ML18303A163
| ML18303A163 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/30/2018 |
| From: | Marvin Sykes NRC/RGN-II/DRS/EB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR 2019010 | |
| Download: ML18303A163 (5) | |
See also: IR 05000327/2019010
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
October 30, 2018
Mr. Joseph W. Shea
Vice President Nuclear Regulatory Affairs
and Support Services
Tennessee Valley Authority
1101 Market Street, LP 4A
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT DESIGN BASES
ASSURANCE INSPECTION (TEAM) - U.S. NUCLEAR REGULATORY
COMMISSION INSPECTION REPORT 05000327/2019010 AND
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 Design Bases Assurance Inspection (DBAI) at your Sequoyah
Nuclear Plant during the weeks of February 25, 2019, and March 11, 2019. Mr. Eric Stamm, a
Senior Reactor Inspector from the NRCs Region II office, will lead the inspection team. The
inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design
Bases Assurance Inspection (Team), dated December 8, 2016 (ADAMS ML16340B000).
The inspection will evaluate the capability of components that have been modified and 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 October 29, 2018, with Mr. Jon Johnson, we confirmed
arrangements for an information-gathering site visit and the two-week onsite inspection. The
schedule is as follows:
- Information-gathering visit: Week of January 14, 2019
- Onsite weeks: Weeks of February 25, 2019, and March 11, 2019
The purpose of the information-gathering visit is to meet with members of your staff to identify
components that have been modified, risk-significant components and operator actions.
Information and documentation needed to support the inspection will also be identified. Mr.
Scott Freeman, a Region II Senior Risk Analyst, will support Mr. Stamm during the information-
gathering visit to review probabilistic risk assessment data and identify components to be
examined during the inspection. Additionally, during the onsite weeks, time will be needed on
the plant-referenced simulator in order to facilitate the development of operator action-based
scenarios.
J. Shea 2
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 Monday, January 7, 2019.
Additional documents will be requested following 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 will be needed in the Region II
office by Friday, February 8, 2019, to support the inspection teams preparation week. During
the information-gathering trip, Mr. Stamm 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.
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Thank you for your cooperation in this matter. If you have any questions, regarding the
information requested or the inspection, please contact Mr. Stamm at 404-997-4575 or contact
me at 404-997-4629.
Sincerely,
/RA/
Marvin D. Sykes, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-327, 50-328
Enclosure:
Notification of Sequoyah Nuclear Plant
Design Bases Assurance Inspection (Team)
cc: Distribution via Listserv
____________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED
OFFICE RII:DRS/EB1 RII:DRS/EB1
SIGNATURE EJS2 MDS1
NAME E. Stamm M. Sykes
DATE 10/ 29 /2018 10/ 29 /2018
E-MAIL COPY? YES NO YES NO
INFORMATION REQUEST FOR SEQUOYAH NUCLEAR PLANT
DESIGN BASES ASSURANCE INSPECTION (TEAM)
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. The requested items below, identified with an asterisk (*),
should have a date range from January 1, 2016, until present.
1. *List and brief description of permanent and fieldwork completed plant modifications
including permanent plant changes, design changes, set point changes, procedure
changes, equivalency evaluations, suitability analyses, calculations, and commercial grade
dedications. Include an index of systems (system numbers/designators and corresponding
names), the safety classification for each modification, and type of modification.
2. From your most recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk
Achievement Worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cut-sets
c. A list of the top 500 LERF contributors
3. From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
and the other sorted by Birnbaum Importance
b. A list of the top 500 cut-sets
4. Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
reliability worksheets for these items
5. List of time-critical operator actions with a brief description of each action
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 motor-operated valve risk-margin rankings, etc.) and
associated evaluations or calculations
7. *List and brief description of Root Cause Evaluations performed
8. *List and brief description of common-cause component failures that have occurred
9. List and brief description of equipment currently in degraded or nonconforming status as
described in NRC Inspection Manual Chapter 0326, issued November 20, 2017
10. *List and brief description of Operability Determinations and Functionality Assessments
Enclosure
2
11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
12. *List of equipment on the sites 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) along with dates added or removed from
the issues list
13. List of current operator work arounds/burdens
14. Copy of Updated Final Safety Analysis Report
15. Copy of Technical Specification(s)
16. Copy of Technical Specifications Bases
17. Copy of Technical Requirements Manual(s)
18. Copy of the Quality Assurance Program Manual
19. Copy of Corrective Action Program Procedure(s)
20. Copy of Operability Determination Procedure(s)
21. Copy of procedures addressing the following: Modifications, design changes, set point
changes, equivalency evaluations or suitability analyses, commercial grade dedications,
post-modifications testing, 10 CFR 50.59 screenings and evaluations, and UFSAR updates.
22. List of motor operated valves and air operated valves in the valve program, and their
associated design margin and risk ranking
23. Primary AC and DC calculations for safety-related buses
24. One-line diagram of electrical plant (Electronic only)
25. Index and legend for electrical plant one-line diagrams
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
27. Index and legend for P&IDs
28. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
29. Copies of corrective action documents generated from previous CDBI
30. Copy of any self-assessments performed, and corrective action documents generated, in
preparation for current DBAI
31. Contact information for a person to discuss PSA information prior to and during the
information-gathering trip (Name, title, phone number, and e-mail address)