ML033250547
| ML033250547 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/19/2003 |
| From: | Ogle C NRC/RGN-II/DRS/EB |
| To: | Beasley J Southern Nuclear Operating Co |
| References | |
| IR-04-006 | |
| Download: ML033250547 (6) | |
See also: IR 05000348/2004006
Text
November 19, 2003
Southern Nuclear Operating Company, Inc.
ATTN: Mr. J. B. Beasley, Jr.
Vice President
P. O. Box 1295
Birmingham, AL 35201-1295
SUBJECT:
NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - SAFETY
SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION - NRC
INSPECTION REPORT 05000348/2004006 AND 05000364/2004006
Dear Mr. Beasley:
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 Joseph M. Farley Nuclear Plant during the weeks of January 26-30, 2004, and February
9-13, 2004. A team of six 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
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 steam generator tube rupture event. Procedures which direct the mitigating actions for this
event will also be evaluated.
During a telephone conversation on November 19, 2003, Mr. Thomas of my staff, and
Mr. Phil Crone 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 5-9, 2004
Onsite inspection weeks: January 26-30, 2004 and February 9-13, 2004
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, 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.
2
SNC, Inc.
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 2.790 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/
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-348, 50-364
Enclosure:
Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl.:
M. J. Ajluni, Licensing
Services Manager, B-031
Southern Nuclear Operating
Company, Inc.
Electronic Mail Distribution
D. E. Grissette
General Manager, Farley Plant
Southern Nuclear Operating
Company, Inc.
Electronic Mail Distribution
J. D. Woodard
Executive Vice President
Southern Nuclear Operating
Company, Inc.
Electronic Mail Distribution
(cc w/encl contd - See page 3)
3
SNC, Inc.
(cc w/encl contd)
State Health Officer
Alabama Department of Public Health
RSA Tower - Administration
Suite 1552
P. O. Box 303017
Montgomery, AL 36130-3017
M. Stanford Blanton
Balch and Bingham Law Firm
P. O. Box 306
1710 Sixth Avenue North
Birmingham, AL 35201
William D. Oldfield
Quality Assurance Supervisor
Southern Nuclear Operating Company
Electronic Mail Distribution
Distribution w/encl:
F. Rinaldi, NRR
L. Slack, RII EICS
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
RA
NAME
MThomas
JMoorman
BBonser
DATE
11/19/2003
11/19/2003
11/19/2003
11/ /2003
11/ /2003
11/ /2003
11/ /2003
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
PUBLIC DOCUMENT
YES
NO
OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML033250547.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. The CDROM should be indexed and hyperlinked to
facilitate ease of use. Please provide 6 copies of each CDROM submitted. 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 and other systems used to
mitigate the steam generator tube rupture (SGTR) event. Design basis documents for
the high, intermediate, and low voltage electrical systems that power these components.
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.
Piping and instrumentation drawings (P&IDs) for the reactor coolant system (RCS), high
pressure injection (HPI), safety injection (SI), auxiliary feedwater (AFW), chemical and
volume control system, main steam and other systems used to mitigate the SGTR
event. (Two paper copies are preferred for these)
3.
All procedures used to implement the mitigation strategy for the SGTR 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.
4.
Procedures used for the operational testing of check valves in the AFW system and
portions of the emergency core cooling systems used during mitigation of the SGTR
event.
5.
Surveillance procedures used to ensure the operability of equipment required by your
Technical Specifications that is used during the mitigation of the SGTR event.
6.
Summary results of the steam generator (SG) in-service inspection program.
7.
List of all temporary modifications and operator work-arounds (for the past 3 years)
involving any components required for detection or mitigation of a SGTR event.
8.
A list of major modifications completed in the past 5 years to components or systems
required for detection or mitigation of a SGTR event.
9.
A list of deferred modifications for any components required for detection or mitigation
of a SGTR event.
10.
System descriptions and operator training modules for the SGTR event and the systems
used to mitigate the event.
2
11.
List of operating experience program evaluations of industry, vendor, or NRC generic
issues related to a SGTR event.
12.
Procedures used to sample the RCS and SGs during a SGTR event.
13.
Calibration and functional testing procedures for radiation monitoring instrumentation
used to detect a SGTR event (e.g. main steam line, condenser air ejector, steam
generator blowdown, etc.).
14.
Calculations used to support the set points in EOPs for a SGTR event.
15.
Performance history of valves or support equipment used to isolate SGs in the event of
a tube rupture.
16.
Calibration and functional test procedures for instruments used to monitor RCS
pressure, pressurizer level and pressure, SG level and pressure, RCS hot leg and cold
leg temperatures, RCS subcooling, feedwater flow, steam flow, core exit temperature,
HPI flow, low pressure injection flow, refueling water storage tank level, pressurizer
heater status, safety relief valve position indicator, AFW flow, condensate storage tank
(CST) level, makeup flow, and letdown flow.
17.
Key electrical one-line drawings depicting the high, intermediate, and low voltage
alternating current systems and of the 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. (Two paper copies are
preferred)
18.
Probabilistic risk assessment (PRA) event tree for the SGTR event. A list of PRA
identified system dependencies and success criteria for systems used to mitigate a
steam generator tube rupture. Provide SGTR cutsets and risk achievement worths for
those basic events (only assuming a SGTR initiating event).
19.
A brief description of the mitigation strategy for handling the SGTR event, including
operator actions and equipment used.
20.
System health reports and/or other performance monitoring information for systems
used to detect and mitigate the SGTR event and their power supply systems.
21.
A list of condition reports and non-routine work requests initiated since 1998 related to:
1) the systems used to detect and mitigate the SGTR event and 2) inservice inspection
activities of steam generator tubes.
22.
Quality Assurance audits, self-assessments, and third party assessments performed on
the systems used to detect and mitigate a SGTR event.
23.
Maintenance Rule performance criteria for systems used to detect and mitigate the
SGTR event and their electrical power systems. A list of maintenance rule failures of
equipment and their power supplies that are used to detect or mitigate the SGTR event.
3
24.
Provide a list of equipment used to mitigate a SGTR that changes state or is manually
manipulated during implementation of the SGTR mitigation strategy and the indications
used by plant operators to make decisions during the event.
25.
Plant Technical Specifications, Bases, and Technical Requirements Manual
26.
A current copy of the Updated Final Safety Analysis Report.
27.
Procedures that provide implementation guidance for the following programs: Corrective
Action Program, Maintenance Rule Program, and Operating Experience Program.