ML050620244
| ML050620244 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/03/2005 |
| From: | Payne D Division of Reactor Safety II |
| To: | Rosalyn Jones Duke Energy Corp |
| References | |
| IR-05-007 | |
| Download: ML050620244 (7) | |
See also: IR 05000269/2005007
Text
March 3, 2005
Duke Energy Corporation
ATTN:
Mr. Ronald A. Jones
Vice President
Oconee Site
7800 Rochester Highway
Seneca, SC 29672
SUBJECT:
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT 05000269/2005007, 05000270/2005007,
Dear Mr. Jones:
The purpose of this letter is to notify you that the U. S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a triennial fire protection baseline inspection at the Oconee Nuclear
Station, in June 2005. The inspection team will be led by Mr. Paul J. Fillion, NRC Fire
Protection Team Leader, of the Region II Office. The team will be composed of personnel from
NRC Region II. The inspection will be conducted in accordance with the NRCs baseline fire
protection inspection procedure 71111.05T.
The inspection objective will be to evaluate your fire protection program implementation with
emphasis on post-fire safe shutdown capability and the fire protection features provided to
ensure at least one post-fire safe shutdown success path is maintained free of fire damage.
The inspection team will focus their review on the separation of systems and equipment
necessary to achieve and maintain safe shutdown and fire protection features of selected fire
areas.
On February 18, 2005, during a telephone conversation between Mr. James Weast, Regulatory
Compliance Engineer, and Mr. Fillion, our respective staff confirmed arrangements for a three-
day information gathering site visit and a two-week onsite inspection. The schedule for the
inspection is as follows:
C
Information gathering visit: May 17-19, 2005
C
Week 1 of onsite inspection: June 6-10, 2005
Week 2 of onsite inspection: June 20-24, 2005
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection and to become familiar with the Oconee Nuclear Station fire
protection program features, post-fire safe shutdown capabilities, and plant layout. The types
of documents the team will be interested in reviewing, and possibly obtaining, are listed in the
Enclosure. Please contact Mr. Fillion prior to preparing copies of the materials listed in the
Enclosure. The inspection team will try to minimize your administrative burden by specifically
identifying those documents required for inspection preparation.
2
During the information gathering visit, the team 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 (including radiation protection
training, security, safety and fitness for duty requirements); and the availability of
knowledgeable plant engineering and licensing organization personnel to serve as points of
contact during the inspection.
We request that during the onsite inspection week you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the
Oconee Nuclear Station fire protection program, including post-fire safe shutdown capability,
be readily accessible to the team for their review. Of specific interest are those documents
which establish that your fire protection program satisfies NRC regulatory requirements and
conforms to applicable NRC and industry fire protection guidance. Also, personnel should be
available at the site during the inspection who are knowledgeable regarding those plant
systems required to achieve and maintain safe shutdown conditions from inside and outside the
control room (including the electrical aspects of the relevant post-fire safe shutdown analyses),
reactor plant fire protection systems and features, and the Oconee Nuclear Station fire
protection program and its implementation.
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection or the inspection team's information or logistical needs, please
contact Mr. Fillion at (404) 562-4623, or me at (404) 562-4669.
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).
Should you have any questions concerning this letter, please contact us.
Sincerely,
\\\\RA\\\\
D. Charles Payne, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos.: 50-269, 50-270, 50-287
License Nos.: DPR-38, DPR-47, DPR-55
Enclosure: Triennial Fire Protection Inspection Support Documentation
3
cc w/encl:
B. G. Davenport
Compliance Manager (ONS)
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
Anne Cottingham
Winston & Strawn LLP
Electronic Mail Distribution
Beverly Hall, Acting Director
Division of Radiation Protection
N. C. Department of Environmental
Health & Natural Resources
Electronic Mail Distribution
Henry J. Porter, Assistant Director
Div. of Radioactive Waste Mgmt.
S. C. Department 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
County Supervisor of
Oconee County
415 S. Pine Street
Walhalla, SC 29691-2145
Lyle Graber, LIS
NUS Corporation
Electronic Mail Distribution
R. L. Gill, Jr., Manager
Nuclear Regulatory Issues
and Industry Affairs
Duke Energy Corporation
526 S. Church Street
Charlotte, NC 28201-0006
Peggy Force
Assistant Attorney General
N. C. Department of Justice
Electronic Mail Distribution
_________________________
OFFICE
RII:DRS
SIGNATURE
PJF
NAME
PFillion
DATE
2/28/2005
3/ /2005
3/ /2005
3/ /2005
3/ /2005
3/ /2005
3/ /2005
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Reactor Fire Protection Program Supporting Documentation
[Note: This is a broad list of the documents the NRC inspection team may be interested
in reviewing, and possibly obtaining, during the information gathering site visit. The
current version of these documents is expected unless specified otherwise. 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 5 copies of each CDROM submitted.) Information in lists should
contain enough information to be easily understood by someone who has a knowledge
of the technology. The lead inspector will discuss specific information needs with the
licensee staff and may request additional documents.
1.
The current version of the Fire Protection Program and Fire Hazards Analysis.
2.
The fire protection program implementing procedures (e.g., administrative controls,
surveillance testing, fire brigade).
3.
Fire brigade training program document and the pre-fire plans for the selected fire
areas/zones (to be determined during information gathering visit).
4.
The post-fire safe shutdown analysis, including system and separation analyses.
5.
The alternative shutdown analysis.
6.
Piping and instrumentation (flow) diagrams for the fire suppression systems.
7.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
the control room.
8.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
alternative or dedicated shutdown capability.
9.
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
10.
Plant layout drawings which identify plant fire area and/or fire zone delineation, areas
protected by automatic fire suppression and detection, and the locations of fire
protection equipment for the selected fire areas/zones (to be determined during
information gathering visit).
11.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
12.
Plant operating procedures used to, and describing, shutdown from inside the control
room with a postulated fire occurring in any plant area outside the control room.
2
13.
Plant operating procedures used to implement the alternative shutdown capability from
outside the control room with a fire in either the control or cable spreading room (or any
other alternative shutdown area).
14.
Maintenance and surveillance testing procedures for alternative shutdown capability
(including Appendix R emergency lights and communication systems) and fire barriers,
detectors, fire pumps and fire suppression systems.
15.
Calculations and/or justifications that verify fuse/breaker coordination for the selected
fire areas/zones (to be determined during information gathering visit) that are fed off the
same electrical buses as components in the protected train. Also, a list of the
maintenance procedures used to routinely verify fuse/breaker coordination in
accordance with the post-fire safety shutdown coordination analysis.
16.
A list of the significant fire protection and post-fire safe shutdown design change
descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter (GL) 86-10 evaluations.
17.
A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,
Section III.G) used to achieve regulatory compliance for the selected fire areas/zones
(to be determined during information gathering visit). That is, please specify whether
3-hour rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and
suppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression
(Section III.G.2.c), or alternative dedicated shutdown capability (Section III.G.3) is used
for the selected fire areas/zones.
18.
Procedures or instructions that govern the implementation of plant modifications,
temporary modifications, maintenance, and special operations, and their impact on fire
protection.
19.
Organization chart(s) of site personnel down to the level of the fire protection staff.
20.
Procedures or instructions that control the configuration of the fire protection program,
features, and post-fire safe shutdown methodology and system design.
21.
A list of applicable codes and standards related to the design of plan fire protection
features and evaluations of code deviations (i.e., a listing of the NFPA code editions
committed to (Code of Record)).
22.
The three most recent fire protection QA audits and/or fire protection self-assessments.
23.
A list of open and closed fire protection problem identification and resolution reports
[also know as action reports/condition reports/problem reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
past three years.
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24.
A list of plant fire protection licensing basis documents (i.e., a list of the SERs and
change evaluations which form the licensing basis for the facilitys post-fire safe
shutdown configuration).
25.
A list of fire protection or Appendix R calculations.
26.
A list of fire impairments identified during the previous year.
27.
A list of abbreviations/designators for plant systems.