ML17027A068
| ML17027A068 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/27/2017 |
| From: | Bartley J NRC/RGN-II/DRS/EB1 |
| To: | Gayheart C Southern Nuclear Operating Co |
| References | |
| IR 2017007 | |
| Download: ML17027A068 (5) | |
See also: IR 05000348/2017007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
January 27, 2017
Mrs. Cheryl A. Gayheart
Vice President
Southern Nuclear Operating Co., Inc.
Joseph M. Farley Nuclear Plant
7388 North State Highway 95
Columbia, AL 36319
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT DESIGN BASES
ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
INSPECTION REPORT 05000348/2017007 AND 05000364/2017007
Dear Mrs. Gayheart:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Design Basis Assurance Inspection (DBAI) at your Joseph M.
Farley Nuclear Plant during the weeks of May 1-5, and May 15-19, 2017. Mr. Marcus Riley, a
Reactor Inspector, will lead the inspection team. The inspection will be conducted in
accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection
(Teams), dated December 8, 2016 (ADAMS ML16238A320).
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 January 23, 2017, with Ms. Julie Collier, 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 April 10-14, 2017
Onsite weeks: Weeks of May 1-5, and May 15-19, 2017
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.
George MacDonald, a Region II Senior Risk Analyst, will support Mr. Riley 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 may be
needed on the plant-referenced simulator in order to facilitate the development of operator
action-based scenarios.
C. Gayheart
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, March 27, 2017.
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, April 21, 2017, to support the inspection teams preparation week. During the
information-gathering trip, Mr. Riley 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
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
Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible
from the NRC website 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. Riley at 404-997-4888 or contact me
at 404-997-4607.
Sincerely,
/RA/
Jonathan H. Bartley, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-348, 50-364
Enclosure:
Information Request for Joseph M. Farley Nuclear Plant,
Design Basis Assurance Inspection (Teams)
cc: Distribution via Listserv
______________
SUNSI REVIEW COMPLETE
FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRS
SIGNATURE
JHB1
NAME
M. RILEY
J. BARTLEY
DATE
1/23/17
1/27/2017
E-MAIL COPY?
YES
NO
YES
NO
Enclosure
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT
DESIGN BASES ASSURANCE INSPECTION (TEAMS)
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 December 1, 2013, until present.
1.
- List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented
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 December 3, 2015
10. *List and brief description of Operability Determinations and Functionality Assessments
11. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
2
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. List of motor operated valves and air operated valves in the valve program, and their
associated design margin and risk ranking
22. Primary AC and DC calculations for safety-related buses
23. One-line diagram of electrical plant (Electronic only)
24. Index and legend for electrical plant one-line diagrams
25. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic only)
26. Index and legend for P&IDs
27. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
28. Copies of corrective action documents generated from previous CDBI
29. Copy of any self-assessments performed, and corrective action documents generated, in
preparation for current DBAI
30. 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)