ML052090202
| ML052090202 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/28/2005 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Gannon C Carolina Power & Light Co |
| References | |
| IR-05-007 | |
| Download: ML052090202 (6) | |
See also: IR 05000324/2005007
Text
July 28, 2005
Carolina Power and Light Company
ATTN: Mr. C. J. Gannon
Vice President
Brunswick Steam Electric Plant
P. O. Box 10429
Southport, NC 28461
SUBJECT:
NOTIFICATION OF BRUNSWICK STEAM ELECTRIC PLANT - SAFETY
SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION -
NRC INSPECTION REPORT 50-325/2005-07 AND 50-324/2005-07
Dear Mr. Keenan:
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 Brunswick Nuclear Plant during the weeks of October 31 - November 4, 2005 and
November 14 - 18, 2005. A team of five inspectors will perform this inspection. The inspection
team will be led by Mr. Larry Mellen, a Team Leader 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, respond to,
and mitigate a loss of residual heat removal (RHR) and RHR service water (RHRSW). The
inspection will also focus on events that may contribute to a loss of RHR and RHRSW. The
inspection will also evaluate personnel response to these events.
During a telephone conversation on July 27, 2005, Mr. Mellen of my staff and Mr. Charles
Elberfeld 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 3, 2005
Onsite inspection: October 31, 2005 and November 14, 2005
The purpose of the information gathering visit is to obtain information and documentation
outlined in the enclosure needed to support the inspection. Mr. Rudolph Bernhard, 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
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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.
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 by L. R. Moore for\\
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-325, 50-324
Enclosure:
Information Request for the Safety System Design
and Performance Capability Inspection
cc w/encls:-(See page 3)
3
cc w/encl:
T. P. Cleary, Director
Site Operations
Brunswick Steam Electric Plant
Progress Energy Carolinas, Inc.
Electronic Mail Distribution
Benjamin C. Waldrep
Plant Manager
Brunswick Steam Electric Plant
Carolina Power & Light Company
Electronic Mail Distribution
James W. Holt, Manager
Performance Evaluation and
Regulatory Affairs PEB 7
Carolina Power & Light Company
Electronic Mail Distribution
Edward T. O'Neil, Manager
Support Services
Carolina Power & Light Company
Brunswick Steam Electric Plant
Electronic Mail Distribution
Lenny Beller, Supervisor
Licensing/Regulatory Programs
Carolina Power and Light Company
Electronic Mail Distribution
David T. Conley
Associate General Counsel - Legal Dept.
Progress Energy Service Company, LLC
Electronic Mail Distribution
John H. O'Neill, Jr.
Shaw, Pittman, Potts & Trowbridge
2300 N. Street, NW
Washington, DC 20037-1128
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environment
and Natural Resources
Electronic Mail Distribution
Peggy Force
Assistant Attorney General
State of North Carolina
Electronic Mail Distribution
Chairman of the North Carolina
Utilities Commission
c/o Sam Watson, Staff Attorney
Electronic Mail Distribution
Robert P. Gruber
Executive Director
Public Staff NCUC
4326 Mail Service Center
Raleigh, NC 27699-4326
Public Service Commission
State of South Carolina
P. O. Box 11649
Columbia, SC 29211
David R. Sandifer
Brunswick County Board of
Commissioners
P. O. Box 249
Bolivia, NC 28422
Warren Lee
Emergency Management Director
New Hanover County Department of
Emergency Management
P. O. Box 1525
Wilmington, NC 28402-1525
INFORMATION REQUEST FOR THE BRUNSWICK SAFETY SYSTEM DESIGN
AND PERFORMANCE CAPABILITY INSPECTION.
Residual Heat Removal (RHR) and RHR Service Water (RHRSW)
(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 RHR & RHRSW. Design basis documents for the
high, medium, and low voltage electrical systems that power RHR & RHRSW
components/systems.
2.
All procedures used to implement the mitigation strategy for the loss of RHR & RHRSW
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 systems used to mitigate the loss
of RHR & RHRSW 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 RHR & RHRSW
event.
5.
List of engineering calculations (electrical, mechanical/nuclear, instrumentation and
controls) applicable to the RHR & RHRSW components and other related systems used
for a loss of RHR & RHRSW event.
6.
List of temporary modifications and operator work-arounds involving any components
required for mitigation of a loss of RHR & RHRSW event for the past 3 years.
7.
System descriptions and operator training modules for the loss of RHR & RHRSW event
and other systems used to mitigate the event. Include a brief overview of the loss of
RHR & RHRSW 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 the loss of RHR & RHRSW event.
9.
A list of major modifications completed in the past five years to the components or
systems used to mitigate a RHR & RHRSW event.
10.
Quality Assurance audits and/or self assessments performed on the RHR & RHRSW
and other systems used to mitigate a loss of RHR & RHRSW in the past 24 months.
11.
Plant Technical Specifications, Bases, and Technical Requirements Manual.
2
12.
A current copy of the Updated Final Safety Analysis Report.
13.
Procedures that provide implementation guidance for the following programs:
Corrective Action Program, Maintenance Rule Program, Design Control Program, and
Operating Experience Program.
14.
Probabilistic risk assessment (PRA) event tree for the loss of RHR & RHRSW event. A
list of PRA identified system dependencies and success criteria for the ECCS and other
systems used to mitigate a loss of RHR & RHRSW. Provide the initiator summary
report, the importance measure report, and the top 500 cutsets report for both units for
the most current revision of your nominal maintenance PSA. If possible provide the risk
achievement worth measured with respect to your loss of nuclear service water, and
loss of normal service water initiators only (set all other initiators to false, solve, get new
importance measures for this solution). Provide the top 100 cutsets for the loss of
nuclear service water, and loss of normal service water initiators.
15.
System health reports and/or other performance monitoring information for the ECCS
and other systems used to mitigate a loss of RHR & RHRSW event.
16.
A list of condition reports and non-routine work requests initiated since 2000 affecting
the RHR & RHRSW and other systems used to detect and mitigate a loss of RHR &
RHRSW event.
17.
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.
18.
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 RHR & RHRSW and other systems used to mitigate the loss of RHR
& RHRSW. 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).
19.
Provide a list of valves used to mitigate a loss of RHR & RHRSW that are required to
change position or are manually manipulated during implementation of the loss of RHR
& RHRSW mitigation strategy. Provide equipment failure rates over the past 10 years
for these components.
_________________________
OFFICE
RII:DRS
RII:DRS
SIGNATURE
P.Fredickson
L.Mellen
NAME
/RA/
/RA/
DATE
7/28/2005
7/28/2005
7/ /2005
7/ /2005
7/ /2005
7/ /2005
7/ /2005
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO