ML070530376

Email: (PA-LR) for Your Review and Comment

ML070530376
Person / Time
Site:	Vermont Yankee
Issue date:	01/18/2007
From:	Rowley J NRC/NRR/ADRO/DLR
To:	Hamer M Entergy Corp
References
TAC MD2297
Download: ML070530376 (6)

Text

iRichard Emch-for your review and comment Page aI 1I From: Jonathan Rowley To: mhamer@entergy.com Date: Thu, Jan 18, 2007 10:13 AM

Subject:

for your review and comment Mike Please review and provide comment as you see fit on the attached meeting summary.

Jonathan Rowley, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301) 415-4053

[c-:\temp\GW}OOOO1.TMP- PZqýel Mail Envelope Properties (45AF8EAA.F33 : 12: 35182)

Subject:

for your review and comment Creation Date Thu, Jan 18, 2007 10:13 AM From: Jonathan Rowley Created By: JGR @nrc.gov Recipients Action Date & Time entergy.com mhamer (mhamer@entergy.com)

Post Office Delivered Route Pending entergy.com Files Size Date & Time MESSAGE 861 Thursday, January 18, 2007 10:13 AM TEXT.htm 603 Summary of Telephone Conference - December 6, 2006(VY).wpd 24901 Thursday, January 18, 2007 10:11 AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification:

Send Notification when Opened Concealed

Subject:

No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened

LICENSEE: Entergy Nuclear Operations, Inc.

FACILITY: Vermont Yankee Nuclear Power Station

SUMMARY

OF A TELEPHONE CONFERENCE CALL HELD ON DECEMBER 6, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING INFORMATION PERTAINING TO THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Entergy Nuclear Operations, Inc., (ENO) held a telephone conference call on December 6, 2006, to discuss and clarify the staff's requests for additional information (RAIs) concerning the Vermont Yankee Nuclear Station (VYNPS) license renewal application (LRA). The conference call was useful in clarifying the staff's questions. provides a listing of the conference call participants. Enclosure 2 contains the issues discussed with the applicant, including a brief discussion of the items' status.

The applicant had an opportunity to comment on this summary.

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

Enclosures:

As stated cc w/encls: See next page

LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION December 6, 2006 Participants Affiliations Jonathan Rowley U.S. Nuclear Regulatory Commission (NRC)

Dan Hoang NRC Duc Nguyen NRC Kenneth Chang NRC Kaihwa Hsu NRC Alan Cox Entergy Nuclear Operations, Inc. (ENO)

Lori Potts ENO Michael Hamer ENO Dave Lach ENO David Mannai ENO Paul Johnson ENO Michael Metel ENO Mike Stroud ENO

VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION December 6, 2006 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on December 6, 2006, to discuss and clarify the staff's requests for additional information (RAls) concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA). The following issues were discussed during the telephone conference call:

RAI 3.6.2.2-N-01-1

... the staff requests that the applicant either provide a plant-specific AMP with the AMP elements found in the Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR), Appendix A.1, Section A.1.2.3 and SRP-LR Table A.1 -1, or an AMP consistent with GALL AMP XI.E6. If the applicant maintains that an AMP is not required, the applicant is requested to explain in detail how the existing program will address the above aging effects and provide a detailed discussion of how each of the ten elements of aging management, as described in the SRP-LR sections mentioned above, is met by the current program. Also, the applicant is requested to provide supporting documentation to show that the aging management program elements, including appropriate tests, are implemented currently and will be continued for the extended period of operation.

Discussion: The applicant agreed to submit a XI.E6 program bases on the discussion and decision made during the November 30, 2006 meeting with the Nuclear Energy Institute (NEI).

The staff will evaluate the program upon its submittal.

RAI 3.6.2.2-N-08-2 Electrical components for the VHS include 2 black-start turbine generators, cables and buses for power transmission, instrumentation and control components and their associated cables and connections. The audit team found that there is an aging management program (AMP) for underground cables from Vernon tie breaker routed to Vermont Yankee. However, there appears to be no AMPs for electrical components from the tie breaker to VHS generators.

Please describe how aging effects on the rest of the electrical components will be managed during the period of extended operation.

Discussion: The applicant first addressed this RAI in their October 20, 2006, letter (License Renewal Application, Amendment 1-7). The staff did not agree with the applicant's methodology used in that response. The staff clarified its position. The applicant will provide a revised response to this concern in a future letter to the NRC.

RAI 3.6.2.2-N-08-4 The applicant stated that VHS switchyard passive long-lived commodity groups are effectively maintained through routine maintenance by the switchyard owner. Describe how this routine Enclosure 2

maintenance will manage the aging effects on the VHS switchyard passive long-lived commodity groups during the period of extended operations.

Discussion: The applicant first addressed this RAI in their October 20, 2006, letter (License Renewal Application, Amendment 17). The staff did not agree with the applicant's methodology used in that response. The staff clarified its position. The applicant will provide a revised response to this concern in a future letter to the NRC.

RAI 3.6.2.2-N-08-5 Address the following SBO AAC related items:

a. Please describe (as stated in Generic Aging Lessons Learned (GALL) AMP XI.E6) how aging effects are managed so that the intended function of cable connections associated with SBO AAC (including VHS) will be maintained during the extended period of operation.

Discussion: The applicant first addressed this RAI in their October 20, 2006, letter (License Renewal Application, Amendment 17). The staff did not agree with the applicant's methodology used in that response. The staff clarified its position. The applicant will provide a revised response to this concern in a future letter to the NRC.

RAI 4.3-H-1 In the basis document of the fatigue monitoring program, 100°F/hour heatup/coodown rate was identfied for the normal transient conditions. The actual operating condition for heatup and cooldown rate is 100°F when averaged over any one hour period. Therefore, the actual operating condition may indicate much higher rate than 100 0 F/hour. For example, 60°F temperature change for the 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period represents 600°F/hour rate. Staff considers that thermal stress is function of rate of temperature difference. The higher the rate, the higher the stress.

Please provide description to ensure that VYNPS's automatic cycle counting program will adequately define the transients and cycle numbers. Please provide description to ensure the fatigue cumulative usage factor and thermal stress are evaluated in accordance with the' actual transients or enveloped the actual transient.

Discussion: The staff requested the applicant provide actual numbers for design cycles versus transients. The applicant agreed to provide the requested numbers in a supplemental response to this concern in a future letter to the NRC.

Enclosure 2