ML032730918
| 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.
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
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)
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)
4
Distribution w/encl:
E. Brown, NRR
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRP
SIGNATURE
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
ENCLOSURE
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.
2
ENCLOSURE
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
3
ENCLOSURE
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.