ML021910237
| ML021910237 | |
| Person / Time | |
|---|---|
| Site: | Summer  (NPF-012) |
| Issue date: | 07/09/2002 |
| From: | Payne D Division Reactor Projects II |
| To: | Byrne S South Carolina Electric & Gas Co |
| References | |
| IR-02-007 | |
| Download: ML021910237 (6) | |
See also: IR 05000395/2002007
Text
South Carolina Electric & Gas Company
ATTN:
Mr. Stephen A. Byrne
Senior Vice President, Nuclear Operations
Virgil C. Summer Nuclear Station
P. O. Box 88
Jenkinsville, SC 29065
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION - NOTIFICATION OF SAFETY
SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION
(NRC INSPECTION REPORT NO. 50-395/02-07)
Dear Mr. Byrne:
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 Virgil C. Summer Nuclear Station during September 23-27, 2002 and October 7-11, 2002.
A team of five inspectors will perform the inspection. The inspection team will be led by
Mr. F. Jape, a Senior Reactor Inspector from the NRC Region II Office. The inspection will be
conducted in accordance with baseline Inspection Procedure 71111.21, Safety System Design
and Performance Capability.
The inspection objective will be to evaluate the capability of the plant and installed equipment to
mitigate a small break loss of coolant accident. We will evaluate the capability of the high
pressure injection system and support systems, as well as other related systems, to perform
the functions required to mitigate a small break loss of coolant accident event.
During a telephone conversation on July 3, 2002, Mr. F. Jape of my staff, and Mr. Melvin N.
Browne 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 July 29, 2002, and August 2, 2002,
Onsite inspection: September 23-27, 2002 and October 7-11, 2002
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. F. Jape during the information gathering visit to
review PRA data and identify risk significant components which will be examined during the
inspection. Please contact Mr. F. Jape 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.
SCE&G
22
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 organization 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 me at (404) 562-4669, or Mr. F. Jape at
(404) 562-4541.
Sincerely,
/original signed by J. Moorman for: RA/
D. Charles Payne, Acting Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-395
License No. NPF-12
Enclosure:
Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl:
R. J. White
Nuclear Coordinator Mail Code 802
S.C. Public Service Authority
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
Kathryn M. Sutton, Esq.
Winston and Strawn
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
(cc w/encl contd - See page 3)
SCE&G
33
(cc w/encl contd)
Gregory H. Halnon, General Manager
Nuclear Plant Operations (Mail Code 303)
South Carolina Electric & Gas Company
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
Melvin N. Browne, Manager
Nuclear Licensing & Operating
Experience (Mail Code 830)
Virgil C. Summer Nuclear Station
Electronic Mail Distribution
Distribution w/encl:
G. Edison, NRR
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
jape
jape for
landis
NAME
JAPE
ROGERS
LANDIS
DATE
7/9/2002
7/9/2002
7/9/2002
7/ /2002
7/ /2002
7/ /2002
7/ /2002
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML021910237.wpd
ENCLOSURE
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION
SMALL BREAK LOCA EVENT
Note: Electronic media is preferred if readily available (i.e., on computer disc).
1.
Site specific administrative procedures related to standard operation, abnormal
operation, and emergency operation of the charging pump system, including support
systems, and other related systems during a small break loss of coolant accident
(LOCA). Other related systems include, but may not be limited to the emergency power
source, other portions of the emergency core cooling system ECCS (e.g. the
accumulator flooding system, residual heat removal pumps, and containment building
sumps), the service water system, and the instrument air system.
2.
Design criteria (i.e., design basis documents) for the ECCS components and other
related systems.
3.
Charging pumps Technical Specification requirements and a list of associated
surveillance test/calibration procedures for the system and related systems.
4.
Charging pumps, and other related systems, piping and instrumentation drawings, one-
line diagrams; electrical schematics, and wiring and logic diagrams.
5.
A list of engineering calculations (Electrical, Instrumentation and Controls and
Mechanical/Nuclear) applicable to the ECCS components, and other related systems.
6.
A list of plant modifications to the ECCS, and other related systems, implemented since
1992.
7.
List of current open temporary modifications and operator work arounds involving
operation of the ECCS components and the other related systems.
8.
List of Problem Investigation Process Reports (PIPs) initiated since 1992 affecting the
ECCS components, and other related systems.
9.
Summary of corrective maintenance activities, including the maintenance rule event log,
performed on ECCS components and other related systems in the past 12 months.
10.
An index of drawings for the ECCS, and other related systems.
1.
Self-assessment performed on ECCS and other related systems in the last 24 months.
12.
System description and operator training modules for the ECCS and other related
systems.
13.
Strategy for handling a small break LOCA.
2
ENCLOSURE
14.
List of Operating Experience Program evaluations of industry, vendor, or NRC generic
issues related to the ECCS components for the past 3 years.
15.
List of valves in the ECCS required to change position for a small break LOCA.
16.
List of instrument setpoint changes affecting the ECCS and related systems initiated
since 1992. Include the number and title, date, brief description, and corresponding
calculation number.
17.
PRA Fault Tree Data for the ECCS.
18.
PRA/Risk Achievement Worth (RAW) listing for the ECCS, and related support systems,
evaluated for failure of the ECCS components.
19.
PRA Event Tree for the small break LOCA initiating event.
20.
A list of PRA system dependencies and success criteria for ECCS, and its support
systems.