ML060670422
| ML060670422 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/22/2006 |
| From: | Julio Lara Engineering Branch 3 |
| To: | Crane C Exelon Generation Co, Exelon Nuclear |
| References | |
| IR-06-002 | |
| Download: ML060670422 (14) | |
See also: IR 05000254/2006002
Text
February 22, 2006
Mr. Christopher M. Crane
President and Chief Nuclear Officer
Exelon Nuclear
Exelon Generation Company, LLC
Quad Cities Nuclear Power Station
4300 Winfield Road
Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2
NOTIFICATION OF AN NRC TRIENNIAL FIRE PROTECTION BASELINE
INSPECTION 05000254/2006002; 05000265/2006002(DRS)
Dear Mr. Crane:
On April 24, 2006, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial fire
protection baseline inspection at the Quad Cities Nuclear Power Station, Units 1 and 2. This
inspection will be performed in accordance with the NRC Baseline Inspection
Procedure 71111.05T.
The schedule for the inspection is as follows:
Information gathering visit - April 12 - 14, 2006.
On-site inspection activity - April 24 - 28, 2006, and May 8 - 12, 2006.
The purpose of the information gathering visit is: (1) to obtain information and documentation
needed to support the inspection; (2) to become familiar with the Quad Cities Nuclear Power
Stations fire protection program, fire protection features, post-fire safe shutdown capabilities
and plant layout; and (3) to arrange administrative details such as office space, availability of
knowledgeable office personnel and to ensure unescorted site access privileges.
Experience has shown that the baseline fire protection inspections are extremely resource
intensive both for the NRC inspectors and the licensee staff. In order to minimize the
inspection impact on the site and to ensure a productive inspection for both organizations, we
have enclosed a request for documents needed for the inspection. These documents have
been divided into four groups. The first group lists information necessary to aid the inspection
team in choosing specific focus areas for the inspection. It is requested that this information be
provided to the lead inspector via mail or electronically no later than April 3, 2006. The second
group lists information necessary to ensure that the inspection team is adequately prepared for
the inspection. This information should be available on-site no later than April 12, 2006. The
third group of requested documents are those items that the team will review, or need access
to, during the inspection. Please have this information available by the first day of the on-site
portion of the inspection (April 24, 2006). The fourth group lists information necessary to aid
C. Crane
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the inspection team in tracking issues identified as a result of the inspection. It is requested
that this information be provided to the lead inspector as the information is generated during the
inspection. It is important that all of these documents are up to date and complete in order to
minimize the number of additional documents requested during the preparation and/or the
on-site portions of the inspection.
The lead inspector for this inspection is Mr. George M. Hausman. We understand that our
regulatory contact for this inspection is Mr. Tony Fuhs of your organization. If there are any
questions about the inspection or the material requested, please contact the lead inspector at
(630) 829-9743 or via e-mail at gmh1@nrc.gov.
In accordance with 10 CFR Part 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/
Julio F. Lara, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-254; 50-265
Enclosure:
Fire Protection Inspection Document Request
See Attached Distribution
C. Crane
-3-
cc w/encl:
Site Vice President - Quad Cities Nuclear Power Station
Plant Manager - Quad Cities Nuclear Power Station
Regulatory Assurance Manager - Quad Cities Nuclear Power Station
Chief Operating Officer
Senior Vice President - Nuclear Services
Senior Vice President - Mid-West Regional
Operating Group
Vice President - Mid-West Operations Support
Vice President - Licensing and Regulatory Affairs
Director Licensing - Mid-West Regional
Operating Group
Manager Licensing - Dresden and Quad Cities
Senior Counsel, Nuclear, Mid-West Regional
Operating Group
Document Control Desk - Licensing
Vice President - Law and Regulatory Affairs
Mid American Energy Company
Assistant Attorney General
Illinois Emergency Management Agency
State Liaison Officer, State of Illinois
State Liaison Officer, State of Iowa
Chairman, Illinois Commerce Commission
D. Tubbs, Manager of Nuclear
MidAmerican Energy Company
C. Crane
-2-
the inspection team in tracking issues identified as a result of the inspection. It is requested
that this information be provided to the lead inspector as the information is generated during the
inspection. It is important that all of these documents are up to date and complete in order to
minimize the number of additional documents requested during the preparation and/or the
on-site portions of the inspection.
The lead inspector for this inspection is Mr. George M. Hausman. We understand that our
regulatory contact for this inspection is Mr. Tony Fuhs of your organization. If there are any
questions about the inspection or the material requested, please contact the lead inspector at
(630) 829-9743 or via e-mail at gmh1@nrc.gov.
In accordance with 10 CFR Part 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/
Julio F. Lara, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos. 50-254; 50-265
Enclosure:
Fire Protection Inspection Document Request
See Attached Distribution
DOCUMENT NAME: E:\\Filenet\\ML060670422.wpd
G Publicly Available
G Non-Publicly Available
G Sensitive
G Non-Sensitive
To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy
OFFICE RIII
RIII
RIII
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NAME
GHausman: ls
MRing
JLara
DATE
02/17/06
02/21/06
02/22/06
OFFICIAL RECORD COPY
C. Crane
-3-
cc w/encl:
Site Vice President - Quad Cities Nuclear Power Station
Plant Manager - Quad Cities Nuclear Power Station
Regulatory Assurance Manager - Quad Cities Nuclear Power Station
Chief Operating Officer
Senior Vice President - Nuclear Services
Senior Vice President - Mid-West Regional
Operating Group
Vice President - Mid-West Operations Support
Vice President - Licensing and Regulatory Affairs
Director Licensing - Mid-West Regional
Operating Group
Manager Licensing - Dresden and Quad Cities
Senior Counsel, Nuclear, Mid-West Regional
Operating Group
Document Control Desk - Licensing
Vice President - Law and Regulatory Affairs
Mid American Energy Company
Assistant Attorney General
Illinois Emergency Management Agency
State Liaison Officer, State of Illinois
State Liaison Officer, State of Iowa
Chairman, Illinois Commerce Commission
D. Tubbs, Manager of Nuclear
MidAmerican Energy Company
ADAMS Distribution:
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GEG
KGO
KKB
CAA1
C. Pederson, DRS
DRPIII
DRSIII
PLB1
JRK1
ROPreports@nrc.gov
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
Enclosure
1
Inspection Report: 05000254/2006002; 05000265/2006002(DRS)
Inspection Dates:
April 12 - 14, 2006
(Information Gathering Visit)
April 24 - 28, 2006
(On-site Inspection Activity)
May 8 - 12, 2006
(On-site Inspection Activity)
Inspection Procedures:
IP 71111.05T, Fire Protection (Triennial)
IP 71152, "Identification and Resolution of Problems"
Inspectors:
Lead Inspector:
George M. Hausman
Team Members:
Alan K. Dahbur
Darrell L. Schrum
I.
Information Requested Prior to the Information Gathering Visit
The following information is requested by April 3, 2006. If you have any questions regarding
this information, please call the lead inspector as soon as possible. All information may be sent
electronically (to Mr. George M. Hausman, e-mail address gmh1@nrc.gov) or provided on
compact disc (preferred method).
(1)
The reactor plant's Individual Plant Examination for External Events (IPEEE) for fire,
results of any post-IPEEE reviews for fire, and listings of actions taken and/or plant
modifications conducted in response to IPEEE information for fire. Alternatively,
probabilistic risk analyses for fire and associated information, if it exists and is more
recent than the IPEEE.
(2)
A list of fire areas requiring alternative shutdown capability, (i.e., those areas for which
10 CFR Part 50, Appendix R, Section III.G) requirements are satisfied under
Section III.G.3.
(3)
A compact disc copy of the current version of the Fire Protection Program (FPP), Fire
Hazards Analysis, UFSAR, and Technical Specification.
II.
Information Requested During the Information Gathering Visit (April 12 - 14, 2006)
This information is requested to be available on-site during the information gathering visit.
(1)
The current version of the Fire Protection Program and Fire Hazards Analysis.
(2)
Listing of plant fire protection licensing basis documents.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
Enclosure
2
(3)
Copies of the NRC Safety Evaluation Reports (SERs) and of the 10 CFR 50.59 reviews
which form the licensing basis for the reactor plant's post-fire safe shutdown
configuration.
(4)
A list of Generic Letter 86-10 evaluations.
(5)
A list of applicable codes and standards related to the design of plant fire protection
features. The list should include National Fire Protection Association (NFPA) code
versions committed to (i.e., the NFPA codes of record).
(6)
A list of plant deviations from code commitments.
(7)
Post-fire safe shutdown analyses, including post-fire safe shutdown systems and
separation analysis.
(8)
Piping and instrumentation (flow) diagrams showing the components used to achieve
and maintain hot standby and cold shutdown for fires outside the control room and those
components used for those areas requiring alternative shutdown capability.
(9)
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment for selected fire zones/areas (to be determined
during information gathering visit).
(10)
Plant layout drawings which identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection equipment
for selected fire zones/areas (to be determined during information gathering visit).
(11)
Listing of open and closed fire protection condition reports (i.e., problem identification
forms and their resolution reports) for the past three years.
(12)
Listing of fire impairments for the previous year.
(13)
Pre-fire plans for selected fire zones/areas (to be determined during information
gathering visit).
(14)
Plant operating procedures which would be used and describe shutdown for a
postulated fire in selected fire zones/areas (to be determined during information
gathering visit).
(15)
A listing of the protection methodologies identified under 10 CFR Part 50, Appendix R,
Section III.G used to achieve compliance for selected fire zones/areas (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
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
Enclosure
3
(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for each
selected fire zone/area.
(16)
One-line schematic drawings of the electrical distribution system for 4160 Volts -
alternating current (Vac) down to 480 Vac.
(17)
One-line schematic drawings of the electrical distribution system for 250 Volts - direct
current (Vdc) and 125 Vdc systems as applicable.
(18)
A listing of abbreviations and/or designators for plant systems.
(19)
Organization charts of site personnel down to the level of fire protection staff personnel.
(20)
A phone list for on-site licensee personnel.
In addition, during the information gathering visit, it is requested that licensee staff be available
for the following:
(21)
Informal discussion on plant procedures operators would use in the event of fire and
under what conditions would the plant be shutdown using alternative shutdown
methodology.
(22)
Informal discussion on the plants safe shutdown cable routing database and the
plant-wide cable routing database, as applicable.
(23)
A tour of alternative shutdown and risk significant fire areas.
III.
Information Requested to be Available on First Day of Inspection (April 24, 2006)
(1)
List of the fire protection program implementing procedures (e.g., administrative
controls, surveillance testing, fire brigade).
(2)
List of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps and suppression systems.
(3)
List of maintenance procedures which routinely verify fuse breaker coordination in
accordance with the post-fire safe shutdown coordination analysis.
(4)
List of procedures and/or instructions that control the configuration of the reactor plant's
fire protection program, features, and post-fire safe shutdown methodology and system
design.
(5)
List of procedures and/or instructions that govern the implementation of plant
modifications, maintenance, and special operations, and their impact on fire protection.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
Enclosure
4
(6)
Coordination calculations and/or justifications that verify fuse/breaker coordination for
selected fire zones/areas (to be determined during information gathering visit) that are
fed off of the same electrical buses as components in the protected safe shutdown train.
(7)
Copies of significant fire protection and post-fire safe shutdown related design change
package descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter (GL) 86-10 evaluations.
(8)
Gaseous suppression system pre-operational testing, if applicable, for selected fire
zones/areas (to be determined during information gathering visit).
(9)
Hydraulic calculations and supporting test data which demonstrate operability for water
suppression systems, if applicable, for selected fire zones/areas (to be determined
during information gathering visit).
(10)
Alternating current (ac) coordination calculations for 4160 Vac down to 480 Vac
electrical systems.
(11)
The three most recent fire protection Quality Assurance (QA) audits and/or fire
protection self-assessments.
(12)
Corrective action documents (e.g., condition reports, including status of corrective
actions) generated as a result of the three most recent fire protection Quality
Assurance (QA) audits and/or fire protection self-assessments.
IV.
Information Requested to Be Provided Throughout the Inspection
(1)
Copies of any corrective action documents generated as a result of the teams questions
or queries during this inspection.
(2)
Copies of the list of questions submitted by the team members and the status/resolution
of the information requested (provide daily during the inspection to each team member).