ML16076A061
| ML16076A061 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/15/2016 |
| From: | Bartley J H NRC/RGN-II/DRS/EB1 |
| To: | Shea J W Tennessee Valley Authority |
| References | |
| IR 2016007 | |
| Download: ML16076A061 (6) | |
See also: IR 05000327/2016007
Text
March 15, 2016
Mr. Joseph Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000327/2016007, 05000328/2016007
Dear Mr. Shea:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) Region II staff will conduct a component design bases inspection (CDBI) at your Sequoyah Nuclear Station during the weeks of May 9 - 13, May 23 - 27, and June 13 - 17, 2016.
Mr. Robert Patterson, a Reactor Inspector in Region II, will lead the inspection team. This inspection will be conducted in accordance with the baseline inspection procedure (IP) 71111.21, "Component Design Bases Inspection," issued November 29, 2013.
The inspection will evaluate the capability of risk-significant/low margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications.
During a telephone conversation on March 14, 2016, Mr. Patterson confirmed with Ms. Rebecca Travis of your staff, arrangements for an information-gathering site visit and the 3-week onsite inspection. The schedule is as follows:
- Information-gathering visit: Week of April 25 - 29, 2016 * Onsite inspection: Weeks of May 9 - 13, May 23 - 27, and June 13 - 17, 2016 The purpose of the information-gathering visit is to meet with members of your staff to identify risk-significant components and operator actions. Information and documentation needed to support the inspection will also be identified. Mr. Rudolph Bernhard, a Region II Senior Reactor Analyst, will support Mr. Patterson during the information-gathering visit to review probabilistic risk assessment data and identify risk-significant components, which will be examined during the inspection.
The enclosure lists documents needed prior to the information-gathering visit. Please provide the referenced information to the Region II Office by April 4, 2016. Additional documents will be requested during the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information should be available to the team in the Region II Office prior to the inspection team's preparation week of May 2, 2016. Mr. Patterson will also discuss the following inspection support administrative details:
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection, (2) method of tracking inspector requests during the inspection, (3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
other applicable information. In accordance with Title 10 of the Code of Federal Regulations 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Patterson at 404-997-4667 or contact me at 404-997-4607.
Sincerely,/RA: Geoffrey Ottenberg for/ Jonathan H. Bartley, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-327, 50-328 License Nos.: DPR-77, DPR-79
Enclosure:
Information Request for Sequoyah Nuclear Plant - Component Design Bases Inspection cc: Distribution via Listserv