TVA (EOC at large)

Mitigation Monitoring FG Steve Williams, Duke (Chairman)

Larry Loomis, Entergy (Vice Chair)

Susan Garcia, (EPRI Task Manager)

Red = gap

Green = new


2014 BWRVIP Major Tasks


2014 BWRVIP Major Tasks • 2014 Water Chemistry Guidelines Revision

– Revision to the current BWR Water Chemistry Guidelines, BWRVIP-190 has been released to VIP members for implementation

• Evaluation of Shroud Cracking (NDE & Boat Sample Analysis at Hatch Unit 1) – See following slides for an update

• Inspection and Evaluation Guidelines Optimization – Core Spray, Jet Pump Guidelines and Core Shroud – Currently Core Spray has been submitted to NRC and Jet

Pump is in-progress • Address Jet Pump Flow-Induced Vibration Issues

– See following slides for an update on the BWRVIP’s Full Scale Jet Pump Test Facility

Core Shroud Inspection and Boat Sample Testing


Background

• Atypical cracking found during 2008 ID visual inspections of core shroud at Hatch Unit 1 – Similar but less extensive cracking observed at several other

BWRs – Cracking did not have characteristics typical of IGSCC – Cracking might be the result of IASCC

• BWRVIP Focus Group formed in 2010 to investigate cause of cracking – Focus Group recommended evaluation of Hatch cracking to

determine cause and recommend further actions – BWRVIP report issued in 2011 recommended UT inspection

to further characterize length, depth and orientation of flaws, and removal of boat sample

– UT and boat sample removal performed in Spring 2014


Boat Sample Location Selection

• Locations for boat sample were pre-selected based on 2008 visual inspection results

• Sample depth sizing and removal was a critical path activity, thus decision tree developed and used to select between locations based on UT results

• Sample taken at a location of high fluence where flaw was ~0.8” deep

• Boat sample: – Approximately 2”x3”x1” – Contains weld and base metal – Crack extends from weld into base

metal (perpendicular to H4)


Boat Sample Evaluation

• BWRVIP is funding testing and analysis of the boat sample to determine cause of cracking

• Boat sample schedule: – Shipment of boat sample is expected in September 2014 – Final report to be published in November 2015

• However, schedule is contingent upon timely NRC approval of Class B shipping container


Ongoing BWRVIP Activities

• BWRVIP Focus Group evaluating required actions – What near term actions are required?

• Interim inspections, prior inspection data review, etc. • Is adequate guidance available for evaluating indications (structural and leakage)

– Longer term • Monitoring of fleet inspection results • Review boat sample results • Revise shroud inspection guidance as necessary


Jet Pump Testing for BWR 4 Configuration


Full Scale Jet Pump Test Facility

Accumulator for pressure control

Heat exchanger

Recirculation pump and motor

Flow meter

Water storage tank

Test vessel

Concrete enclosure


View from Top of Pressure Vessel

Filled with water


Status of Full Scale Jet Pump Testing

• Testing of the facility in the BWR/5 jet pump configuration was completed in Fall of 2012 and demonstrated that the test facility met all flow, temperature and pressure requirements, and was able to replicate the flow-induced vibration (FIV) phenomena. The testing provided a significant amount of knowledge regarding the causes of jet pump FIV.

• Vendor demonstrations for FIV repair hardware have been performed.

• Vendors and utilities have used the facility for hardware developmental testing.

• Currently reconfiguration of the test facility for BWR/4 testing is underway.


Status of Key NRC Topics


Status of Key Topics with NRC

• GE Safety Communications impact on BWRVIP Guidance • Remote VT Round Robin • BWRVIP-62, Rev 1 - Inspection Relief with OLNC & HWC • Integrated Surveillance Program (ISP) for BWRs


GE Safety Communications impact on BWRVIP Guidelines • GEH issued (June 2013) three Safety Communications

(SCs) that deal with RLB loads – 09-03, Rev 1: Core Shroud Screening Reports

(consideration of RLB acoustic loads in the reports) – 11-07, Rev 0: Impact of Inertial Loading and Potential

New Load Combination from Recirculation Suction Line Break Acoustic Loads

– 12-20, Rev 0: Error in Method of Characteristics Boundary Conditions Affecting Acoustic Loads Analyses

• SCs are an output of GEH’s 10 CFR Part 21 evaluation program and all three of these SCs conclude that the issues do not present substantial safety concerns and are not reportable under Part 21


GE Safety Communications impact on BWRVIP Guidelines • Focus Group meeting held 9-19-13 at Exelon offices. • Goal to identify reports that were directly impacted or could

benefit from augmented guidance. • Reviewed the BWRVIP Guidelines for components addressed

by the BWRVIP. • Focused on those sections that discuss loads , load

combinations and example flaw evaluations. • Meeting minutes were published to BWRVIP members. • 4 reports were identified as likely having “technical bases

impact” • BWRVIP-25, Core Plate / BWRVIP-26-A, Top Guide /

BWRVIP-38, Shroud Support / BWRVIP-136, Shroud Support Gussets


Future and Ongoing Actions GE Safety Communications & BWRVIP reports • Develop augmented guidance for loads and load combinations • Evaluate reports for impact BWRVIP-25 I&E Guideline (Core Plate) underway Remaining reports will follow based upon scope and

budget. • Based on current knowledge and conservatisms, the BWRVIP

believes there are no near-term concerns with use of BWRVIP guidelines.

• When evaluations are complete, BWRVIP will advise the NRC and revise documents as warranted.


Remote VT Round Robin - Involvement in Industry Wide Projects • Remote VT Round Robin

– Joint Memorandum of Understanding (MOU) project between EPRI and the NRC Research

– BWRVIP co-funds the project – The BWRVIP Inspection Focus Group Chairman also Chairs

the utility Ad hoc committee overseeing the project – There is extensive use of remote VT by the BWRVIP

Inspection & Evaluation Guidelines (I&EGs) so the BWRVIP is a major stakeholder in the project

– Objective and planning meeting (Phase 3) is scheduled for August 5 & 6, 2014 in Charlotte. NRC Research and their contractor for the Remote VT MOU, Pacific Northwest National Laboratories (PNNL), are participating.


Topical Report Reviews

• BWRVIP-62, Rev. 1 (Inspection Relief with OLNC & HWC) – Submitted to the NRC March 7, 2012 – NRC requested review of many of the reference documents

for BWRVIP-62, Rev. 1 – NRC has questioned aspects of the already approved

technology for classic Noble Metals Chemical Addition (NMCA) and Hydrogen Water Chemistry (HWC)

– Good communications between Industry and Staff via several teleconferences and a face-to-face meeting (March 28, 2013) held to outline the issues and work toward resolution

– RAIs received from the staff in March 2014 – The BWRVIP is working on RAI responses with a pre-RAI

submittal meeting with the staff scheduled for July 18, 2014


Integrated Surveillance Program (ISP) for BWRs

• Due to the BWRVIP’s capsule testing process, including BWRVIP Committee review and approval of the capsule reports, the capsule reports cannot be completed within one-year and thus extensions to 18 months are necessary.

• Historically, the BWRVIP provided notification letters for the delays, but in recent years submitted formal extension requests for the last three ISP capsule withdrawals (Susquehanna 1, Duane Arnold and Perry).

• A conversation was held with the NRC in November 2013 and the NRC noted that the SE for the ISP acknowledges the BWRVIP as being responsible for submittal of ISP capsule reports and, if needed, extension requests.


Integrated Surveillance Program (ISP) for BWRs

• The NRC asked that extension requests include the current Effective Full Power Years (EFPY) for the plants affected by the capsule results and the EFPY for the approved P-T curves at those plants. The BWRVIP agreed to include that information in future requests and provided that information to the NRC for Duane Arnold and Perry via letter 2013-211, dated 11/20/13.

• Several communications with the staff have followed to ensure all technical information was available for the staff to complete their review.

• It is expected that the staff will provide responses to the extension requests shortly.


BWRVIP Key Contact Information

• BWRVIP Executive Chairman Tim Hanley, Exelon

– Phone: 630-657-3724 – E-Mail: [email protected]

• Utility Technical Chairman Drew Odell, Exelon – Phone: 610-212-1155 – Email: [email protected]

• EPRI Program Manager Andy McGehee – Phone: 704-502-6440 – Email: [email protected]


David Czufin, TVA, PMMP Executive Chairman Randy Stark, EPRI, SGMP Program Manager Anne Demma, EPRI, MRP Program Manager

June 25, 2014

PWR Materials – MRP and SGMP


BWRVIP BWR Vessel &

Internals Program

Exec Chair Dennis Madison

SNC

IC Chair Drew Odell

Exelon

Andy McGehee EPRI PM

Advisory Structure Action Plan Committee

Executive Chair: Bill Pitesa, Duke Technical Chair: Scot Greenlee, Exelon

Kurt Edsinger, Director

MRP PWR Materials

Reliability Program

Exec Chair David Czufin

TVA

IC Chair Bernie Rudell

Exelon

Anne Demma EPRI PM

WRTC Welding & Repair

Technology Center

Exec Chair Bill Pitesa

Duke

IC Chair Dan Patten

FENOC

Greg Frederick EPRI PM

SGMP Steam Generator Mgmt Program

Exec Chair David Czufin

TVA

IC Chair Jim Stevens

Luminant

Randy Stark EPRI PM

PSCR Primary Systems

Corrosion Research

Exec Chair Bill Pitesa

Duke

IC Chair Ian Armson Rolls

Royce

TG Lian EPRI PM

Exec Sponsor Elliott Flick, Exelon

Exec Sponsor Eric Larson, FENOC

Exec Sponsor Ben Mays, Luminant


Materials Reliability Program


Outline

• MRP Organization • NEI 03-08 Guidelines • Technical Areas Examples


2014 MRP Organization

Materials Reliability Program (IC)

Rudell, Constellation IC Vice Chairman-TBD

Demma, EPRI

Regulatory Interface Richter, NEI Dyle, EPRI

Technical Support TAC Hoehn, Ameren

Childress, Duke Energy McDevitt, EPRI

Inspection TAC Fernandez, APS

Cordes, Southern Nuclear Swain, EPRI

Mitigation/Testing TAC

Gobell, Entergy Efsing, Ringhals

Smith, EPRI

Assessment TAC Sims, Entergy DeBoo, Exelon Amberge, EPRI

Harrington, EPRI

Technical Advisory Group

IC Vice Chairman-TBD Demma, EPRI Materials Review Visits

Crane, INPO


MRP Documents with Mandatory & Needed Elements Governed by the Materials Initiative

Doc Number (EPRI PID)

Rev Document Title Date Implementation

Level Comments

MRP-126 (1009561)

0 Generic Guidance for an Alloy 600 Management Plan

Nov 2004 Mandatory

MRP-146 (1022564)

1 Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines

Jun 2011 Needed

MRP-146S (1018330)

0 Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines – Supplemental Guidance

Jan 2009 Needed

MRP-227-A (1022863)

A MRP 227-A, Pressurized Water Reactors Internals Inspection and Evaluation Guidelines

Dec 2011 Mandatory

MRP 2014-006

0 MRP-227-A Interim Guidance Modification to inspection requirements of tables 4-3 and 5-3 for Westinghouse Control Rod Guide Tube Assemblies

Feb 2014 Needed MRP Letter

Documents Incorporated Within (i.e., issued prior to the initiative) or Under the Materials Initiative (i.e., issued since the initiative)

http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000000001009561�




http://membercenter.epri.com/programs/061145/cockpit library/MRP Letters/2014 Letters/MRP 2014-006.pdf�



MRP Documents with Mandatory & Needed Elements Governed by the Materials Initiative

Doc Number (EPRI PID)

Rev Document Title Date Implementatio

n Level Comments

MRP-228 (1025147)

1 MRP-228 Inspection Standard for PWR Internals

Dec 2012 Needed

MRP 2013-023

0 MRP-228 Interim Guidance Reactor Internal Baffle-Former Bolting Ultrasonic Examinations

Oct 2013 Needed Letter

MRP-139 (1015009)

MRP 2010-046

1 MRP-139, Primary System Piping Butt Welds Inspection and Evaluation Guideline, and Interim Guidance Letter MRP 2010-046

Dec 2008 N/A Superseded by requirements of Code Case N-770 as amended by 50.55a Listed for historical purposes only. MRP maintains the technical basis.

MRP-326 (1022871)

MRP 2012-031

0 MRP-326, Coordinated PWR Vessel Surveillance Program (CRVSP) Guidelines, and Interim Guidance Letter MRP 2012-031

Dec 2011 N/A All required member actions have been completed. Listed for historical purposes only.

Documents Incorporated Within (i.e., issued prior to the initiative) or Under the Materials Initiative (i.e., issued since the initiative)











MRP Technical Area: Irradiated Material Testing

Zorita Internals Research Project (ZIRP)

Current Participants • EPRI • U.S. NRC • CSN (Spanish regulator) • SSM (Swedish regulator) • Tractebel • AXPO • Additional in-kind contribution

from Japanese utilities/MHI

Objective: Characterize the effects of neutron irradiation on the mechanical and microscopic properties of stainless steel materials irradiated under service conditions to increase the understanding of fluence effects at end of service life (40, 60 years and beyond)

Jose Cabrera NPP “Zorita” Westinghouse design

1968 – 2006 (~26 EFPY)


Zorita Internals Research Project Zorita Baffle Plate Materials

• Baffle plate material from between 3rd and 4th formers

• Type 304 Stainless Steel • Doses ranging from a few

dpa to ~50 dpa • Thickness 28.6 mm • Piece B1 contains eight

Type 347 SS bolts

Piece B3 ~10 dpa max

Piece B1 ~50 dpa max Piece B2

~30 dpa max


Zorita Internals Research Project Current Status

• Tensile Testing complete – 10, 30, and 50 dpa specimens at

RT and 320°C • Crack Growth Rate Testing

– 30 and 50 dpa specimens currently underway

– 10 dpa specimen and duplicates of all doses to follow

• Crack Initiation Testing – High dpa material tests to begin

4Q2014 • Fracture Toughness Testing

– Begin with 10 dpa specimens in air and primary water in 3Q2014

– 30 and 30 dpa specimens to follow • Microstructural Testing

– Shipment of material to MHI in Japan for TEM, gas analysis

Piece B1 Piece B2 Piece B3


MRP Projects Using Additional Zorita Materials

• Determine combined effects of irradiation & elevated temperature on embrittlement of stainless steel welds and characterize environmental effect on fracture toughness in irradiated stainless steel welds

• Currently in contracting process with vendor • Project uses Zorita core barrel weld material

Thermal and Irradiation Embrittlement and

Environmental Effects Testing of Stainless Steel

Welds

• Develop IASCC CGR data in irradiated stainless steel weld and HAZ materials for comparison to existing data for base materials

• Currently in contracting process with vendor • Project uses Zorita core barrel weld material

CGR Testing of Irradiated SS Weld and HAZ Materials

• Evaluate IASCC crack initiation and crack growth rates and degree of void swelling in highly-irradiated (near end-of-life conditions) stainless steel base metal and welds

• Currently evaluating responses to RFP • Project uses Zorita baffle plate & core barrel weld

material

Determination of IASCC CGR, Initiation Rate, and Void Swelling in Zorita

Material after Post-Reactor Irradiation


Peening for PWSCC Mitigation - Components of Interest


• Peening prevents PWSCC initiation and eliminates growth of shallow flaws within the surface compressive residual stress zone

• In mid-2012, EPRI completed the MRP-335 topical report supporting inspection optimization for peening mitigation of Alloy 82/182 piping dissimilar metal butt welds and Alloy 600 RV top head nozzles

• ASME Section XI is addressing peening

• Code Case N-770-4 addressing the Alloy 82/182 piping butt welds was approved on May 7, 2014

• A revision to Code Case N-729 is now being developed to address Alloy 600 top head nozzles, and is expected to be approved in 2015

• U.S. industry is eager for U.S. NRC to complete its SE review of the topical report formally submitted in February 2013

MRP Technical Area: PWSCC Mitigation by Peening

Laser Peening

Bubbles collapse

Water Jet Peening

Bubble cloud

Plans for peening two US PWRs in 2016 have been announced


MRP Technical Area: Alloy 690 • Testing and field experience

confirm high PWSCC resistance of Alloys 690/52/152

• More extensive work explored or underway to further understand – Vulnerability to abnormal

microstructure and to welding residual stresses and strains

– Role of weld imperfections in initiation and growth of PWSCC

• Work substantiates technical basis for optimized inspection of A690 replacement components such as the reactor pressure vessel head

Repair Weld 1


MRP-375 Technical Basis for Reexamination Interval for RV Heads with Alloy 690 Nozzles • Lab and plant data support a technically based longer volumetric/surface

examination interval using appropriate analytical tools

• Currently, more than 100 replacement and new heads with Alloy 690 nozzles and Alloy 52/152 attachment welds are in service worldwide

• A detailed technical basis document supporting extension of the current 10-year interval of N-729-1 was published by EPRI in February 2014 – MRP-375 (EPRI 3002002441), freely downloadable at www.epri.com – Recommends a 20-year interval, and includes options for sample inspection

programs – Proposes that the existing visual exam (VE) interval for evidence of leakage of no

more than 5 calendar years be maintained

• ASME Section XI is now considering a revision to Code Case N-729 that includes a revised interval for volumetric/surface exams

• Licensees are now developing relief requests based on MRP-375

• Request technical dialogue on efficient regulator review approach for multiple relief requests or other alternatives

http://www.epri.com/�


MRP Technical Area: PWR Internals

• PWR Internals Inspection and Evaluation Guidelines MRP-227-A (Report 1022863) issued in Jan. 2012

• Revising the guidelines • Publish in 2015

Experience to date shows limited degradation

• Inspection guidance and flaw evaluation methodologies


PWR Internals Inspection Results to Date and Reporting • Initial full inspections at W and B&W and partial CE NSSS

designs have not identified any major issues of concern • Issues of greatest concern not seen

– SCC of austenitic welded components not observed • Cracking currently limited to high strength bolting

– IASCC of welds not observed, indications limited to bolts – Macroscopic effect of void swelling not observed

• EPRI MRP provided internals inspection results to NRC

staff in EPRI letter MRP-2014-009, consistent with MRP-227-A ‘Needed’ requirement for reporting results – Submitted to NRC on May 12, 2014 (ML14135A383, 84, 85)


Industry Near Term Inspection Plans

Anticipated near term schedule of U.S. inspections

Fall 2014 – 1 Westinghouse Design

Spring 2015 – 1 CE Design

Fall 2015 – 3 Westinghouse Designs

Several more in 2016-2018 time frame


PWR Internals Topic of Interest

Cold Work of Stainless Steels (Licensee Action Item 1) • NRC staff reviewers provided plant-specific RAIs related to

>20% cold work (CW) of stainless steel • MRP and OEM prepared RAI response template provided

to licensees via MRP-2013-025 – Criteria defined by MRP – Resource intensive effort with no cases of CW found yet


Steam Generator Management Program


Outline

• SGMP Organization • NEI 03-08 Guidelines • Current Key Technical Areas


EPRI SGMP Organization

SGMP Integration Committee (IC) J. Stevens, Luminant (Chair)

J. Arhar, PG&E (V.C.) R. Stark, EPRI

Technical Advisory Group J. Arhar, PG&E

J. Benson, EPRI NEI M. Richter

Technical Support TAC L. Miller, Dominion (Chair) K. Johnson, Duke (V.C.)

R. Wolfe, EPRI

Engineering & Regulatory TAC P. Fabian, PSEG(Chair)

W. Leaverton, APS (V.C.) H. Cothron, EPRI

NDE TAC D. Folsom, TVA (Chair) S. Redner, Xcel (V.C.)

R. Guill, EPRI

INPO C. Lane


SGMP Guidelines Status (Page 1 of 2)

Guideline Title Current Rev #

Report #

Last Pub

Implementation

Interim Guidance

Review Date Comments

Steam Generator Integrity

Assessment Guidelines

3 1019038 Nov 2009 9/1/2010

SGMP-IG-10-01

SGMP-IG-12-01

Rev 4 in progress

EPRI Steam Generator In Situ Pressure

Test Guidelines

4 1025132 Oct 2012 10/10/2013 none 2015

PWR Steam Generator

Examination Guidelines

7 1013706 Oct 2007 9/1/2008

SGMP-IG-08-04

SGMP-IG-12-01

Rev 8 in progress

PWR Steam Generator Primary-to-Secondary

Leak Guidelines

4 1022832 Sep 2011

4/11/20127/11/2012 none 2014


SGMP Guidelines Status (Page 2 of 2)

Guideline Title Current Rev # Report # Last Pub

DateImplementation

Date(s)Interim

GuidanceReview

Date Comments

PWR Primary Water Chemistry Guidelines 7 3002000505 April

2014 1/28/2015

PWR Secondary Water Chemistry Guidelines 7 1016555 Feb 2009 8/20/2009

11/20/2009

SGMP-IG-13-01

SGMP-IG-14-02

2014

Steam Generator Management Program

Administrative Procedures

3 1022343 Dec 2010 9/1/201112/31/2011 none n/a Rev 4 in

progress

Steam Generator Degradation Specific

Flaw Handbook1 1019037 Dec 2009 n/a none n/a Rev 2 in

progress


Steam Generator Management Program Current Issues for the SGMP

• Channel Head divider plate to stub runner weld cracking • Cracking of Alloy 600TT steam generator tubing

– PWSCC & ODSCC – Cracking at tube end and indications at tube end welds (both

hot and cold legs) • Mechanical wear of tubes due to contact with support structures

and foreign objects • Improved thermal-hydraulics code (Triton) • Improved inspection capabilities

– Total inspection system performance – Auto analysis capabilities – Maintenance of the Examination Technique Specification

Sheets (ETSS) program

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

Annual Materials Programs Executive Information Exchange Meeting

June 2014 PWROG Materials Subcommittee

Update

Scot Greenlee (Exelon) Technical Chairman of the Materials Action Plan Committee


Annual Materials Programs Executive Information Exchange Meeting June 2014

PWR Owners Group MSC Agenda

2

• PWROG MSC Key Strategic Areas Core/Planning Team Organization

• PWROG MSC/NRC Interactions

• PWROG MSC Areas of Coordination & Strategic Planning with MRP

• PWROG MSC Focus Areas for 2014-2015

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 3


PWROG MSC Key Strategic Areas Core/Planning Team Organization

Materials Committee Chris Koehler, Xcel (Chairman)

(612) 330-6755

Heather Malikowski, Exelon (Vice-Chair) (610) 765-5864

Reactor Internals Planning Team

Glenn Gardner (860) 440-0373

Stainless Steels Core Team Heather Malikowski, Exelon

(610) 765-5864

Reactor Vessel Integrity Core Team

Jim Nurrenbern, Ameren (314) 225-1908

Zinc Mitigation Core Team Heather Malikowski, Exelon

(610) 765-5864

Jim Molkenthin PWROG PMO (860) 731-6727

Tammy Natour

AREVA (434) 832-2763

BMI Core Team Mike Garner

(361) 972-4004


Annual Materials Programs Executive Information Exchange Meeting June 2014 PWROG MSC/NRC Interactions

• NRC Interactions: WCAP-17096 under PA-MSC-0473 “Reactor Internals Acceptance

Criteria Methodology & Data Requirements “ Draft SE received. Working on “A” version of report, which is

scheduled in be completed by the end of 2014.

PWROG MSC participated in the March 2014 Joint Industry Discussion with the NRC and the EPRI MRP on Doel-3 Reactor Vessel Results.

PWROG MSC participated in the March 2014 Joint Industry Discussion with the NRC and the EPRI MRP on Clevis Bolt Questions.



PWROG MSC/NRC Interactions • NRC Interactions:

Pre-Submittal Meeting held on June 16 discuss an update to the PWROG Topical Report pertaining to the Master Integrated Reactor Vessel Surveillance Program (MIRVP) for B&W Fabricated Reactor Vessels (PA-MSC-1182).

Meeting to discuss the methodology that is being developed for performing a functionality analysis for the Lower Support Columns. Tentatively to be scheduled for the Fall 2014 (PA-MSC-1103).

Technical meeting to discuss RV Integrity Issues • Present PWROG approach and initial findings under project PA-

MSC-1091 “Demonstrate Appendix G Margins for PWR RPV Nozzles.”

• Discuss the other RV integrity issues as committed in PA-MSC-0554, “Proactively Drive Changes in Reactor Vessel Embrittlement Regulations” Task 1 such as BTP 5-3, RG1.99 revision, and Appendix H.

• Both tentatively to be scheduled for the Fall 2014.



PWROG MSC Areas of Coordination & Strategic Planning with MRP

• Reactor Vessel Integrity

Subsidizing the host utilities for the PSSP program. Participating in ASTM E10.02 to develop consensus ETC.

• Reactor Internals

Coordinating with EPRI MRP on MRP-227 LAI/RAI Responses. NRC meetings held in November 2012, January 2013 and March 2014.

Supporting utilities in plant-specific Applicability Determinations, including MRP-191, Fluence, and Cold Worked Stainless.

• Stainless Steel Degradation/BMIs/BMNs Working with the EPRI MRP on the development of I&E guidance

for ID and OD initiated SCC of PWR SS pressure boundary components.

Coordination of industry activities relative to BMIs/BMNs.



PWROG MSC Focus Areas for 2014-2015

• PA-MSC-0688 - Westinghouse Upper Internals Guide Tube Card Wear – Fleet-wide Operational Projections Guidance of guide card inspections finalized recommendations endorsed per the

NEI 03-08 recommendations. Six needed elements. EPRI MRP incorporated into MRP-227-A via interim guidance.

• Work to Support MRP-227-A - Reactor Internals PA-MSC-1122 - Reactor Vessel Internals Industry Coordination 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-0942 - Dynamic Response Model of Westinghouse Internals PA-MSC-0835 – B&W Internals MRP-227 Phase III Functionality & Core Barrel

Assembly Modeling PA-MSC-0784 - Development of Generic Acceptance Criteria for W and CE

Reactor Internals – MRP-227 Primary and Expansion Components (Grouping of primary and expansion components, adding new ones based on MRP-127-A)

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


PA-MSC-1103R0 – “Functionality Analysis: Westinghouse Lower Support Columns”

– The purpose of the program is as follows: Develop a methodology which will form the basis for generic or, if needed,

plant-specific analyses. Complete first steps in substantiating the qualitative safety argument.

– This program is designed to: Potentially eliminate the need for plant-specific evaluations,

Provides a level of confidence that performing a more detailed functionality analysis, if required, will be successful and

Demonstrates to the NRC that the licensees are working to make progress towards a final resolution of the embrittlement issue for lower support columns.




PA-MSC-1091R0 – “Demonstrate Excessive Appendix G Margins for PWR RPV Nozzles”

– The purpose of the program is as follows: Identify the magnitude of the various Appendix G margins related to

assessment of the inlet/outlet nozzles. – This program is designed to:

Develop a consistent and less conservative basis for responding to RAIs,

Demonstrate continuous and ongoing compliance with Appendix G,

Minimize, and potentially eliminate, future RAIs on this topic,

Reduce plant costs in updating P-T curves and

Perform generic bounding evaluations.




• PA-MSC-0257 - PWSCC Crack Initiation Testing of Farley Unit 2 Alloy

600 CRDM Penetrations Work to be complete in Summer 2014.

o Provides key chemical mitigation input regarding the beneficial effect of zinc addition to delay primary water stress corrosion cracking in nickel based Alloys (A600/A690) and their associated weld metals (A82/182/52M/152) ,

o Used in PWR primary systems. Program will provide inputs to the extremely low probability of rupture (xLPR) program.

• PA-MSC-0551 - Development of I&E Guidelines for ID and OD-

Initiated SCC of PWR SS Pressure Boundary Components The program has three phases:

o Phase 1: Establishing screening criteria (COMPLETE) o Phase 2: Consequences evaluation (IN PROCESS) o Phase 3: Develop I&E guidelines (PLANNED)




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.

11

Global Expertise • One Voice www.pwrog.com

Joe Donahue, Duke Energy Chairman, NDE Action Plan Committee

Steve Swilley, EPRI Director, NDE

Robin Dyle, EPRI Technical Executive

Industry / NRC Management Meeting

June 25, 2014

NDE Program


Cross-cutting issues: Actions to address human performance issues • Research directions

– Proficiency maintenance – Technology

• Implementation of post-North Anna guidance – Proceeding well – INPO role

• Vendor engagement – Vendor outreach – Vendor engagement in NDE Program advisory process


Regulatory interface

• Successes – Interaction on PDI bolting issue – Remote VT collaboration – Modeling and simulation collaboration

• Recent improvements – Annual NDE focus meeting – Quarterly calls; maintaining action item list – Project review meeting with RES

• Challenges – Improve communications as to NRC comments – Structure projects in anticipation of supporting regulatory interface


Effects of improving inspections due to continuous learning • We may continue to find flaws that were missed before • Coordinating with licensees

– Help licensees deal with these situations – Got slightly out of step with PG&E on the DCPP OE

• RCE cited areas for improvement • NDE IC sent out an NDE Alert memo addressing the procedure technical items

• Other items were already being addressed, or are being addressed now, through the research program

Mike Gallagher, Exelon

Chairman, EPRI LTO Advisory Committee Sherry Bernhoft, EPRI

Program Manager, LTO Annual Materials Update to NRC Management

June 25,2014

EPRI Long Term Operations Program


EPRI LTO Program Goals and Objectives • Technical basis for safe, reliable

plant operation through extended lifetime

• Useful results in 2014 to 2019 timeframe

• Demonstrated technologies to support long-term plant management

• Research projects integrated with other EPRI programs

• External collaboration (DOE, NRC Research, EDF, Owners Groups )

Expect first SLR submittals in

2018


Basis for Implementation of Aging Management • R&D to understand aging

degradation – Mechanism and failure modes – Initiation and growth rates – Inspection and Evaluation GLs

• Inspection methods

– Detection and measurement – Non destructive examination and

qualification

• Mitigation strategies – Chemistry – Stress relieving techniques – Weld overlays

• Condition Monitoring – On-line monitoring – In-field detection

• Prediction of Remaining Useful Life

– Health Monitoring software and algorithms

• Repair & Replacement Decisions – Life Cycle Management GLs – Advanced welding for irradiated

materials – Integrated Life Cycle Management

(ILCM)


EPRI LTO R&D Focus Areas • Aging Management

– Primary system metals, welds and piping – Reactor pressure vessel – Steam Generators – Electrical cables – Concrete and containment structures – Buried piping – Coatings – Flow Accelerated Corrosion (FAC)

• Opportunities for Modernization – Advanced Instrumentation & Controls – Advanced risks and PRA – Advanced welding for irradiated materials – Non-destructive testing methodologies (NDE)

• Enabling technologies – Pilot plant projects and demonstrations – Integrated Life Cycle Management


EPRI R&D Projects – Cross Referenced to GALL, Rev 2

• EPRI Report 3002000576 “Assessment of R&D Supporting Aging Management Programs for Long-Term Operations”

• Report cross-references the EPRI R&D Projects to the AMPs

• Three categories of AMPs – On-going long-term R&D – Established Programs – One-time plant specific

inspections

Examples: • On-going long-term R&D (8)

– Effects of irradiation – Thermal effects – Reactor Pressure Vessel

embrittlement • Established Programs (20)

– Chemistry – Steam Generator Inspections – FAC

• Plant Specific (22) – Fuel oil – Fire Protection System


Material Category 1 AMP

GALL AMP ID AMP Name Potential LTO Impact on AMP XI.M9 BWR Vessel Internals Irradiation and environmental effects on material

performance

XI.M11B Cracking of Nickel-Alloy Components and Loss of Material Due to Boric Acid-Induced Corrosion in Reactor Coolant Pressure Boundary Components

Environmental effects on material performance

XI.M12 Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS)

Thermal aging and possible irradiation effects on material performance

XI.M16A PWR Vessel Internals Irradiation and environmental effects on material

XI.M31 Reactor Vessel Surveillance Neutron fluence on reactor pressure vessel materials


Summary of Category 1 Materials AMPs

• The existing AMPs are effective and in use to detect and management aging effects

• R&D is managed by the EPRI Materials Programs – NEI 03-08 – Continuous improvements – Updated based on inspection results, operating

experience and R&D • Continuous improvements will

– Improved modeling of degradation – Improved inspection technologies – Advances in assessment and evaluation methodology – On-line condition monitoring


Summary

• There maybe some plant specific issues but no show stoppers to-date

• Program will need to be dynamic to respond to changing R&D needs when the first US plant applies for SLR

Materials Degradation/Aging Action Plan Committee (MAPC). · – See following slides for an update...

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Transcript of Materials Degradation/Aging Action Plan Committee (MAPC). · – See following slides for an update...