ML091060654

IR 05000313-09-007, IR 05000368-09-007, for Arkansas One-Initial Information Request for NRC Triennial Baseline Component Design Bases Inspection

ML091060654
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/16/2009
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Walsh K Entergy Operations
References
IR-09-007
Download: ML091060654 (9)

See also: IR 05000313/2009007

Text

UNITED S TATE S

N UCLE AR REGU LATORY COMMI SS ION

R E GI ON I V

6 1 2 E. LAMAR BLVD. , SU ITE 4 00

AR LIN GTON , TEXAS 7 6 01 1- 4005

April 16, 2009

Kevin Walsh, Vice President, Operations

Entergy Operations, Inc.

Arkansas Nuclear One

1448 S.R. 333

Russellville, AR 72802

SUBJECT: ARKANSAS NUCLEAR ONE - INITIAL INFORMATION REQUEST FOR NRC

TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC

INSPECTION REPORT 05000316; 05000368/2009007

Dear Mr. Mitchell:

On June 15, 2009, the NRC will begin a triennial baseline Component Design Bases Inspection

at the Arkansas Nuclear One. A six-person team will perform this inspection using NRC

Inspection Procedure 71111.21, Component Design Bases Inspection.

The inspection focuses on components and operator actions that have high risk and low design

margins. The samples reviewed during this inspection will be identified during an information

gathering visit and during the subsequent in-office preparation week. In addition, a number of

operating experience issues will also be selected for review.

The inspection will include an information gathering site visit by the team leader and a senior

reactor analyst, and 3-weeks of onsite inspection by the team. The inspection will consist of

four NRC inspectors and two contractors, of which five will focus on engineering and one on

operations. The current inspection schedule is as follows:

Onsite information gathering visit: Week of June 15, 2009

Preparation Week: June 29, 2009

Onsite weeks: July 6 and July 20 thru July 31, 2009

The purpose of the information gathering visit is to meet with members of your staff to identify

potential risk-significant components and operator actions. The lead inspector will also request

a tour of the plant with members of your operations staff and probabilistic safety assessment

staff. During the onsite weeks, several days of time will be needed on the plant-referenced

simulator in order to facilitate the development of operator action-based scenarios. Additional

information and documentation needed to support the inspection will be identified during the

inspection, including interviews with engineering managers, engineers, and probabilistic safety

assessment staff.

Entergy Operations, Inc. -2-

Our experience with these inspections has shown that they 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, we have enclosed a

request for information needed for the inspection. The request has been divided into

three groups. The first group lists information necessary for the information gathering

visit and for general preparation. This information should be available to the regional

office no later than May 26, 2009. Insofar as possible, this information should be

provided electronically to the lead inspector. Since the inspection will be concentrated

on high risk/low margin components, calculations associated with your list of high risk

components should be available to review during the information gathering visit to assist

in our selection of components based on available design margin.

The second group of documents requested is those items that the team will need access

to during the preparation week in order to finalize the samples to be inspected. The third

group lists 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. Additional requests by

inspectors will be made throughout all three onsite weeks for specific documents needed

to complete the review of that component/selection. 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.

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.

The lead inspector for this inspection is Wayne Sifre. We understand that our licensing

engineer contact for this inspection is Dick Scheide. If there are any questions about

the inspection or the requested materials, please contact the lead inspector at (817) 860-

8193 or via e-mail at Wayne.Sifre@nrc.gov .

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter

will be made 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/

Thomas Farnholtz, Chief

Engineering Branch 1

Division of Reactor Safety

Dockets: 50-313; 50-368

Licenses: DPR-51; NPF-6

Enclosure:

Component Design Basis Inspection

Document Request

Entergy Operations, Inc. -3-

cc w/enclosure:

Senior Vice President

Entergy Operations, Inc.

P.O. Box 31995

Jackson, MS 39286-1995

Senior Vice President

& Chief Operating Officer

Entergy Operations, Inc.

P.O. Box 31995

Jackson, MS 39286-1995

Vice President, Oversight

Entergy Operations, Inc.

P.O. Box 31995

Jackson, MS 39286-1995

Manager, Licensing

Entergy Operations, Inc.

Arkansas Nuclear One

1448 SR 333

Russellville, AR 72802

Associate General Counsel

Entergy Nuclear Operations

P.O. Box 31995

Jackson, MS 39286-1995

Senior Manager, Nuclear Safety & Licensing

Entergy Operations, Inc.

P.O. Box 31995

Jackson, MS 39286-1995

Chief, Radiation Control Section

Arkansas Department of Health

4815 West Markham Street, Slot 30

Little Rock, AR 72205-3867

Section Chief, Division of Health

Emergency Management Section

Arkansas Department of Health

4815 West Markham Street, Slot 30

Little Rock, AR 72205-3867

David E. Maxwell, Director

Arkansas Department of Emergency

Management, Bldg. 9501

Camp Joseph T. Robinson

North Little Rock, AR 72199

Entergy Operations, Inc. -4-

Pope County Judge

Pope County Courthouse

100 West Main Street

Russellville, AR 72801

Entergy Operations, Inc. -5-

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov )

Deputy Regional Administrator (Chuck.Casto@nrc.gov )

DRP Director (Dwight.Chamberlain@nrc.gov)

DRP Deputy Director (Anton.Vegel@nrc.gov )

DRS Director (Roy.Caniano@nrc.gov )

DRS Deputy Director (Troy.Pruett@nrc.gov )

Senior Resident Inspector (Alfred.Sanchez@nrc.gov)

Resident Inspector (Jeffrey.Josey@nrc.gov )

Branch Chief, DRP/E (Jeff.Clark@nrc.gov )

Senior Project Engineer, DRP/E (George.Replogle@nrc.gov)

ANO Site Secretary (Vicki.High@nrc.gov )

Public Affairs Officer (Victor.Dricks@nrc.gov )

Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov )

RITS Coordinator (Marisa.Herrera@nrc.gov )

OEMail Resource

Senior Enforcement Specialist (Mark.Haire@nrc.gov )

File located: R:REACTORS\ANO RFI - WCS ML091060654

SUNSI Rev Compl. ; Yes No ADAMS  ; Yes No Reviewer WCS

Initials

Publicly Avail  ; Yes No Sensitive Yes ; No Sens. Type WCS

Initials

EB 1 C:EB 1

W. Sifre T. Farnholtz

/RA/ /RA/

4/15/09 4/16/09

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

INFORMATION REQUEST FOR ARKANSAS NUCLEAR ONE COMPONENT DESIGN

BASES (CDBI) INSPECTION

Inspection Report: 05000313; 05000368/2009007

Information Gathering Dates: June 16-18, 2009

On-site Inspection Dates: July 6-10 and July 20-31, 2009

Inspection Procedure: IP 71111.21, Component Design Bases

Inspection

Lead Inspector/Team Leader: Wayne C. Sifre

817-860-8193

Wayne.Sifre@nrc.gov

I. Information Requested Prior to the information Gathering Visit (June 16-18,

2009)

The following information (Section I of this enclosure) should be sent to the

Region IV office in hard copy or electronic format (ims.certrec.com preferred), in

care of Wayne C. Sifre, by May 26,2009 to facilitate the reduction in the items to

be selected for a final list during the preparation week June 29, 2009. The

inspection team will finalize the selected list during the prep week using the

additional documents requested in Section II of this enclosure. The specific items

selected from the lists shall be available and ready for review on the day

indicated in this request. *Please provide requested documentation electronically

in pdf files, Excel, or other searchable formats, if possible. The information

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 pressurized water reactor

technology. If requested documents are large and only hard copy formats are

available, please inform the inspector(s), and provide subject documentation

during the first day of the onsite inspection.

1. An excel spreadsheet of equipment basic events (with definitions)

including importance measures sorted by risk achievement worth (RAW)

and Fussell-Vesely (FV) from your internal events probabilistic risk

assessment (PRA). Include basic events with RAW value of 1.3 or

greater.

2. Provide a list of the top 500 cut-sets from your PRA.

3. Copies of PRA system notebooks, and the latest PRA summary

document.

-1- Enclosure

4. An excel spreadsheet of PRA human action basic events or risk ranking

of operator actions from your site specific PSA sorted by RAW and FV.

Provide copies of your human reliability worksheets for these items.

5. If you have an external events or fire PSA model, provide the information

requested in items 1-4 for external events and fire.

6. 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.).

7. List of high risk maintenance rule systems/components and functions;

based on engineering or expert panel judgment.

8. A list of operating experience evaluations for the last 2 years.

9. A list of all time-critical operator actions in procedures.

10. A list of permanent and temporary modifications sorted by component

identified in Item 1.

11. List of current operator work arounds/burdens.

12. A list of the design calculations, which provide the design margin

information for components included in Item 1. (Calculations should be

available during the information gathering visit).

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 charts.

15. Arkansas Nuclear One IPEEE, if available electronically.

16. Mechanical piping drawings for:

Engineered safety features

Emergency core cooling systems

Emergency diesel generators

17 Electrical one-line drawings for:

Offsite power/switchyard supplies

Normal AC power systems

Emergency AC/DC power systems including

120VAC power, and

125VDC/24VDC safety class systems

18. List of any common-cause failures of components in the last 3 years.

19. An electronic copy of the Design Bases Documents.

20. An electronic copy of the System Health notebooks.

II. Information Requested to be Available on First Day of Preparation Week

(June 29, 2009)

1. List of condition reports (corrective action documents) associated with

each of the selected components for the last 5 years.

2. The corrective maintenance history associated with each of the selected

components for the last 2 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 reference material (such as

drawings, engineering requests, and 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 the selected components and plans for resolution, if applicable.

6. Copies of any open temporary modifications associated with each of the

selected components, if applicable.

7. 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).

8. A copy of any internal/external self-assessments and associated

corrective action documents generated in preparation for the inspection.

9. A copy of engineering/operations related audits completed in the last 2

years.

10. List of motor operated valves (MOVs) in the program, design margin and

risk ranking.

11. List of air operated valves (AOVs) in the valve program, design and risk

ranking.

12. Structure, system and components in the Maintenance Rule (a)(1)

category.

13. Site top 10 issues list.

14. Procedures used to accomplish operator actions associated with the

basic events in your PRA.

15. List of licensee contacts for the inspection team with pager or phone

numbers.

III. 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. Reference materials (available electronically and as needed during all

onsite weeks):

General set of plant drawings

IPE/PRA report

Procurement documents for components selected

Plant procedures (normal, abnormal, emergency, surveillance, etc.)

Technical Specifications

Updated Final Safety Analysis Report

Vendor manuals

Inspector Contact Information:

Wayne C. Sifre

Senior Reactor Inspector

(817) 860-8193

Wayne.Sifre@nrc.gov

Mailing Address:

US NRC, Region IV

Attn: Wayne C. Sifre

612 East Lamar Blvd, Ste 400

Arlington, TX 76011