ML070290588

Information Request for NRC Biennial Baseline Component Design Basis Inspection, IR 05000249-07-006, (Drs); 05000249-07-006 (DRS)

ML070290588
Person / Time
Site:	Dresden
Issue date:	01/29/2007
From:	Ann Marie Stone NRC/RGN-III/DRS/EB2
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-07-006
Download: ML070290588 (8)

See also: IR 05000249/2007006

Text

January 29, 2007Mr. Christopher M. CranePresident and Chief Nuclear Officer

Exelon Nuclear

Exelon Generation Company, LLC

4300 Winfield Road

Warrenville, IL 60555SUBJECT:DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, INFORMATION REQUEST FOR AN NRC BIENNIAL BASELINE COMPONENT DESIGN BASES

INSPECTION (CDBI) 05000237/2007006(DRS); 05000249/2007006(DRS)Dear Mr. Crane:

On April 9, 2007, the NRC will begin a biennial baseline Component Design Bases Inspection(CDBI) at the Dresden Nuclear Power Station. A team of six inspectors will perform this 3-weekinspection. This inspection will be performed in accordance with revised NRC Baseline

Inspection Procedure (IP) 71111.21 and replaces the biennial Safety System Design and

Performance Capability inspection. The CDBI inspection focuses on components which have high risk and low design margins. The components to be reviewed during this baseline inspection will be identified during an

in-office preparation week prior to the first week of on-site inspection. In addition, a number of

risk significant operator actions and operating experience issues, associated with the

component samples, will also be selected for review. The inspection will include three weeks of on-site inspection. The inspection team will consistof six NRC inspectors, of which, five will focus on engineering and one on operations. The

current inspection schedule is as follows: *On-site weeks: April 9, 2007, April 23, 2007, and May 7, 2007The team will be preparing for the inspection mainly during the week of April 2, 2007, asdiscussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany theinspection team during the week of April 9, 2007, to review probabilistic risk assessment data

and assist in identifying risk significant components, which will be reviewed during the

inspection.

C. Crane-2-Experience with previous baseline design inspections of similar depth and length has shownthat these types of 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 parties, we have enclosed a request for information needed for

the inspection.It is important that all of these documents are up to date and complete in order to minimize thenumber of additional documents requested during the preparation and/or the on-site portions of

the inspection. Insofar as possible, this information should be provided electronically to the

lead inspector. The information request has been divided into three groups:*The first group lists information necessary for our initial inspection scoping activities. This information should be available to the lead inspector no later than March 8, 2007.

By March 16, 2007, the lead inspector will communicate the initial selected set of 30

high risk components;*The second group of documents requested are those items needed to support ourin-office preparation activities. This set of documents, including the calculations

associated with the initial selected components, should be available at the Regional

Office no later than March 28, 2007. During the in-office preparation activities, the team

may identify additional information needed to support the inspection; and*The last group includes the additional information identified above, as well as plantspecific reference material. This information should be available to the team on

April 9, 2007. It is also requested that corrective action documents and/or questions

developed during the inspection be provided to the lead inspector as the documents are

generated. The lead inspector for this inspection is Mr. John Jacobson. In order to facilitate the inspection,we request that a contact individual be assigned to each inspector to ensure information

requests, questions, and concerns are addressed in a timely manner. If there are any

questions about the inspection or the material requested in the Enclosure, please contact the

lead inspector at (630) 829-9736 or via e-mail at jmj3@nrc.govIn accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter andits enclosure will be available electronically for public inspection in the NRC Public Document

C. Crane-3-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/Ann Marie Stone, ChiefEngineering Branch 2

Division of Reactor Safety Docket No. 50-237; 50-249License No. DPR-019; DPR-025Enclosure:Component Design Bases Inspection Document Request

cc w/encl:Site Vice President - Dresden Nuclear Power StationDresden Nuclear Power Station Plant Manager

Regulatory Assurance Manager - Dresden

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

Assistant Attorney General

Illinois Emergency Management Agency

State Liaison Officer

Chairman, Illinois Commerce Commission

C. Crane-3-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 (thePublic Electronic Reading Room).Sincerely,Ann Marie Stone, ChiefEngineering Branch 2

Division of Reactor Safety Docket No. 50-237; 50-249License No. DPR-019; DPR-025Enclosure:Component Design Bases Inspection Document Request

cc w/encl:Site Vice President - Dresden Nuclear Power StationDresden Nuclear Power Station Plant Manager

Regulatory Assurance Manager - Dresden

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

Assistant Attorney General

Illinois Emergency Management Agency

State Liaison Officer

Chairman, Illinois Commerce CommissionDOCUMENT NAME:ML070290588.wpd

G Publicly Available

G Non-Publicly Available

G Sensitive

G Non-SensitiveTo receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copyOFFICERIIIRIIIRIIIRIIINAMEMJones: lsAMStone

DATE1/29/071/29/07OFFICIAL RECORD COPY

C. Crane-4-ADAMS DISTRIBUTION

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INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION COMPONENT DESIGN BASES INSPECTIONEnclosureInspection Report:05000237/249/2007006(DRS)Inspection Dates:April 9, 2007, April 23, 2007, and May 7, 2007 Inspection Procedure:IP 71111.21, "Component Design Bases Inspection"Lead Inspector:John Jacobson, Lead Inspector (630) 829-9736 JMJ3@nrc.govI. Information Requested Prior to the On-site Inspection Activities

(by March 8, 2007, or sooner)The following information is requested by March 8, 2007, or sooner, to facilitateinspection preparation. If you have any questions regarding this information, please call

the team leader as soon as possible. (Please provide the information electronically in

"pdf" files, Excel, or other searchable formats, preferably on CDROM (two copies). The

CDROM should contain descriptive names, and be indexed and hyperlinked to facilitate

ease of use. Information in "lists" should contain enough information to be easily

understood by someone who has a knowledge of pressurized water reactor technology).1.Risk ranking of top 100 components from your site specific probabilistic safetyanalysis (PSA) sorted by Risk Achievement Worth (RAW). Include values for

Birnbaum Importance, Risk Reduction Worth (RRW), and Fussell-Veseley

(FV) (as applicable);2.Provide a list of the top 500 cut-sets from your PSA;

3.Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide copies of your human reliability worksheets for these items;4.If you have an External Events or Fire PSA Model, provide the informationrequested in Items 1 and 2 for external events and fire;5.Any pre-existing evaluation or list of components and associated calculationswith low design margins, (i.e., pumps closest to the design limit for flow or

pressure, diesel generator close to design required output, heat exchangers

close to rated design heat removal etc.);6.List of high risk Maintenance Rule systems/components based on engineeringor expert panel judgement;7.A list of operating experience evaluations for the last 3 years;

8.A list of modifications sorted by component identified in Item 1;

INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION COMPONENT DESIGN BASES INSPECTIONEnclosure9.List of and information on any common cause failure of components experiencedin the last 5 years at your facility;10.A list of the design calculations which provide the design margin information for components included in Item 1;11.List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last 5 years;12.Current management and engineering organizational chart;

13.List of Motor Operator Valves in the program, design margin and risk ranking;

14.List of System, Structures and Components in the maintenance rule (a)(1) category; and15.Site Top Ten issues list.II.Information Requested (for the approximate 30 selected components) to beAvailable by March 28, 20071.List of condition reports (corrective action documents) associated with each of theselected components for the last 3 years.2.The corrective maintenance history associated with each of the selectedcomponents for the last 2 years.3.Copies of calculations associated with each of the selected components, excluding data files. Please review the calculations and also provide copies ofreferenced material (such as drawings, engineering requests, vendor letters);4.Copies of operability evaluations associated with each of the selected components and plans for restoring operability, if applicable;5.Copies of selected operator work-around evaluations associated with each of theselected components and plans for resolution, if applicable;6.Copies of any open temporary modifications associated with each of the selectedcomponents, if applicable;7.Trend data on the selected electrical/mechanical components' performance forlast three years (For example, pumps' performance including in-service testing,

other vibration monitoring, oil sample results, (etc., as applicable); and8.Audits completed in the last 2 years.

INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION COMPONENT DESIGN BASES INSPECTIONEnclosureIII.Additional Information to be Provided on Ap

ril 9, 2007, On-siteRequest for any additional information as needed will be provided during the week ofApril 2, 2007. The lead inspector will provide a list of added information.IV.Information Requested to be provided throughout the inspection1.Copies of any corrective action documents generated as a result of the team'squestions or queries during this inspection;2.Copies of the list of questions submitted by the team members and thestatus/resolution of the information requested (provide daily during the inspection

to each team member);3.Reference materials (if available on electronic media, please provide a copy);4.General set of plant drawings;

5.IPE/PRA report; and

6.Procurement documents for components selected (verify retrievable):*Plant procedures (normal, abnormal, emergency, surveillance, etc.);

• Technical Specifications;

• Updated Final Safety Analysis Report; and

• Vendor manuals.If you have questions regarding the information requested, please contact the lead inspector.