ML043420135
| ML043420135 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/07/2004 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Moyer J Carolina Power & Light Co |
| References | |
| IR-05-006 | |
| Download: ML043420135 (5) | |
See also: IR 05000261/2005006
Text
December 7, 2004
Carolina Power & Light Company
ATTN: Mr. J. W. Moyer
Vice President
H. B. Robinson Steam Electric Plant Unit 2
3581 West Entrance Road
Hartsville, SC 29550
SUBJECT:
NOTIFICATION OF H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 -
SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION -
NRC INSPECTION REPORT 05000261/2005006
Dear Mr. Moyer:
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 H. B. Robinson Steam Electric Plant Unit 2 during the weeks of February 14-18, 2005, and
February 28 - March 4, 2005. A team of five inspectors will perform this inspection. The
inspection team will be led by Mr. McKenzie Thomas, 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 November 30, 2004, Mr. Thomas of my staff, and
Mr. Chuck Baucom, Supervisor, 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 January 17, 2005
Onsite inspection: February 14-18, 2005 and February 28 - March 4, 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. Thomas 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. Thomas 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. Thomas 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
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. Thomas at (404) 562-4673 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 No.: 50-261
License No.: DPR-23
Enclosure:
Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl:
William G. Noll
Director, Site Operations
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
Daniel G. Stoddard
Plant General Manager
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
Chris L. Burton, Manager
Performance Evaluation and
Regulatory Affairs CPB 9
Electronic Mail Distribution
cc w/encl contd - (See page 3)
3
(cc w/encl contd:)
C. T. Baucom, Supervisor
Licensing/Regulatory Programs
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
J. F. Lucas, Manager
Support Services - Nuclear
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
Henry J. Porter, Director
Div. of Radioactive Waste Mgmt.
Dept. of Health and Environmental
Control
Electronic Mail Distribution
R. Mike Gandy
Division of Radioactive Waste Mgmt.
S. C. Department of Health and
Environmental Control
Electronic Mail Distribution
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environment,
Health and Natural Resources
Electronic Mail Distribution
Steven R. Carr
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
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
Enclosure
INFORMATION REQUEST FOR THE H.B. ROBINSON 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 (EOP) 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.
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.
10.
Calculations used to support the setpoints in EOPs for a LOCA event.
11.
A brief description of the mitigation strategy for handling a LOCA event, including
operator actions and equipment used.
2
Enclosure
12.
Calibration and functional test procedures for instruments used to monitor RCS
pressure, pressurizer level, RCS hot and cold leg temperatures, RCS subcooling, HPI
flow, LPI flow, RWST level, AFW flow, CST level, and containment sump level.
13.
Quality Assurance audits and/or self assessments performed on the ECCS and other
systems used to mitigate a LOCA in the past 24 months.
14.
Plant Technical Specifications, Bases, and Technical Requirements Manual.
15.
A current copy of the Updated Final Safety Analysis Report.
16.
Procedures that provide implementation guidance for the following programs: Corrective
Action Program, Maintenance Rule Program, Design Control Program, and Operating
Experience Program.
17.
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).
18.
System health reports and/or other performance monitoring information for the ECCS
and other systems used to mitigate a LOCA event.
19.
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.
20.
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.
21.
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)
22.
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.