ML053360602
| ML053360602 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/01/2005 |
| From: | Ann Marie Stone NRC/RGN-III/DRS/EB2 |
| To: | Pearce L FirstEnergy Nuclear Operating Co |
| References | |
| IR-06-009 | |
| Download: ML053360602 (9) | |
See also: IR 05000440/2006009
Text
December 1, 2005
Mr. W. Pearce
Acting Vice President
FirstEnergy Nuclear Operating Company
Perry Nuclear Power Plant
10 Center Road, A290
Perry, OH 44081
SUBJECT:
PERRY NUCLEAR POWER PLANT - INFORMATION REQUEST FOR AN NRC
BIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION (CDBI)
Dear Mr. Pearce:
On January 30, 2006, the NRC will begin a biennial baseline Component Design Bases
Inspection (CDBI) at the Perry Nuclear Power Plant. A team of six inspectors will perform this
3-week inspection. This inspection will be performed in accordance with revised NRC baseline
Inspection Procedure 71111.21 and replaces the biennial Safety System Design and
Performance Capability inspection. Please note that the revised inspection procedure will be
available shortly.
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
information gathering visit and during the subsequent in-office preparation week. 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 4 weeks on-site, including the information gathering site visit and 3
weeks of on-site inspection. The inspection team will consist of six NRC inspectors. The
current inspection schedule is as follows:
Information gathering visit: Week of January 17, 2006
On-site weeks: January 30, 2006, February 13, 2006, and February 27, 2006
The purpose of the information gathering visits, is to meet with members of your staff to identify
potential risk-significant components, and operator actions. Additional information and
documentation needed to support the inspection will also be identified. A Region III Senior
Reactor Analyst will accompany the inspection team during the information gathering visit, to
review probabilistic risk assessment data and assist in identifying risk significant components,
which will be reviewed during the inspection.
W. Pearce
-2-
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. The request has been divided into three groups. The first group lists,
information necessary for a productive information gathering visit and for general preparation.
This information should be available to the Regional Office by no later than January 6, 2006.
Insofar as possible, this information should be provided electronically to the lead inspector.
Since the inspection will concentrate on high risk/low margin components, calculations
associated with your list of high risk components should be available for the inspectors 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 are those items which the team will need access to
when on-site. 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. 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. 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 Mr. Andrew Dunlop. We understand that our regulatory
contact for this inspection is Mr. Ken Russell 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). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA by Andrew Dunlop Acting For/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-440
License No. NPF-58
Enclosure:
Component Design Bases Inspection (CDBI) Document Request
W. Pearce
-3-
cc w/encl:
G. Leidich, President - FENOC
J. Hagan, Chief Operating Officer, FENOC
D. Pace, Senior Vice President Engineering and Services, FENOC
Director, Site Operations
Director, Regulatory Affairs
M. Wayland, Director, Maintenance Department
Manager, Regulatory Compliance
T. Lentz, Director, Performance Improvement
J. Shaw, Director, Nuclear Engineering Department
D. Jenkins, Attorney, First Energy
Public Utilities Commission of Ohio
Ohio State Liaison Officer
R. Owen, Ohio Department of Health
DOCUMENT NAME:E:\\Filenet\\ML053360602.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: LS
EDuncan
ADunlop for AMStone
DATE
11/29/05
12/1/05
12/1/05
OFFICIAL RECORD COPY
W. Pearce
-3-
cc w/encl:
G. Leidich, President - FENOC
J. Hagan, Chief Operating Officer, FENOC
D. Pace, Senior Vice President Engineering and Services, FENOC
Director, Site Operations
Director, Regulatory Affairs
M. Wayland, Director, Maintenance Department
Manager, Regulatory Compliance
T. Lentz, Director, Performance Improvement
J. Shaw, Director, Nuclear Engineering Department
D. Jenkins, Attorney, First Energy
Public Utilities Commission of Ohio
Ohio State Liaison Officer
R. Owen, Ohio Department of Health
W. Pearce
-4-
ADAMS Distribution:
GYS
WAM1
RidsNrrDipmIipb
GEG
KGO
RJP
CAA1
DRPIII
DRSIII
PLB1
JRK1
WDL (IRs only)
ROPreports@nrc.gov
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
1
Inspection Report: 05000440/2006009(DRS)
Information Gathering
Dates:
January 17-20, 2006
Inspection Dates:
January 30, 2006, through February 3, 2006, February 13-17,
2006, and February 27, 2006, through March 3, 2006
Inspection Procedure:
IP 71111.21, Component Design Bases Inspection
Lead Inspector:
Andrew Dunlop, Lead Inspector
(630) 829-9726
(axd7@nrc.gov)
I.
Information Requested Prior to the Information Gathering Visit
The following information is requested by January 6, 2005, 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. 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 boiling water reactor technology).
1.
Risk ranking of top 50 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.
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
2
7.
A list of operating experience evaluations for the last 2 years.
8.
A list of modifications sorted by component identified in item 1.
9.
Information of 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. (Calculations should be available during the
information gathering visit).
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.
II.
Information Requested to be Available on First Day of Inspection (January 30,
2006)
1.
List of condition reports (corrective action documents) associated with each of
the selected components for the last 2 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 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).
8.
A copy of any internal/external self-assessments and associated corrective
action documents generated in preparation for the inspection.
INFORMATION REQUEST FOR PERRY NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
3
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 (make available if needed during all on-site weeks):
General set of plant drawings;
IPE/PRA report;
Procurement documents for components selected (verify retrievable);
Plant procedures (normal, abnormal, emergency, surveillance, etc.);
Technical Specifications;
Updated Final Safety Analysis Report; and
Vendor manuals.
If you have questions regarding the information requested, please contact the lead inspector.