ML051170013
| ML051170013 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/26/2005 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Jamil D Duke Energy Corp |
| References | |
| IR-05-009 | |
| Download: ML051170013 (7) | |
See also: IR 05000413/2005009
Text
April 26, 2005
Duke Energy Corporation
ATTN: Mr. D. M. Jamil
Site Vice President
Catawba Nuclear Station
4800 Concord Road
York, SC 29745
SUBJECT: CATAWBA NUCLEAR STATION - SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION REPORT
05000413/2005009 AND 05000414/2005009
Dear Mr. Jamil:
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 Catawba Nuclear Station during the weeks of September 19 and October 3, 2005. A team
of five inspectors will perform this inspection. The inspection team will be led by
Mr. Randy Moore, 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 used for the identification
and mitigation of a small break loss of coolant accident (SBLOCA) in conjunction with a loss of
offsite power (LOOP). Procedures which direct the mitigating actions for this event will also be
evaluated.
During a telephone conversation on April 21, 2005, Mr. Randy Moore of my staff, and
Mr. G. Strickland 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 August 22, 2005
- Onsite inspection weeks: September 19 and October 3, 2005
The purpose of the information gathering visit is to obtain information and documentation
outlined in the enclosure needed to support the inspection. Mr. R. Bernhard, a Region II Senior
Reactor Analyst, may accompany Mr. Moore 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. Moore 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.
DPC 2
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; scheduling a simulator
demonstration of a SBLOCA/LOOP event; and the availability of knowledgeable plant
engineering and licensing 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 Mr. Moore at (404) 562-4642 or me at
(404) 562-4605.
In accordance with 10 CFR 2.390 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 Publicly Available Records (PARS) component of NRC's 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.: 50-413, 50-414
Enclosure: Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl:
Lee A. Keller (CNS)
Regulatory Compliance Manager
Duke Energy Corporation
Electronic Mail Distribution
Lisa Vaughn
Legal Department (PB05E)
Duke Energy Corporation
422 South Church Street
P. O. Box 1244
Charlotte, NC 28201-1244
(cc w/encl: - See page 3)
DPC 3
(cc w/encl contd)
Anne Cottingham Peggy Force
Winston & Strawn LLP Assistant Attorney General
Electronic Mail Distribution N. C. Department of Justice
Electronic Mail Distribution
North Carolina MPA-1
Electronic Mail Distribution County Manager of York County, SC
Electronic Mail Distribution
Henry J. Porter, Asst. Director
Div. of Radioactive Waste Mgmt. Piedmont Municipal Power Agency
S. C. Department of Health Electronic Mail Distribution
and Environmental Control
Electronic Mail Distribution R. L. Gill, Jr., Manager
Nuclear Regulatory Issues
R. Mike Gandy and Industry Affairs
Division of Radioactive Waste Mgmt. Duke Energy Corporation
S. C. Department of Health and 526 S. Church Street
Environmental Control Charlotte, NC 28201-0006
Electronic Mail Distribution
Elizabeth McMahon
Assistant Attorney General
S. C. Attorney General's Office
Electronic Mail Distribution
Vanessa Quinn
Federal Emergency Management Agency
Electronic Mail Distribution
North Carolina Electric
Membership Corporation
Electronic Mail Distribution
_________________________
OFFICE RII:DRS RII:DRP RII:DRS
SIGNATURE RLM MEE LSM
NAME RMoore MErnstes LMellen
DATE 4/21/2005 4/21/2005 4/21/2005 4/ /2005 4/ /2005 4/ /2005 4/ /2005
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
INFORMATION REQUEST FOR THE CATAWBA SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION
SMALL BREAK LOCA IN CONJUNCTION WITH A LOSS OF OFFSITE POWER
(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 someone who has a
knowledge of pressurized water reactor technology.)
1. Piping and instrumentation drawings for the following systems: Chemical Volume and
Control, Residual Heat Removal, Safety Injection, Auxiliary Feedwater, Component
Cooling, and supporting systems. Two paper copies are preferred.
2. The normal operating procedures for the systems listed above. Include the procedures
which specify the normal valve alignment for these systems. Include an index of
procedure titles with this file.
3. A list of surveillance procedures used to ensure the operability of the equipment in the
systems in Item 1 above required by your Technical Specifications that are used during
the mitigation of the LOOP/SBLOCA event. Please include procedure titles with this list.
4. A list of procedures (with titles) used for the operational testing of check valves in
portions of the Item 1 systems and supporting systems used during mitigation of the
event.
5. Document which lists the time critical operator actions assumed in the safety analysis
for SBLOCA.
6. System description and/or design basis document (DBD) for Item 1 systems and
supporting systems.
7. A list, with titles, of calibration and functional test procedures for instruments used in the
identification and mitigation of a SBLOCA including subcooling margin.
8. A list of manual actions required outside the control room during a LOOP/SBLOCA
event.
9. A list, with titles, of test procedures for the pressurizer PORVs.
10. A list of corrective work orders and non-routine work requests initiated since 2003
affecting the systems in Item 1, and support systems, used to detect and mitigate a
LOOP/SBLOCA event, including their power supplies. If work orders are prioritized, just
include the highest priority WOs. If list is more than 25 pages, discuss with lead
inspector how to focus this information to a smaller size.
Enclosure
2
11. Emergency Operating Procedures (EOPs) and supporting procedures, EOP basis
documents, step deviation document, writers guide, and users guide.
Abnormal Operating Procedures that would be used during a LOOP/SBLOCA event.
Please include an index of procedures with this file.
12. Calculations used to support the setpoints in EOPs for this event.
13. A list of engineering calculations applicable to Item 1 systems and support systems. If
these calculations are listed in the DBDs refer this request to Item 6.
14. A list of temporary modifications and operator work-arounds since 2003 for Item 1
systems and support systems.
15. A list of operability determinations performed since 2003 related to Item 1 systems and
support systems.
16. A list of corrective action program documents (PERs) initiated since 2003 for Item 1
systems and support systems.
17. System health reports and system performance trends for Item 1 systems and support
systems going back 2 years.
18. A copy of the Maintenance Rule program procedure and performance criteria for Item 1
systems and support systems. A list of plant systems currently monitored under
50.65(a)(1) and the performance goals. A list of Maintenance Rule functional failures
since 2003
19. Operator training lesson plans, system descriptions, and job performance measures for
the EOPs, EOP support procedures, abnormal, and normal operating procedures that
would be used to mitigate an LOOP/SBLOCA event.
20. Key electrical single line drawings of the intermediate and low voltage alternating current
(AC) and DC power systems that include the power distribution for Item 1 systems, and
support systems equipment. Two paper copies are preferred for these.
21. A current copy of the Updated Final Safety Analysis Report (UFSAR)
22. A brief description of the mitigation strategy for the LOOP/SBLOCA event. This should
include operator actions, equipment and power sources, as well as indications and
control circuits.
23. A list of Operating Experience Program evaluations of industry, vendor, or NRC generic
issues for the past 3 years, related to Item 1 systems and support systems equipment or
operation.
Enclosure
3
24 A list of equipment and operator actions with a Risk Achievement Worth (RAW) greater
than 1.02 for Item 1 systems and support systems.
25. Probabilistic Risk Assessment (PRA) Event Tree for LOOP/SBLOCA initiating event. A
List of PRA system dependencies and success criteria for Item 1 systems and their
support systems.
26. A current revision of the Plant Technical Specifications, Bases, and Technical
Requirements Manual (or equivalent).
27. A list of Catawba design basis requirements, commitments, and industry standards
related to mitigation of the LOOP/SBLOCA event.
28. A list of all permanent plant changes, design changes, setpoint changes, procedure
changes, equivalency evaluations, suitability analyses, calculations, and commercial
grade dedications since 2003 related to Item 1 systems and support systems.
29. Plant procedures that provide the guidelines for the following programs: 1) Corrective
Action Program, 2) program for the evaluation of changes, tests, and experiments
[50.59 Program], 3) program for the incorporation of local and industry operating
experience into Catawba programs and procedures, 4) the design control program.
30. A list of operations training packages which were required due to modifications related
to Item 1 systems and support systems, if any.
31. Summary of differences between Unit 1 and Unit 2 Item 1 systems or SBLOCA
procedures and manual actions.
32. A list of valves that are required to change position or are manually operated during
implementation of the SBLOCA/LOOP mitigation strategy. If possible, provide
equipment failure rates for these valves over the past 10 years.
Enclosure