ML100350156

Notification of Crystal River Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 05000302-10-007

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

05000302/2010007

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.

FPC 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)

FPC 3

cc w/encl: Daniel R. Westcott

R. J. Duncan, II Supervisor

Vice President Licensing & Regulatory Programs

Nuclear Operations Crystal River Nuclear Plant (NA1B)

Carolina Power & Light Company Electronic Mail Distribution

Electronic Mail Distribution

Joseph W. Donahue

Brian C. McCabe Vice President

Manager, Nuclear Regulatory Affairs Nuclear Oversight

Progress Energy Carolinas, Inc. Carolina Power and Light Company

Electronic Mail Distribution Electronic Mail Distribution

James W. Holt Jack E. Huegel

Plant General Manager Manager, Nuclear Oversight

Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant

Electronic Mail Distribution Electronic Mail Distribution

Stephen J. Cahill Mark Rigsby

Engineering Manager Manager, Support Services - Nuclear

Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2C)

Electronic Mail Distribution Electronic Mail Distribution

R. Alexander Glenn Senior Resident Inspector

Associate General Counsel U.S. Nuclear Regulatory Commission

(MAC - BT15A) Crystal River Nuclear Generating Plant

Florida Power Corporation U.S. NRC

Electronic Mail Distribution 6745 N Tallahassee Rd

Crystal River, FL 34428

Steven R. Carr

Associate General Counsel Attorney General

Legal Department Department of Legal Affairs

Progress Energy Service Company, LLC The Capitol PL-01

P.O. Box 1551 Tallahassee, FL 32399-1050

Raleigh, NC 27602-1551

Ruben D. Almaguer

Christos Kamilaris Director

Director Division of Emergency Preparedness

Fleet Support Services Department of Community Affairs

Carolina Power & Light Company Electronic Mail Distribution

Electronic Mail Distribution

Chairman

William A. Passetti Board of County Commissioners

Chief Citrus County

Florida Bureau of Radiation Control 110 N. Apopka Avenue

Department of Health Inverness, FL 36250

Electronic Mail Distribution

_________________________ 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

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.

Enclosure

2

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.

Enclosure