ML050540383
| ML050540383 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/23/2005 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Young D Florida Power Corp |
| References | |
| IR-05-006 | |
| Download: ML050540383 (6) | |
See also: IR 05000302/2005006
Text
February 23, 2005
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 05000302/20050006
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 April 25 - 29, 2005 and May 9 -13, 2005.
A team of five inspectors will perform this inspection. The inspection team will be led by
Mr. Larry Mellen, a Senior Reactor Inspector from the NRC Region II Office. This 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 loss of coolant accident. Procedures which direct the mitigating actions for this event will also
be evaluated.
During a telephone conversation on February 23, 2005, Mr. Mellen of my staff, and
Mr. Dennis Herrin, Lead Engineer, Licensing and Regulatory Programs, 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 28, 2005
- Onsite inspection weeks: April 25 - 29, 2005 and May 9 -13, 2005
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. Mellen 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. Mellen 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, Mr. Mellen 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
FPC 2
knowledgeable plant engineering and licensing personnel to serve as points of contact during
the inspection.
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Mellen at (404) 562-4531 or me at
(404) 562-4605.
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 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
cc w/encl contd: - (See page 3)
FPC 3
cc w/encl contd:
Michael J. Annacone
Engineering Manager
Crystal River Nuclear Plant (NA2C)
Electronic Mail Distribution
R. Alexander Glenn
Associate General Counsel (MAC - BT15A)
Florida Power Corporation
Electronic Mail Distribution
Steven R. Carr
Associate General Counsel - Legal Dept.
Progress Energy Service Company, LLC
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
_________________________
OFFICE RII:DRS
SIGNATURE LSM
NAME LMellen
DATE 2/23/2005 2/ /2005 2/ /2005 2/ /2005 2/ /2005 2/ /2005 2/ /2005
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
INFORMATION REQUEST FOR THE CRYSTAL RIVER 3 SAFETY SYSTEM DESIGN
AND PERFORMANCE CAPABILITY INSPECTION
LOSS OF COOLANT ACCIDENT (Small Break, Large Break, Inter-System)
(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. Design basis documents for the engineered safety features (ESF) and emergency core
cooling systems (ECCS) used to mitigate the loss of coolant accident (LOCA) event.
Design basis documents for the high, medium, and low voltage electrical systems that
power the ESF and ECCS components/systems.
2. All procedures used to implement the mitigation strategy for the LOCA event. Include
alarm response procedures as well as normal, abnormal, and emergency operating
procedures (EOPs) as appropriate. Also include the EOP users guide and EOP setpoint
document as well as calculations used to support the setpoints in EOPs for the LOCA
event.
3. Piping and instrumentation drawings (P&IDs) for the ECCS and other systems used to
mitigate the LOCA event. Two (2) paper copies are preferred for these.
4. List of surveillance procedures used to ensure the operability of equipment required by
your Technical Specifications that is used during the mitigation of the LOCA event.
5. List of engineering calculations (electrical, mechanical/nuclear, instrumentation and
controls) applicable to the ECCS components and other related systems used for a
LOCA event.
6. List of temporary modifications and operator work-arounds involving any components
required for mitigation of a LOCA event for the past 3 years
7. System descriptions and operator training modules for the LOCA event, the ECCS, and
other systems used to mitigate the event. Include a brief overview of the LOCA event
mitigation strategy, including operator actions and equipment used.
8. List of operating experience program evaluations of industry, vendor, or NRC generic
issues related to a LOCA event.
9. A list of major modifications completed in the past five years to the ECCS and other
systems used to mitigate a LOCA event.
Enclosure
2
10. Calibration and functional test procedures for instruments used to monitor Reactor
Coolant System (RCS) pressure, pressurizer level, RCS hot and cold leg temperatures,
RCS subcooling, high pressure coolant injection flow, low pressure coolant injection
flow, borated water storage tank level, auxillary feedwater flow, condensate storage
tank level, and containment sump level.
11. Quality Assurance audits and/or self assessments performed on the ECCS and other
systems used to mitigate a LOCA in the past 24 months.
12. Plant Technical Specifications, Bases, and Technical Requirements Manual.
13. A current copy of the Updated Final Safety Analysis Report.
14. Procedures that provide implementation guidance for the following programs: Corrective
Action Program, Maintenance Rule Program, Design Control Program, and Operating
Experience Program.
15. Probabilistic risk assessment (PRA) event tree for the LOCA event. A list of PRA
identified system dependencies and success criteria for the ECCS and other systems
used to mitigate a LOCA. Provide LOCA cutsets and risk achievement worths for those
basic events (assuming only a LOCA initiating event).
16. System health reports and/or other performance monitoring information for the ECCS
and other systems used to mitigate a LOCA event.
17. A list of condition reports and non-routine work requests initiated since 1999 affecting
the ECCS and other systems used to detect and mitigate a LOCA event.
18. Maintenance Rule performance criteria for systems used to detect and mitigate a LOCA
event. A list of maintenance rule failures of equipment used to detect or mitigate a
LOCA event.
19. Key one line diagrams for the alternating current and the 125-volt direct current systems
that provide power for the pumps, valves, and instrumentation and control circuits
associated with the ECCS and other systems used to mitigate the LOCA. Also, include
the one line diagrams for the Class 1E medium and low voltage switchgear and the 480
volt motor control centers. (Paper copies are preferred for these)
20. Provide a list of valves used to mitigate a LOCA that are required to change position or
are manually manipulated during implementation of the LOCA mitigation strategy.
Provide equipment failure rates over the past 10 years for these components.
Enclosure