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{{#Wiki_filter:November 1, 2011 Lahey Declaration 1 UNITED STATES NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD  
{{#Wiki_filter:United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.
--------------------------------------------------------------x In re:       Docket Nos. 50-247-LR; 50-286-LR  
In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3)
ASLBP #: 07-858-03-LR-BD01                                                      NYS000303 Docket #: 05000247 l 05000286                                                  Submitted: December 22, 2011 Exhibit #: NYS000303-00-BD01                  Identified: 10/15/2012 Admitted: 10/15/2012                        Withdrawn:
Rejected:                                      Stricken:
Other:
UNITED STATES NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
                      --------------------------------------------------------------x In re:                                                             Docket Nos. 50-247-LR; 50-286-LR License Renewal Application Submitted by                          ASLBP No. 07-858-03-LR-BD01 Entergy Nuclear Indian Point 2, LLC,                              DPR-26, DPR-64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc.                                  November 1, 2011
                      --------------------------------------------------------------x DECLARATION OF DR. RICHARD T. LAHEY, JR.
I, Richard T. Lahey, Jr., declare under penalty of perjury that the following is true and correct:
: 1.        I submit this declaration in response to Entergy NL-11-107 communication with NRC Staff and in support of the proposed contention pending before the Board.
: 2.        I am the Edward E. Hood Professor Emeritus of Engineering at Rensselaer Polytechnic Institute (RPI) in Troy, New York, a member of the National Academy of Engineering (NAE), a Fellow of the American Nuclear Society (ANS) and the American Society of Mechanical Engineers (ASME), and an expert in matters relating to the operations, safety, and the aging of nuclear power plants. I have previously submitted declarations in this proceeding and for the sake of brevity refer the parties and the Board to those submissions with respect to my qualifications and experience. My curricula vitae, which more fully describes my November 1, 2011 Lahey Declaration 1


License Renewal Application Submitted by  ASLBP No. 07-858-03-LR-BD01 Entergy Nuclear Indian Point 2, LLC,   DPR-26, DPR-64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc. November 1, 2011
educational and professional background and qualifications, is available at:
--------------------------------------------------------------x
http://www.rpi.edu/~laheyr/laheyvita.html.
: 3. The September 28, 2011 Entergy NL-11-107 document on reactor pressure vessel internals is claimed by them to contain the completion of commitment #30 to their license renewal application for the Indian Point reactors and the aging management programs for RPV internals. While this document does give a comprehensive list of the Indian Point RPV internal structures, components and fittings to be evaluated, and the NDT techniques they plan to employ in these inspections, no details are given on the timing for these inspections. Moreover, in some cases, instead of details, Entergy simply states: In accordance with SER Section 4.2.7, IPEC will submit this information to the NRC as part of the submittal to apply the approved version of MRP-227(e.g., see compliance item-7 on page-22 of Section 3.6). Since MRP-227A is not expected to be released until year end (i.e.,
December 2011), this information will not be available in time for review and discussion in the State's upcoming submissions and consideration in the ASLB hearings on IP license renewal.
: 4. In addition, Entergy frequently states that the NDT inspections of 100% of the RPV internal structures, components and fittings of interest are not possible. Moreover, Entergy even states that in some cases failed or missing bolts can be considered the indicated aging effect (see Table 5-2, page - 36). Significantly, they also state that planar flaws in bolts can be reliably detected if - and only if -
these flaws occupy more than 30% of the bolt's cross-sectional area (see Section November 1, 2011 Lahey Declaration 2


DECLARATION OF DR. RICHARD T. LAHEY, JR.
4.1.5, page-25). This means that - under Entergy's proposal - incore bolts can be deemed adequate for continued operations even if they are significantly degraded.
I, Richard T. Lahey, Jr., declare under penalty of perjury that the following is true and correct: 1.I submit this declaration in response to Entergy NL-11-107 communication with NRC Staff and in support of the proposed contention pending before the Board. 2.I am the Edward E. Hood Professor Emeritus of Engineering at Rensselaer Polytechnic Institute (RPI) in Troy, New York, a member of the National
While these type of acceptance criteria might make some sense when considering steady-state and normal plant transients, it is not at all clear that they are adequate to assure core coolability subsequent to various accidents which produce severe shock loads on highly embrittled and fatigued RPV internals and which may result in an uncoolable core geometry. As USNRC Staff and Entergy are aware, the State of New York has significant safety concerns about this interrelationship between fatigue and embrittlement and the adequacy of the AMPs of RPV internals, and, unfortunately, the State's concerns have not been addressed at all by Entergy or USNRC Staff.
 
Pursuant to 28 U.S.C. § 1746, I declare under penalty of perjury that the foregoing is true and correct.
Academy of Engineering (NAE), a Fellow of the American Nuclear Society (ANS) and the American Society of Mechanical Engineers (ASME), and an expert in matters relating to the operations, safety, and the aging of nuclear power plants. I have previously submitted declarations in this proceeding and for the sake of brevity refer the parties and the Board to those submissions with respect to my
November 1, 2011 Signed (electronically) by Dr. Richard T. Lahey, Jr.
 
November 1, 2011 Lahey Declaration 3}}
qualifications and experience. My curricula vitae , which more fully describes my 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: NYS000303-00-BD01 10/15/2012 10/15/2012 NYS000303 Submitted: December 22, 2011 November 1, 2011 Lahey Declaration 2 educational and professional background and qualifications, is available at: http://www.rpi.edu/~laheyr/laheyvita.html. 3.The September 28, 2011 Entergy NL-11-107 document on reactor pressure vessel internals is claimed by them to contain the completion of commitment #30 to their license renewal application for the Indian Point reactors and the aging management programs for RPV internals. While this document does give a comprehensive list of the Indian Point RPV internal structures, components and fittings to be evaluated, and the NDT techniques they plan to employ in these inspections, no details are given on the timing for these inspections. Moreover, in some cases, instead of details, Entergy simply states: In accordance with SER Section 4.2.7, IPEC will submit this information to the NRC as part of the submittal
 
to apply the approved version of MRP-227(e.g., see compliance item-7 on page-22 of Section 3.6). Since MRP-227A is not expected to be released until year end (i.e., December 2011), this information will not be available in time for review and discussion in the State's upcoming submissions and consideration in the ASLB
 
hearings on IP license renewal. 4.In addition, Entergy frequently states that the NDT inspections of 100% of the RPV internal structures, components and fittings of interest are not
 
possible. Moreover, Entergy even states that in some cases failed or missing bolts can be considered the indicated aging effect (see Table 5-2, page - 36). Significantly, they also state that planar flaws in bolts can be reliably detected if -
and only if
- these flaws occupy more than 30% of the bolt's cross-sectional area (see Section November 1, 2011 Lahey Declaration 3 4.1.5, page-25). This means that - under Entergy's proposal - incore bolts can be deemed adequate for continued operations even if they are significantly degraded.
While these type of acceptance criteria might make some sense when considering steady-state and normal plant transients, it is not at all clear that they are adequate to assure core coolability subsequent to various accidents which produce severe shock loads on highly embrittled and fatigued RPV internals and which may result in an uncoolable core geometry. As USNRC Staff and Entergy are aware, the State of New York has significant safety concerns about this interrelationship between fatigue and embrittlement and the adequacy of the AMPs of RPV internals, and, unfortunately, the State's concerns have not been addressed at all by Entergy  
 
or USNRC Staff. Pursuant to 28 U.S.C. § 1746, I declare under penalty of perjury that the foregoing is true and correct.  
 
November 1, 2011 Signed (electronically) by
_________________________
Dr. Richard T. Lahey, Jr.}}

Latest revision as of 11:01, 6 February 2020

Official Exhibit - NYS000303-00-BD01 - Declaration of Dr. Richard T. Lahey, Jr. in Response to Entergy NL-11-107
ML12335A461
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 11/01/2011
From: Lahey R
State of NY
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 21617, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12335A461 (3)
v • d • e


Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 NYS000303 Docket #: 05000247 l 05000286 Submitted: December 22, 2011 Exhibit #: NYS000303-00-BD01 Identified: 10/15/2012 Admitted: 10/15/2012 Withdrawn:

Rejected: Stricken:

Other:

UNITED STATES NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD

x In re: Docket Nos. 50-247-LR; 50-286-LR License Renewal Application Submitted by ASLBP No. 07-858-03-LR-BD01 Entergy Nuclear Indian Point 2, LLC, DPR-26, DPR-64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc. November 1, 2011

x DECLARATION OF DR. RICHARD T. LAHEY, JR.

I, Richard T. Lahey, Jr., declare under penalty of perjury that the following is true and correct:

1. I submit this declaration in response to Entergy NL-11-107 communication with NRC Staff and in support of the proposed contention pending before the Board.
2. I am the Edward E. Hood Professor Emeritus of Engineering at Rensselaer Polytechnic Institute (RPI) in Troy, New York, a member of the National Academy of Engineering (NAE), a Fellow of the American Nuclear Society (ANS) and the American Society of Mechanical Engineers (ASME), and an expert in matters relating to the operations, safety, and the aging of nuclear power plants. I have previously submitted declarations in this proceeding and for the sake of brevity refer the parties and the Board to those submissions with respect to my qualifications and experience. My curricula vitae, which more fully describes my November 1, 2011 Lahey Declaration 1

educational and professional background and qualifications, is available at:

http://www.rpi.edu/~laheyr/laheyvita.html.

3. The September 28, 2011 Entergy NL-11-107 document on reactor pressure vessel internals is claimed by them to contain the completion of commitment #30 to their license renewal application for the Indian Point reactors and the aging management programs for RPV internals. While this document does give a comprehensive list of the Indian Point RPV internal structures, components and fittings to be evaluated, and the NDT techniques they plan to employ in these inspections, no details are given on the timing for these inspections. Moreover, in some cases, instead of details, Entergy simply states: In accordance with SER Section 4.2.7, IPEC will submit this information to the NRC as part of the submittal to apply the approved version of MRP-227(e.g., see compliance item-7 on page-22 of Section 3.6). Since MRP-227A is not expected to be released until year end (i.e.,

December 2011), this information will not be available in time for review and discussion in the State's upcoming submissions and consideration in the ASLB hearings on IP license renewal.

4. In addition, Entergy frequently states that the NDT inspections of 100% of the RPV internal structures, components and fittings of interest are not possible. Moreover, Entergy even states that in some cases failed or missing bolts can be considered the indicated aging effect (see Table 5-2, page - 36). Significantly, they also state that planar flaws in bolts can be reliably detected if - and only if -

these flaws occupy more than 30% of the bolt's cross-sectional area (see Section November 1, 2011 Lahey Declaration 2

4.1.5, page-25). This means that - under Entergy's proposal - incore bolts can be deemed adequate for continued operations even if they are significantly degraded.

While these type of acceptance criteria might make some sense when considering steady-state and normal plant transients, it is not at all clear that they are adequate to assure core coolability subsequent to various accidents which produce severe shock loads on highly embrittled and fatigued RPV internals and which may result in an uncoolable core geometry. As USNRC Staff and Entergy are aware, the State of New York has significant safety concerns about this interrelationship between fatigue and embrittlement and the adequacy of the AMPs of RPV internals, and, unfortunately, the State's concerns have not been addressed at all by Entergy or USNRC Staff.

Pursuant to 28 U.S.C. § 1746, I declare under penalty of perjury that the foregoing is true and correct.

November 1, 2011 Signed (electronically) by Dr. Richard T. Lahey, Jr.

November 1, 2011 Lahey Declaration 3

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