ML072470534

(PA-LR) Call Summaries for Your Review and Comment

ML072470534
Person / Time
Site:	Vermont Yankee
Issue date:	08/01/2007
From:	Rowley J NRC/NRR/ADRO/DLR/RLRB
To:	Hamer M Entergy Nuclear Vermont Yankee
References
Download: ML072470534 (12)

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Jnathan Row*ey - summaries for your review . ..

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page From: Jonathan Rowley To: mhamer@entergy.com Date: 08/01/2007 4:25:47 PM

Subject:

summaries for your review Please review and provided comments as deem necessary on the attached call summaries.

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Jonathan Rowley-- Summary of Telephone Conference - June 29, 2007.wpd Page 1' LICENSEE: Entergy Nuclear Operations, Inc.,

FACILITY: Vermont Yankee Nuclear Power Station

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JUNE 29, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC.,, CONCERNING REQUEST FOR ADDITIONAL INFORMATION 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 June 29, 2007, to discuss and clarify the staff's request for additional information (RAI) concerning the Vermont Yankee Nuclear Power Station license renewal application. The telephone conference call was useful in clarifying the intent of the staff's RAI.

Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the RAI discussed with the applicant, including a brief description on the status of the item.

The applicant had an opportunity to comment on this summary.

Jonathan G. Rowley, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear ReactorRegulation

• Docket No. 50-271

Enclosures:

1. List of Participants

2. List of Request for Additional Information cc w/encls: See next page

DOCUMENT NAME: Conference - June 29, 2007.wpdctempgwprintSummary of Telephone Conference - June 29, 2007.wpd OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME JRowley RAuluck DATE / / / I / /

JI.o..onathan Rowley - Summary of Telephone-CPonferen*ce.- Jun 29, 020...7.wpdPg ,Ppýqe 3 ]

TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JUNE 29, 2007 PARTICIPANTS AFFILIATIONS Jonathan Rowley NRC Rajender Auluck NRC David Lach Entergy Nuclear Operations, Inc. (Entergy)

Michael Hamer Entergy David Mannai Entergy Michael Metel Entergy John Dreyfuss Entergy Gary Young Entergy Enclosure 1

Jonathan Rowley - Summary of Telephone Conference - June 29, 2007.wpdPae4 -Page 4:1 REQUEST FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION JUNE 29, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on June 29, 2007, to discuss and clarify the following request for additional information (RAI) concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).

RAI 3.6.2.2-N-08-1 The applicant responded to the staffs Request for Additional Information (RAI) 3.6.2.2-N-08 in a letter dated July 14, 2006, "License Renewal Application, Amendment 4". In the letter the applicant stated:

"Entergy,consistent with the Peach Bottom precedent, credited the [FederalEnergy Regulatory Commission] FERC dam inspection program to manage the effects of aging on civil and structuralelements of the [Vernon Hydroelectric Station] VHS."

A FERC letter to the previous owner of the VHS, New England Power Company (currently owned by TransCanada Hydro Northeast Inc.), dated August 6, 1997 states: "By letter dated June 26, 1997, you requested an exemption from filing an Independent Consultant's Safety Inspection Report under Part 12, Subpart D, of the Commission's Regulations..." and "..]. am granting your request for an exemption from the Part 12, Subpart D requirement for submittal of an Independent Consultant's Safety Inspection Report."

As the exemption is only on the filing of an Independent Consultant's Safety Inspection Report under Part 12, Subpart D, describe specific Vermont Yankee Nuclear Power Station aging management activities, provide inspection reports, and describe any corrective actions that have been take as a result of the inspection reports - as they pertain to the VHS in accordance with 10 CFR 54.21(a)(3) - since the exemption was granted.

Discussion: The initial response to this RAI was sent in a letter dated October 20, 2006, then provided further clarification in a letter dated January 4, 2007. The staff re-evaluated its position on aging management of the VHS subsequent to the January 4, 2007, letter. The staff informed the applicant of its final position during this conference call. Based on the discussion with the applicant, the staff indicated that the response to this RAI requires clarification.

Therefore, the applicant will clarify the information.

Enclosure 2

1:Jonathan Rowley - Summary of Telephone Conference - July 18, 2007.wpd Page 1; LICENSEE: Entergy Nuclear Operations, Inc.,

FACILITY: Vermont Yankee Nuclear Power Station

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON JULY 18, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING REQUESTS FOR ADDITIONAL INFORMATION 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 July 18, 2007, to discuss and clarify the staff's draft request for additional information (D-RAI) and the supplemental response to an RAI concerning the Vermont Yankee Nuclear Power Station license renewal application.

The telephone conference call was useful in clarifying the intent of the staff's RAIs.

Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the RAIs 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 License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-271

Enclosures:

1. List of Participants

2. List of Requests for Additional Information cc w/encls: See next page

DOCUMENT NAME: Conference - July 18, 2007.wpdctempgwprintSummary of Telephone Conference - July 18, 2007.wpd OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME JRowley RAuluck DATE I / / / / I 1;JqnýtLhýn Rowley -Sum ma ofT"elephone Conference - July 18, 2007.wpd Page Page 33jýj Jonathan Rowley Summary of Telephone Conference

- - July 18, 2007.wpd ... . . . . .... ... .... . ....... ... .............................................. .... .... .............. w ........... I TELEPHONE CONFERENCE CALL VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS JULY 18, 2007 PARTICIPANTS AFFILIATIONS Jonathan Rowley NRC Kenneth Chang NRC Kaihwa Hsu NRC Ron Young NRC Jim Nickolaus Pacific Northwest National Lab. (PNNL)

Donnie Draper PNNL David Lach Entergy Nuclear Operations, Inc. (Entergy)

Michael Hamer Entergy James Fitzpatrick Entergy Michael Metel Entergy Alan Cox Entergy Gary Young Entergy Stan Batch Entergy Enclosure 1

Jonathan -Rowley- Summary of Telephone Conference - July 1-8, 207.wPd _____Page 5 DRAFT REQUEST FOR ADDITIONAL INFORMATION VERMONT YANKEE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION JULY 18, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on July 18, 2007, to discuss and clarify the following draft request for additional information (D-RAI) and the supplemental response to an RAI concerning the Vermont Yankee Nuclear Power Station (VYNPS) license renewal application (LRA).

D-RAI 4.3.3-1:

The license renewal application (LRA) for the Vermont Yankee Nuclear Power Station listed several reactor coolant pressure boundary components that did not receive a plant-specific metal fatigue analysis and cumulative usage factor (CUF). The applicant generated LRA Commitment No. 27 to address this issue. In the commitment, the applicant committed to take one of the following options or a combination of options to ensure that the time-limited aging analysis (TLAA) on environmentally-assisted fatigue (EAF) of these components, and any other Class 1 components requiring reanalysis for EAF, will be acceptable under 10 CFR 54.21 (c)(1) for the period of extended operation:

Option (1): either refine the existing fatigue analyses or perform new fatigue analyses using at least one of four suboptions under this option.

Option (2): manage aging by an aging management program for the period of extended operation Option (3): repair or replace the impacted component prior to exceeding a CUF of 1.0.

In order to make a determination under the requirements of 10 CFR 54.21 (c)(1), the staff requests that the applicant provide additional information on the option (or options) that will be used to comply with the actions committed under LRA Commitment No. 27. Specifically, the methodology that will be used for the chosen option or options needs to be described in sufficient detail such that the staff can perform a review and make a determination on the acceptability of the option when implemented. The staff requests that:

A. If Option (1) will be the option used to comply with the pertinent commitment, describe the methodology and the process that will be used to ensure that assumptions, transients, cycles, external loadings, Fen values, and analysis methods are valid for the refined or new fatigue analyses.

5 Enclosure 2

JonathanRowley - Summary of Telephone Conference - July 18, 2007.wpdPg 'Page B. If Option (2) will be the option used to comply with the pertinent commitment, describe the AMP in sufficient detail with regard to inspection scope, inspection methods, inspection frequency, and inspection qualification techniques.

C. If Option (3) will be the option used to comply with the pertinent commitments, describe how the repair or replacement activity will be implemented in accordance with applicable repair or replacement requirements of the ASME Code Section XI.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

Follow-up questions to RAI 2.1-2

1. For the Service Water, Circulating Water, and Reactor Water Cleanup Systems, has the applicant identified the nonsafety-related portions of the system, attached to safety-related systems, structures, and components (SSCs), which are required to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2)? Are all scoping activities complete and have all component types been identified and included in the applicable tables in the LRA.

2. Are there any nonsafety-related systems for which the applicant has not identified the nonsafety-related portion of the system, attached to safety-related SSCs, which are required to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2)?

3. For all nonsafety-related systems, are all scoping activities complete and have all component types been identified and included in the applicable tables in the LRA?

4. Is the applicant taking credit for, or committing to perform, any future scoping activities?

Discussion: The applicant provided a supplemental response to these follow-up questions in a July 3, 2007, letter to the NRC. Based on the discussion with the applicant, the staff indicated that the supplemental response to this RAI requires clarification. Therefore, the applicant will clarify the information.

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