ML13280A151

Component Design Bases Inspection 05000250/2014007 and 05000251/2014007, Notification Letter Final

ML13280A151
Person / Time
Site:	Turkey Point
Issue date:	10/03/2013
From:	Nease R NRC/RGN-II/DRS/EB1
To:	Nazar M Florida Power & Light Co
References
IR-14-007
Download: ML13280A151 (5)

See also: IR 05000250/2014007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

October 3, 2013

Mr. Mano Nazar

Executive Vice President and Chief Nuclear Officer

Florida Power and Light Company

P.O. Box 14000

Juno Beach, FL 33408-0420

SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4

COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000250/2014007 AND 05000251/2014007

Dear Mr. Nazar:

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 Turkey Point

Nuclear Generating Units 3 and 4 during the weeks of January 27 - 31, February 10 - 14, and

February 24 - 28, 2014. Mr. Shakur Walker, a Senior Reactor Inspector from the NRCs Region

II Office, will lead the inspection team. This inspection will be conducted in accordance with the

baseline inspection procedure, Procedure 71111.21, Component Design Bases Inspection,

issued August 14, 2012.

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 October 2, 2013, Mr. Walker confirmed with Ms. Stavy

Mihalakea 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 January 6 - 10, 2014

• Onsite weeks: January 27 - 31, February 10 - 14, and February 24 - 28, 2014

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. John Hanna, a Region II Senior Reactor

Analyst, will support Mr. Walker 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 that will be needed prior to the information-gathering visit.

Please provide the referenced information to the Region II Office by December 2, 2013.

M. Nazar 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 will need to be available to the

team in the Region II Office prior to the inspection teams preparation week of January 20, 2014.

Mr. Walker 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 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 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. Walker at 404-997-4639 or contact

me at 404-997-4530.

Sincerely,

RA

Rebecca L. Nease, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-250, 50-251

License Nos.: DPR-31, DPR-41

Enclosure:

Information Request for Turkey Point

Nuclear Generating Units 3 and 4

Component Design Bases Inspection

cc: Distribution via Listserv

__ML13280A151 x SUNSI REVIEW COMPLETE x FORM 665 ATTACHED

OFFICE RII:DRS RII:DRS

SIGNATURE RA RA

NAME WALKER NEASE

DATE 10/ 2 /2013 10/3 /2013 10/ /2013 10/ /2013 10/ /2013 10/ /2013 10/ /2013

E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

Letter to Mr. Mano Nazar from Rebecca L. Nease dated October 3, 2013.

SUBJECT: NOTIFICATION OF TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4

COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000250/2014007 AND 05000251/2014007

Distribution

RIDSNRRDIRS

PUBLIC

RidsNrrPMTurkeyPoint Resource

INFORMATION REQUEST FOR TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4

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.

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. 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 (significant) since

September 1, 2011, 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) since September 1, 2011.

8. List and brief description of safety-related structures, systems, or components (SSCs)

design modifications implemented since September 1, 2011.

9. List and brief description of common-cause component failures that have occurred since

September 1, 2011.

10. List and brief description of operability evaluations completed since September 1, 2011.

Enclosure

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

September 1, 2011, 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 Technical Requirements Manual(s).

19. List and brief description of Root Cause Evaluations performed since September 1, 2011.

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

January 6, 2014)

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 January 6, 2014)

27. Index and Legend for P&IDs.

28. Copy of Operability Determination procedure(s).

30. Copies of condition reports associated with findings from previous CDBI (Inspection Report

2011-008).

31. Index (procedure number, title, and current revision) of station Emergency Operating

Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures.

32. Copy of any self-assessments performed in preparation for this inspection.

Enclosure

3

33. List of any condition reports generated in preparation for this inspection.

34. Copies of all condition reports generated from previous CDBI (Inspection Report 2011-008).

35. Contact information for a person to discuss PSA information prior to the information-

gathering trip. (Name, title, phone number, and e-mail address)

Enclosure