ML032730918

Notification of St. Lucie Nuclear Plant - Safety System Design and Performance Capability Inspection - NRC Inspection Report 05000335/2003009 and 05000389/2003009

ML032730918
Person / Time
Site:	Saint Lucie
Issue date:	09/29/2003
From:	Ogle C Division of Reactor Safety II
To:	Stall J Florida Power & Light Co
References
IR-03-009
Download: ML032730918 (7)

See also: IR 05000335/2003009

Text

September 29, 2003

Florida Power and Light Company

ATTN: Mr. J. A. Stall, Senior Vice President

Nuclear and Chief Nuclear Officer

P. O. Box 14000

Juno Beach, FL 33408-0420

SUBJECT: NOTIFICATION OF ST. LUCIE NUCLEAR PLANT - SAFETY SYSTEM DESIGN

AND PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION

REPORT 05000335/2003009 AND 05000389/2003009

Dear Mr. Stall:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a safety system design and performance capability inspection at

your St. Lucie Nuclear Plant during the weeks of December 1, 2003, and December 15, 2003.

A team of seven inspectors will perform this inspection. The inspection team will be led by Mr.

Jim Moorman, a Senior Reactor Inspector from the NRC Region II Office. This biennial

inspection will be conducted in accordance with baseline pilot inspection program Attachment

71111.DS, Safety System Design and Performance Capability.

The inspection will evaluate the capability of installed plant equipment to detect and respond to

a steam generator tube rupture event. Procedures which direct the mitigating actions for this

event will also be evaluated.

During a telephone conversation on September 26, 2003, Mr. Moorman of my staff, and

Mr. George Madden of your staff, confirmed arrangements for an information gathering site visit

and the two-week onsite inspection. The schedule is as follows:

• Information gathering visit: Week of October 27, 2003

• Onsite inspection weeks: December 1, 2003, and December 15, 2003.

The purpose of the information gathering visit is to obtain information and documentation

outlined in the enclosure needed to support the inspection. Mr. Rudy Bernhard, a Region II

Senior Reactor Analyst, may accompany Mr. Moorman during the information gathering visit to

review probabilistic risk assessment data and identify risk significant components which will be

examined during the inspection. Please contact Mr. Moorman prior to preparing copies of the

materials listed in the Enclosure. The inspectors will try to minimize your administrative burden

by specifically identifying only those documents required for inspection preparation. During the

information gathering visit, the team leader will also discuss the following inspection support

administrative details: office space; specific documents requested to be made available to the

team in their 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.

FP&L 2

Thank you for your cooperation in this matter. If you have any questions regarding the

information requested or the inspection, please contact Mr. Moorman at (404) 562-4647 or me

at (404) 562-4605.

In accordance with 10 CFR 2.790 of the NRCs "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 Publically Available Records (PARS) component of NRCs 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).

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-335, 50-389

License Nos.: DPR-67, NPF-16

Enclosure: Information Request for the Safety System Design and Performance Capability

Inspection

cc w/encl:

William Jefferson, Jr.

Site Vice President

St. Lucie Nuclear Plant

Florida Power & Light Company

Electronic Mail Distribution

R. E. Rose

Plant General Manager

St. Lucie Nuclear Plant

Electronic Mail Distribution

Terry L. Patterson

Licensing Manager

St. Lucie Nuclear Plant

Electronic Mail Distribution

Don Mothena, Manager

Nuclear Plant Support Services

Florida Power & Light Company

Electronic Mail Distribution

(cc w/encl contd - See page 3)

FP&L 3

(cc w/encl contd)

Mark Dryden

Administrative Support & Special Projects

Florida Power & Light Company

Electronic Mail Distribution

Rajiv S. Kundalkar

Vice President - Nuclear Engineering

Florida Power & Light Company

Electronic Mail Distribution

M. S. Ross, Attorney

Florida Power & Light Company

Electronic Mail Distribution

William A. Passetti

Bureau of Radiation Control

Department of Health

Electronic Mail Distribution

Craig Fugate, Director

Division of Emergency Preparedness

Department of Community Affairs

Electronic Mail Distribution

J. Kammel

Radiological Emergency

Planning Administrator

Department of Public Safety

Electronic Mail Distribution

Douglas Anderson

County Administrator

St. Lucie County

2300 Virginia Avenue

Ft. Pierce, FL 34982

Distribution w/encl: (See page 4)

FP&L 4

Distribution w/encl:

E. Brown, NRR

L. Slack, RII EICS

RIDSNRRDIPMLIPB

PUBLIC

OFFICE RII:DRS RII:DRP

SIGNATURE RA RA

NAME MOORMAN MUNDAY

DATE 9/26/2003 9/26/2003 10/ /2003 10/ /2003 10/ /2003 10/ /2003 10/ /2003

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

PUBLIC DOCUMENT YES NO

OFFICIAL RECORD COPY DOCUMENT NAME: C:\ORPCheckout\FileNET\ML032730918.wpd

INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND

PERFORMANCE CAPABILITY INSPECTION

ST. LUCIE STEAM GENERATOR TUBE RUPTURE EVENT

(The preferred file format is searchable .pdf files on CDROM. The CDROM should be

indexed and hyperlinked to facilitate ease of use. Please provide 5 copies of each

CDROM submitted. Information in lists should contain enough information to be easily

understood by someone who has a knowledge of pressurized water reactor technology.)

1. Piping and instrumentation drawings for High Pressure Safety Injection System (HPSI),

Auxiliary Feedwater System (AFW), Main Steam (MS), Chemical and Volume Control

System (CVCS), Component Cooling Water System (CCW), Low Pressure Safety

Injection System (LPSI), Reactor Coolant System (RCS) (Paper copies are preferred for

these)

2. The normal operating procedures for the systems listed above. Include the procedures

which specify the normal valve alignment for these systems.

3. Surveillance procedures used to ensure the operability of equipment required by your

Technical Specifications that is used during the mitigation of the SGTR event.

4. Procedures used for the operational testing of check valves in portions of the

emergency core cooling systems used during mitigation of the SGTR event.

5. Procedures used to sample the steam generators during a SGTR event.

6. Calibration and functional testing procedures for the radiation monitoring instrumentation

used during a SGTR event.

7. Calibration and functional test procedures for instruments used to monitor RCS

pressure, pressurizer level and pressure, SG level and pressure, RCS hot and cold leg

temperature, RCS subcooling, feedwater flow, steam flow, core exit temperature, high

pressure injection flow, LPSI flow, refueling water storage tank level, pressurized heater

status, safety relief valve position indicator, AFW flow, condensate storage tank (CST)

level, makeup flow, and letdown flow.

8. Test procedures for the primary and secondary system safety relief valves and power

operated relief valves.

9. Test procedures for the AFW starting logic.

10. A list of Condition Reports and non-routine work requests initiated since 1998 affecting

the systems used to detect and mitigate a SGTR event; including their power supplies.

11. Emergency Operating Procedures (EOPs) and supporting procedures, EOP basis

documents, step deviation document, writers guide, and users guide.

ENCLOSURE

2

12. Calculations used to support the set points in Emergency Operating Procedures for a

SGTR event.

13. A list of engineering calculations applicable to AFW, HPSI, LPSI, RCS, CCW, MS and

other systems used in the mitigation of the SGTR event.

14. A list of existing temporary modifications and operator work-arounds.

15. A list of operability determinations performed since 1998.

16. System Health Reports and System Performance Trends for all systems going back 2

years.

17. A copy of the Maintenance Rule program procedure and performance criteria for all

plant systems. A list of plant systems currently monitored under 50.65(a)(1) and the

performance goals. A list of Maintenance Rule functional failures since 2000.

18. Quality Assurance audits, self-assessments, and third party assessments performed on

AFW, HPSI, LPSI, RCS, CCW systems and other related systems in the last 24 months.

Quality Assurance audits, self-assessments and third party assessments performed on

engineering and maintenance department activities in the last 24 months.

19. Operator training lesson plans, system descriptions, and job performance measures for

the EOPs, EOP support procedures, off-normal and operating procedures that would be

used to mitigate an SGTR event.

20. Key electrical single line drawings of the intermediate and low voltage alternating current

and direct current power systems. (Paper copies are preferred for these)

21. The electrical system load list(s).

22. A brief description of the mitigation strategy for handling the SGTR event, including

operator actions and equipment used.

23. A list of Operating Experience Program evaluations of industry, vendor, or NRC generic

issues for the past 3 years.

24. A list of equipment and operator actions with a Risk Achievement Worth greater than

1.02.

25. Probabilistic Risk Assessment (PRA) Event Tree for SGTR initiating event. A list of

PRA system dependencies and success criteria for AFW, HPSI, MS, CCW, and their

support systems.

26. Design Basis Manual for major plant electrical, mechanical, and control systems.

27. Plant Technical Specifications, Bases, and Technical Requirements Manual

ENCLOSURE

3

28. A current copy of the Updated Final Safety Analysis Report.

29. A list of 50.59 evaluations and screenings conducted since 2001. The plant procedure

which defines the St. Lucie 50.59 process.

30. A list of all permanent plant changes, design changes, setpoint changes, procedure

changes, equivalency evaluations, suitability analyses, calculations, and commercial

grade dedications since 2001. The plant procedure which defines the design control

and modifications process at St. Lucie.

31. Plant procedures that provide the guidelines for the Corrective Action Program and the

incorporation of local and industry operating experience into St. Lucie programs and

procedures.

ENCLOSURE