ML080350699
| ML080350699 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/04/2008 |
| From: | Julio Lara Engineering Branch 3 |
| To: | O'Connor T Nuclear Management Co |
| References | |
| IR-08-006 | |
| Download: ML080350699 (10) | |
See also: IR 05000263/2008006
Text
February 4, 2008
Mr. Timothy J. OConnor
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 TO CONDUCT A TRIENNIAL FIRE PROTECTION BASELINE
INSPECTION WHILE TRANSITION TO 10 CFR PART 50.48(C) IS IN
PROGRESS INSPECTION REPORT 05000263/2008006(DRS)
Dear Mr. OConnor:
On March 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial fire
protection baseline inspection at the Monticello Nuclear Generating Plant. The inspection will
be conducted in accordance with Inspection Procedure 71111.05TTP, the NRCs baseline fire
protection inspection procedure for plants in the process of implementing 10 CFR 50.48(c),
NFPA 805. The inspection guidance is different from the regular triennial inspections in that the
inspectors will concentrate on the fire protection program infrastructure and the adequacy of
compensatory measures implemented for identified departures from code requirements. The
inspectors will not routinely inspect for or evaluate circuit related issues.
The schedule for the inspection is as follows:
y
Information gathering visit - February 27 - 29, 2008; and
y
On-site inspection activity - March 31 - April 4, 2008, and April 14 - 18, 2008.
The purpose of the information gathering visit is to: (1) obtain information and documentation
needed to support the inspection; (2) become familiar with the Monticello Nuclear Generating
Plants fire protection program, fire protection features, post-fire safe shutdown capabilities, and
plant layout; and (3) 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
T. OConner
-2-
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 February 11, 2008. 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
February 27, 2008. The third group of requested documents are those items that the inspection
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 (March 31, 2008). The fourth
group lists the 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 on-site portions of the inspection.
The lead inspector for this inspection is Mr. George M. Hausman. We understand that our initial
regulatory contact for this inspection is Mr. Ronald Baumer 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 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), 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 No.:
50-263
License No.: DPR-22
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
M. Sellman, President and Chief Executive Officer
D. Koehl, Chief Nuclear Officer
Manager, Nuclear Safety Assessment
J. Rogoff, Vice President, Counsel, and Secretary
Nuclear Asset Manager, Xcel Energy, Inc.
State Liaison Officer, Minnesota Department of Health
R. Nelson, President
Minnesota Environmental Control Citizens
Association (MECCA)
Commissioner, Minnesota Pollution Control Agency
R. Hiivala, Auditor/Treasurer,
Wright County Government Center
Commissioner, Minnesota Department of Commerce
Manager - Environmental Protection Division
Minnesota Attorney Generals Office
T. OConnor
-2-
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 February 11, 2008. 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 February 27, 2008. The third group of
requested documents is those items that the inspection 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
(March 31, 2008). The fourth group lists the 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 on-site portions of the inspection.
The lead inspector for this inspection is Mr. George M. Hausman. We understand that our initial
regulatory contact for this inspection is Mr. Ronald Baumer 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 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), accessible from the
NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
Julio F. Lara, Chief
Engineering Branch 3
Division of Reactor Safety
Docket No.:
50-263
License No.:
Enclosure:
Fire Protection Inspection Document Request
cc w/encl:
M. Sellman, President and Chief Executive Officer
D. Koehl, Chief Nuclear Officer
Manager, Nuclear Safety Assessment
J. Rogoff, Vice President, Counsel, and Secretary
Nuclear Asset Manager, Xcel Energy, Inc.
State Liaison Officer, Minnesota Department of Health
R. Nelson, President
Minnesota Environmental Control Citizens
Association (MECCA)
Commissioner, Minnesota Pollution Control Agency
R. Hiivala, Auditor/Treasurer,
Wright County Government Center
Commissioner, Minnesota Department of Commerce
Manager - Environmental Protection Division
Minnesota Attorney Generals Office
DISTRIBUTION
See next page
DOCUMENT NAME: G:\\DRS\\Work in Progress\\Ltr 01 08 Monticello FPI Triennial Notification Ltr GMH.doc
9 Publicly Available 9 Non-Publicly Available 9 Sensitive 9 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
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DATE
02/04/2008
02/04/2008
OFFICIAL RECORD COPY
Letter to Mr. Timothy J. OConnor from Julio F. Lara dated February 4, 2008
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT
NOTIFICATION TO CONDUCT A TRIENNIAL FIRE PROTECTION BASELINE
INSPECTION WHILE TRANSITION TO 10 CFR PART 50.48(C) IS IN
PROGRESS INSPECTION REPORT 05000263/2008006(DRS)
DISTRIBUTION:
TEB
PST
RidsNrrDirsIrib
MAS
KGO
JKH3
CST1
CAA1
GLS
DRPIII
DRSIII
PLB1
TXN
ROPreports@nrc.gov
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
1
Enclosure
Inspection Report: 05000263/2008006(DRS)
Inspection Dates:
February 27 - 29, 2008
(Information Gathering Visit)
March 31 - April 4, 2008
(On-site Inspection Activity)
April 14 - 18, 2008
(On-site Inspection Activity)
Inspection Procedures:
IP 71111.05TTP, Fire Protection-NFPA Transition Period
(Triennial) IP 71152, "Identification and Resolution of Problems"
Inspectors:
Lead Inspector:
George M. Hausman, (630) 829-9743
Team Members:
Benny Jose, (630) 829-9756
Robert A.Winter, (630) 829-9758
I
INFORMATION REQUESTED PRIOR TO THE INFORMATION GATHERING VISIT
The following information is requested by February 11, 2008. If you have any questions
regarding this information, please call the lead inspector as soon as possible. Please
ensure that the information to be provided in lists contain enough information to be easily
understood by someone who has a knowledge of the technology. All information should be
sent to Mr. George M. Hausman (e-mail address gmh1@nrc.gov). Electronic media is
preferred, if readily available. The preferred file format is a searchable .pdf file on a
CDROM. The CDROM should be indexed and hyper-linked to facilitate ease of use, if
possible. Please provide four copies of each CDROM submitted (one for each inspector
and for a senior reactor analysis).
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, or where both safe shutdown trains can be affected.
3. A copy of the current version of the Fire Protection Program (FPP), Fire Hazards
Analysis (FHA), Safe Shutdown Analysis (SSA), Updated Safety Analysis Report
(USAR), Technical Specifications and License.
4. A copy of the current fire protection system Health Report, if available.
5. A copy of the current plant drawings referred to as Horse Notes, if available.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
2
Enclosure
II STATUS OF 10 CFR 50.48(C), NFPA 805 IMPLEMENTATION INFORMATION
REQUESTED DURING THE INFORMATION GATHERING VISIT
(FEBRUARY 27 - 29, 2008)
The following information is requested to be provided to the inspection team during the
on-site information gathering visit as one set of hard-copy documents. In addition, the
requested information is to be provided as a file searchable compact disc (CD), if possible.
If a CD(s) can be provided, three sets (one for each inspector) are requested.
1. Licensing Information:
a.
The Facilitys license, including the fire protection license condition;
b.
All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
applicable to fire protection (specifically including those SERs referenced by
the plant fire protection license condition) and all other associated licensing
correspondence applicable to fire protection;
c.
The FPP and applicable portions of the USAR, as referenced by the fire protection
license condition;
d.
Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and associated
licensing correspondence;
e.
For pre-1979 plants (i.e., Appendix R plants), a listing of all 10 CFR Part 50,
Appendix R sections and paragraphs that are applicable to the plant under
f.
For pre-1979 plants, all licensing correspondence associated with those sections
of 10 CFR Part 50, Appendix R, that are not applicable to the plant under
10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with
those fire protection features proposed or implemented by the licensee that have
been accepted by the NRC staff as satisfying the provisions of Appendix A to
Branch Technical Position (BTP) APCSB 9.5-1 reflected in the NRC fire protection
SERs issued before February 19, 1981, (10 CFR 50.48(b)(1)(i)); or those fire
protection features which were accepted by the NRC staff in comprehensive fire
protection SERs issued before Appendix A to BTP APCSB 9.5-1 was published in
August 1976 (10 CFR 50.48(b)(1)(ii));
g.
For post-1979 plants, all licensing correspondence associated with the comparison
to Standard Review Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing
purposes; and
h.
For plants intending to transition to NFPA 805, provide: (1) all correspondence to
and responses from the NRC; (2) a list of all areas showing assessment review
status; (3) assessments for all areas that have been completed; and (4) a list of all
identified non-conformances, and their respective compensatory measure(s).
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
3
Enclosure
2. Fire Protection Program:
a.
If not already provided under request II.(1)(c) above, FPP documents including
b.
A listing of changes made to the FPP (including associated adverse to SSA);
c.
For pre-1979 plants, 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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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;
d.
A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe shutdown
evaluations);
e.
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);
f.
List of plant deviations from code commitments and associated evaluations; and
g.
Plant layout drawings which identify plant fire area delineation, areas protected by
automatic fire suppression and detection, and the locations of fire protection
equipment.
3. Facility Information:
a.
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;
b.
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);
c.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units;
d.
One-line schematic drawings of the electrical distribution system for 4160 Volts
alternating current (Vac) down to 480 Vac;
e.
One-line schematic drawings of the electrical distribution system for 250 Volts
direct current (Vdc) and 125 Vdc systems as applicable; and
f.
Safe shutdown cable routing database (requested electronically such as on
compact disc, if available.
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
4
Enclosure
4. Operations Response for Fire Protection:
a.
Pre-fire plans for selected fire zones/areas (to be determined during information
gathering visit); and
b.
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).
5. Corrective Actions:
a.
Listing of open and closed fire protection condition reports (i.e., problem
identification forms and their resolution reports) since the date of the last triennial
fire protection inspection; and
b.
Listing of fire impairments since the date of the last triennial fire protection
inspection.
6. General Information:
a.
A listing of abbreviations and/or designators for plant systems;
b.
Organization charts of site personnel down to the level of fire protection staff
personnel; and
c.
A phone list for on-site licensee personnel.
7. On-Site Discussions.
In addition, during the information gathering visit, it is requested that licensee staff be
available for the following:
a.
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;
b.
Informal discussion on the plants safe shutdown cable routing database and the
plant-wide cable routing database, as applicable; and
A tour of alternative shutdown and risk significant fire areas.
III. Information Requested to be Available on First Day of Inspection (March 31, 2008)
1. Procedures:
a.
List of the FPP implementing procedures (e.g., administrative controls, surveillance
testing, fire brigade);
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
5
Enclosure
b.
List of maintenance and surveillance testing procedures for alternative shutdown
capability and fire barriers, detectors, pumps, and suppression systems;
c.
List of maintenance procedures which routinely verify fuse breaker coordination
in accordance with the post-fire safe shutdown coordination analysis;
d.
List of procedures and/or instructions that control the configuration of the reactor
plant's FPP, features, and post-fire safe shutdown methodology and system
design; and
e.
List of procedures and/or instructions that govern the implementation of plant
modifications, maintenance, and special operations, and their impact on fire
protection.
2. Design and Equipment Information:
a.
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;
b.
Copies of 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 (or adverse to safe shutdown)
evaluations;
c.
Gaseous suppression system pre-operational testing, if applicable, for selected fire
zones/areas (to be determined during information gathering visit);
d.
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);
e.
Alternating current (ac) coordination calculations for 4160 Vac down to 480 Vac
electrical systems;
f.
Vendor manuals and information for fire protection equipment (such as detection,
suppression systems, fire pumps), applicable to selected fire zones/areas (to be
determined during information gathering visit); and
g.
List of all fire protection or Appendix R calculations.
3. Assessment and Corrective Actions:
a.
The three most recent fire protection Quality Assurance (QA) audits and/or fire
protection self-assessments; and
b.
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.
6
Enclosure
IV. Information Requested to Be Provided Throughout the Inspection
1.
Copies of any corrective action documents generated as a result of the inspection
teams questions or queries during this inspection.
2.
Copies of the list of questions submitted by the inspection team members and the
status/resolution of the information requested (provided daily during the inspection to
each inspection team member).