ML022690680
| ML022690680 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 09/20/2002 |
| From: | Falevits Z NRC/RGN-III/DRS/EEB |
| To: | O'Connor W Detroit Edison |
| References | |
| IR-02-008 | |
| Download: ML022690680 (8) | |
See also: IR 05000341/2002008
Text
September 20, 2002
Mr. William OConnor, Jr.
Vice President
Nuclear Generation
Detroit Edison Company
6400 North Dixie Highway
Newport, MI 48166
SUBJECT:
FERMI 2 NUCLEAR POWER STATION - NOTIFICATION OF AN NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION 50-341/02-08
Dear Mr. OConnor:
On November 18, 2002, the NRC will begin a triennial fire protection baseline inspection at the
Fermi 2 Nuclear Power Station. 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 - October 29 - 31, 2002
On-site inspection activity - November 18 - 22, 2002, and December 2-6, 2002
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 Fermi 2 Nuclear Power Station
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 October 21, 2002. The
second group lists information necessary to ensure that the inspection team is adequately
prepared for the inspection. This information should be available to the on-site by no later than
October 29, 2002. 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, November 18, 2002. The fourth group lists
W. OConnor, Jr.
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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
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. Joseph Pendergast 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 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 by HWalker Acting for/
Zelig Falevits, Acting Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket No. 50-341
License No. DPR-43
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
N. Peterson, Director, Nuclear Licensing
P. Marquardt, Corporate Legal Department
Compliance Supervisor
R. Whale, Michigan Public Service Commission
Michigan Department of Environmental Quality
Monroe County, Emergency Management Division
Emergency Management Division
MI Department of State Police
W. OConnor, Jr.
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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
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. Joseph Pendergast 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 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 by HWalker Acting for/
Zelig Falevits, Acting Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket No. 50-341
License No. DPR-43
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
N. Peterson, Director, Nuclear Licensing
P. Marquardt, Corporate Legal Department
Compliance Supervisor
R. Whale, Michigan Public Service Commission
Michigan Department of Environmental Quality
Monroe County, Emergency Management Division
Emergency Management Division
MI Department of State Police
DOCUMENT NAME: G:DRS\\ML022690680.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
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NAME
RLangstaff:sd
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ZFalevits
DATE
09/19/02
09/19/02
09/20/02
OFFICIAL RECORD COPY
W. OConnor, Jr.
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ADAMS Distribution:
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MAS4
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C. Ariano (hard copy)
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INITIAL DOCUMENT REQUEST
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
Inspection Report:
50-341/02-08
Inspection Dates:
October 29 - 31, 2002
(Information Gathering)
November 18 - 22, 2002
(On-site Inspection Activity)
December 2 - 6, 2002
(On-site Inspection Activity)
Inspection Procedures:
IP 71111.05, Fire Protection
Inspectors:
Lead Inspector:
R. Langstaff
Team Members:
D. Chyu
R. Daley
Accompanying Personnel:
R. Echoles
S. Pergande
Information Requested Prior to the Information Gathering Visit
The following information is requested by October 21, 2002. If you have any questions
regarding this information, please call the team leader as soon as possible. All information may
be sent electronically (to R. Langstaff, e-mail address ral4@nrc.gov).
(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 more recent than the
IPEEE and if it exist.
(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 (October 29 - 31, 2002)
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
(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
(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 informal discussion of the following topics:
(1)
Plant procedures operators would use in the event of fire and under what conditions
would the plant be shutdown using alternative shutdown methodology.
(2)
The plants safe shutdown cable routing database and the plant-wide cable routing
database, as applicable.
Information Requested to be Available on First Day of Inspection (November 18, 2002)
(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 plants 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).
(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).
INITIAL DOCUMENT REQUEST
(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).