ML030440333
| ML030440333 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/10/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Young D Florida Power Corp |
| References | |
| IR-03-002 | |
| Download: ML030440333 (7) | |
See also: IR 05000302/2003002
Text
February 10, 2003
Mr. Dale E. Young, Vice President
Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing &
Regulatory Programs
15760 West Power Line Street
Crystal River, FL 34428-6708
SUBJECT: NOTIFICATION OF CRYSTAL RIVER NUCLEAR PLANT - SAFETY SYSTEM
DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC
INSPECTION REPORT 50-302/2003-02
Dear Mr. Young:
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 Crystal River Nuclear Plant during the weeks of May 5, 2003, and May 19, 2003. 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 February 6, 2003, Mr. Moorman of my staff, and
Mr. Sid Powell 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 March 31, 2003
- Onsite inspection weeks: May 5, 2003 and May 19, 2003
The purpose of the information gathering visit is to obtain information and documentation
outlined in the enclosure needed to support the inspection. Mr. Walter 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.
FPC 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.: 50-302
License Nos.: DPR-72
Enclosure: Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl:
Daniel L. Roderick
Director Site Operations
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Jon A. Franke
Plant General Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Richard L. Warden
Manager Nuclear Assessment
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
Donald L. Taylor
Manager Support Services
Crystal River Nuclear Plant (NA2C)
15760 W. Power Line Street
Crystal River, FL 34428-6708
(cc w/encl contd - See page 3)
FPC 3
(cc w/encl contd)
R. Alexander Glenn
Associate General Counsel (MAC - BT15A)
Florida Power Corporation
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
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
Chairman
Board of County Commissioners
Citrus County
110 N. Apopka Avenue
Inverness, FL 36250
Jim Mallay
Framatome Technologies
Electronic Mail Distribution
Distribution w/encl:
J. Goshen, NRR
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
OFFICE RII:DRS RII:DRP
SIGNATURE MOORMAN MUNDAY
NAME Moorman Munday
DATE 2/10/2003 2/10/2003 2/ /2003 2/ /2003 2/ /2003 2/ /2003 2/ /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\ML030440333.wpd
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION
STEAM GENERATOR TUBE RUPTURE EVENT
Note: Electronic media is preferred if readily available. (The preferred file format is
searchable .pdf files on CDROM. The CDROM should be indexed to facilitate use.
Please provide 5 copies of each CDROM submitted.)
1. Design basis documents for the engineered safety features and other systems used to
mitigate the steam generator tube rupture (SGTR) event. Design basis documents for
the high, intermediate, and low voltage electrical systems that power these components.
Design basis documents for pressurizer relief valves, secondary system relief valves,
atmospheric dump valves and turbine bypass valves. Include performance history of
these valves for the past 10 years.
2. All procedures used to implement the mitigation strategy for the SGTR event. Include
alarm response procedures as well as emergency, abnormal, and normal operating
procedures as appropriate.
3. Procedures used for the operational testing of check valves in the auxiliary feedwater
(AFW) systems and portions of the emergency core cooling systems used during
mitigation of the SGTR event.
4. Surveillance procedures used to ensure the operability of equipment required by your
Technical Specifications that is used during the mitigation of the SGTR event.
5. Summary results of the steam generator (SG) in service inspection program.
6. List of temporary modifications and operator work-arounds involving any components
required for detection or mitigation of a SGTR event for the past 3 years.
7. List of major modifications to any components required for detection or mitigation of a
SGTR event completed in the past 5 years.
8. List of deferred modifications for any components required for detection or mitigation of
a SGTR event.
9. System description and operator training modules for the SGTR event.
10. List of operating experience program evaluations of industry, vendor, or NRC generic
issues related to a SGTR event.
11. Procedures used to sample the reactor coolant system during a SGTR event.
12. Calibration and functional testing procedures for the main steam line, condenser air
ejector, and steam generator blowdown. radiation monitoring instrumentation.
Enclosure
2
13. Calculations used to support the set points in Emergency Operating Procedures for a
SGTR event.
14. Performance history of valves or support equipment used to isolate SGs in the event of
a tube rupture.
15. Calibration and functional test procedures of instruments used to monitor reactor coolant
system (RCS) pressure, pressurizer level and pressure, SG level and pressure, hot and
cold leg temperature, subcooling monitor, feedwater flow, steam flow, core exit
temperature, high pressure injection (HPI) flow, low pressure injection 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.
16. P&IDs for RCS, HPI, SI, AFW, chemical and volume control system, main steam and
other systems used to mitigate the SGTR event. P&IDs for the high, intermediate, and
low voltage electrical systems which supply power to these components. (Paper copies
are preferred for these.)
17. Electrical schematic showing start circuit for the AFW pumps. (Paper copies are
preferred for these.)
18. Test procedures for the primary and secondary system safety relief valves including any
position indications and code safety valves.
19. Loop uncertainly calculations for SG level, pressurizer pressure and level, and RCS
pressure.
20. Test procedures for any defeat switches associated with AFW starting/control logic, if
applicable.
21. Instrument loop diagrams for items identified in Number 16 above. (Paper copies are
preferred for these.)
22. Probabilistic risk assessment event tree for the SGTR event. A list of PRA identified
system dependencies and success criteria for systems used to mitigate a steam
generator tube rupture.
23. System health reports and all performance monitoring information for systems used to
detect and mitigate the SGTR event and their power supply systems.
24. A list of Problem Evaluation Reports and non-routine work requests initiated since 1998
affecting the systems used to detect and mitigate the SGTR event.
25. Maintenance Rule performance criteria for systems used to detect and mitigate the
SGTR event and their electrical power systems. A list of maintenance rule failures of
equipment and their power supplies that are used to detect or mitigate the SGTR event.
Enclosure
3
26. Key electrical single line diagrams of the high, intermediate, and low voltage alternating
current systems and of the direct current power systems that provide power for the
pumps, valves, and instrumentation and control circuits associated with the systems that
accomplish the SGTR mitigation strategy. (Paper copies are preferred for these.)
27. Provide a list of equipment used to mitigate a SGTR that changes state or is manually
manipulated during implementation of the SGTR mitigation strategy. Provide equipment
failure rates over the past 10 years for these components.
28. Plant Technical Specifications, Bases, and Technical Requirements Manual
29. A current copy of the Updated Final Safety Analysis Report.
Enclosure