ML020990655
| ML020990655 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/04/2002 |
| From: | Gardner R Division of Reactor Safety I |
| To: | Forbes J Nuclear Management Co |
| References | |
| IR-02-011 | |
| Download: ML020990655 (7) | |
See also: IR 05000263/2002011
Text
April 4, 2002
Mr. J. Forbes
Site Vice-President
Monticello Nuclear Generating Plant
Nuclear Management Company, LLC
2807 West County Road 75
Monticello, MN 55362-9637
SUBJECT: MONTICELLO POWER STATION- NOTIFICATION OF AN NRC TRIENNIAL
FIRE PROTECTION BASELINE INSPECTION 50-263/02-11(DRS)
Dear Mr. Forbes:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission
(NRC), Region III staff will conduct a triennial fire protection baseline inspection at the
Monticello Station in May and June 2002. The inspection will be led by a senior reactor
engineer from the NRC Region III Office and will be composed of personnel from NRC
Region III. The inspection will be conducted in accordance with IP 71111.05, the NRCs
baseline fire protection inspection procedure.
The schedule for the inspection is as follows:
Information gathering visit - May 20-24, 2002
Days of onsite inspection - June 3-7 and June 17-21, 2002
The purpose of the information gathering visit is to obtain information and documentation
needed to support the inspection, to become familiar with the Monticello Station fire protection
programs, fire protection features, post-fire safe shutdown capabilities, and plant layout. As
necessary, the team members will obtain plant specific site access training and badging for
unescorted site access. A list of the types of documents the team members may be interested
in reviewing, and possibly obtaining, are listed in the Enclosure to this letter.
During the information gathering visit, the team members will also discuss the following
inspection support administrative details: office space size and location; specific documents
requested to be made available to the team members in their office spaces; arrangements for
reactor site access (including radiation protection training, security, and safety); and the
availability of knowledgeable plant engineering and licensing organization personnel to serve as
points of contact during the inspection.
J. Forbes -2-
We request that during the onsite inspection weeks you ensure that copies of analyses,
evaluations or documentation regarding the implementation and maintenance of the Monticello
Station fire protection program, including post-fire safe shutdown capability, be readily
accessible to the team members 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, appropriate personnel,
knowledgeable with respect to 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 the
Monticello Station fire protection program and its implementation, should be available at the site
during the inspection.
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection, or the inspection teams information or logistical needs, please
contact Mr. Kenneth OBrien at (630) 829-9821 or myself at (630) 829-9751.
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/NRC/ADAMS/index.html (the Public Electronic Reading Room).
Sincerely,
/RA by John Jacobson Acting For/
Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosure: Reactor Fire Protection Program
Supporting Documentation
See Attached Distribution
J. Forbes -3-
cc w/encl: J. Purkis, Plant Manager
R. Anderson, Executive Vice President
and Chief Nuclear Officer
Nuclear Asset Manager
Site Licensing Manager
Commissioner, Minnesota Department of Health
J. Silberg, Esquire
Shaw, Pittman, Potts, and Trowbridge
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
A. Neblett, Assistant Attorney General
ADAMS Distribution:
WDR
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RidsNrrDipmIipb
GEG
SXB3
C. Ariano (hard copy)
DRPIII
DRSIII
PLB1
JRK1
J. Forbes -2-
We request that during the onsite inspection weeks you ensure that copies of analyses,
evaluations or documentation regarding the implementation and maintenance of the Monticello
Station fire protection program, including post-fire safe shutdown capability, be readily
accessible to the team members 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, appropriate personnel,
knowledgeable with respect to 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 the
Monticello Station fire protection program and its implementation, should be available at the site
during the inspection.
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection, or the inspection teams information or logistical needs, please
contact Mr. Kenneth OBrien at (630) 829-9821 or myself at (630) 829-9751.
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/NRC/ADAMS/index.html (the Public Electronic Reading Room).
Sincerely,
/RA by John Jacobson Acting For/
Ronald N. Gardner, Chief
Electrical Engineering Branch
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosure: Reactor Fire Protection Program
Supporting Documentation
See Attached Distribution
DOCUMENT NAME: G:\DRS\ML020990655.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 C RIII RIII
NAME DChyu for BBurgess JJacobson for
KOBrien:aa RGardner
DATE 04/03/02 04/03/02 04/04/02
OFFICIAL RECORD COPY
J. Forbes -3-
cc w/encl: J. Purkis, Plant Manager
R. Anderson, Executive Vice President
and Chief Nuclear Officer
Nuclear Asset Manager
Site Licensing Manager
Commissioner, Minnesota Department of Health
J. Silberg, Esquire
Shaw, Pittman, Potts, and Trowbridge
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
A. Neblett, Assistant Attorney General
ENCLOSURE
Reactor Fire Protection Program Supporting Documentation
This is a broad list of the documents the NRC inspection team may be interested in reviewing,
and possibly obtaining, to support the inspection. The lead inspector will discuss specific
information needs with the licensee staff and may request additional documents.
Prior to the Information Gathering Visit
1. The reactor plants Individual Plant Examination for External Events (IPEEE), results of
any post-IPEEE reviews, and listings of actions taken/plant modifications conducted in
response to IPEEE information.
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 plants post-fire safe shutdown
configuration.
4. Listing of Generic Letter 86-10 evaluations.
5. Listing of National Fire Protection Association (NFPA) code versions committed to
(NFPA codes of record).
6. Listing of plant deviations from code commitments.
7. A list of applicable codes and standards related to the design of plant fire protection
features and evaluations of code deviations.
8. Post-fire safe shutdown systems and separation analysis.
9. Post-fire alternative shutdown analysis.
10. 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.
11. Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
12. Plant layout drawings which identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection equipment.
13. Current versions of the fire protection program implementing procedures (e.g.,
administrative controls, surveillance testing, fire brigade).
14. Organization charts of site personnel down to the level of fire protection staff personnel.
15. A listing of abbreviations/designators for plant systems.
16. Listing of open and closed fire protection condition reports (problem identification forms
and their resolution reports).
17. Listing of fire impairments for previous year.
18. Plant operating procedures which would be used and describe shutdown for a
postulated fire in the fire areas/zones selected by the inspectors.
During the Inspection
1. Fire brigade training program.
2. Operator training for shutdown procedures in the event of fire.
3. Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
4. Maintenance and surveillance testing procedures for alternative shutdown capability and
fire barriers, detectors, pumps and suppression systems.
5. Maintenance procedures which routinely verify fuse breaker coordination in accordance
with the post-fire safe shutdown coordination analysis.
6. Procedures/instructions that control the configuration of the reactor plants fire protection
program, features, and post-fire safe shutdown methodology and system design.
7. Procedures/instructions that govern the implementation of plant modifications,
maintenance, and special operations, and their impact on fire protection.
8. Significant fire protection and post-fire safe shutdown related design change package
descriptions (including their associated 10 CFR Part 50.59 evaluations) and Generic
Letter (GL) 86-10 evaluations.
9. The three most recent fire protection Quality Assurance (QA) audits and/or fire
protection self-assessments.
10. Recent QA surveillances of fire protection activities.
11. Pre-fire plans for fire areas/zones selected by the inspectors for review.