ML091060654
| 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
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
4815 West Markham Street, Slot 30
Little Rock, AR 72205-3867
Section Chief, Division of Health
Emergency Management Section
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
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