ML032100641

Re Notification of an NRC Triennial Fire Protection Baseline Inspection; IR 05000254-03-012 & 05000265-03-012, on 10/06/03, for Exelon Generation Co., LLC, Warrenville, Il

ML032100641
Person / Time
Site:	Quad Cities
Issue date:	07/22/2003
From:	Julio Lara NRC/RGN-III/DRS/EEB
To:	Skolds J Exelon Generation Co
References
IR-03-012
Download: ML032100641 (11)

See also: IR 05000254/2003012

Text

July 22, 2003

Mr. John L. Skolds, President

Exelon Nuclear

Exelon Generation Company, LLC

Quad Cities Nuclear Power Station

4300 Winfield Road

Warrenville, IL 60555

SUBJECT: QUAD CITIES NUCLEAR POWER STATION

NOTIFICATION OF AN NRC TRIENNIAL FIRE PROTECTION BASELINE

INSPECTION 50-254/03-12(DRS); 50-265/03-12(DRS)

Dear Mr. Skolds:

On October 6, 2003, the NRC will begin a triennial fire protection baseline inspection at the

Quad Cities Nuclear Power Station. This inspection will be performed in accordance with the

NRC baseline Inspection Procedure 71111.05.

The schedule for the inspection is as follows:

• Information gathering visit - September 17-19, 2003

• On-site inspection activity - October 6-10, 2003 and October 20-24, 2003

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 Quad Cities Nuclear Power

Station 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

provided to the lead inspector via mail or electronically no later than September 12, 2003. 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

September 17, 2003. 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 6, 2003). The fourth group lists

information necessary to aid the inspection team in tracking issues identified as a result of the

J. Skolds -2-

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 onsite portions of the inspection.

The lead inspector for this inspection is Ronald A. Langstaff. We understand that our

regulatory contact for this inspection is Mr. Fuhs 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 2.790 of the NRCs "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 NRCs

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

Electrical Engineering Branch

Division of Reactor Safety

Docket Nos. 50-254; 50-265

License Nos. DPR-29; DPR-30

Enclosure: Fire Protection Inspection Document Request

See Attached Distribution

J. Skolds -2-

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 onsite portions of the inspection.

The lead inspector for this inspection is Ronald A. Langstaff. We understand that our

regulatory contact for this inspection is Mr. Fuhs 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 2.790 of the NRCs "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 NRCs

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

Electrical Engineering Branch

Division of Reactor Safety

Docket Nos. 50-254; 50-265

License Nos. DPR-29; DPR-30

Enclosure: Fire Protection Inspection Document Request

See Attached Distribution:

DOCUMENT NAME: C:\ORPCheckout\FileNET\ML032100641.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 RIII RIII RIII

NAME RLangstaff:tr MRing JLara

DATE 07/22/03 07/22/03 07/24/03

OFFICIAL RECORD COPY

INITIAL DOCUMENT REQUEST

FIRE PROTECTION INSPECTION DOCUMENT REQUEST

Inspection Report: 50-254/03-12; 50-265/03-12

Inspection Dates: September 17-19, 2003 (Information Gathering)

October 6-10, 2003 (On-site Inspection Activity)

October 20-24, 2003 (On-site Inspection Activity)

Inspection Procedures: IP 71111.05, Fire Protection

Inspectors: Lead Inspector: R. Langstaff

Team Members: R. Daley

R. Echoles

G. Hausman

Information Requested Prior to the Information Gathering Visit

The following information is requested by September 12, 2003. 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 (September 17-19, 2003)

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) The NRC Safety Evaluation Reports (SERs) and actual copies of the 50.59 reviews

which form the licensing basis for the reactor plant's post-fire safe shutdown

configuration.

(4) A list of Generic Letter 86-10 evaluations.

1 Enclosure

INITIAL DOCUMENT REQUEST

(5) 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).

(6) A list of plant deviations from code commitments.

(7) Post-fire safe shutdown analyses, including post-fire safe shutdown systems and

separation analysis.

(8) 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.

(9) 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).

(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 (problem identification forms

and their resolution 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 and describe 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.

(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.

2 Enclosure

INITIAL DOCUMENT REQUEST

(19) Organization charts of site personnel down to the level of fire protection staff personnel.

(20) A phone list for on-site licensee personnel.

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.

(3) A tour of alternative shutdown and risk significant fire areas.

Information Requested to be Available on First Day of Inspection (October 6, 2003)

(1) List of the fire protection program implementing procedures (e.g. administrative controls,

surveillance testing, fire brigade).

(2) List of maintenance and surveillance testing procedures for alternative shutdown

capability and fire barriers, detectors, pumps and suppression systems.

(3) List of maintenance procedures which routinely verify fuse breaker coordination in

accordance with the post-fire safe shutdown coordination analysis.

(4) 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.

(5) List of procedures/instructions that govern the implementation of plant modifications,

maintenance, and special operations, and their impact on fire protection.

(6) 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.

(7) 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).

3 Enclosure

INITIAL DOCUMENT REQUEST

(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) Alternating current (AC) coordination calculations for 4160 VAC down to 480 VAC

electrical systems.

(11) The three most recent fire protection Quality Assurance (QA) audits and/or fire

protection self-assessments.

(12) 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.

(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).

4 Enclosure

J. Skolds -3-

cc w/encl: Site Vice President - Quad Cities Nuclear Power Station

Quad Cities Nuclear Power Station Plant Manager

Regulatory Assurance Manager - Quad Cities

Chief Operating Officer

Senior Vice President - Nuclear Services

Senior Vice President - Mid-West Regional

Operating Group

Vice President - Mid-West Operations Support

Vice President - Licensing and Regulatory Affairs

Director Licensing - Mid-West Regional

Operating Group

Manager Licensing - Dresden and Quad Cities

Senior Counsel, Nuclear, Mid-West Regional

Operating Group

Document Control Desk - Licensing

Vice President - Law and Regulatory Affairs

Mid American Energy Company

M. Aguilar, Assistant Attorney General

Illinois Department of Nuclear Safety

State Liaison Officer, State of Illinois

State Liaison Officer, State of Iowa

Chairman, Illinois Commerce Commission

D. Tubbs, Manager of Nuclear

MidAmerican Energy Company

J. Skolds -3-

cc w/encl: Site Vice President - Quad Cities Nuclear Power Station

Quad Cities Nuclear Power Station Plant Manager

Regulatory Assurance Manager - Quad Cities

Chief Operating Officer

Senior Vice President - Nuclear Services

Senior Vice President - Mid-West Regional

Operating Group

Vice President - Mid-West Operations Support

Vice President - Licensing and Regulatory Affairs

Director Licensing - Mid-West Regional

Operating Group

Manager Licensing - Dresden and Quad Cities

Senior Counsel, Nuclear, Mid-West Regional

Operating Group

Document Control Desk - Licensing

Vice President - Law and Regulatory Affairs

Mid American Energy Company

M. Aguilar, Assistant Attorney General

Illinois Department of Nuclear Safety

State Liaison Officer, State of Illinois

State Liaison Officer, State of Iowa

Chairman, Illinois Commerce Commission

D. Tubbs, Manager of Nuclear

MidAmerican Energy Company

ADAMS Distribution:

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C. Ariano (hard copy)

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