ML073390201

(PA-LR) 10/16/2007 Summary of Telephone Conference Call Between NRC and Entergy Nuclear Operations, Inc., Concerning Audit Questions Pertaining to the Vermont Yankee Nuclear Power Station License Renewal Application

ML073390201
Person / Time
Site:	Vermont Yankee
Issue date:	11/19/2007
From:	Devincentis J Entergy Nuclear Operations
To:	Rowley J Office of Nuclear Reactor Regulation
References
TAC MD2297
Download: ML073390201 (7)

Text

Message Page I of I Jonathan Rowley -FW: October 11 and 16 conference call summaries From: To: Date:

Subject:

"Devincentis, Jim" <jdevinc@entergy.com>"Jonathan Rowvley" <JGR@nrc.gov>

11/19/2007 11:52 AM FW: October 11 and 16 conference call summaries Some minor comments with one set of minutes -the other was OK as is.Jim.From: Jonathan Rowley [1]

Sent: Friday, November 16, 2007 10:33 AM To: Devincentis, Jim

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 I c.\ternp\GW}00003 TMP Pa '~c:\tem P\GWI00003.TM P Page 1 Mail Envelope Properties (4741BF37.1C2

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Creation Date From: Created By: FW: October 11 and 16 conference call summaries 11/19/2007 11:51:35 AM"Devincentis, Jim" <jdevinc@entergy.com>

jdevinc@entergy.com Recipients nrc.gov TWGWPO03.HQGWDOO1 JGR (Jonathan Rowley)Post Office TWGWPO03.HQGWDOO1 Route nrc.gov Files Size Date & Time MESSAGE 406 11/19/2007 11:51:35 AM TEXT.htm 3628 Summary of Telephone Conference

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d'ocPg Page LICENSEE:.

Entergy Nuclear Operations, Inc.FACILITY:

Vermont Yankee Nuclear Power Station

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 staffs 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 IJona'than "Rowley"'-

Su m'mar~y o6f Tel-e'p'ho'ne

'C-onf-erence

-October 16 2007.doc PaeI Pag 1 LICENSEE:

Entergy Nuclear Operations, Inc.FACILITY:

Vermont Yankee Nuclear Power Station

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 renewai 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 DISTRIBUTION:

See next page ADAMS Accession No: OFFICE LA:DLR PM:RLRB:DLR BC:RPB2:DLR NAME JRowley RFranovich DATE 11/ /07 11/ /07 11/ /07 OFFICIAL RECORD COPY Jonathan Rowley -Summary of Telephone Conference

-October 16 doc-Page 3 Jonathan Rowley 1 Summ aryof Telephone Conference

-October 16 2007.doc Page ~i 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 Herrmann Gary Stevens AFFILIATIONS U.S. Nuclear Regulatory Commission (NRC)NRC Entergy Nuclear Operations, Inc. (Entergy)Entergy Entergy Entergy Entergy Entergy Structural Integrity Associates (SIA)SIA ENCLOSURE 1

Jonathan Rowley S Summary of Telephone Conference 0 ctober 16 2007.doc a 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).11' 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.2'- Audit question Provide justification for statement on page 5 of 34 of Calculation No. VY-16Q-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-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.4t 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 JonathanRowley

-Summary of Telephone Conference

-October 16 2007.doc Pa ~Jon athan R owley 7 Summar'y of Telephone Conference

-October 16 2007.doc 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.6M 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.71 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