ML023260479
| ML023260479 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/20/2002 |
| From: | Gardner R NRC/RGN-III/DRS/EEB |
| To: | Peifer M Nuclear Management Co |
| References | |
| IR-03-002 | |
| Download: ML023260479 (9) | |
See also: IR 05000331/2003002
Text
November 20, 2002
Mr. Mark Peifer
Site Vice-President
Duane Arnold Energy Center
Nuclear Management Company, LLC
3277 DAEC Road
Palo, IA 52324
SUBJECT:
DUANE ARNOLD ENERGY CENTER NOTIFICATION OF AN NRC TRIENNIAL
FIRE PROTECTION BASELINE INSPECTION 50-331/03-02
Dear Mr. Peifer:
On January 27, 2003, the NRC will begin a triennial fire protection baseline inspection at the
Duane Arnold Energy Center. This inspection will be performed in accordance with the NRC
baseline Inspection Procedure 71111.05.
The schedule for the inspection is as follows:
Information gathering visit - January 14 - 16, 2003
On-site inspection activity - January 27 - 31 and February 10 - 14, 2003
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 Duane Arnold Energy Center
fire protection programs, 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 sides, 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 January 6, 2003. 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 January
14, 2003. 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, January 27, 2003. The fourth group lists information
necessary to aid 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
M. Peifer
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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 onsite portions of the inspection.
The lead inspector for this inspection is Ronald A. Langstaff. We understand that our
regulatory contact for this inspection is Mr. John Karrick of your organization. If there are any
questions about the inspection or the material requested, please contact the lead inspector at
(630) 829-9747 or via e-mail at ral4@nrc.gov.
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 Publicly 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 by Zelig Falevits Acting for/
Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket No. 50-331
License No. DPR-49
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
E. Protsch, Executive Vice President -
Energy Delivery, Alliant;
President, IES Utilities, Inc.
Robert G. Anderson, Plant Manager
State Liaison Officer
Chairperson, Iowa Utilities Board
The Honorable Charles W. Larson, Jr.
Iowa State Representative
DOCUMENT NAME: G:\\DRS\\DUA11_ _02DRS.wpd
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy
OFFICE
RIII
E RIII
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NAME
RLangstaff:aa
B.Burgess
RGardner
DATE
11/15/02
11/20/02
11/20/02
OFFICIAL RECORD COPY
M. Peifer
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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 onsite portions of the inspection.
The lead inspector for this inspection is Ronald A. Langstaff. We understand that our
regulatory contact for this inspection is Mr. John Karrick of your organization. If there are any
questions about the inspection or the material requested, please contact the lead inspector at
(630) 829-9747 or via e-mail at ral4@nrc.gov.
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 Publicly 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 by Zelig Falevits Acting for/
Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket No. 50-331
License No. DPR-49
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
E. Protsch, Executive Vice President -
Energy Delivery, Alliant;
President, IES Utilities, Inc.
Robert G. Anderson, Plant Manager
State Liaison Officer
Chairperson, Iowa Utilities Board
The Honorable Charles W. Larson, Jr.
Iowa State Representative
M. Peifer
-3-
ADAMS Distribution:
WDR
DSH
RidsNrrDipmIipb
GEG
C. Ariano (hard copy)
DRPIII
DRSIII
PLB1
JRK1
INITIAL DOCUMENT REQUEST
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
Inspection Report:
50-331/03-02
Inspection Dates:
January 14 -16, 2003
(Information Gathering)
January 27 - 31, 2003
(On-site Inspection Activity)
February 10 - 14, 2003
(On-site Inspection Activity)
Inspection Procedures:
IP 71111.05, Fire Protection
Inspectors:
Lead Inspector:
R. Langstaff
Team Members:
D. Schrum
Contractor
Information Requested Prior to the Information Gathering Visit
The following information is requested by January 6, 2003. If you have any questions regarding
this information, please call the team leader as soon as possible. All information may sent
electronically (to R. Langstaff, e-mail address ral4@nrc.gov) or provided on compact disc.
(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/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.
Information Requested During the Information Gathering Visit (January 14 - 16, 2003)
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.
(3)
The NRC Safety Evaluation Reports (SERs) and actual copies of the 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.
INITIAL DOCUMENT REQUEST
2
(7)
Post-fire safe shutdown systems and separation analysis.
(8)
Post-fire safe shutdown analyses.
(9)
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.
(10)
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).
(11)
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).
(12)
Listing of open and closed fire protection condition reports (problem identification forms
and their resolution reports) for the past three years.
(13)
Listing of fire impairments for the previous year.
(14)
Pre-fire plans for selected fire zones/areas (to be determined during information
gathering visit).
(15)
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).
(16)
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
(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for each
selected fire zone/area.
(17)
One-line schematic drawings of the electrical distribution system for 4160 volts -
alternating current (VAC) down to 480 VAC.
(18)
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/designators for plant systems.
(19)
Organization charts of site personnel down to the level of fire protection staff personnel.
INITIAL DOCUMENT REQUEST
3
(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:
(1)
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.
(2)
Informal discussion on the plants safe shutdown cable routing database and the plant-
wide cable routing database, as applicable.
(3)
A tour of alternative shutdown and risk significant fire areas.
Information Requested to be Available on First Day of Inspection (January 27, 2003)
(1)
Operator training for shutdown procedures in the event of fire.
(2)
Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
(3)
Current versions of the fire protection program implementing procedures (e.g.,
administrative controls, surveillance testing, fire brigade).
(4)
List of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps and suppression systems.
(5)
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.
(6)
List of maintenance procedures which routinely verify fuse breaker coordination in
accordance with the post-fire safe shutdown coordination analysis.
(7)
Procedures/instructions that control the configuration of the reactor plant's fire protection
program, features, and post-fire safe shutdown methodology and system design.
(8)
Procedures/instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection.
(9)
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.
(10)
Gaseous suppression system pre-operational testing, if applicable, for selected fire
zones/areas (to be determined during information gathering visit).
INITIAL DOCUMENT REQUEST
4
(11)
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).
(12)
Alternating current (AC) coordination calculations for 4160 VAC down to 480 VAC
electrical systems.
(13)
The three most recent fire protection Quality Assurance (QA) audits and/or fire
protection self-assessments.
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).