ML12335A515

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Official Exhibit - RIV000035-PUB-00-BD01 -Dr. Hopenfeld Report
ML12335A515
Person / Time
Site: Indian Point  
Issue date: 12/20/2011
From: Hopenfeld J
Riverkeeper
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21625, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12335A515 (32)
v • d • e


Text

RIV000035 Submitted: December 22, 2011







 

  









    

 



 





















 



































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Riverkeeper, Inc. provisionally designates the attached Report of Dr. Joram Hopenfeld dated December 20, 2011 as containing Confidential Proprietary Information Subject to Nondisclosure Agreement REDACTED, PUBLIC VERSION



















United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of:

Entergy Nuclear Operations, Inc.

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #:

Identified:

Admitted:

Withdrawn:

Rejected:

Stricken:

Other:

RIV000035-PUB-00-BD01 10/15/2012 10/15/2012

RIV000035 Submitted: December 22, 2011







 

  









    

 



 





















 



































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REPORT OF DR. JORAM HOPENFELD IN SUPPORT OF CONTENTION RIVERKEEPER TC-1B - METAL FATIGUE

RIV000035 Submitted: December 22, 2011







TABLE OF CONTENTS I.

Introduction''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''5 II. Background'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''5 A.

Basic Principles Concerning Metal Fatigue''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''5 B.

Safety Implications of Metal Fatigue'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''2 III. NRC Regulations''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''2 IV. Entergys 2010 Refined CUFen EAF Analyses''''''''''''''''''''''''''''''''''''''''''''''''''''''''''0 A.

Laboratory Data''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''0 B.

Dissolved Oxygen'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''6 C.

Heat Transfer'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''52

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$$' 7%8%"! "$%'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''5,

1.

Pressurizer Surge Line'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''5,

2.

Inlet and Outlet Reactor Vessel Nozzles''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''51

3.

Other Table 4.3-13 and Table 4.3-14 Components'''''''''''''''''''''''''''''''''''''''''''51 D.

Number of Transients'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''53

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Summary and Conclusions Concerning Entergys Refined CUFen EAF Analysis'/-

V. Inadequacy of Entergys Aging Management Plan (AMP) for Metal Fatigue.''''/5 A.

Improper Reliance on Entergys Refined Fatigue Evaluations'''''''''''''''''''''''''''''''//

B.

Improper Failure to Identify Additional Components for Review'''''''''''''''''''''''''''''''//

C.

Failure to Define Specific Criteria Concerning Component Inspection, Monitoring, Repair, or Replacement'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''/,

VI. Conclusion'''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''/,

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41 Environmental Fatigue Evaluation for Indian Point Unit 2, WCAP-17199-P. Revision 0 (Westinghouse, JIme 2010), IPECPROPOOO56486. a p.5-24: Envu:Ollllental Fatigue Evaluation for Indian Point Unit 3. WCAP-I7200-P, Revision 0 (Westinghouse, June 2010), IPECPROPOO056577. at p.5-24.

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Conclusion

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Docket Nos. 5()..247*LR &; 50-286--LR Report of Dr. Joram Hopeofeld In support oflUC.-TC-IB I I I I As a result of these deficiencies, Entergy's calculations have a wide margin of error and have likely underestimated the CUF co values. As many of the values derived by Entergy'5 new evaluation are very close to unlty, the regulatory threshold, it is biibly liI<ely that if Entergy had accurately considered 011 relevant factors, many of the CUF_

values would, in actuality, exceed 1.0; Entcrgy has improperly failed to confirm that the components evaluated represent the most limiting locations providing a hounding analysis, and failed to expand the scope of oomponents to be subject to a CUF on analysis accordingly;

  • In light of the insufficiency ofEntergy' $ CUF f:JI analyses, Entergy bas otb~ failed to provide any details concerning the inspection. monitoring, repair, and rq>lacement to ensure that the degradation effects of metal fatigue would he sufficiently handled.

Accordingly, Entcrgy bas failed to demonstrate that the aging effects of metal futigue will he adequately managed for the period of ""tended operation, and has, thus, failed to comply with 10 C.F.R. § 54.21(c) or regulatory guidance, including the GALL Report.

December 19, 2011 Rockville, MD Dr. Jonun H eld 1724 Yale Place Rockville, MD 20850 26

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LIST OF REFERENCES



E.46-6&Effect of LWR Coolant Environment on Fatigue Life of Reactor Materials&

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E.4/4-&Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components )566,A' ---2,,



E.,1-0&Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels&

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E.4,32&

.61E53&Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, A' ---2,4



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