ML052280286
| ML052280286 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/16/2005 |
| From: | Julio Lara Division of Reactor Safety III |
| To: | Conway J Nuclear Management Co |
| References | |
| IR-05-013 | |
| Download: ML052280286 (8) | |
See also: IR 05000263/2005013
Text
August 16, 2005
Mr. J. Conway
Site Vice President
Monticello Nuclear Generating Plant
Nuclear Management Company, LLC
2807 West County Road 75
Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - NOTIFICATION OF AN NRC
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION 05000263/2005013
Dear Mr. Conway:
On October 17, 2005, the NRC will begin a triennial fire protection baseline inspection at the
Monticello Nuclear Generating Plant. This inspection activity will be performed in accordance
with the NRC baseline Inspection Procedure 71111.05T.
The schedule for the inspection is as follows:
Information gathering visit: October 4 - 5, 2005
On-site inspection activity: October 17 - 21 and October 31 - November 4, 2005
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 Monticello Nuclear Generating
Plant 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 September 23, 2005. 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
October 4, 2005. 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, October 17, 2005. 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
information is generated during the inspection. It is important that all of these documents are
J. Conway
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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. Ronald A. Langstaff. We understand that our
technical contact for this inspection is Ms. Michelle Kelly 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 2.390 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. 50-263
License Nos. DPR-22
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
J. Cowan, Executive Vice President
and Chief Nuclear Officer
Manager, Regulatory Affairs
J. Rogoff, Vice President, Counsel, and Secretary
Nuclear Asset Manager, Xcel Energy, Inc.
Commissioner, Minnesota Department of Health
R. Nelson, President
Minnesota Environmental Control Citizens
Association (MECCA)
Commissioner, Minnesota Pollution Control Agency
D. Gruber, Auditor/Treasurer,
Wright County Government Center
Commissioner, Minnesota Department of Commerce
Manager - Environmental Protection Division
Minnesota Attorney Generals Office
J. Conway
-2-
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. Ronald A. Langstaff. We understand that our
technical contact for this inspection is Ms. Michelle Kelly 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 2.390 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. 50-263
License Nos. DPR-22
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
J. Cowan, Executive Vice President
and Chief Nuclear Officer
Manager, Regulatory Affairs
J. Rogoff, Vice President, Counsel, and Secretary
Nuclear Asset Manager, Xcel Energy, Inc.
Commissioner, Minnesota Department of Health
R. Nelson, President
Minnesota Environmental Control Citizens
Association (MECCA)
Commissioner, Minnesota Pollution Control Agency
D. Gruber, Auditor/Treasurer,
Wright County Government Center
Commissioner, Minnesota Department of Commerce
Manager - Environmental Protection Division
Minnesota Attorney Generals Office
- Concurrence via email
DOCUMENT NAME: ML052280286.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
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DATE
08/12/05
08/16/05
08/16/05
OFFICIAL RECORD COPY
J. Conway
-3-
ADAMS Distribution:
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INITIAL DOCUMENT REQUEST
Enclosure
1
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
Inspection Report: 05000263/2005013(DRS)
Inspection Dates:
October 4 - 5, 2005
(Information Gathering)
October 17 - 21, 2005
(On-site Inspection Activity)
October 31 - November 4, 2005
(On-site Inspection Activity)
Inspection Procedures:
IP 71111.05T, Fire Protection
IP 71152, Identification and Resolution of Problems
Inspectors:
Lead Inspector:
R. Langstaff
Team Members:
A. Dahbur
Contractor
Information Requested Prior to the Information Gathering Visit
The following information is requested by September 23, 2005. If you have any questions
regarding this information, please call the lead inspector as soon as possible. All information
may be sent electronically (to R. A. 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 (October 4 - 5, 2005)
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)
Copies of NRC Safety Evaluation Reports, relevant to fire protection and safe shutdown
in the event of a fire;
(4)
Listing of changes to the fire protection program and associated adverse to safe
shutdown evaluations;
(5)
A list of Generic Letter 86-10 evaluations;
INITIAL DOCUMENT REQUEST
Enclosure
2
(6)
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);
(7)
A list of plant deviations from code commitments;
(8)
Post-fire safe shutdown analyses, including the identification of post-fire safe shutdown
systems and separation analyses, plant transient response analyses, and manual action
feasibility analyses, as applicable;
(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 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 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 to respond to a fire alarm/annunciator,
for dispatching a fire brigade, and implementing safe 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
(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for each
selected fire zone/area (to be determined during information gathering visit);
(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/designators for plant systems;
(19)
Organization charts of site personnel down to the level of fire protection staff personnel;
and
(20)
A phone list for on-site licensee personnel.
INITIAL DOCUMENT REQUEST
Enclosure
3
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; and
(3)
A tour of alternative shutdown and risk significant fire areas.
Information Requested to be Available on First Day of Inspection (October 17, 2005)
(1)
List of the fire protection program implementing procedures (e.g., administrative controls
and fire brigade);
(2)
List of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps, and fire suppression systems;
(3)
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;
(4)
List of maintenance procedures which routinely verify fuse breaker coordination in
accordance with the post-fire safe shutdown coordination analysis;
(5)
List of procedures/instructions that control the configuration of the reactor plant's fire
protection program, features, and post-fire safe shutdown methodology and system
design;
(6)
List of procedures/instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection;
(7)
List 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)
Piping and instrumentation diagram for fire suppression systems, if applicable, for
selected fire zones/areas (to be determined during information gathering visit);
INITIAL DOCUMENT REQUEST
Enclosure
4
(11)
Isometric piping diagrams, if applicable, for piping associated with fire suppression
systems for selected fire zones/areas (to be determined during information gathering
visit);
(12)
Drawings showing the location of fire detectors, if applicable, for selected fire
zones/areas (to be determined during information gathering visit);
(13)
Structural drawings showing the location of structural members (e.g., beams) for the
floor above selected fire zones/areas (to be determined during information gathering
visit);
(14)
Ventilation flow diagrams, if applicable, for selected fire zones/areas (to be determined
during information gathering visit);
(15)
Alternating current (AC) coordination calculations for 4160 Vac down to 480 Vac
electrical systems;
(16)
The three most recent fire protection Quality Assurance (QA) audits and/or fire
protection self-assessments; and
(17)
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.
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; and
(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).