ML16076A061
| ML16076A061 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/15/2016 |
| From: | Bartley J NRC/RGN-II/DRS/EB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR 2016007 | |
| Download: ML16076A061 (6) | |
See also: IR 05000327/2016007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
March 15, 2016
Mr. Joseph W. Shea
Vice President, Nuclear Licensing
Tennessee Valley Authority
Chattanooga, TN 37402-2801
SUBJECT:
NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000327/2016007,
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.
J. Shea
2
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 teams 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
Enclosure:
Information Request for Sequoyah
Nuclear Plant - Component Design Bases
Inspection
cc: Distribution via Listserv
_________________________
SUNSI REVIEW COMPLETE
FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRS
SIGNATURE
RNP1
GKO FOR JHB1
NAME
RPATTERSON
JBARTLEY
DATE
3/ 15 /2016
3/ 15/2016
3/ /2016
3/ /2016
3/ /2016
3/ /2016
3/ /2016
E-MAIL COPY?
YES
NO YES
NO
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NO
YES
NO YES
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Enclosure
INFORMATION REQUEST FOR SEQUOYAH NUCLEAR STATION
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 Web site) 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 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 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 cutsets
3.
Risk ranking of operator actions from your site-specific PSA sorted by RAW, including
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 1, 2013, 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 motor-operated valve risk-margin rankings, etc.), and
associated evaluations or calculations
7.
List of station operating experience evaluations/reviews performed and documented in the
stations corrective action program for industry events and safety-related equipment
failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
Communications, 10 CFR Part 21 Notifications) since April 1, 2013
8.
List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented since April 1, 2013
9.
List and brief description of common-cause component failures that have occurred
since April 1, 2013
10. List and brief description of operability evaluations completed since April 1, 2013
2
11. 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)
12. List and brief description of equipment currently in degraded or nonconforming status as
described in Regulatory Issue Summary 05-020
13. List and reason for equipment classified in maintenance rule (a)(1) status from
April 1, 2013, to present
14. Copies of system descriptions (or the design basis documents) for safety-related systems
15. Copy of Updated Final Safety Analysis Report
16. Copy of Technical Specification(s)
17. Copy of Technical Specifications Bases
18. Copy of Selected Licensee Commitment Manual(s)
19. List and brief description of Root Cause Evaluations performed since April 1, 2013
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
March 28, 2016)
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. Piping and instrumentation diagrams (P&IDs) for safety-related systems (electronic and 1/2
size - hard copy week of March 28, 2016)
27. Index and Legend for P&IDs
28. Copy of Operability Determination procedure(s)
29. Copies of corrective action documents (i.e. condition reports (CRs)) associated with
findings from previous CDBI, if applicable
30. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
31. Copy of any self-assessments performed in preparation for this inspection
3
32. List of any PIPs generated in preparation for this inspection
33. Copies of PIPs generated from previous CDBI (2013)
34. Contact information for a person to discuss PSA information prior to the information-
gathering trip (name, title, phone number, and e-mail address)