ML073390241

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(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)


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.

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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:

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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