ML063120428

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Ltr. 11/07/06 D. C. Cook Request for Information IR 07-002
ML063120428
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 11/07/2006
From: Ann Marie Stone
NRC/RGN-III/DRS/EB2
To: Nazar M
Indiana Michigan Power Co
References
IR-07-002
Download: ML063120428 (9)


Text

November 7, 2006 Mr. Mano K. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

SUBJECT:

D.C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2, INFORMATION REQUEST FOR AN NRC BIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI) 05000315/2007002(DRS); 316/2007002(DRS)

Dear Mr. Nazar:

On January 29, 2007, the NRC will begin a biennial baseline Component Design Bases Inspection (CDBI) at the D.C. Cook Nuclear Power Plant. A team of six inspectors will perform this 3-week onsite inspection. 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 one week of in-office preparation/information gathering and three weeks of on-site inspection. The inspection team will consist of six NRC inspectors, of which five will focus on engineering and one on operations. The current inspection schedule is as follows:

On-site weeks: January 29, February 12, and February 26, 2007.

The team will be preparing for the inspection mainly during the week of January 22, 2007, as discussed in the attached enclosure. A Region III Senior Reactor Analyst will accompany the inspection team during the week of January 29, 2007, to review probabilistic risk assessment data and assist in identifying risk significant components, which will be reviewed during the inspection.

Experience with previous baseline design inspections of similar depth and length has shown that these type 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 the

number of additional documents requested during the preparation and/or the on-site portions of M. Nazar 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 January 2, 2007. By January 8, 2007, the lead inspector will communicate the initial selected set of approximately 30 high risk components.

The second group of documents requested are those items needed to support our in-office preparation activities. This set of documents, including the calculations (please provide the mechanical calculations on one disk and the electrical calculations on another disk) associated with the initial selected components, should be available at the Regional Office no later than January 18, 2007. During the in-office preparation activities, the team may identify additional information needed to support the inspection.

The last group includes the additional information above as well as plant specific reference material. This information should be available to the team on January 29, 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. George Hausman. We understand that our regulatory assurance contact for this inspection is Mr. Richard Miester of your organization. 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) 829-9743 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/

Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74

Enclosure:

Component Design Bases Inspection (CDBI) Document Request

See Attached Distribution

M. Nazar cc w/encl:

M. Peifer, Site Vice President L. Weber, Plant Manager S. Simpson, Regulatory Affairs Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality -

Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan

M. Nazar 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 January 2, 2007. By January 8, 2007, the lead inspector will communicate the initial selected set of approximately 30 high risk components.

The second group of documents requested are those items needed to support our in-office preparation activities. This set of documents, including the calculations (please provide the mechanical calculations on one disk and the electrical calculations on another disk) associated with the initial selected components, should be available at the Regional Office no later than January 18, 2007. During the in-office preparation activities, the team may identify additional information needed to support the inspection.

The last group includes the additional information above as well as plant specific reference material. This information should be available to the team on January 29, 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. George Hausman. We understand that our regulatory assurance contact for this inspection is Mr. Mr. Richard Miester of your organization. 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) 829-9743 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, Ann Marie Stone, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74

Enclosure:

Component Design Bases Inspection (CDBI) Document Request See Attached Distribution DOCUMENT NAME:C:\\FileNet\\ML063120428.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 RIII RIII NAME GHausman: ls AMStone DPassehl DATE 11/02/06 11/06/06 11/07/06 OFFICIAL RECORD COPY

M. Nazar cc w/encl:

M. Peifer, Site Vice President L. Weber, Plant Manager S. Simpson, Regulatory Affairs Manager G. White, Michigan Public Service Commission L. Brandon, Michigan Department of Environmental Quality -

Waste and Hazardous Materials Division Emergency Management Division MI Department of State Police State Liaison Officer, State of Michigan DISTRIBUTION:

TEB PST RidsNrrDirsIrib GEG KGO GLS BJK1 CAA1 DRPIII DRSIII PLB1 TXN ROPreports@nrc.gov

INFORMATION REQUEST FOR D.C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 COMPONENT DESIGN BASES INSPECTION (CDBI)

Enclosure 1

Inspection Report:

05000315/316/2007002(DRS)

Information Gathering Dates: In-Office Week:

January 22, 2007 Inspection Dates:

Onsite Weeks:

January 29, February 12, and February 26, 2007 Inspection Procedure:

IP 71111.21, Component Design Bases Inspection Lead Inspector:

George Hausman, Lead Inspector (630) 829-9743 (gmh1@nrc.gov)

I.

Information Requested Prior to the On-site Information Gathering/Inspection Week The following information is requested by January 2, 2007, or sooner, to facilitate inspection 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. 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 boiling water reactor technology).

1.

Risk ranking of top 150 components from your site specific probabilistic safety analysis (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 200 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 information requested in Items 1 and 2 for external events and fire. Provide narrative description of each coded event (including fire, flood zone description);

5.

Any pre-existing evaluation or list of components and associated calculations with 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.);

INFORMATION REQUEST FOR D.C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 COMPONENT DESIGN BASES INSPECTION (CDBI)

Enclosure 2

6.

List of available design (setup) margins for valves in the motor-operated valve (MOV) and air-operated valve (AOV) programs; 7.

List of high risk Maintenance Rule systems/components based on engineering or expert panel judgement; 8.

Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1) category; 9.

Site top ten issues list (if applicable);

10.

System Health Reports, System Descriptions, and/or Design Basis Documents that are associated with each of the selected components; 11.

A list of operating experience evaluations for the last 3 years; 12.

Information of any common cause failure of components experienced in the last 5 years at your facility; 13.

List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last 5 years; 14.

Current management and engineering organizational chart; and 15.

Electronic copies of Updated Final Safety Analysis Report, Technical Specifications, Technical Specifications Bases, and Technical Requirements Manual.

II.

Information Requested (for the approx. 30 selected components) to be Available by January 18, 2007, (will be reviewed by the team in the Regional office during the week of January 22, 2007). This information should be separated for each selected component, especially if provided electronically (e.g., folder with component name that includes calculations, condition reports, maintenance history, etc).

1.

List of condition reports (corrective action documents) associated with each of the selected components for the last 4 years; 2.

The corrective maintenance history associated with each of the selected components for the last 4 years; 3.

Copies of calculations associated with each of the selected components (if not previously provided), excluding data files. Please review the calculations and also provide copies of referenced material (such as drawings, engineering requests, vendor letters);

INFORMATION REQUEST FOR D.C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 COMPONENT DESIGN BASES INSPECTION (CDBI)

Enclosure 3

4.

A list of modifications associated with each of the selected components; 5.

Copies of operability evaluations associated with each of the selected components and plans for restoring operability, if applicable; 6.

Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable; 7.

Copies of any open temporary modifications associated with each of the selected components, if applicable; 8.

Trend data on the selected electrical/mechanical components performance for last 3 years (For example, pumps performance including in-service testing, other vibration monitoring, oil sample results, etc., as applicable);

9.

A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection; 10.

A copy of engineering/operations related audits completed in the last 2 years; and 11.

Provide list of PRA assumptions regarding operator actions and the associated procedures.

III.

Additional Information to be Provided on January 29, 2007 On-site (for final 15 -

20 selected components)

Request for the additional information needed will be provided during the week of January 22, 2007. The lead inspector will provide a list of added information.

IV.

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);

3.

One complete set of P&IDs and one line electrical drawings (paper copies); and

INFORMATION REQUEST FOR D.C. COOK NUCLEAR POWER PLANT, UNITS 1 AND 2 COMPONENT DESIGN BASES INSPECTION (CDBI)

Enclosure 4

4.

Reference materials (make available if needed during all on-site weeks):

IPE/PRA report; Procurement documents for components selected (verify retrievable);

Plant procedures (normal, abnormal, emergency, surveillance, etc.); and Vendor manuals.

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