IR 05000327/2013007
| ML13098A141 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/05/2013 |
| From: | Nease R L NRC/RGN-II/DRS/EB1 |
| To: | Shea J W Tennessee Valley Authority |
| References | |
| IR-13-007 | |
| Download: ML13098A141 (8) | |
Text
April 5, 2013
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 05000327/2013007, 05000328/2013007
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 Plant during the weeks of July 08 - 12, July 22 - 26, and August 5 - 9, 2013. The inspection team will be led by Shakur Walker, a Senior Reactor Inspector from the NRC's Region II Office. This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71111.21, "Component Design Bases Inspection," issued August 14, 2012. 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 April 2, 2013, Mr. Walker confirmed with Mike McBrearty of your staff, arrangements for an information-gathering site visit and the three-week onsite inspection. The schedule is as follows:
- Information-gathering visit: Week of June 17 - 21, 2013
- Onsite weeks: July 08 - 12, July 22 - 26, and August 5 - 9, 2013 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. John Hanna, a Region II Senior Reactor Analyst, may accompany Mr. Walker 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 that will be needed prior to the information-gathering visit. Please provide the referenced information to the Region II office by May 20, 2013. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation.
Additional documents will be requested during the information-gathering visit. The additional information will need to be made available to the team in the Region II office prior to the inspection team's preparation week of July 1. Mr. Walker, 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 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
Enclosure will be available electr onically 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).
Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Walker at 404-997-4639 or me at 404-997-4530.
Sincerely,/RA/
Rebecca L. Nease, 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: (See page 3)
_________________________ x G SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE RA RA NAME WALKER NEASE DATE .4/5/2013 .4/5/2013 4/ /2013 4/ /2013 4/ /2013 4/ /2013 4/ /2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO cc: J. T. Carlin Site Vice President Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
P. R. Simmons
Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
J. W. Proffitt Manager, Site Licensing Sequoyah Nuclear Plant Electronic Mail Distribution
C. D. Mackaman Program Manager, Corporate Licensing Tennessee Valley Authority Electronic Mail Distribution
Edward J. Vigluicci Associate General Counsel, Nuclear Tennessee Valley Authority Electronic Mail Distribution
County Mayor
208 Courthouse 625 Georgia Avenue Chattanooga, TN 37402-2801
Tennessee Department of Environment & Conservation Division of Radiological Health 401 Church Street Nashville, TN 37243
Senior Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, TN 37379-3624
Ann Harris
341 Swing Loop Rockwood, TN 37854 Letter to Joseph from Rebecca L. Nease dated April 5, 2013.
SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000327/2013007, 05000328/2013007 DISTRIBUTION
- RIDSNRRDIRS PUBLIC RidsNrrPMSequoyah Resource
Enclosure INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT COMPONENT DESIGN BASES INSPECTION Please provide the information electronically in ".pdf" files, Excel, or other searchable format on CDROM. (or FTP site, Sharepoint, etc.) The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use.
1. From your most-recent probabilistic safety analysis (PSA)
excluding external events and fires: a. Two risk rankings of components from your site-specific probabilistic safety analysis (PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cutsets 2. From your most-recent probabilistic safety analysis (PSA)
including external events and fires:
a. Two risk rankings of components from your site-specific probabilistic safety analysis (PSA): one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance b. A list of the top 500 cutsets
3. Risk ranking of operator actions from y our site-specific PSA sorted by RAW. Provide human reliability worksheets for these items.
4. List of time critical operator actions with a brief description of each action.
5. List of Emergency and Abnormal Operating Procedures revised (significant) since April 16, 2010, with a brief description of each revision.
6. List of components with low design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and MOV risk-margin rankings, etc.), and associated evaluations or calculations.
7. List of station operating experience evaluations/reviews performed, and documented in the station's corrective action program, fo r industry events and safety related equipment failures/vulnerabilities [as communicated by NRC Generic Communications, Industry Communications, 10 CFR Part 21 Notifications, etc.] since April 16, 2010.
8. List and brief description of safety related SSC design modifications implemented since April 16, 2010.
9. List and brief description of common-cause component failures that have occurred since April 16, 2010.
10. List and brief description of operability evaluations completed since April 16, 2010.
2 Enclosure 11. List of equipment on the site's Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list, and summaries (if available) of your plans to address the issue(s).
12. List and brief description of equipment currently in degraded or nonconforming status as described in RIS 05-020.
13. List and reason for equipment classified in maintenance rule (a)(1) status since April 16, 2010, to present.
14. Copies of System Descriptions (or the like design basis documents) for Safety-Related Systems.
15. Copy of UFSAR(s).
16. Copy of Technical Specification(s).
17. Copy of Technical Specifications Bases.
18. Copy of Technical Requirements Manual(s).
19. List and brief description of Root Cause Evaluations that have been performed since April 16, 2010.
20. In-service Testing Program Procedure(s).
21. Corrective Action Program Procedure(s).
22. One line diagram of electrical plant. (Electronic and full size - hard copy week of June 17)
23. Index and legend for electrical plant one-line diagrams.
24. Primary AC calculation(s) for safety-related buses.
25. Primary DC calculation(s) for safety-related buses.
26. PI&D's for Safety-Related systems. (Electronic and 1/2 size - hard copy week of June 17)
27. Index and Legend for PI&Ds.
28. Copy of Operability determination procedure(s).
30. Copies of condition reports associated with findings from previous CDBI.
31. Index (procedure number, titles, and current revision) of station Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response Procedures (ARPs).
32. Copy of any self-assessments performed in preparation for this inspection.
3 Enclosure 33. List of any condition reports generated in preparation for this inspection.
34. Copies of condition reports generated from previous CDBI (2010).
35. Contact information for a person to discuss PRA information prior to the information-gathering trip. (Name, title, phone number, and e-mail address)