ML13120A095

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(BFN) RFI Letter - IP71003 Phase 2 - IR 2013-009
ML13120A095
Person / Time
Site: Browns Ferry  
Issue date: 04/29/2013
From: Vias S
NRC/RGN-II/DRS/EB3
To: James Shea
Tennessee Valley Authority
References
Download: ML13120A095 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 April 29, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION

Dear Mr. Shea:

The U.S. Nuclear Regulatory Commission (NRC) will perform a post-approval inspection for license renewal from August 15 - August 23, 2013 at the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The inspection will be conducted in accordance with inspection procedure (IP) 71003, Post-Approval Site Inspection for License Renewal. Previous inspections confirm this inspection is resource intensive for both the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents. The enclosed document request identifies the information the inspection team will need upon arrival. Requested documents should be current and completed. This maximizes efficiency during on-site portions of the inspection.

On April 23, 2013, NRC Region II staff discussed and confirmed the schedule of this inspection with Mr. Steven Austin of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector, Joel Rivera-Ortiz at 404-997-4825 (Joel.Rivera-Ortiz@nrc.gov).

J. Shea 2

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its Enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/ reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

//RA//

Steven J. Vias, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68

Enclosure:

Information Request for Post-Approval Inspection for License Renewal cc (See page 3)

J. Shea 3

cc:

K. J. Polson Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution S. M. Bono Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution James E. Emens Manager, Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution E. W. Cobey Manager, Corporate Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution T. A. Hess Program Manager Corporate Licensing Tennessee Valley Authority Electronic Mail Distribution Edward J. Vigluicci Associate General Counsel, Nuclear Tennessee Valley Authority Electronic Mail Distribution Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 State Health Officer Alabama Dept. of Public Health P.O. Box 303017 Montgomery, AL 36130-3017 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970

Enclosure INFORMATION REQUEST FOR POST-APPROVAL INSPECTION FOR LICENSE RENEWAL Site:

Browns Ferry Nuclear Plant, Units 1, 2, and 3 Inspection Dates:

August 15 - August 23, 2013 Inspection Procedure:

IP 71003, Post-Approval Site Inspection for License Renewal Lead Inspector:

Joel E. Rivera-Ortiz, Senior Reactor Inspector The following information should be made available to the inspection team in hard copy or electronic format upon arrival to the site. Due to differences in license conditions and regulatory commitments among operating reactor sites as a result of the license renewal process, the information requested below may not be entirely applicable to Browns Ferry Nuclear Plant.

Prior to the inspection, the lead inspector will select a sample of regulatory commitments and aging management programs (AMPs) for review, including time-limited aging analyses (TLAAs).

The information listed in section B of this enclosure should be provided for each item selected for review. If there are any questions regarding this information request, please contact the lead inspector as soon as possible.

A.

General Information Request (As Applicable)

(1)

Sections of the quality assurance program manual applicable to license renewal activities.

(2)

Corrective action program procedure.

(3)

Regulatory commitment change process procedure.

(4)

Operating experience program procedure.

(5)

Latest version of the final safety analysis report (FSAR) supplement for license renewal submitted with the license renewal application (LRA).

(6)

Last version of the FSAR supplement for license renewal submitted to the NRC per 10CFR 50.71.

(7)

Living version of the FSAR supplement for license renewal.

(8)

Any post-approval evaluation or assessment performed to verify that in-scope structures, systems, or components (SSCs) were not excluded from the license renewal application (LRA) and appropriate aging management has been considered in accordance with 10CFR 54.37(b).

(9)

List of plant modifications with a brief description of the modification scope that were approved and/or implemented from the date the LRA was submitted to the date the renewed license was issued.

2 Enclosure (10) Any self-assessment performed after the renewed license was issued associated with the implementation of license renewal commitments, including AMPs and TLAAs.

(11) Any gap analysis performed to assess the differences between the current AMPs and the recommendations in the latest revision of NUREG-1801, Generic Aging Lessons Learned (GALL), and subsequent Interim Staff Guidance.

(12) Licensee responses and/or evaluations for NRC generic communications issued after the renewed license was granted and associated with license renewal issues.

(13) Description of the overall completion status of action items associated with license renewal commitments, including AMPs and TLAAs.

(14) Description of administrative controls that will be used to ensure that all activities due prior to (and during) the period of extended operation (PEO) will be satisfactorily completed as described in the license renewal documents.

(15) Description of plans or processes that would be used during the PEO to continuously incorporate operating experience into license renewal activities.

B.

Specific Requests for each License Renewal Commitment Selected for Review, including AMPs and TLAAs (As Applicable)

(1)

Program basis documents and administrative procedures describing key program attributes such as program objectives, scope, detection and monitoring methods, administrative controls, acceptance criteria, corrective actions, and scope expansion requirements.

(2)

Implementing procedures (e.g. visual examination procedure, ultrasonic examination procedures, etc).

(3)

Updated scoping drawings showing the SSCs within the scope of the AMP.

(4)

Applicable sections of the LRA.

(5)

Applicable requests for additional information issued by NRC technical reviewers during the review of the LRA and corresponding responses.

(6)

Applicable sections of the NRCs safety evaluation report.

(7)

Copy or ready access to the key industry standards that will be followed during the PEO for the implementation of the program (e.g. American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Electric Power Research Institute Guidelines, Nuclear Energy Institute Guidelines, etc).

(8)

Description of changes made to the license renewal commitment, including the associated technical and regulatory evaluations supporting the change.

3 Enclosure (9)

Description of activities completed to meet license conditions, license renewal commitments, and the UFSAR. For example, this should include completed work orders with associated inspection reports describing the work done and the results of the inspection.

(10) Description of instances where scope expansion was required based on the initial examination of an SSC. Please describe the logic to select the scope expansion and any resulting changes to the AMP.

(11) Description of pending activities due prior to the PEO, which are necessary to meet license conditions, license renewal commitments, and the activities described in the UFSAR. For example, this may include a list of pending work orders with a brief description of the work to be done.

(12) Any correspondence between the licensee and the NRC after the license was issued associated with regulatory issues affecting the license renewal commitment. For example, this may include notifications of commitment changes or license amendment requests affecting a license condition or a license renewal commitment.

(13) List of corrective action program documents (e.g. Problem Evaluation Reports) associated with the implementation of the AMP. This includes conditions associated with unacceptable aging effects identified during the implementation of license renewal activities and programmatic deficiencies requiring resolution.

(14) Evaluations performed for applicable external and internal operating experience issues associated with license renewal. This request is limited to operating experience Items issued after the renewed operating license was granted.

Inspector Contact Information:

Joel Rivera-Ortiz Sr. Reactor Inspector Region II - Division of Reactor Safety 404-997-4825 Joel.Rivera-Ortiz@nrc.gov