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New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000328, NRC Staff, Division of Component Integrity, Rc Perspectives on PWR Materials Issues(ML101520577) (June 2010) (PWR Materials Issues)
	ML11356A323
Person / Time
Site:	Indian Point
Issue date:	06/01/2010
From:	John Lubinski; NRC/NRR/DCI
To:	; Atomic Safety and Licensing Board Panel
	SECY RAS
Shared Package
ML11356A318	List: Information Notice 2011-13, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000329, NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13); ML11356A323; ML11356A324; ML11356A325; ML11356A326; ML11356A328;
References
	RAS 21619, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
	Download: ML11356A323 (15)
	v • d • e

NYS000328 Submitted: December 22, 2011 U.S.NRC UNITED STATES NUCLEAR REGULATORY COMMISSION Protecting People and the Environ1nent NRC Perspectives on PWR Materials Issues John W. Lubinski, Deputy Director Division of Component Integrity 0

Office of Nuclear Reactor Regulation

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Introduction

~Retired St. Lucie Pressurizer Nozzle Flaws

Highly complex technical issues

Significant level of attention by all NRC stakeholders

Level of dedication by staff on both sides to try to get things right 0

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. liS""'i NRC"'1 PWR RPV Internals

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Aging Management

~Historical Background

PWR internal components may be subject to a number of degradation mechanisms

Degradation management an issue for license renewal and power uprates

Materials Reliability Program project 0

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. liS""'i NRC"'1 PWR RPV Internals

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Aging Management

~Topical Report MRP-227 submitted for NRC review in Spring 2009

Evaluated components based on susceptibility to a variety of mechanisms and consequences of component failure

Divided components into several "bins" for inspection

Identified inspection technologies to be used for component inspection 0

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Aging Management

~Next steps

Review of MRP-227 is a high priority

The NRC staff is continuing to work with MRP and EPRI regarding staff concerns related to MRP-227

Review of plant-specific aging management programs

Implementation of MRP-227 by other licensees 0

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Davis -Besse RPV Head

-~-"""'""""""--* Cracking

~Historical background

Cracking and head corrosion in 2002

Replacement head from Midland installed -also Alloy 82/182/600

How long before PWSCC would be observed in the replacement RPV head?

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~Current status

Licensee performed RPV head inspection in Spring 2010 and found evidence of boric acid deposits and indications of primary water stress corrosion cracking in their nozzles and welds

The inspections identified penetration nozzles and/or welds with indications of cracking 0

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~Next steps

Licensee performing half-nozzle repairs on all nozzles with indications

NRC staff reviewing licensee's engineering assessment of the as-found condition of the RPV head

Potential generic implications 0

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. liS""'i NRC"'1 ODSCC of Stainless

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Steel Piping

~Recent operating experience

Fall 2008- Leak in Callaway Pressurizer Auxiliary Spray Line

Fall 2008- Indications in Wolf Creek Pressurizer Auxiliary Spray Line

Fall 2009- Leaks found in multiple lines at San Onofre, Units 2 and 3 0

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. liS""'i NRC"'1 ODSCC of Stainless

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~Current status

Industry researching operating experience databases for additional instances of ODSCC

Typical instances of ODSCC involved TGSCC due to chloride contamination of 304 stainless steel piping

NRC preparing an Information Notice 0

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. liS""'i NRC"'1 ODSCC of Stainless

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~Next steps

Industry in the process of developing inspection and evaluation guidelines to be issued under NEI 03-08, "Guideline for the Management of Materials Issues"

NRC staff will continue to monitor operating experience and review industry guidelines when issued 0

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. liS""'i NRC"'1 Repair and Mitigation

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Technology

~Focus on repair or mitigation of PWSCC in lnconel piping butt welds

Weld overlay/inlay/on lay repair and mitigation

Mechanical stress improvement

~Developments in welding-based repair and mitigation technology have lead to a variety of 0

repair options

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. liS""'i NRC"'1 Repair and Mitigation

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~NRC staff focus areas

Welding with lnconel Alloy 52

Implementation of new or advanced welding techniques

Implications of the application of weld overlays to Leak-Before-Break approvals 0

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~Next Steps

NRC will continue to place significant resources on monitoring and reviewing the development of welding-based repair and mitigation technology

Issuance of Regulatory Issue Summary (RIS) regarding weld overlays and Leak-Before-Break 0

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- -* * .'-1 l'lfflt.s.:ti<<g ~rq;h< ,.m;i f1ut l!;*.,_d.,.,mmmtt Conclusions

~Understand that the NRC staff looks at every materials degradation issue from both a plant-specific and generic perspective

~Communication between the industry and NRC is a key issue

~Proactive measures to deal with potential 0

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issues are better than reactive measures to G>

deal with an emerging significant issue 0

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ML11356A323

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