ML091320540
| ML091320540 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/12/2009 |
| From: | Robert Daley Engineering Branch 3 |
| To: | Jensen J Indiana Michigan Power Co |
| References | |
| IR-09-006 IR-09-006 | |
| Download: ML091320540 (10) | |
See also: IR 05000315/2009006
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210
LISLE, IL 60532-4352
May 12, 2009
Mr. Joseph Jensen
Senior Vice President and
Chief Nuclear Officer
Indiana Michigan Power Company
Nuclear Generation Group
One Cook Place
Bridgman, MI 49106
SUBJECT: DONALD C. COOK NUCLEAR PLANT - NOTIFICATION TO PERFORM
A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE
TRANSITION TO 10 CFR PART 50.48(C) IS IN PROGRESS
INSPECTION REPORT 05000315/2009006(DRS); 05000316/2009006(DRS)
Dear Mr. Jensen:
On November 2, 2009, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial fire
protection baseline inspection at the Donald C. Cook Nuclear Plant. This inspection will be
performed in accordance with Inspection Procedure 71111.05TTP, the NRCs baseline fire
protection inspection procedure for plants in the process of implementing the National Fire
Protection Association (NFPA) Standard 805 (10 CFR Part 50.48(c)). 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: October 6 - 8, 2009; and
y On-site inspection activity: November 2 - 6, 2009, and November 16 - 20, 2009.
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 Donald C. Cook Nuclear
Plants 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 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
J. Jensen -2-
provided to the lead inspector via mail or electronically no later than September 7, 2009. The
second group also lists information and areas for discussion necessary to aid the inspection
team in choosing specific focus areas for the inspection and to ensure that the inspection team
is adequately prepared for the inspection. It is requested this information be available during
the information gathering visit (October 6 - 8, 2009). The third group of requested documents
consists of 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 2, 2009). 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
regulatory contact for this inspection is Mr. John Nimtz 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 George.Hausman@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/
Robert C. Daley, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos.: 50-315; 50-316
Enclosure: Fire Protection Inspection Document Request
cc w/encl: L. Weber, Site Vice President
J. Gebbie, Plant Manager
O. Isiogu, Michigan Public Service Commission
Michigan Department of Environmental Quality
Planning Manager, Emergency Management and Homeland
Security Division, Michigan State Police Department
T. Strong, State Liaison Officer
J. Jensen -2-
provided to the lead inspector via mail or electronically no later than September 7, 2009. The second
group also lists information and areas for discussion necessary to aid the inspection team in choosing
specific focus areas for the inspection and to ensure that the inspection team is adequately prepared for
the inspection. It is requested this information be available during the information gathering visit (October
6 - 8, 2009). The third group of requested documents consists of 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 2, 2009). 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 regulatory
contact for this inspection is Mr. John Nimtz 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
George.Hausman@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/
Robert C. Daley, Chief
Engineering Branch 3
Division of Reactor Safety
Docket Nos.: 50-315; 50-316
Enclosure: Fire Protection Inspection Document Request
cc w/encl: L. Weber, Site Vice President
J. Gebbie, Plant Manager
O. Isiogu, Michigan Public Service Commission
Michigan Department of Environmental Quality
Planning Manager, Emergency Management and Homeland
Security Division, Michigan State Police Department
T. Strong, State Liaison Officer
DISTRIBUTION
See next page
DOCUMENT NAME: G:\DRS\Work in Progress\Ltr 05__09 DC Cook Request for Information 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 RIII E RIII RIII RIII RIII
NAME GHausman: ls RDaley
DATE 05/08/09 05/12/09
OFFICIAL RECORD COPY
Letter to Mr. Joseph Jensen from Mr. Robert C. Daley dated May 12, 2009.
SUBJECT: DONALD C. COOK NUCLEAR PLANT - NOTIFICATION TO PERFORM
A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION WHILE
TRANSITION TO 10 CFR PART 50.48(C) IS IN PROGRESS INSPECTION
REPORT 05000315/2009006(DRS); 05000316/2009006(DRS)
DISTRIBUTION:
RidsNrrDorlLpl3-1 Resource
RidsNrrPMDCCook Resource
RidsNrrDirsIrib Resource
Patrick Hiland
Kenneth Obrien
DRPIII
DRSIII
Patricia Buckley
ROPreports Resource
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
Inspection Report: 05000315/2009006(DRS); 05000316/2009006(DRS)
Inspection Dates: October 6 - 8, 2009, (Information Gathering Visit)
November 2 - 6, 2009, (On-site Inspection Activity)
November 16 - 20, 2009, (On-site Inspection Activity)
Inspection Procedures: IP 71111.05TTP, Fire Protection-NFPA 805 Transition Period
(Triennial)
IP 71152, "Identification and Resolution of Problems"
Inspectors: George M. Hausman, Lead Inspector
(630) 829-9743
George.Hausman@nrc.gov
Mohammad Munir Robert A. Winter
(630) 829-9797 (630) 829-9758
Mohammad.Munir@nrc.gov Robert.Winter@nrc.gov
I. Information Requested Prior To the Information Gathering Visit
The following information is requested by September 7, 2009. If you have any questions
regarding this request, please call the lead inspector as soon as possible. All information
should be sent to Mr. George M. Hausman (e-mail address George.Hausman@nrc.gov).
Electronic media is preferred. The preferred file format is a searchable pdf file on a
compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of use, if
possible. Please provide four copies of each CD 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 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.
3. 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.
4. Plant operating procedures, which would be used and describe shutdown for a
postulated fire (for both areas requiring alternative shutdown and areas which do not
require alternative shutdown). Only those procedures with actions specific to shutdown
in the event of a fire need be included.
5. A copy of the current fire protection system Health Report, if available.
1 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
6. A copy of the current plant drawings referred to as Horse Notes, if available.
7. Status of NFPA 805 (10 CFR Part 50.48(c)) implementation.
II. Information Requested During the Information Gathering Visit (OCTOBER 6-8, 2009)
The following information is requested to be provided to the inspection team during the
on-site information gathering visit. Except for Item 1, it is requested that the following
information be provided on four sets of CDs (searchable, if possible). In addition, two sets
of hard copy drawings are requested for Items 4.a. through 4.f.
1. One set of hard-copy documents for facility layout drawings, which identify plant fire area
delineation; areas protected by automatic fire suppression and detection; and locations
of fire protection equipment.
2. 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 licensing correspondence
referenced by the SERs;
c. All licensing correspondence associated with the comparison to Standard Review
Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;
d. Exemptions from 10 CFR Part 50.48 and 10 CFR Part 50, Appendix R, and
associated licensing correspondence;
e. The FPP and applicable portions of the USAR, as referenced by the fire protection
license condition;
f. 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 10 CFR
Part 50.48(b)(1);
g. 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
Part 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 Part 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 Part 50.48(b)(1)(ii));
2 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
h. 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
i. For NFPA 805 transition plants 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).
3. Fire Protection Program:
a. If not already provided under request II.(2)(e) above, FPP documents including
b. A listing of changes made to the FPP (including associated adverse to SSA) since
the last triennial fire protection inspection;
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 as a strategy 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.
4. 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);
3 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
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 480Vac;
e. One-line schematic drawings of the electrical distribution system for 250 Volts
direct current (Vdc) and 125Vdc systems as applicable;
f. Logic diagrams showing the components used to achieve and maintain hot
standby and cold shutdown; and
g. Safe shutdown cable routing database (requested electronically such as on
compact disc, if available.
5. 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).
6. 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.
7. 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.
8. 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;
4 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
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.
III. Information Requested to be Available on First Day of Inspection (November 2, 2009)
The following information is requested to be provided on the first day of inspection. It is
requested that this information be provided on four sets of CDs (searchable, if possible).
1. Program Procedures:
a. List of the FPP 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 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);
5 Enclosure
FIRE PROTECTION INSPECTION DOCUMENT REQUEST
e. Alternating current (ac) coordination calculations for 4160Vac down to 480Vac
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). It is acceptable to make vendor
manuals available to the inspectors in lieu of providing a copy; 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.
4. Any updates to information previously provided.
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).
6 Enclosure