ML100350156
| ML100350156 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/03/2010 |
| From: | Binoy Desai Engineering Region 1 Branch 1 |
| To: | Franke J Progress Energy Florida |
| References | |
| IR-10-007 | |
| Download: ML100350156 (6) | |
See also: IR 05000302/2010007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER
61 FORSYTH STREET, SW, SUITE 23T85
ATLANTA, GEORGIA 30303-8931
February 3, 2010
Mr. Jon A. Franke
Vice President, Crystal River Nuclear Plant
Crystal River Nuclear Plant (NA2C)
15760 W. Power Line Street
Crystal River, FL 34428-6708
SUBJECT:
NOTIFICATION OF CRYSTAL RIVER NUCLEAR PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
Dear Mr. Franke:
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 at your Crystal River Nuclear
Plant during the weeks of May 24 - 28, June 7 - 11, and June 21 - 25, 2010. The inspection
team will be led by D. Jones, 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 19, 2008.
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 January 25, 2010, Mr. Jones confirmed with Mr. D. Herrin
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 May 10 - 14, 2010
Onsite weeks: May 24 - 28, June 7 - 11, and June 21 - 25, 2010
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. R. Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Jones during the information gathering visit to review probabilistic
risk assessment data and identify risk significant components which will be examined during the
inspection.
2
Please provide the information requested in the enclosure to the Region II office by April 19,
2010. The enclosure lists documents that will be needed prior to the information gathering visit.
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation. Contact Mr. Jones with any questions
related to the information request. During the information gathering visit, the team leader will
also discuss the following inspection support administrative details: request for supplemental
documents to be made available to the inspection team in the Region II office prior to the team
preparation week of May 17 - 21, 2010; office space; arrangements for site access; and the
availability of knowledgeable plant engineering and licensing personnel to serve as points of
contact during the inspection.
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 electronically 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. Jones at (404) 562-4631.
Sincerely,
/RA/
Binoy Desai, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-391
License Nos.: CPPR-92
Enclosure: Information Request for Crystal River
Component Design Bases Inspection
cc w/encl.: (See page 3)
3
cc w/encl:
R. J. Duncan, II
Vice President
Nuclear Operations
Carolina Power & Light Company
Electronic Mail Distribution
Brian C. McCabe
Manager, Nuclear Regulatory Affairs
Progress Energy Carolinas, Inc.
Electronic Mail Distribution
James W. Holt
Plant General Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Stephen J. Cahill
Engineering Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
R. Alexander Glenn
Associate General Counsel
(MAC - BT15A)
Florida Power Corporation
Electronic Mail Distribution
Steven R. Carr
Associate General Counsel
Legal Department
Progress Energy Service Company, LLC
P.O. Box 1551
Raleigh, NC 27602-1551
Christos Kamilaris
Director
Fleet Support Services
Carolina Power & Light Company
Electronic Mail Distribution
William A. Passetti
Chief
Florida Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
Daniel R. Westcott
Supervisor
Licensing & Regulatory Programs
Crystal River Nuclear Plant (NA1B)
Electronic Mail Distribution
Joseph W. Donahue
Vice President
Nuclear Oversight
Carolina Power and Light Company
Electronic Mail Distribution
Jack E. Huegel
Manager, Nuclear Oversight
Crystal River Nuclear Plant
Electronic Mail Distribution
Mark Rigsby
Manager, Support Services - Nuclear
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
Crystal River Nuclear Generating Plant
U.S. NRC
6745 N Tallahassee Rd
Crystal River, FL 34428
Attorney General
Department of Legal Affairs
The Capitol PL-01
Tallahassee, FL 32399-1050
Ruben D. Almaguer
Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
Chairman
Board of County Commissioners
Citrus County
110 N. Apopka Avenue
Inverness, FL 36250
_________________________
xG SUNSI REVIEW COMPLETE
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
\\RA\\
\\RA\\
\\RA\\
NAME
DJONES
RBERNHARD
MSYKES
DATE
1/27/2010
1/27/2010
1/27/2010
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
Information Request for Crystal River Component Design Bases Inspection
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM 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 your 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 since January 1, 2007 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, MOV 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.] since January 1, 2007.
8.
List and brief description of safety related SSC design modifications implemented since
January 1, 2007.
9.
List and brief description of common-cause component failures that have occurred since
January 1, 2007.
10. List and brief description of operability evaluations completed since January 1, 2007.
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 RIS 05-020.
2
Enclosure
13. List and reason for equipment classified in maintenance rule (a)(1) status since January 1,
2007 to present.
14. Copies of System Descriptions (or the like) for Safety-Related Systems
15. Copy of UFSAR(s)
16. List and brief description of Root Cause Evaluations that have been performed since
January 1, 2007.
17. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address.