ML033250418
| ML033250418 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/20/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Gordon Peterson Duke Energy Corp |
| References | |
| IR-04-002 | |
| Download: ML033250418 (6) | |
See also: IR 05000369/2004002
Text
November 20, 2003
Duke Energy Corporation
ATTN: Mr. G. Peterson
Vice President
McGuire Nuclear Station
12700 Hagers Ferry Road
Huntersville, NC 28078-8985
SUBJECT:
NOTIFICATION OF McGUIRE NUCLEAR STATION - SAFETY SYSTEM
DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC
INSPECTION REPORT 05000369/2004002 AND 05000370/2004002
Dear Mr. Peterson:
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 McGuire Nuclear Station during the weeks of January 25, 2004, and February 8, 2004. A
team of five inspectors will perform this inspection. The inspection team will be led by
Mr. Norman Merriweather, a Senior Reactor Inspector from the NRC Region II Office. This
biennial inspection will be conducted in accordance with baseline pilot inspection program
Attachment 71111.21, 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 November 13, 2003, Mr. Merriweather of my staff, and
Ms. Kay Crane 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 January 4, 2004
- Onsite inspection weeks: January 25, 2004, and February 8, 2004.
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. Merriweather 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. Merriweather 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. Merriweather at (404) 562-4627 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.: 50-369, 50-370
Enclosure:
Information Request for the Safety System Design and Performance Capability
Inspection
cc w/encl:
C. J. Thomas
Regulatory Compliance Manager (MNS)
Duke Energy Corporation
Electronic Mail Distribution
M. T. Cash, Manager
Regulatory Issues & Affairs
Duke Energy Corporation
526 S. Church Street
Charlotte, NC 28201-0006
Lisa Vaughn
Legal Department (PB05E)
Duke Energy Corporation
422 South Church Street
P. O. Box 1244
Charlotte, NC 28201-1244
(cc w/encl contd - See page 3)
3
(cc w/encl contd)
Anne Cottingham
Winston & Strawn LLP
Electronic Mail Distribution
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environmental
Health & Natural Resources
Electronic Mail Distribution
County Manager of Mecklenburg County
720 East Fourth Street
Charlotte, NC 28202
Peggy Force
Assistant Attorney General
N. C. Department of Justice
Electronic Mail Distribution
Distribution w/encl:
R. Martin, NRR
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
(SEE PREVIOUS PAGE FOR CONCURRENCE)
OFFICE
RII:DRS
RII:DRP
SIGNATURE
RA
NAME
MERRIWEATHE R. HAAG
DATE
11/17/2003
11/20/2003
11/ /2003
11/ /2003
11/ /2003
11/ /2003
11/ /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\\ML033250418.wpd
ENCLOSURE
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION
MCGUIRE STEAM GENERATOR TUBE RUPTURE EVENT
Note: Electronic media is the preferred if readily available. (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.
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. Also include the EOP users guide and EOP setpoint
document.
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.
Summary results of the steam generator (SG) in service inspection program.
5.
A list of all temporary modifications and operator work-arounds for the past 3 years.
6.
A list of major modifications completed in the past 5 years to components or systems
required for detection or mitigation of a SGTR event.
7.
A list of deferred modifications for any components required for detection or mitigation
of a SGTR event.
8.
System descriptions and operator training modules for the SGTR event and the systems
used to mitigate the event.
9.
Procedures used to sample the reactor coolant system and the steam generators during
a SGTR event.
10.
Calibration and functional testing procedures for radiation monitoring instrumentation
used to detect a SGTR event ( e.g. main steam line, condenser air ejector, and steam
generator blowdown).
11.
Performance history of valves or support equipment used to isolate SGs in the event of
a tube rupture.
2
ENCLOSURE
12.
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.
13.
P&IDs for RCS, HPI, SI, AFW, chemical and volume control system, main steam and
other systems used to mitigate the SGTR event. (Paper copies are preferred for these.)
14.
Key electrical one-line drawings depicting 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.)
15.
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.
16.
System health reports and/or other performance monitoring information for systems
used to detect and mitigate the SGTR event and their power supply systems.
17.
A list of non-routine work requests initiated since 1998 related to: 1) the systems used to
detect and mitigate the SGTR event and 2) inservice inspection activities of steam
generator tubes.
18.
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.
19.
Provide a list of equipment used to mitigate a SGTR that changes state or is manually
manipulated during implementation of the SGTR mitigation strategy and the indications
used by plant operators to make decisions during the event.
20.
Plant Technical Specifications, Bases, and Technical Requirements Manual
21.
A current copy of the Updated Final Safety Analysis Report.
22.
Procedures that provide implementation guidance for the following programs: Corrective
Action Program, Maintenance Rule Program, and Operating Experience Program.