ML070290588
| 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, 2007
Mr. Christopher M. Crane
President and Chief Nuclear Officer
Exelon Nuclear
Exelon Generation Company, LLC
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: 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-week
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 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: April 9, 2007, April 23, 2007, and May 7, 2007
The team will be preparing for the inspection mainly during the week of April 2, 2007, as
discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the
inspection 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 shown
that 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 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:
- 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 our
in-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 plant
specific 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.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
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, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-237; 50-249
Enclosure: Component Design Bases Inspection Document Request
cc w/encl: Site Vice President - Dresden Nuclear Power Station
Dresden 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 (the
Public Electronic Reading Room).
Sincerely,
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-237; 50-249
Enclosure: Component Design Bases Inspection Document Request
cc w/encl: Site Vice President - Dresden Nuclear Power Station
Dresden 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
DOCUMENT NAME:ML070290588.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 RIII
NAME MJones: ls AMStone
DATE 1/29/07 1/29/07
OFFICIAL RECORD COPY
C. Crane -4-
ADAMS DISTRIBUTION:
TEB
JFW1
RidsNrrDirsIrib
GEG
KGO
GLS
CJP3
CAA1
DRPIII
DRSIII
PLB1
TXN
INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION
COMPONENT DESIGN BASES INSPECTION
Inspection 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.gov
I. 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 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 (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 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 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 information
requested in Items 1 and 2 for external events and fire;
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.);
6. List of high risk Maintenance Rule systems/components based on engineering
or 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;
Enclosure
INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION
COMPONENT DESIGN BASES INSPECTION
9. List of and information on any common cause failure of components experienced
in 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; and
15. Site Top Ten issues list.
II. Information Requested (for the approximate 30 selected components) to be
Available by March 28, 2007
1. List of condition reports (corrective action documents) associated with each of the
selected components for the last 3 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,
excluding data files. Please review the calculations and also provide copies of
referenced 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 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 three years (For example, pumps performance including in-service testing,
other vibration monitoring, oil sample results, (etc., as applicable); and
8. Audits completed in the last 2 years.
Enclosure
INFORMATION REQUEST FOR DRESDEN NUCLEAR POWER STATION
COMPONENT DESIGN BASES INSPECTION
III. Additional Information to be Provided on April 9, 2007, On-site
Request for any additional information as needed will be provided during the week of
April 2, 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. 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;
- Vendor manuals.
If you have questions regarding the information requested, please contact the lead inspector.
Enclosure