ML061990603
| ML061990603 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/17/2006 |
| From: | Julio Lara Engineering Branch 3 |
| To: | Vanmiddlesworth G Nuclear Management Co |
| References | |
| IR-06-014 | |
| Download: ML061990603 (10) | |
See also: IR 05000331/2006014
Text
July 17, 2006
Mr. Gary Van Middlesworth
Vice-President
Duane Arnold Energy Center
3277 DAEC Road
Palo, IA 52324-9785
SUBJECT: DUANE ARNOLD ENERGY CENTER NOTIFICATION OF AN NRC TRIENNIAL
FIRE PROTECTION BASELINE INSPECTION 05000331/2006014(DRS)
Dear Mr. Van Middlesworth:
On September 11, 2006, the U.S. Nuclear Regulatory Commission (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 71111.05TTP.
The schedule for the inspection is as follows:
- Information gathering visit - August 23 - 25, 2006
- On-site inspection activity - September 11 - 15, 2006, and September 25 - 29, 2006
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 program, 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 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 choosing specific focus areas for the inspection. It is requested that this information be
provided to Mr. Dariusz Szwarc via mail or electronically, (dxs4@nrc.gov) no later than
August 14, 2006. 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 August 23, 2006. 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
(September 11, 2006). The fourth group lists information necessary to aid the inspection team
in tracking issues identified as a result of the inspection.
G. Van Middlesworth -2-
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. Ronald A. Langstaff. We understand that our
regulatory contact for this inspection is Ms. Laura Swenzinski of your organization, and that our
technical contact is Mr. Gary Ellis, also 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the
Public Electronic Reading Room).
Sincerely,
/RA by R.A. Langstaff Acting For/
Julio F. Lara, Chief
Engineering Branch 3
Division of Reactor Safety
Docket No. 50-331
License No. DPR-49
Enclosure: Fire Protection Inspection Document Request
cc w/encl: J. Stall, Senior Vice President, Nuclear and Chief
Nuclear Officer
R. Helfrich, Senior Attorney
M. Ross, Managing Attorney
W. Webster, Vice President, Nuclear Operations
M. Warner, Vice President, Nuclear Operations Support
R. Kundalkar, Vice President, Nuclear Engineering
J. Bjorseth, Site Director
D. Curtland, Plant Manager
S. Catron, Manager, Regulatory Affairs
Chairman, Linn County Board of Supervisors
D. McGhee, State Liaison Officer
G. Van Middlesworth -2-
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. Ronald A. Langstaff. We understand that our
regulatory contact for this inspection is Ms. Laura Swenzinski of your organization and that our
technical contact is Mr. Gary Ellis, also 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), 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. 50-331
License No. DPR-49
Enclosure: Fire Protection Inspection Document Request
cc w/encl: J. Stall, Senior Vice President, Nuclear and Chief
Nuclear Officer
R. Helfrich, Senior Attorney
M. Ross, Managing Attorney
W. Webster, Vice President, Nuclear Operations
M. Warner, Vice President, Nuclear Operations Support
R. Kundalkar, Vice President, Nuclear Engineering
J. Bjorseth, Site Director
D. Curtland, Plant Manager
S. Catron, Manager, Regulatory Affairs
Chairman, Linn County Board of Supervisors
D. McGhee, State Liaison Officer
DOCUMENT NAME:E:\Filenet\ML061990603.wpd
G Publicly Available G Non-Publicly Available G Sensitive G 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 RIII DRS RIII DRS RIII RIII
NAME RLangstaff: ls BBurgess JLara
DATE 07/17/06 07/17/06 07/17/06
OFFICIAL RECORD COPY
G. Van Middlesworth -3-
ADAMS Distribution:
JLD
DWS
RidsNrrDirsIrib
GEG
KGO
GAW1
CAA1
DRPIII
DRSIII
PLB1
TXN
ROPreports@nrc.gov
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
Inspection Report: 05000331/2006014(DRS)
Inspection Dates: August 23 - 25, 2006, Information Gathering Visit
September 11 - 15, 2006, On-site Inspection Activity
September 25 - 29, 2006, On-site Inspection Activity
Inspection Procedures: IP 71111.05TTP, Fire Protection-NFPA 805 Transition Period
IP 71152, "Identification and Resolution of Problems"
Inspectors: Ronald A. Langstaff, Lead Inspector
630-829-9747
ral4@nrc.gov
Carl R. Moore,
630-829-9732
crm4@nrc.gov
Darrell L. Schrum,
630-829-9741
dls3@nrc.gov
630-829-9515
dxs4@nrc.gov
A. Information Requested Prior to the Information Gathering Visit
The following information is requested by August 14, 2006. If you have any questions
regarding this information, please call the lead inspector as soon as possible. All
information may be sent electronically (to Mr. Dariusz Szwarc, e-mail address
dxs4@nrc.gov) or provided on compact disc (the preferred method). If compact discs
are provided, four sets (one for each inspector) are requested.
(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.
1 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
B. Information Requested During the Information Gathering Visit
(August 23 - 25, 2006)
This information is requested to be available in one set of hard-copy documents (where
possible) on-site during the information gathering visit. In addition, if the requested
information is available electronically, it is requested that the information be provided on
three sets of compact discs (searchable, if possible).
(1) Licensing Information
(a) The facility 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 fire protection program and applicable portions of the Updated Safety
Analysis Report, 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 all 10 CFR
Part 50, Appendix R, sections and paragraphs that are applicable to the
facility under 10 CFR 50.48(b)(1);
(f) For pre-1979 plants, all licensing correspondence associated with those
sections of CFR Part 50, Appendix R, which 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 NRC fire protection safety evaluation reports
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 safety evaluation reports issued before
Appendix A to BTP APCSB 9.5-1 was published in August 1976,
(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 those plants intending to transition to NFPA 805, all correspondence
to and responses from the NRC relating to the planned transition.
2 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
(a) If not already provided under request II(1)(c) above, fire protection
program documents including fire hazards analyses and post-fire safe
shutdown analyses;
(b) A listing of changes made to the fire protection program (including
associated adverse to safe shutdown analyses);
(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-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;
(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) A list of plant deviations from code commitments and associated
evaluations; and
(g) Facility 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) Facility layout and equipment drawings which identify the physical facility
locations of hot standby and cold shutdown equipment for selected fire
zones/areas (to be determined during information gathering visit);
(c) One-line schematic drawings of the electrical distribution system for
4160 Volts - alternating current (Vac) down to 480 Vac;
3 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
(d) One-line schematic drawings of the electrical distribution system for
250 Volts - direct current (Vdc) and 125 Vdc systems as applicable; and
(e) Safe shutdown cable routing database (requested electronically such as
on compact disc), if available.
(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
(c) A tour of alternative shutdown and risk significant fire areas.
4 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
C. Information Requested to be Available on First Day of Inspection
(September 11, 2006)
This information is requested to be available in one set of hard-copy documents (where
possible) on-site during the information gathering visit. In addition, if the requested
information is available electronically, it is requested that the information be provided on
three sets of compact discs (searchable, if possible).
(1) Procedures
(a) List of the fire protection program implementing procedures
(e.g., administrative controls, surveillance testing, fire brigade);
(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 fire protection program, 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);
5 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
INITIAL REQUEST
(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; and
(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). It is
acceptable to make vendor manuals available to the inspectors in lieu of
providing a copy.
(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.
D. 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).
6 Enclosure