ML022190508
| ML022190508 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/06/2002 |
| From: | Payne D Division of Reactor Safety I |
| To: | Stall J Florida Power & Light Co |
| References | |
| IR-02-006 | |
| Download: ML022190508 (6) | |
See also: IR 05000250/2002005
Text
Florida Power and Light Company
ATTN: Mr. J. A. Stall, Senior Vice President
Nuclear and Chief Nuclear Officer
Chief Nuclear Officer
P. O. Box 14000
Juno Beach, FL 33408-0420
SUBJECT:
SAFETY SYSTEM DESIGN AND PERFORMANCE CAPABILITY INSPECTION
NRC INSPECTION REPORT NOS. 50-250/2002-06, 50-251/2002-06
Dear Mr. Stall:
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 Turkey Point facility during October - November, 2002. A team of five inspectors will
perform the inspection. The inspection team will be led by Mr. J. Lenahan, 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 emergency diesel generators
and support systems, as well as other related systems, to perform the functions required to
mitigate a loss of offsite power (LOOP)/station blackout (SBO) event.
During a telephone conversation on July 26, 2002, Mr. J. Lenahan of my staff, and
Mr. W. Parker 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 September 23, 2002
Onsite inspection: October 28 - November 1 and November 18 - 22, 2002
The purpose of the information gathering visit is to obtain information and documentation
outlined in the enclosure needed to support the inspection. Mr. W. Rogers, a Region II Senior
Reactor Analyst, will accompany Mr. Lenahan during the information gathering visit to review
PRA data and identify risk significant components which will be examined during the
inspection. Please contact Mr. Lenahan 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 reactor site access; and the availability of
knowledgeable plant engineering and licensing organization 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 me at (404) 562-4669, or Mr. Lenahan
at (404) 562-4625.
Sincerely,
/RA/
D. Charles Payne, Acting Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-250, 50-251
Enclosure:
Information Request for the Safety System Design and Performance Capability
Inspection: Loss of Offsite Power/Station Blackout Events
cc w/encl:
T. O. Jones
Plant General Manager
Turkey Point Nuclear Plant
Florida Power and Light Company
Electronic Mail Distribution
John P. McElwain
Site Vice President
Turkey Point Nuclear Plant
Florida Power and Light Company
9760 SW 344th Street
Florida City, FL 33035
Walter Parker
Licensing Manager
Turkey Point Nuclear Plant
Florida Power and Light Company
Electronic Mail Distribution
Don Mothena, Manager
Nuclear Plant Support Services
Florida Power & Light Company
Electronic Mail Distribution
(cc w/encl contd - See page 3)
3
(cc w/encl contd)
Rajiv S. Kundalkar
Vice President - Nuclear Engineering
Florida Power & Light Company
Electronic Mail Distribution
M. S. Ross, Attorney
Florida Power & Light Company
Electronic Mail Distribution
Jim Reed
Document Control Supervisor
Florida Power & Light Company
Electronic Mail Distribution
Attorney General
Department of Legal Affairs
The Capitol
Tallahassee, FL 32304
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
County Manager
Metropolitan Dade County
Electronic Mail Distribution
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
Curtis Ivy
City Manager of Homestead
Electronic Mail Distribution
Distribution w/encl: (See page 4)
4
Distribution w/encl:
E. Brown, NRR
RIDSNRRDIPMLIPB
PUBLIC
OFFICE
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
SCHIN FOR:
MOORMAN
WERT
NAME
LENAHAN
MOORMAN
WERT
DATE
8/1/2002
8/6/2002
8/6/2002
8/ /2002
8/ /2002
8/ /2002
8/ /2002
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\\ML022190508.wpd
Enclosure
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION:
LOSS OF OFFSITE POWER (LOOP)/STATION BLACKOUT (SBO) EVENTS
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 emergency diesel generators (EDGs),
including support systems, and other related systems during a loss of offsite power
and/or a station blackout. Other related systems include, but may not be limited to the
station transformers, the 480V and 4.16 KV buses, station batteries, ventilation, starting
air, EDG cooling water systems, and auxiliary feedwater system (turbine driven auxiliary
feedwater (TDAFW) pump, including water source).
2.
Design criteria (i.e., design basis documents) for the EDGs, in addition to support
systems and interfaces for the EDGs, the 480V and 4.16 KV electrical systems, and
station batteries.
3.
Technical Specification requirements and a list of associated surveillance test/calibration
procedures for the EDG and related systems.
4.
Copies of applicable sections of the UFSAR for the EDGs and other related systems,
and copies of applicable sections of changes to the UFSAR which have yet to be
docketed.
5.
Piping and instrumentation drawings, one-line diagrams; electrical schematics, and
wiring and logic diagrams (i.e., logic of voltage relays and load sequencing for LOOP)
for the EDGs and other related systems.
6.
A list of engineering calculations (Electrical, Instrumentation and Controls and
Mechanical/Nuclear) applicable to the EDGs and other related systems.
7.
List of calculations related to meeting 10 CFR 50.63 Station Blackout rule.
8.
Strategy for handling LOOP/SBO events.
9.
A list of plant modifications to the EDGs and other related systems implemented since
1994.
10.
List of current open temporary modifications and operator work arounds involving
operation of the EDGs and the other related systems.
11.
List of Condition Reports (CRs) initiated since 1994 affecting the EDGs and other
related systems.
2
Enclosure
12.
Summary of corrective maintenance activities, including the maintenance rule event log,
performed on the EDGs and other related systems in the past 12 months.
13.
An index of drawings for the EDGs and other related systems.
14.
Self-assessment performed on EDGs and other related systems in the last 24 months.
15.
System description and operator training modules for the EDGs and other related
systems.
16.
EDG nameplate data for engine and generators.
17.
List of Operating Experience Program evaluations of industry, vendor, or NRC generic
issues related to the EDGs for the past 3 years.
18.
List of valves required to change position for a LOOP/SBO event.
19.
List of instrument setpoint changes affecting EDGs and related systems initiated since
1994. Include the number and title, date, brief description, and corresponding
calculation number.
20.
Information describing the type and material used for the seals and O-rings for each
reactor coolant pump (RCP).
21.
PRA Fault Tree Data for the 4.16 KV buses, vital AC, EDGs, the station batteries, and
the turbine driven auxiliary feedwater pump.
22.
PRA/Risk Achievement Worth (RAW) listing for the EDGs and related support systems.
23.