ML073390241
| 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.
file://C:\temp\GW} 00002.HTM 12/03/2007
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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)
Post Office Delivered Route entergy.com Files Size Date & Time MESSAGE 441 11/16/2007 10:32:52 AM TEXT.htm 347 Summary of Telephone Conference - October 11, 2007.wpd 58368 11/14/2007 11:51:04 AM Summary of Telephone Conference - October 16, 2007.doc 73216 11/16/2007 10:15:02 AM Options Auto Delete: No Expiration Date: 154one Notify Recipients: Ses Priority: S~tandard ReplyRequested: 0o Return Notification:
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owe-Joaha 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.
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.
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 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)
Kenneth Chang NRC Robert Hsu NRC Michael Metell Entergy Nuclear Operations, Inc. (Entergy)
David Mannai Entergy James Fitzpatrick Entergy Alan cox Entergy ENCLOSURE1
11, 2007.wpd Page 41 Row!ey -Summary Jonathan Rowley of Teiephop~ Confer ce -~O6t6ber
,'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).
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 -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.
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 ctob er 16, 2007.d oc 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.
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.
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 aage 3i....
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)
Kenneth Chang NRC Michael Metell Entergy Nuclear Operations, Inc. (Entergy)
David Mannai Entergy James Fitzpatrick Entergy Alan Cox Entergy James DeVincentis Entergy David Lach Entergy Terry Herman Structural Integrity Associates (SIA)
Garry Stephens 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
16,2007.do& Page 5~j Jonathan~6~ley Jonathan Rowley - Summary
- of Telephone Sum mary of Co n fere n c e October Telep h o ne Conference- 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