ML051570033
| ML051570033 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/03/2005 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Gasser J Southern Nuclear Operating Co |
| References | |
| IR-05-006 | |
| Download: ML051570033 (6) | |
See also: IR 05000424/2005006
Text
June 3, 2005
Southern Nuclear Operating Company, Inc.
ATTN: Mr. J. T. Gasser, Vice President
P. O. Box 1295
Birmingham, AL 35201-1295
SUBJECT:
NOTIFICATION OF VOGTLE NUCLEAR PLANT - SAFETY SYSTEM DESIGN
AND PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION
REPORT 50-424,425/2005006
Dear Mr. Gasser:
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 Vogtle Nuclear Plant during the weeks of August 15-19, 2005 and August 29-September
2, 2005. A team of five inspectors will perform this inspection. The inspection team will be led
by Mr. Caswell Smith, a Senior Reactor Inspector from the NRC Region II Office. This biennial
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 May 26, 2005, Mr. Smith of my staff, and
Mr. Ken Lowery 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 18, 2005
Onsite inspection weeks: August 15 and August 29, 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. Smith 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. Smith 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.
SNOC
2
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Smith at (404) 562-4630 or me at
(404) 562-4605.
In accordance with 10 CFR 2.790 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 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.: 50-424 and 50-425
License Nos.: NPF-68 and NPF-81
Enclosure:
Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl: (See page 3)
SNOC
3
cc w/encl:
J. T. Gasser
Executive Vice President
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
W. F. Kitchens
General Manager, Plant Vogtle
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
N. J. Stringfellow
Manager-Licensing
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution
Director, Consumers' Utility Counsel
Division
Governor's Office of Consumer Affairs
2 M. L. King, Jr. Drive
Plaza Level East; Suite 356
Atlanta, GA 30334-4600
Office of the County Commissioner
Burke County Commission
Waynesboro, GA 30830
Director, Department of Natural Resources
205 Butler Street, SE, Suite 1252
Atlanta, GA 30334
Manager, Radioactive Materials Program
Department of Natural Resources
Electronic Mail Distribution
Attorney General
Law Department
132 Judicial Building
Atlanta, GA 30334
Laurence Bergen
Oglethorpe Power Corporation
Electronic Mail Distribution
Resident Manager
Oglethorpe Power Corporation
Alvin W. Vogtle Nuclear Plant
Electronic Mail Distribution
Arthur H. Domby, Esq.
Troutman Sanders
Electronic Mail Distributioin
Senior Engineer - Power Supply
Municipal Electric Authority
of Georgia
Electronic Mail Distribution
Reece McAlister
Executive Secretary
Georgia Public Service Commission
244 Washington Street, SW
Atlanta, GA 30334
_________________________
OFFICE
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
/RA/
/RA/
/RA/
NAME
CSmith
MWidmann
COgle
DATE
5/31/05
6/2/05
6/3/05
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
INFORMATION REQUEST FOR VOGTLE 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 some one 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 a loss of coolant 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 loss of coolant
accidents (LOCA) 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 set-point document as well as calculations used to
support the set-points in EOPs for the LOCA event.
3.
Piping and instrumentation drawings (PI&Ds) for the ECCS and other systems used to
mitigate the LOCA event. Two paper copies are preferred for these.
4.
List of surveillance procedures used to ensure the operability of the equipment required
by your Technical Specifications that is used during the mitigating 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 three years.
7.
System descriptions and operator training modules for the LOCA event, the ECCS, and
other systems used to mitigate the event. Include a brief overview of the LOCA 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 LOCA event within the last 2 years.
9.
A list of major modifications completed in the past five years to the ECCS and other
systems used to mitigate a LOCA event.
2
Enclosure
10.
Calibration and functional test procedures for instruments used to monitor reactor
coolant system (RCS) pressure, pressurizer level, RCS hot and cold leg temperatures,
RCS subcooling, high pressure coolant injection flow, low pressure coolant injection
flow, borated water storage tank level, auxiliary feedwater flow, condensate storage tank
level, and containment sump level.
11.
Quality assurance audits and/or self-assessments performed on the ECCS and other
systems used to mitigate a LOCA in the past 24 months.
12.
Plant Technical Specifications, Bases, and Technical Requirements Manual.
13.
A current copy of the Updated Final Safety Analysis Report.
14.
Procedures that provide implementation guidance for the following programs: Corrective
Action Program, Maintenance Rule Program, Design Control Program, and Operating
Experience Program.
15.
Probabilistic risk assessment (PRA) event tree for the LOCA event. A list of PRA
identified system dependencies and success criteria for the ECSS 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).
16.
System health reports and/or other performance monitoring information for the ECCS
and other systems used to mitigate a LOCA event.
17.
A list of condition reports and non-routine work requests initiated since 1999 affecting
the ECCS and other systems used to mitigate a LOCA event.
18.
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.
19.
Key one line diagrams for the alternating current and the 125 VDC 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 V motor
control centers. ( Paper copies are preferred for these).
20.
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.