ML070851413
| ML070851413 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/26/2007 |
| From: | Ann Marie Stone NRC/RGN-III/DRS/EB2 |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| References | |
| IR-07-007 | |
| Download: ML070851413 (10) | |
See also: IR 05000346/2007007
Text
March 26, 2007
Mr. Mark B. Bezilla
Site Vice President
FirstEnergy Nuclear Operating Company
Davis-Besse Nuclear Power Station
5501 North State Route 2
Oak Harbor, OH 43449-9760
SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION - INFORMATION REQUEST
FOR AN NRC BIENNIAL BASELINE COMPONENT DESIGN BASES
INSPECTION 05000346/2007007(DRS)
Dear Mr. Bezilla:
On October 22, 2007, the NRC will begin a biennial baseline Component Design Bases
Inspection (CDBI) at the Davis-Besse Nuclear Power Station. 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 the 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 on-site, including the information gathering during the
first on-site week. The inspection team will consist of six NRC inspectors, of whom five will
focus on engineering and one on operations. The current inspection schedule is as follows:
- October 22 through October 26, 2007;
- November 5 through November 9, 2007; and
- November 26 through November 30, 2007.
The team will be preparing for the inspection, mainly during the week of October 15, 2007, as
discussed in the attached enclosure. A Region III Senior Reactor Analyst may accompany the
inspection team during the week of October 22, 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.
M. Bezilla -2-
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
September 24, 2007. By October 3, 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
associated with the initial selected components, should be available at the Regional
Office no later than October 10, 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 the first day of
the inspection. It is also requested that corrective action documents and questions
developed during the inspection be provided to the inspectors throughout the inspection.
The lead inspector for this inspection is Mr. Andrew Dunlop. We understand that our licensing
contact for this inspection is Mr. G. Wolfe of your organization. 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 AXD7@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 No. 50-346
License No. NPF-3
Enclosure: Component Design Bases Inspection Document Request
See Attached Distribution
M. Bezilla -3-
cc w/encl: The Honorable Dennis Kucinich
G. Leidich, President and Chief
Nuclear Officer - FENOC
J. Hagan, Senior Vice President of
Operations and Chief Operating Officer
Richard Anderson, Vice President, Nuclear Support
Manager - Site Regulatory Compliance
D. Pace, Senior Vice President of
of Fleet Engineering
J. Rinckel, Vice President, Fleet Oversight
D. Jenkins, Attorney, FirstEnergy
Director, Fleet Regulatory Affairs
Manager - Fleet Licensing
Ohio State Liaison Officer
R. Owen, Administrator, Ohio Department of Health
Public Utilities Commission of Ohio
President, Lucas County Board of Commissioners
President, Ottawa County Board of Commissioners
M. Bezilla -2-
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
September 24, 2007. By October 3, 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
associated with the initial selected components, should be available at the Regional
Office no later than October 10, 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 the first day of
the inspection. It is also requested that corrective action documents and questions
developed during the inspection be provided to the inspectors throughout the inspection.
The lead inspector for this inspection is Mr. Andrew Dunlop. We understand that our licensing
contact for this inspection is Mr. G. Wolfe of your organization. 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 AXD7@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 No. 50-346
License No. NPF-3
Enclosure: Component Design Bases Inspection Document Request
See Attached Distribution
DOCUMENT NAME:C:\FileNet\ML070851413.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 ADunlop:jb DPassehl AM Stone
DATE 03/ /07 03/ /07 03/ /07
OFFICIAL RECORD COPY
M. Bezilla -3-
cc w/encl: The Honorable Dennis Kucinich
G. Leidich, President and Chief
Nuclear Officer - FENOC
J. Hagan, Senior Vice President of
Operations and Chief Operating Officer
Richard Anderson, Vice President, Nuclear Support
Manager - Site Regulatory Compliance
D. Pace, Senior Vice President of
of Fleet Engineering
J. Rinckel, Vice President, Fleet Oversight
D. Jenkins, Attorney, FirstEnergy
Director, Fleet Regulatory Affairs
Manager - Fleet Licensing
Ohio State Liaison Officer
R. Owen, Administrator, Ohio Department of Health
Public Utilities Commission of Ohio
President, Lucas County Board of Commissioners
President, Ottawa County Board of Commissioners
DISTRIBUTION:
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SPS1
TJW2
RidsNrrDirsIrib
GEG
KGO
GLS
JER7
CAA1
DRPIII
DRSIII
PLB1
TXN
COMPONENT DESIGN BASES INSPECTION
INFORMATION REQUEST
Site: Davis-Besse Nuclear Power Station
Inspection Report: 05000346/2007007(DRS)
Inspection Dates: October 22 through October 26, November 5 through
November 9; and November 26 through November 30, 2007
Inspection Procedure: IP 71111.21, Component Design Bases Inspection
Lead Inspector: Andrew Dunlop, (630) 829-9726 (AXD7@nrc.gov)
I. Information Requested Prior to the On-site Information Gathering/Inspection
Week
The following information is requested by September 24, 2007, or sooner, to facilitate
inspection preparation. If you have any questions regarding this information, please call
the lead inspector as soon as possible. (Please provide the information electronically in
pdf files, Excel, or other searchable formats, preferably either through electronic mail
or 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 light water
reactor technology).
1. Provide the 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). If possible, list the system, train, and PSA
failure mode for each component.
2. Provide a list of the top 200 cut-sets from your PSA.
3. 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).
4. Provide a risk ranking of operator actions from your site specific PSA sorted by
RAW. Provide copies of your human reliability worksheets for these items.
5 Provide a list of PSA assumptions regarding operator actions.
6. Provide 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.).
1 Enclosure
COMPONENT DESIGN BASES INSPECTION
INFORMATION REQUEST
7. Provide a list of available design (setup) margins for valves in the motor-
operated valve (MOV) and air-operated valve (AOV) programs.
8. Provide a list of high risk Maintenance Rule systems/components based on
engineering or expert panel judgement.
9. Provide a list of structures, systems, or components (SSCs) in the Maintenance
Rule (a)(1) category.
10. Provide the site top ten issues list (if applicable).
11. Provide information on any common cause failure of components experienced in
the last five years at your facility.
12. Provide a list of Root Cause Evaluations associated with component failures or
design issues initiated or completed in the last five years.
II. Information requested (for the approximately 30 selected components) to be
available by October 10, 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.). Please provide separate disks for electrical and mechanical
components.
1. Provide a list and copies of condition reports (corrective action documents)
associated with each of the selected components for the last four years.
2. Provide the completed corrective maintenance history associated with each of
the selected components for the last four years. Please ensure this list only
includes completed activities and does not include routine surveillances.
3. Provide copies of calculations associated with each of the selected components
(if not previously provided), excluding data files. Please review the calculations
and provide copies of referenced material (such as drawings, engineering
requests, or vendor letters).
4. Provide a list of modifications 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.
5. Provide copies of electrical single-lines and mechanical piping and
instrumentation drawings.
2 Enclosure
COMPONENT DESIGN BASES INSPECTION
INFORMATION REQUEST
6. Provide copies of operability evaluations associated with each of the selected
components and plans for restoring operability, if applicable.
7. Provide copies of any operator work-around evaluations associated with each of
the selected components and plans for resolution, if applicable.
8. Provide copies of any open temporary modifications associated with each of the
selected components, if applicable.
9. Provide 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).
10. Provide System Health Reports, System Descriptions, and/or Design Basis
Documents that are associated with each of the selected components.
11. Provide copies of operating experience evaluations associated with the selected
components for the last three years.
12. Provide copies of any simulator scenarios, lesson plans, or job performance
measures for the selected operator actions.
13. Provide copies of the emergency operating procedures, normal and abnormal
operating procedures and any alarm response procedures for the selected
operator actions.
14. Provide a copy of any engineering or operations related audits completed in the
last two years which addressed the selected components.
15. Provide a copy of the current management and engineering organizational chart.
Highlight or otherwise provide the names of any inspection contacts or inspector
shadows.
16. Provide electronic copies of Updated Final Safety Analysis Report, Technical
Specifications, Technical Specifications Bases, and Technical Requirements
Manual, if available.
17. Provide a copy of any internal/external self-assessments and associated
corrective action documents generated in preparation for the inspection.
III. Additional Information to be Provided on October 22, 2007 On-site (for final 15 -
20 selected components)
1. A request for any additional information needed will be provided during the week
of October 15, 2007. The lead inspector will provide a list of added information.
3 Enclosure
The lead inspectors may request hard copies of information provided
electronically, especially drawings and calculations.
2. One complete set of piping and instrumentation drawings (P&IDs) and one-line
electrical drawings (paper copies)
3. The following background materials may be requested. It is recommended that
these materials be identified and located prior to the inspection:
- IPE/PRA report;
- Procurement documents for components selected;
- Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
- Vendor manuals.
4. Please arrange for a short presentation of the design control process. This
presentation may include any information deemed pertinent to the inspection.
5. Please arrange for an overview walkdown of the selected components. This
should include any required radiological briefings. For any components not
normally accessible, please arrange for a briefing on what conditions prevent
access to the components.
6. If plant information, such as corrective action documents or procedures, is
available electronically onsite, please consider providing access for the
inspectors, along with simple instructions.
IV. Information Requested to be provided throughout the inspection
1 Provide copies of any corrective action documents generated as a result of the
teams questions or queries during this inspection. This includes and
licensee-identified corrective action documents generated while answering an
inspector question. Please provide two copies: one to the inspector and one to
the lead inspector. At the end of the inspection, please provide the lead
inspector with a complete list of all corrective action documents generated as a
result of the inspection.
2 Provide copies of the list of questions submitted by the team members and the
status/resolution of the information requested. Each inspector should receive at
least a copy of his/her open questions, while the lead inspector should receive a
complete list. At the end of the inspection, please provide the lead inspector with
a complete electronic copy of the database.
If you have questions regarding any of the information requested, please contact the lead
inspector.
4 Enclosure