ML023470094
| ML023470094 | |
| Person / Time | |
|---|---|
| Site: | Robinson  (DPR-023) |
| Issue date: | 12/12/2002 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Moyer J Carolina Power & Light Co |
| References | |
| IR-03-002 | |
| Download: ML023470094 (7) | |
See also: IR 05000261/2003002
Text
December 12, 2002
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 NUCLEAR PLANT - SAFETY SYSTEM
DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC
INSPECTION REPORT 50-261/2003-02
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 Nuclear Plant during the weeks of February 24-28, 2003, and March
10 -14, 2003. A team of five inspectors will perform this inspection. The inspection team will be
led by Mr. Robert Schin, 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 steam generator tube rupture event. Procedures which direct the mitigating actions for this
event will also be evaluated.
During a telephone conversation on December 10, 2002, Mr. Schin of my staff, and
Mr. Curt Castell 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 25, 2003
Onsite inspection: February 24-28, 2003 and March 10-14, 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. Schin 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. Schin 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. Schin 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. Schin (404) 562-4629 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: Walter Rogers for:/
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:
Chris L. Burton
Director, Site Operations
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
T. P. Cleary
Plant General Manager
Carolina Power & Light Company
H. B. Robinson Steam Electric Plant
Electronic Mail Distribution
Terry C. Morton, 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
B. L. Fletcher III, Manager
Regulatory Affairs
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
William D. Johnson
Vice President & Corporate Secretary
Carolina Power & Light Company
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
(cc w/encl contd - See page 4)
4
(cc w/encl contd)
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
Distribution w/encl:
R. Subbaratnam, NRR
RIDSNRRDIPMLIPB
PUBLIC
(*) = PER E-MAIL
OFFICE
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RII:DRS
RII:DRP
SIGNATURE
SCHIN
SCHIN FOR *
FREDRICKSON
NAME
RSCHIN
JMOORMAN
PFREDRICKSON
DATE
12/11/2002
12/12/2002
12/12/2002
12/ /2002
12/ /2002
12/ /2002
12/ /2002
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
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PUBLIC DOCUMENT
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OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML023470094.wpd
Enclosure
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.)
1.
Design basis documents for the engineered safety features used to mitigate the steam
generator tube rupture (SGTR) event. 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 detection and mitigation strategy for the SGTR
event. Include emergency, abnormal, annunciator response, and normal operating
procedures as appropriate.
3.
Procedures used for the operational testing of check valves in 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 are 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.
System description and operator training modules for a SGTR event.
8.
List of operating experience program evaluations of industry, vendor, or NRC generic
issues related to a SGTR event.
9.
Procedures used to sample the reactor coolant system during a SG tube leak or SGTR
event.
10.
Calibration and functional testing procedures for the main steam line radiation
monitoring instrumentation used to detect and mitigate a SGTR event.
11.
Calculations used to support the set points in Emergency Operating Procedures for a
SGTR event.
12.
Performance history of valves or support equipment used to isolate SGs in the event of
a tube rupture.
13.
Calibration and functional test procedures of instruments used to monitor reactor coolant
system (RCS) pressure, pressurizer level and pressure, SG level and pressure, RDS hot
and cold leg temperature, RCS subcooling monitor, feedwater flow, steam flow, core exit
temperature, high pressure injection (HPI) flow, low pressure injection flow, refueling
2
Enclosure
water storage tank level, pressurized heater status, safety relief valve position indicator,
auxiliary feedwater flow (AFW) flow, condensate storage tank (CST) level, makeup flow,
and letdown flow.
14.
P&IDs for RCS, HPI, SI, AFW, chemical and volume control system, main steam, and
electrical distribution system. (Paper copies are preferred for these)
15.
Electrical schematic showing start circuit for the AFW pumps. (Paper copies are
preferred for these)
16.
Test procedures for the primary and secondary system safety relief valves including any
position indications and code safety valves.
17.
Loop uncertainly calculations for SG level, pressurizer pressure and level, and RCS
pressure.
18.
Test procedures for any defeat switches associated with AFW starting logic.
19.
Instrument loop diagrams for items identified in Number 13 above. (Paper copies are
preferred for these)
20.
Probability Risk Assessment (PRA) Event tree for a SGTR event. A list of PRA
identified system dependencies and success criteria for systems used to mitigate a
steam generator tube rupture.
21.
System health reports and all performance monitoring information for systems used to
detect and mitigate a SGTR event.
22.
A list of Action Reports and non-routine work requests initiated since 1998 affecting the
systems used to detect and mitigate a SGTR event.
23.
Maintenance Rule performance criteria for systems used to detect and mitigate a SGTR
event. A list of maintenance rule failures of equipment used to detect or mitigate a
SGTR event.
24.
Key electrical single line diagrams of the alternating current and 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)
25.
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.