ML16205A003
| ML16205A003 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/19/2016 |
| From: | Bartley J NRC/RGN-II/DRS/EB1 |
| To: | William Gideon Progress Energy Carolinas |
| References | |
| IR 2016007 | |
| Download: ML16205A003 (6) | |
See also: IR 05000324/2016007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
July 19, 2016
William R. Gideon
Site Vice President
Brunswick Steam Electric Plant
8470 River Rd. SE (M/C BNP001)
Southport, NC 28461
SUBJECT: NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT COMPONENT
DESIGN BASES INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION
INSPECTION REPORT 05000325/2016007 AND 05000324/2016007
Dear Mr. Gideon:
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 Brunswick
Steam Electric Plant, Units 1 and 2, during the weeks of November 14, November 28, and
December 12, 2016. 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 71111.21, Component Design Bases Inspection, dated 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 July 11, 2016, with Mr. Lee Grzeck, we confirmed
arrangements for an information-gathering site visit and the three-week onsite inspection. The
schedule is as follows:
Information-gathering visit: Week of October 17, 2016
Onsite weeks: Weeks of November 14-18, November 28-December 2, and
December 12-16, 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 Risk
Analyst, will support Mr. Stamm during the information-gathering visit to review probabilistic risk
assessment data and identify risk-significant 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.
W. Gideon
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 Friday, October 7, 2016.
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, October 28, 2016, 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.
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. Stamm at 404-997-4575 or contact
me at 404-997-4607.
Sincerely,
/RA: ERIC J. STAMM FOR/
Jonathan H. Bartley, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-325, 50-324
Enclosure:
Information Request for Brunswick Steam Electric Plant,
Component Design Bases Inspection
cc: Distribution via Listserv
__ ____________
SUNSI REVIEW COMPLETE
FORM 665 ATTACHED
OFFICE
RII:DRS
RII:DRS
SIGNATURE
EJS2
EJS2
NAME
E. Stamm
J. Bartley
DATE
7/19 /2016
7/19/2016
E-MAIL COPY?
YES
NO
YES
NO
Enclosure
INFORMATION REQUEST FOR BRUNSWICK STEAM ELECTRIC 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. The requested items below, identified with an asterisk (*),
should have a date range from June 2013, until present.
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 cut-sets
c. A list of the top 500 LERF contributors
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 cut-sets
3.
Risk ranking of operator actions from your site-specific PSA sorted by RAW and human
reliability worksheets for these items
4.
List of time-critical operator actions with a brief description of each action
5.
- List of revised (significant) Emergency and Abnormal Operating Procedures 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, etc.)
8.
- List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented
9.
- List and brief description of Root Cause Evaluations performed
10. *List and brief description of common-cause component failures that have occurred
2
11. List and brief description of equipment currently in degraded or nonconforming status as
described in NRC Inspection Manual Chapter 0326, issued December 3, 2015
12. *List and brief description of Operability Determinations and Functionality Assessments
13. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
14. *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
15. List of current operator work arounds/burdens
16. Copy of Updated Final Safety Analysis Report
17. Copy of Technical Specification(s)
18. Copy of Technical Specifications Bases
19. Copy of Technical Requirements Manual(s)
20. Copy of the Quality Assurance Program Manual
21. Copy of systems Design Bases Documents
22. Copy of Corrective Action Program Procedure(s)
23. Copy of Operability Determination Procedure(s)
24. Copy of In-service Testing Program Procedure(s)
25. List of motor operated valves and air operated valves in the valve program, and their
associated design margin and risk ranking
26. Primary AC and DC calculations for safety-related buses
27. One-line diagram of electrical plant (Electronic and full size - hard copy on bagman visit)
28. Index and legend for electrical plant one-line diagrams
29. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic
and 1/2 size - hard copy on bagman visit)
30. Index and Legend for P&IDs
31. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
32. Copies of corrective action documents generated from previous CDBI
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33. Copy of any self-assessments performed in preparation for current and previous CDBI
34. List of corrective action documents generated in preparation for this inspection
35. 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)