ML11361A494: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 14: | Line 14: | ||
| page count = 24 | | page count = 24 | ||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD | |||
___________________________________________ ) | |||
In the Matter of ) ) | |||
Entergy Nuclear Operations, Inc. ) Docket Nos. | |||
(Indian Point Nuclear Generating ) 50-247-LR Units 2 and 3) ) and 50-286-LR ___________________________________________ ) | |||
Riverkeeper, Inc. provisionally designates the attached Testimony of Dr. Joram Hopenfeld dated December 20, 2011 as containing Confidential Proprietary Information Subject to Nondisclosure Agreement | |||
REDACTED, PUBLIC VERSION | |||
RIV000034 Submitted: December 22, 2011 | |||
PREFILED WRITTEN TESTI MONY OF DR. JORAM HOPENFELD REGARDING NYS-26-B/RK-TC-1B - METAL FATIGUE | |||
Q. Please state your name and address. | |||
Q. What is your educational and professional background? curriculum vita, which is Q. What is the purpose of your testimony? | |||
Q.Have you prepared a report in support of your testimony? | |||
Q. What materials have you reviewed in preparation for your expert report and testimony?SeeSee Q. What conclusions have you reached about metal fatigue at Indian Point? Q. What is metal fatigue? | |||
Q. What are the safety implications of metal fatigue? | |||
Q. Please explain how component susceptibility to metal fatigue is predicted. | |||
Q.Entergy's LRA contained the results of an analysis of the effects of environmentally assisted fatigue on certain reactor components during the proposed period of extended operation. What was the outcome of this CUF analysis? | |||
Q. Have you reviewed Entergy's refined environmentally assisted fatigue analyses? | |||
Q. What is your opinion regarding the validity of the results of Entergy's refined analyses? | |||
Q. Please explain why the use of laboratory data must be adjusted in order to determine appropriate F factors in the calculation of CUF. Effect of LWR Coolant Environment on Fatigue Life of Reactor MaterialsEffect of LWR Coolant Environment on Fatigue Life of Reactor MaterialsSeeSee Q. How did you reach the conclusion that Entergy's refined fatigue evaluations Q. | |||
Q. Entergy has previously claimed that using the bounding Fen values recommended in NUREG/CR-6909 "would actually yield less conservative CUF values, because the ASME Code design air curves for carbon steel and low | |||
-alloy steels contained in air [which is what Entergy considered] . . . are more conservative than the newer air curves in NUREG/CR | |||
-6909."4 How would you respond to this assertion? | |||
Q. Please explain how DO levels affect the determination of appropriate Fen values for calculating CUFen. | |||
Q. How did you reach the conclusion that Entergy's refined fatigue evaluations Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels | |||
Q. Can you please explain what a heat transfer coefficient is in relation to determining CUF en. | |||
Q. How did you reach the conclusion that Entergy's refined fatigue evaluations Q. Can you please explain how you reached the conclusion that Entergy See | |||
Q. Can you please explain how you reached the conclusion that Entergy failed to justify that heat transfer was appropriately considered in the calculation of CUF en for certain components. | |||
Q. How did you reach the conclusion that Entergy's refined fatigue evaluations . | |||
Q. Please summarize your conclusions about Entergy's refined EAF analyses. | |||
Q. In your opinion, does Entergy otherwise have an adequate program for managing the effects of metal fatigue during the proposed period of extended operation? | |||
Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components Generic Aging Lessons Learned (GALL) Report GALL Reportnow, Q. Please summarize your opinions regarding whether or not Entergy has demonstrated that metal fatigue of reactor components will be adequately managed during the proposed periods of extended operation as required by 10 C.F.R. § 54.21(c).GALL Report Q. Does this conclude your initial testimony regarding Riverkeeper Contention TC | |||
-1B?}} | |||
Revision as of 01:19, 31 July 2018
| ML11361A494 | |
| 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 21652, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |
| Download: ML11361A494 (24) | |
Text
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD
___________________________________________ )
In the Matter of ) )
Entergy Nuclear Operations, Inc. ) Docket Nos.
(Indian Point Nuclear Generating ) 50-247-LR Units 2 and 3) ) and 50-286-LR ___________________________________________ )
Riverkeeper, Inc. provisionally designates the attached Testimony of Dr. Joram Hopenfeld dated December 20, 2011 as containing Confidential Proprietary Information Subject to Nondisclosure Agreement
REDACTED, PUBLIC VERSION
RIV000034 Submitted: December 22, 2011
PREFILED WRITTEN TESTI MONY OF DR. JORAM HOPENFELD REGARDING NYS-26-B/RK-TC-1B - METAL FATIGUE
Q. Please state your name and address.
Q. What is your educational and professional background? curriculum vita, which is Q. What is the purpose of your testimony?
Q.Have you prepared a report in support of your testimony?
Q. What materials have you reviewed in preparation for your expert report and testimony?SeeSee Q. What conclusions have you reached about metal fatigue at Indian Point? Q. What is metal fatigue?
Q. What are the safety implications of metal fatigue?
Q. Please explain how component susceptibility to metal fatigue is predicted.
Q.Entergy's LRA contained the results of an analysis of the effects of environmentally assisted fatigue on certain reactor components during the proposed period of extended operation. What was the outcome of this CUF analysis?
Q. Have you reviewed Entergy's refined environmentally assisted fatigue analyses?
Q. What is your opinion regarding the validity of the results of Entergy's refined analyses?
Q. Please explain why the use of laboratory data must be adjusted in order to determine appropriate F factors in the calculation of CUF. Effect of LWR Coolant Environment on Fatigue Life of Reactor MaterialsEffect of LWR Coolant Environment on Fatigue Life of Reactor MaterialsSeeSee Q. How did you reach the conclusion that Entergy's refined fatigue evaluations Q.
Q. Entergy has previously claimed that using the bounding Fen values recommended in NUREG/CR-6909 "would actually yield less conservative CUF values, because the ASME Code design air curves for carbon steel and low
-alloy steels contained in air [which is what Entergy considered] . . . are more conservative than the newer air curves in NUREG/CR
-6909."4 How would you respond to this assertion?
Q. Please explain how DO levels affect the determination of appropriate Fen values for calculating CUFen.
Q. How did you reach the conclusion that Entergy's refined fatigue evaluations Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels
Q. Can you please explain what a heat transfer coefficient is in relation to determining CUF en.
Q. How did you reach the conclusion that Entergy's refined fatigue evaluations Q. Can you please explain how you reached the conclusion that Entergy See
Q. Can you please explain how you reached the conclusion that Entergy failed to justify that heat transfer was appropriately considered in the calculation of CUF en for certain components.
Q. How did you reach the conclusion that Entergy's refined fatigue evaluations .
Q. Please summarize your conclusions about Entergy's refined EAF analyses.
Q. In your opinion, does Entergy otherwise have an adequate program for managing the effects of metal fatigue during the proposed period of extended operation?
Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components Generic Aging Lessons Learned (GALL) Report GALL Reportnow, Q. Please summarize your opinions regarding whether or not Entergy has demonstrated that metal fatigue of reactor components will be adequately managed during the proposed periods of extended operation as required by 10 C.F.R. § 54.21(c).GALL Report Q. Does this conclude your initial testimony regarding Riverkeeper Contention TC
-1B?