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{{#Wiki_filter:Page 1 of 1 Jonathan Rowley - October 11 and 16 conference call summaries From:         Jonathan Rowley To:           jdevinc@entergy.com Date:         11/16/2007 10:32 AM
{{#Wiki_filter:Page 1 of 1 Jonathan Rowley - October 11 and 16 conference call summaries From:
Jonathan Rowley To:
jdevinc@entergy.com Date:
11/16/2007 10:32 AM


==Subject:==
==Subject:==
October 11 and 16 conference call summaries Attached are the summaries for conference calls held on Oct. 11 and Oct. 16, 2007. Please review and comment where necessary.
October 11 and 16 conference call summaries Attached are the summaries for conference calls held on Oct. 11 and Oct. 16, 2007. Please review and comment where necessary.
file://C:\temp\GW} 00002.HTM                                                                 12/03/2007
file://C:\\temp\\GW} 00002.HTM 12/03/2007


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I c:\\temp\\GW}0q003.TMP Page 1 1ý,c:\\temp\\GW)00003.TMP Page_'1j Mail Envelope Proper


==Subject:==
==Subject:==
October 11 and 16 conference call summaries Creation Date          11/16/2007 10:32:53 AM From:                  Jonathan Rowley Created By:            JGR(anrc.gov Recipients                                         Action              Date & Time entergy.com                                       Transferred          11/16/2007 .10:33:05 AM jdevinc (jdevinccýentergv.com)
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*ties (473DB825.347 : 12 : 35182)
October 11 and 16 conference call summaries 11/16/2007 10:32:53 AM Jonathan Rowley JGR(anrc.gov Recipients entergy.com AM jdevinc (jdevinccýentergv.com)
Post Office Files Size MESSAGE 441 TEXT.htm 347 Summary of Telephone Conference -
11:51:04 AM Summary of Telephone Conference -
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==Subject:==
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0I Security:                       S~tandard To Be Delivered:               Immediate Status Tracking:               Delivered & Opened
Security:
To Be Delivered:
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owe-Joaha        umryo TeehnCneerd                       coe1, 20071.wpd                                       - ~ Page 1 LICENSEE: Entergy Nuclear Operations, Inc.
Joaha owe-umryo TeehnCneerd coe1, 20071.wpd  
FACILITY:     Vermont Yankee Nuclear Power Station
~
Page 1 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY:
Vermont Yankee Nuclear Power Station


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 11, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING AUDIT QUESTIONS PERTAINING TO THE VERMONT'YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 11, 2007, to discuss and clarify the staff=s audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application asked during the October 9 - 10, 2007, audit of the VYNPS time-limited aging analyses. The telephone conference call was useful in clarifying the intent of the staff=s audit questions.
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 11, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING AUDIT QUESTIONS PERTAINING TO THE VERMONT'YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 11, 2007, to discuss and clarify the staff=s audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application asked during the October 9 - 10, 2007, audit of the VYNPS time-limited aging analyses. The telephone conference call was useful in clarifying the intent of the staff=s audit questions. provides a listing of the participants and Enclosure 2 contains a listing of the audit questions discussed with the applicant, including a brief description on the status of the items.
Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the audit questions discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
The applicant had an opportunity to comment on this summary.
Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271
Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271
Line 49: Line 68:
: 2. List of Audit Questions cc w/encls: See next page
: 2. List of Audit Questions cc w/encls: See next page


ML OFFICE       LA:DLR             PM:RLRB:DLR           BC:RPB2:DLR NAME                             JRowley               RFranovich DATE         11/ /07           11/   /07             11/   /07 J6natlhan Rowl.ey - Summary of Tele p.hone Conference - October 11, 2007.wpdP j,                                                                                                          ,page 3,,tl TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS OCTOBER 11, 2007 PARTICIPANTS                                 AFFILIATIONS Jonathan Rowley                               U.S. Nuclear Regulatory Commission (NRC)
ML OFFICE LA:DLR PM:RLRB:DLR BC:RPB2:DLR NAME JRowley RFranovich DATE 11/  
Kenneth Chang                                NRC Robert Hsu                                  NRC Michael Metell                              Entergy Nuclear Operations, Inc. (Entergy)
/07 11/  
David Mannai                                Entergy James Fitzpatrick                            Entergy Alan cox                                      Entergy ENCLOSURE1
/07 11/  
/07
 
j, J6natlhan Rowl.ey - Summary of Tele p.hone Conference - October 11, 2007.wpdP
,page 3,,tl TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS OCTOBER 11, 2007 PARTICIPANTS Jonathan Rowley Kenneth Chang Robert Hsu Michael Metell David Mannai James Fitzpatrick Alan cox AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)
NRC NRC Entergy Nuclear Operations, Inc. (Entergy)
Entergy Entergy Entergy ENCLOSURE1


11, 2007.wpd                                Page 41 Row!ey -Summary Jonathan Rowley              of Teiephop~ Confer ce -~O6t6ber
Jonathan Row!ey -Summary of Teiephop~ Confer ce -~O6t6ber 11, 2007.wpd Page 41
,'ýqnathan       - Summa Eý_ofTelep.hone,,,,C,,o.nlference Octo -ber 11- 2007.wpd                                _0 -age4 1 REQUESTS FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION OCTOBER 11, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 11, 2007, to discuss and clarify the following audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).
,'ýqnathan Rowley - Summa Octo -ber 11 - 2007.wpd Eý_ofTelep.hone,,,,C,,o.nlference
_0 -age 4 1 REQUESTS FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION OCTOBER 11, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 11, 2007, to discuss and clarify the following audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).
1Is Audit question The ASME Code defines that stress intensity from two temperature transients is calculated from the stress components from the two conditions. Please explain how it could be calculated from stress intensities of the two conditions derived from Greens Functions, especially at locations of geometric discontinuity. Also, please justify the validity of combining the thermal transient stress intensities with the stress intensities from the external loads and pressure loading.
1Is Audit question The ASME Code defines that stress intensity from two temperature transients is calculated from the stress components from the two conditions. Please explain how it could be calculated from stress intensities of the two conditions derived from Greens Functions, especially at locations of geometric discontinuity. Also, please justify the validity of combining the thermal transient stress intensities with the stress intensities from the external loads and pressure loading.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
Line 65: Line 91:
ENCLOSURE2
ENCLOSURE2


JonahanRowey~~~-Sumaryof Telephone Conference -October 11, 2007,wpd                                         -Pý66e--6 Pg      ý 51 Audit question Page 1-1 of Report VY-16Q-401 indicates that refined transient definitions for 60 years of operation are used in the computation of the CUF incorporating environmentally assisted fatigue effects. Please explain the refinements in the transient definitions.
JonahanRowey~~~-Sumaryof Telephone Conference -October 11, 2007,wpd Pg
-Pý66e--6 ý 51 Audit question Page 1-1 of Report VY-16Q-401 indicates that refined transient definitions for 60 years of operation are used in the computation of the CUF incorporating environmentally assisted fatigue effects. Please explain the refinements in the transient definitions.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
61 Audit question For the feedwater nozzles there are large differences between the CUFs without the environmental fatigue life correction (Fen) factors shown in Table 4.3.1 of the Vermont Yankee license renewal application and those shown in Calculation No. VY-16Q-302. Section 2.0 of the calculation on page 4 of 32 states, A.. .several of the conservatisms originally used in the original feedwater evaluation (such as grouping of transients) are removed...@ Please explain what conservatisms were removed.
61 Audit question For the feedwater nozzles there are large differences between the CUFs without the environmental fatigue life correction (Fen) factors shown in Table 4.3.1 of the Vermont Yankee license renewal application and those shown in Calculation No. VY-16Q-302. Section 2.0 of the calculation on page 4 of 32 states, A...several of the conservatisms originally used in the original feedwater evaluation (such as grouping of transients) are removed...@ Please explain what conservatisms were removed.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
7L' Audit question For stainless steel components listed in table 3-10 of Structural Integrity Report SIR-07-132 (VY-16Q-404), please justify that the calculated Fen values are conservative.
7L' Audit question For stainless steel components listed in table 3-10 of Structural Integrity Report SIR-07-132 (VY-16Q-404), please justify that the calculated Fen values are conservative.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
Joahn Rowley Summary of Telephone Conference 0 ctob er 16, 2007.d oc                                          g_
Joahn Rowley Summary of Telephone Conference 0 c tob er 16, 2 007.d o c g_
LICENSEE: Entergy Nuclear Operations, Inc.
LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY:     Vermont Yankee Nuclear Power Station
FACILITY:
Vermont Yankee Nuclear Power Station


==SUBJECT:==
==SUBJECT:==
==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 16, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING AUDIT QUESTIONS PERTAINING TO THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. (Entergy) held a telephone conference call on October 16, 2007, to discuss and clarify the staff=s audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application asked during the October 9 - 10, 2007, audit of the VYNPS time-limited aging analyses. While attempting to address the staff's audit questions, Entergy determined that further clarification was needed on some of the questions. The telephone conference call was useful .in clarifying the intent of the staff=s audit questions.
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 16, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING AUDIT QUESTIONS PERTAINING TO THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. (Entergy) held a telephone conference call on October 16, 2007, to discuss and clarify the staff=s audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application asked during the October 9 - 10, 2007, audit of the VYNPS time-limited aging analyses. While attempting to address the staff's audit questions, Entergy determined that further clarification was needed on some of the questions. The telephone conference call was useful.in clarifying the intent of the staff=s audit questions. provides a listing of the participants and Enclosure 2 contains a listing of the audit questions discussed with the applicant, including a brief description on the status of the items.
Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the audit questions discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
The applicant had an opportunity to comment on this summary.
Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271
Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271
Line 87: Line 113:
: 2. List of Audit Questions cc w/encls: See next page
: 2. List of Audit Questions cc w/encls: See next page


OFFICE     LA:DLR             PM:RLRB:DLR             BC:RPB2:DLR NAME                           JRowley                 RFranovich DATE       11/   /07           11/   /07               11/ /07 L4j2 Tan Rowley - Summary of Telephone C onfer ence -October 16, 2007.doc                                 aage 3i....
OFFICE LA:DLR PM:RLRB:DLR BC:RPB2:DLR NAME JRowley RFranovich DATE 11/  
Pg    3 TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS OCTOBER 16, 2007 PARTICIPANTS                               AFFILIATIONS Jonathan Rowley                             U.S. Nuclear Regulatory Commission (NRC)
/07 11/  
Kenneth Chang                              NRC Michael Metell                              Entergy Nuclear Operations, Inc. (Entergy)
/07 11/  
David Mannai                                Entergy James Fitzpatrick                          Entergy Alan Cox                                    Entergy James DeVincentis                          Entergy David Lach                                  Entergy Terry Herman                                Structural Integrity Associates (SIA)
/07
Garry Stephens                              SIA ENCLOSURE1
 
L4j2 Tan Rowley - Summary of Telephone C onfer ence -October 16, 2007.doc Pg 3 aage 3i....
TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS OCTOBER 16, 2007 PARTICIPANTS Jonathan Rowley Kenneth Chang Michael Metell David Mannai James Fitzpatrick Alan Cox James DeVincentis David Lach Terry Herman Garry Stephens AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)
NRC Entergy Nuclear Operations, Inc. (Entergy)
Entergy Entergy Entergy Entergy Entergy Structural Integrity Associates (SIA)
SIA ENCLOSURE1


Jonahan Rowley - Sum mary of Telephone Conference       - October 16, 2007.doc                                   P.age REQUESTS FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION OCTOBER 16, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 16, 2007, to discuss and clarify the following audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).
Jonahan Rowley - Sum mary of Telephone Conference - October 16, 2007.doc P.age REQUESTS FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION OCTOBER 16, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 16, 2007, to discuss and clarify the following audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).
1t Audit question The ASME Code defines that stress intensity from two temperature transients is calculated from the stress components from the two conditions. Please explain how it could be calculated from stress intensities of the two conditions derived from Greens Functions, especially at locations of geometric discontinuity. Also, please justify the validity of combining the thermal transient stress intensities with the stress intensities from the external loads and pressure loading.
1t Audit question The ASME Code defines that stress intensity from two temperature transients is calculated from the stress components from the two conditions. Please explain how it could be calculated from stress intensities of the two conditions derived from Greens Functions, especially at locations of geometric discontinuity. Also, please justify the validity of combining the thermal transient stress intensities with the stress intensities from the external loads and pressure loading.
Discussion: The staff provided further clarification on the question.
Discussion: The staff provided further clarification on the question.
22- Audit question Provide justification for statement on page 5 of 34 of Calculation No. VY-1 6Q-302, that AThe Green function methodology provides identical results compared to running the input transient through the finite element model.@
22-Audit question Provide justification for statement on page 5 of 34 of Calculation No. VY-1 6Q-302, that AThe Green function methodology provides identical results compared to running the input transient through the finite element model.@
Discussion: The staff provided further clarification on the question.
Discussion: The staff provided further clarification on the question.
3V Audit question For the blend radius for the feedwater nozzle in Calculation No. VY-16Q-3.02, Table 4, Page 16, why are the Total and M+B stresses for thermal transient 3, shown in columns 3 and 4, high at 0 seconds (t = 0)? This question also applies to transient 4 at t = 1801.9 seconds, transient 9 at t = 2524 seconds, and transient 21-23 at t = 20144 seconds.
3V Audit question For the blend radius for the feedwater nozzle in Calculation No. VY-16Q-3.02, Table 4, Page 16, why are the Total and M+B stresses for thermal transient 3, shown in columns 3 and 4, high at 0 seconds (t = 0)? This question also applies to transient 4 at t = 1801.9 seconds, transient 9 at t = 2524 seconds, and transient 21-23 at t = 20144 seconds.
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ENCLOSURE2
ENCLOSURE2


16,2007.do&                                 Page 5~j Jonathan~6~ley Jonathan Rowley - Summary
Jonathan~6~ley - Sum mary of Telephone Conference-October 1 6,2007.do&
                -          of Telephone Sum mary of              Co n fere n c e October Telep h o ne Conference-    0 ct ob.1 e
Page 5~j Jonathan Rowley - Summary of Telep h o ne Co n fe re n c e 0 ct ob.1 e
Vermont Yankee Nuclear Power Station                                     cc:
Vermont Yankee Nuclear Power Station cc:
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
51 Audit question Page 1-1 of Report VY-16Q-401 indicates that refined transient definitions for 60 years of operation are used in the computation of the CUF incorporating environmentally assisted fatigue effects. Please explain the refinements in the transient definitions.
51 Audit question Page 1-1 of Report VY-16Q-401 indicates that refined transient definitions for 60 years of operation are used in the computation of the CUF incorporating environmentally assisted fatigue effects. Please explain the refinements in the transient definitions.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
6P Audit question For the feedwater nozzles there are large differences between the CUFs without the environmental fatigue life correction (Fen) factors shown in Table 4.3.1 of the Vermont Yankee license renewal application and those shown in Calculation No. VY-16Q-302. Section 2.0 of the calculation on page 4 of 32 states, A.. .several of the conservatisms originally used in the original feedwater evaluation (such as grouping of transients) are removed...@ Please explain what conservatisms were removed.
6P Audit question For the feedwater nozzles there are large differences between the CUFs without the environmental fatigue life correction (Fen) factors shown in Table 4.3.1 of the Vermont Yankee license renewal application and those shown in Calculation No. VY-16Q-302. Section 2.0 of the calculation on page 4 of 32 states, A...several of the conservatisms originally used in the original feedwater evaluation (such as grouping of transients) are removed...@ Please explain what conservatisms were removed.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
7L Audit question For stainless steel components listed in table 3-10 of Structural Integrity Report SIR-07-132 (VY-16Q-404), please justify that the calculated Fen values are conservative.
7L Audit question For stainless steel components listed in table 3-10 of Structural Integrity Report SIR-07-132 (VY-16Q-404), please justify that the calculated Fen values are conservative.
Discussion: The applicant indicated that the question is clear.
Discussion: The applicant indicated that the question is clear.
ENCLOSURE2}}
ENCLOSURE2}}

Latest revision as of 19:42, 14 January 2025

(PA-LR) October 11 and 16 Conference Call Summaries
ML073390241
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 11/16/2007
From: Rowley J
NRC/NRR/ADRO/DLR
To: Devincentis J
Entergy Nuclear Operations
References
TAC MD2297
Download: ML073390241 (12)
v • d • e


Text

Page 1 of 1 Jonathan Rowley - October 11 and 16 conference call summaries From:

Jonathan Rowley To:

jdevinc@entergy.com Date:

11/16/2007 10:32 AM

Subject:

October 11 and 16 conference call summaries Attached are the summaries for conference calls held on Oct. 11 and Oct. 16, 2007. Please review and comment where necessary.

file://C:\\temp\\GW} 00002.HTM 12/03/2007

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Creation Date From:

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  • ties (473DB825.347 : 12 : 35182)

October 11 and 16 conference call summaries 11/16/2007 10:32:53 AM Jonathan Rowley JGR(anrc.gov Recipients entergy.com AM jdevinc (jdevinccýentergv.com)

Post Office Files Size MESSAGE 441 TEXT.htm 347 Summary of Telephone Conference -

11:51:04 AM Summary of Telephone Conference -

10:15:02 AM Action Transferred Date & Time 11/16/2007.10:33:05 Delivered Route entergy.com Date & Time 11/16/2007 10:32:52 AM October 11, 2007.wpd October 16, 2007.doc 58368 11/14/2007 73216 11/16/2007 Options Auto Delete:

Expiration Date:

Notify Recipients:

No 15 Priority:

S ReplyRequested:

Return Notification:

Send Notification when Opened 4one Ses

~tandard 0o 0I

~tandard Concealed

Subject:

Security:

To Be Delivered:

Status Tracking:

S Immediate Delivered & Opened

Joaha owe-umryo TeehnCneerd coe1, 20071.wpd

~

Page 1 LICENSEE: Entergy Nuclear Operations, Inc.

FACILITY:

Vermont Yankee Nuclear Power Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 11, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING AUDIT QUESTIONS PERTAINING TO THE VERMONT'YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 11, 2007, to discuss and clarify the staff=s audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application asked during the October 9 - 10, 2007, audit of the VYNPS time-limited aging analyses. The telephone conference call was useful in clarifying the intent of the staff=s audit questions. provides a listing of the participants and Enclosure 2 contains a listing of the audit questions discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. List of Participants
2. List of Audit Questions cc w/encls: See next page

ML OFFICE LA:DLR PM:RLRB:DLR BC:RPB2:DLR NAME JRowley RFranovich DATE 11/

/07 11/

/07 11/

/07

j, J6natlhan Rowl.ey - Summary of Tele p.hone Conference - October 11, 2007.wpdP

,page 3,,tl TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS OCTOBER 11, 2007 PARTICIPANTS Jonathan Rowley Kenneth Chang Robert Hsu Michael Metell David Mannai James Fitzpatrick Alan cox AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)

NRC NRC Entergy Nuclear Operations, Inc. (Entergy)

Entergy Entergy Entergy ENCLOSURE1

Jonathan Row!ey -Summary of Teiephop~ Confer ce -~O6t6ber 11, 2007.wpd Page 41

,'ýqnathan Rowley - Summa Octo -ber 11 - 2007.wpd Eý_ofTelep.hone,,,,C,,o.nlference

_0 -age 4 1 REQUESTS FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION OCTOBER 11, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 11, 2007, to discuss and clarify the following audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).

1Is Audit question The ASME Code defines that stress intensity from two temperature transients is calculated from the stress components from the two conditions. Please explain how it could be calculated from stress intensities of the two conditions derived from Greens Functions, especially at locations of geometric discontinuity. Also, please justify the validity of combining the thermal transient stress intensities with the stress intensities from the external loads and pressure loading.

Discussion: The applicant indicated that the question is clear.

2nd Audit question Provide justification for statement on page 5 of 34 of Calculation No. VY-1 6Q-302, that AThe Green function methodology provides identical results compared to running the input transient through the finite element model.@

Discussion: The applicant indicated that the question is clear.

3V Audit question For the blend radius for the feedwater nozzle in Calculation No. VY-16Q-302, Table 4, Page 16, why are the Total and M+B stresses for thermal transient 3, shown in columns 3 and 4, high at 0 seconds (t = 0)? This question also applies to transient 4 at t = 1801.9 seconds, transient 9 at t = 2524 seconds, and transient 21-23 at t = 20144 seconds.

Discussion: The applicant indicated that the question is clear.

41 Audit question Explain why there are differences in the calculated cumulative usage factor (CUF) values between Rev. A and Rev. 0 of the Structural Integrity calculations. Also, why are the CUFs calculated by Structural Integrity different from the CUFs shown in Tables 4.3.1 and 4.3.3 of the Vermont Yankee license renewal application?

Discussion: The applicant indicated that the question is clear.

ENCLOSURE2

JonahanRowey~~~-Sumaryof Telephone Conference -October 11, 2007,wpd Pg

-Pý66e--6 ý 51 Audit question Page 1-1 of Report VY-16Q-401 indicates that refined transient definitions for 60 years of operation are used in the computation of the CUF incorporating environmentally assisted fatigue effects. Please explain the refinements in the transient definitions.

Discussion: The applicant indicated that the question is clear.

61 Audit question For the feedwater nozzles there are large differences between the CUFs without the environmental fatigue life correction (Fen) factors shown in Table 4.3.1 of the Vermont Yankee license renewal application and those shown in Calculation No. VY-16Q-302. Section 2.0 of the calculation on page 4 of 32 states, A...several of the conservatisms originally used in the original feedwater evaluation (such as grouping of transients) are removed...@ Please explain what conservatisms were removed.

Discussion: The applicant indicated that the question is clear.

7L' Audit question For stainless steel components listed in table 3-10 of Structural Integrity Report SIR-07-132 (VY-16Q-404), please justify that the calculated Fen values are conservative.

Discussion: The applicant indicated that the question is clear.

Joahn Rowley Summary of Telephone Conference 0 c tob er 16, 2 007.d o c g_

LICENSEE: Entergy Nuclear Operations, Inc.

FACILITY:

Vermont Yankee Nuclear Power Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 16, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING AUDIT QUESTIONS PERTAINING TO THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. (Entergy) held a telephone conference call on October 16, 2007, to discuss and clarify the staff=s audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application asked during the October 9 - 10, 2007, audit of the VYNPS time-limited aging analyses. While attempting to address the staff's audit questions, Entergy determined that further clarification was needed on some of the questions. The telephone conference call was useful.in clarifying the intent of the staff=s audit questions. provides a listing of the participants and Enclosure 2 contains a listing of the audit questions discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary.

Jonathan G. Rowley, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. List of Participants
2. List of Audit Questions cc w/encls: See next page

OFFICE LA:DLR PM:RLRB:DLR BC:RPB2:DLR NAME JRowley RFranovich DATE 11/

/07 11/

/07 11/

/07

L4j2 Tan Rowley - Summary of Telephone C onfer ence -October 16, 2007.doc Pg 3 aage 3i....

TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS OCTOBER 16, 2007 PARTICIPANTS Jonathan Rowley Kenneth Chang Michael Metell David Mannai James Fitzpatrick Alan Cox James DeVincentis David Lach Terry Herman Garry Stephens AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)

NRC Entergy Nuclear Operations, Inc. (Entergy)

Entergy Entergy Entergy Entergy Entergy Structural Integrity Associates (SIA)

SIA ENCLOSURE1

Jonahan Rowley - Sum mary of Telephone Conference - October 16, 2007.doc P.age REQUESTS FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION OCTOBER 16, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc. held a telephone conference call on October 16, 2007, to discuss and clarify the following audit questions concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).

1t Audit question The ASME Code defines that stress intensity from two temperature transients is calculated from the stress components from the two conditions. Please explain how it could be calculated from stress intensities of the two conditions derived from Greens Functions, especially at locations of geometric discontinuity. Also, please justify the validity of combining the thermal transient stress intensities with the stress intensities from the external loads and pressure loading.

Discussion: The staff provided further clarification on the question.

22-Audit question Provide justification for statement on page 5 of 34 of Calculation No. VY-1 6Q-302, that AThe Green function methodology provides identical results compared to running the input transient through the finite element model.@

Discussion: The staff provided further clarification on the question.

3V Audit question For the blend radius for the feedwater nozzle in Calculation No. VY-16Q-3.02, Table 4, Page 16, why are the Total and M+B stresses for thermal transient 3, shown in columns 3 and 4, high at 0 seconds (t = 0)? This question also applies to transient 4 at t = 1801.9 seconds, transient 9 at t = 2524 seconds, and transient 21-23 at t = 20144 seconds.

Discussion: The applicant indicated that the question is clear.

4L Audit question Explain why there are differences in the calculated cumulative usage factor (CUF) values between Rev. A and Rev. 0 of the Structural Integrity calculations. Also, why are the CUFs calculated by Structural Integrity different from the CUFs shown in Tables 4.3.1 and 4.3.3 of the Vermont Yankee license renewal application.

ENCLOSURE2

Jonathan~6~ley - Sum mary of Telephone Conference-October 1 6,2007.do&

Page 5~j Jonathan Rowley - Summary of Telep h o ne Co n fe re n c e 0 ct ob.1 e

Vermont Yankee Nuclear Power Station cc:

Discussion: The applicant indicated that the question is clear.

51 Audit question Page 1-1 of Report VY-16Q-401 indicates that refined transient definitions for 60 years of operation are used in the computation of the CUF incorporating environmentally assisted fatigue effects. Please explain the refinements in the transient definitions.

Discussion: The applicant indicated that the question is clear.

6P Audit question For the feedwater nozzles there are large differences between the CUFs without the environmental fatigue life correction (Fen) factors shown in Table 4.3.1 of the Vermont Yankee license renewal application and those shown in Calculation No. VY-16Q-302. Section 2.0 of the calculation on page 4 of 32 states, A...several of the conservatisms originally used in the original feedwater evaluation (such as grouping of transients) are removed...@ Please explain what conservatisms were removed.

Discussion: The applicant indicated that the question is clear.

7L Audit question For stainless steel components listed in table 3-10 of Structural Integrity Report SIR-07-132 (VY-16Q-404), please justify that the calculated Fen values are conservative.

Discussion: The applicant indicated that the question is clear.

ENCLOSURE2

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