ML040990170
| ML040990170 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/06/2004 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Stall J Florida Power & Light Co |
| References | |
| IR-04-008 | |
| Download: ML040990170 (8) | |
See also: IR 05000250/2004008
Text
April 6, 2004
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 TURKEY POINT NUCLEAR PLANT - SAFETY SYSTEM
DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC
INSPECTION REPORT 05000250/2004008 AND 05000250/2004008
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 Turkey Point Nuclear Plant during the weeks of June 7 and June 21, 2004. A team of five
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 inspection program Attachment 71111.21, 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 April 5, 2004, Mr. Norman Merriweather, and Mr. Walt
Parker 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 May 16, 2004
- Onsite inspection weeks: June 7 and June 21, 2004
The purpose of the information gathering visit is to obtain information and documentation,
outlined in the Enclosure, that is needed to support the inspection. Mr. Walt Rogers, 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 2.390 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: Walter Rogers for:/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-250, 50-251
Enclosure: Information Request for the Safety System Design and Performance Capability
Inspection.
cc w/encl:
T. O. Jones
Site Vice President
Turkey Point Nuclear Plant
Florida Power and Light Company
Electronic Mail Distribution
Walter Parker
Licensing Manager
Turkey Point Nuclear Plant
Florida Power and Light Company
Electronic Mail Distribution
Michael O. Pearce
Plant General Manager
Turkey Point Nuclear Plant
Florida Power and Light Company
Electronic Mail Distribution
(cc w/encl contd - See page 3)
FP&L 3
(cc w/encl contd)
David Moore, Vice President
Nuclear Operations Support
Florida Power & Light Company
Electronic Mail Distribution
Rajiv S. Kundalkar
Vice President - Nuclear Engineering
Florida Power & Light Company
Electronic Mail Distribution
M. S. Ross, Managing Attorney
Florida Power & Light Company
Electronic Mail Distribution
Marjan Mashhadi, Senior Attorney
Florida Power & Light Company
Electronic Mail Distribution
Attorney General
Department of Legal Affairs
The Capitol
Tallahassee, FL 32304
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
County Manager
Metropolitan Dade County
Electronic Mail Distribution
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
Curtis Ivy
City Manager of Homestead
Electronic Mail Distribution
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
NAME MOORMAN MUNDAY
DATE 4/6 /2004 4/6 /2004
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\ML040990170.wpd
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND PERFORMANCE
CAPABILITY INSPECTION
TURKEY POINT STEAM GENERATOR TUBE RUPTURE MITIGATION
(Please provide the information electronically in searchable .pdf files on CDROM. The
CDROM should be indexed and hyperlinked to facilitate ease of use. 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 Safety Injection System (SI), Auxiliary
Feedwater System (AFW), Main Steam (MS), Chemical and Volume Control System
(CVCS), Residual Heat Removal System (RHR), Intake Cooling Water (ICW),
Component Cooling Water, (CCW) Reactor Coolant System, including the pressurizer
(RCS), and Instrument Air (IA) (Paper copies (2) 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. System description and operator training modules for a SGTR event.
6. Procedures used to sample the reactor coolant system and steam generators during an
SGTR event.
7. Calibration and functional testing procedures for all radiation monitoring instrumentation
used in the detection and mitigation phases of the SGTR event.
8. 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, SI flow, refueling water storage tank level, pressurizer heater
status, safety relief valve position indicator, AFW flow, condensate storage tank (CST)
level, makeup flow, and letdown flow.
9. Test procedures for the primary and secondary system safety relief valves and
pressurizer power operated relief valves.
10. Test procedures for the AFW starting logic.
11. Emergency Operating Procedures (EOPs) and supporting procedures, EOP basis
documents, step deviation document, writers guide, and users guide. Abnormal
Operating Procedures that would be used during a steam generator tube leak/rupture
event.
Enclosure
2
12. Calculations used to support the setpoints in Emergency Operating Procedures for a
SGTR event.
13. A list of engineering calculations applicable to AFW, SI, CVCS, RCS, CC, and other
systems used in the mitigation of the SGTR event.
14. A list of temporary modifications and operator work-arounds since 2001.
15. A list of operability determinations performed since 1999.
16. A list of corrective action program documents and non-routine work requests initiated
since 2001 for the following: CVCS, AFW, SI, ICW, CCW, MS, Radiation Monitoring,
intermediate voltage electrical, low voltage electrical, direct current systems as well as
the Pressurizer PORVs and Steam Generator atmospheric dump valves.
17. System Health Reports and System Performance Trends for all systems going back 2
years.
18. A copy of the Maintenance Rule 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.
19. Quality Assurance audits, self-assessments and third party assessments performed on
AFW, SI, CVCS, RCS, IA systems and other related systems in the last 24 months.
20. Quality Assurance audits, self-assessments, and third party assessments performed on
engineering and maintenance department activities performed in the last 24 months.
21. Operator training lesson plans, system descriptions, and job performance measures for
the EOPs, EOP support procedures, abnormal, and normal operating procedures that
would be used to mitigate an SGTR event.
22. Key electrical single line drawings of the intermediate and low voltage alternating current
(AC) and DC power systems. (Paper copies (2) are preferred for these)
23. The electrical system load list(s).
24. A brief description of the mitigation strategy for handling the SGTR event, including
operator actions and equipment used.
25. A list of Operating Experience Program evaluations of industry, vendor, or NRC generic
issues for the past 3 years.
26. A list of equipment and operator actions with a Risk Achievement Worth (RAW) greater
than 1.02.
Enclosure
3
27. Probabilistic Risk Assessment (PRA) Event Tree for SGTR initiating event. A List of
PRA system dependencies and success criteria for AFW, SI, CVCS, MS, CCW
systems, and their support systems.
28. Design Basis Manual for major plant electrical, mechanical, and control systems.
29. Plant Technical Specifications, Bases, and Technical Requirements Manual
30. A current copy of the Updated Final Safety Analysis Report.
31. A list of all plant permanent plant changes, design changes, setpoint changes,
procedure changes, equivalency evaluations, suitability analyses, calculations, and
commercial grade dedications since 2001.
32. Plant procedures that provide the guidelines for the following: 1) Corrective Action
Program, 2) Program for the evaluation of changes, tests, and experiments [50.59
Program] 3) Program for the incorporation of local and industry operating experience
into Turkey Point programs and procedures 4) Program for modifications to safety-
related plant systems 5) Program for implementation of the Maintenance Rule
33. A current copy of the Offsite Dose Calculation Manual
Enclosure