ML12146A423

IR 05000346-12-008 (Drs), on 05/24/12 Davis-Besse Nuclear Power Station Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection

ML12146A423
Person / Time
Site:	Davis Besse
Issue date:	05/25/2012
From:	Ann Marie Stone NRC/RGN-III/DRS/EB2
To:	Allen B FirstEnergy Nuclear Operating Co
References
IR-12-008
Download: ML12146A423 (8)

See also: IR 05000346/2012008

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE ROAD, SUITE 210

LISLE, IL 60532-4352

May 25, 2012

Mr. Barry Allen

Site Vice President

FirstEnergy Nuclear Operating Company

Davis-Besse Nuclear Power Station

5501 North State Route 2, Mail Stop A-DB-3080

Oak Harbor, OH 43449-9760

SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION

FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES

INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS)

Dear Mr. Allen:

On August 13, 2012, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial

baseline Component Design Bases Inspection (CDBI) at Davis-Besse Nuclear Power Station. A

team of six inspectors will perform this 3-week inspection. This inspection will be performed in

accordance with NRC Baseline Inspection Procedure (IP) 71111.21.

The CDBI focuses on the design, maintenance, and operation of risk significant components

associated with one or more accident scenario. The components to be reviewed during this

baseline inspection will be identified during the in office preparation week that occurs prior to the

first on-site inspection week. In addition, operating experience issues, associated with the

component samples, will also be selected for review.

The inspection will include three weeks on-site. The inspection team will consist of six NRC

inspectors, of which five will focus on engineering/maintenance and one on operations. The

current inspection schedule is as follows:

• On-site weeks: August 13 - 17, 2012;

August 27 - 31, 2012; and

September 10 - 14, 2012.

The team will be preparing for the inspection, mainly during the week of August 6, 2012, as

discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the

inspection team during the week of August 13, 2012, to review probabilistic risk assessment

data, and assist in identifying risk significant components and/or specific component functions,

which will be reviewed during the inspection.

Experience with previous baseline design inspections of similar depth and length has shown

that this type of inspection is 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

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

inspector. The information request has been divided into three groups:

B. Allen -2-

• The first group lists information necessary for our initial inspection scoping activities.

This information should be provided to the lead inspector no later than July 2, 2012. By

July 13, 2012, the lead inspector will communicate the initial selected set of approximately 20

components.

• The second group of documents requested is those items needed to support our in-office

preparation activities. This set of documents, including the calculations associated with the

initial selected components, should be provided to the lead inspector at the Regional Office no

later than August 1, 2012. 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 onsite on August 13, 2012. 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 Andrew Dunlop. If you have questions regarding the

information requested, please contact Mr. Dunlop at (630) 829-9726 or via e-mail at

andrew.dunlop@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, control number 3150-0011.

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for

information or an information collection requirement unless the requesting document displays a

currently valid Office of Management and Budget control number.

In accordance with 10 CFR 2.390 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),

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 No. 50-346

License No. NPF-3

Enclosure: INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

cc w/encl: Distribution via ListServ'

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

Inspection Report: 05000346/2012008(DRS)

Inspection Dates: August 13 - 17, 2012; August 27 - 31, 2012; and

September 10 - 14, 2012

Inspection Procedure: Inspection Procedure (IP) 71111.21 Component Design Bases

Inspection

Lead Inspector: Andrew Dunlop, Lead Inspector

(630) 829-9726

andrew.dunlop@nrc.gov

I. Information Requested Prior to the On-site Information Gathering/Inspection Week

The following information is requested by July 2, 2012, 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 some portable electronic media (e.g.,

CDROM, DVD, flash drive, etc.). The portable electronic media 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

knowledge of light water reactor technology).

1. Risk ranking of top 250 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. Risk ranking of top 100 containment-related components from your site specific PSA

sorted by Large Early Release Frequency (LERF).

3. Provide a list of the top 200 cut-sets from your PSA.

4. Provide a list of the top 100 cut-sets for each initiator modeled in the PSA that

contributes more than 5 percent to the baseline plant core damage frequency

(CDF).

5. Copies of PSA system notebooks and latest PSA summary document.

6. List of time critical operator actions. Identify those actions that do not have job

performance measures (JPMs).

7. Provide copies of the emergency operating procedures (EOPs).

8. 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).

1 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

9. Electronic copy of the site IPEEE, if available.

10. 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.).

11. List of available design (setup) margins in both the open and closed direction

(identify safety-related direction) for valves in the motor-operated valve (MOV) and

air-operated valve (AOV) programs. Identify the basis for how the margin was

determined.

12. List of high risk Maintenance Rule systems/components based on engineering or

expert panel judgment (i.e., those systems/components not identified in the PRA).

13. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1)

category for the last 3 years.

14. Site top ten issues list (if applicable).

15. A list of operating experience evaluations for the last three years.

16. Information of any common cause failure of components experienced in the last 5

years at your facility.

17. List of Root Cause Evaluations associated with component failures or design issues

initiated/completed in the last 5 years.

18. List of open operability evaluations.

19. List of components/systems considered operable but degraded/nonconforming.

20. Current management and engineering organizational chart.

21. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications,

Technical Specifications Bases, and Technical Requirements Manual.

22. Major one line electrical drawings (ac and dc) and key diagrams (paper copies).

23. Electronic copy of P&IDs (if available).

2 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

II. Information Requested (For The Approx. 20 Selected Components) to be Available

By August 1, 2012, (Will Be Reviewed by the Team in the Regional Office During the

Week of August 6, 2012)

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 four years.

2. The maintenance history (corrective, preventive, and elective) associated with each

of the selected components for the last 10 years. Identify frequency of preventive

maintenance activities.

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 important referenced material (such as drawings, engineering

requests, and vendor letters).

4. System Health Reports, System Descriptions, Design Basis Documents, and/or

Training Lesson Plans that are associated with each of the selected components.

5. A list of modifications, including equivalency evaluations and setpoint changes,

associated with each of the selected components. This list should include a

descriptive paragraph on the purpose of the modification. Please ensure this list

only includes design completed (not canceled) modifications.

6. Copies of operability evaluations (open/closed for last three years) associated with

each of the selected components and plans for restoring operability, if applicable.

7. Copies of selected operator work-around evaluations associated with each of the

selected components and plans for resolution, if applicable.

8. Copies of any open temporary modifications associated with each of the selected

components, if applicable.

9. Trend data on the selected electrical/mechanical components performance for last

three years (For example, pumps performance including in-service testing, other

vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate

results, etc.).

10. Copy of latest completed surveillance tests for each component (for example, for

pumps this would include: comprehensive test, quarterly test, flow balance, etc., for

valves: stroke time testing, diagnostic testing, leak testing, etc.). Acceptance criteria

basis calculations should also be included.

11. Provide copies of the normal and abnormal operating procedures associated with

the selected components and selected scenarios.

3 Enclosure

INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION

12. A copy of any internal/external self-assessments and associated corrective action

documents generated in preparation for the inspection.

13. A copy of engineering/operations related audits completed in the last two years.

III. Additional Information to be Provided on August 13, 2012, On-Site (for final selected

Components)

During the in-office preparation activities, the team will be making final selections and may

identify additional information needed to support the inspection. The lead inspector will

provide a list of the additional information needed during the week of August 6, 2012.

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 (paper copies).

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.

The lead inspector for this inspection is Andrew Dunlop. If there are any questions about the

inspection or the material requested in the enclosure, please contact the lead inspector at

(630) 829-9726 or via e-mail at andrew.dunlop@nrc.gov.

4 Enclosure

B. Allen -2-

• The first group lists information necessary for our initial inspection scoping activities. This information should

be provided to the lead inspector no later than July 2, 2012. By July 13, 2012, the lead inspector will

communicate the initial selected set of approximately 20 components.

• The second group of documents requested is those items needed to support our in-office preparation

activities. This set of documents, including the calculations associated with the initial selected components,

should be provided to the lead inspector at the Regional Office no later than August 1, 2012. 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 onsite on August 13, 2012. 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 Andrew Dunlop. If you have questions regarding the information

requested, please contact Mr. Dunlop at (630) 829-9726 or via e-mail at andrew.dunlop@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the Paperwork

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by

the Office of Management and Budget, control number 3150-0011. The NRC may not conduct or sponsor, and a

person is not required to respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control number.

In accordance with 10 CFR 2.390 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), 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 No. 50-346

License No. NPF-3

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OFFICE RIII RIII

NAME ADunlop:ls AMStone

DATE 05/24/12 05/24/12

OFFICIAL RECORD COPY

Letter to Mr. Barry Allen from Ms. Ann Marie Stone dated May 24, 2012.

SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION REQUEST FOR INFORMATION

FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES

INSPECTION (CDBI) INSPECTION REPORT 05000346/2012008 (DRS)

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