ML060670336
| ML060670336 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/07/2006 |
| From: | Ann Marie Stone NRC/RGN-III/DRS/EB2 |
| To: | Conway J Nuclear Management Co |
| References | |
| IR-06-009 | |
| Download: ML060670336 (6) | |
See also: IR 05000263/2006009
Text
March 7, 2006
Mr. J. Conway
Site Vice President
Monticello Nuclear Generating Plant
Nuclear Management Company, LLC
2807 West County Road 75
Monticello, MN 55362-9637
SUBJECT:
MONTICELLO NUCLEAR GENERATING PLANT - INFORMATION REQUEST
FOR AN NRC BIENNIAL BASELINE COMPONENT DESIGN BASES
INSPECTION (CDBI) 05000263/2006009(DRS)
Dear Mr. Conway:
On May 8, 2006, the NRC will begin a biennial baseline Component Design Bases Inspection
(CDBI) at the Monticello Nuclear Generating Plant. A team of six inspectors will perform this
3 weeks 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.
The CDBI inspection focuses on components which have high risk and low margins. The
components to be reviewed during this baseline inspection will mainly be identified during an
information gathering visit and during the subsequent in-office preparation week. In addition, a
number of risk significant operator actions, modifications, 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, of which
five will focus on engineering and one on operations. The current inspection schedule is as
follows:
On-site Information gathering visit: Week of May 8-12, 2006
On-site weeks: May 22-26, 2006, June 5-9, 2006, and June 19-23, 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.
J. Conway
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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 no later than April 24, 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 team will attempt to narrow down the list of components prior to the information
gathering visit such that you will be able to focus your resources for document retrieval to those
components.
The second group of documents requested are those items which the team will need access to
after the selection of components. Additional information, such as operating experience
evaluations, procedures, condition reports, and modification packages will be requested as
those selections are completed. The third group lists information necessary to aid the
inspection team in tracking issues identified as a result of the inspection and reference material
necessary to conduct 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 licensing
contact for this inspection is Mr. Ron Baumer 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
J. Conway
-3-
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/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosure:
Component Design Bases Inspection (CDBI) Document Request
cc w/encl:
M. Sellman, Chief Executive Officer
and Chief Nuclear Officer
Manager, Regulatory Affairs
J. Rogoff, Vice President, Counsel, and Secretary
Nuclear Asset Manager, Xcel Energy, Inc.
Commissioner, Minnesota Department of Health
R. Nelson, President
Minnesota Environmental Control Citizens
Association (MECCA)
Commissioner, Minnesota Pollution Control Agency
D. Gruber, Auditor/Treasurer,
Wright County Government Center
Commissioner, Minnesota Department of Commerce
Manager - Environmental Protection Division
Minnesota Attorney Generals Office
J. Conway
-3-
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/
Ann Marie Stone, Chief
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosure:
Component Design Bases Inspection (CDBI) Document Request
cc w/encl:
M. Sellman, Chief Executive Officer
and Chief Nuclear Officer
Manager, Regulatory Affairs
J. Rogoff, Vice President, Counsel, and Secretary
Nuclear Asset Manager, Xcel Energy, Inc.
Commissioner, Minnesota Department of Health
R. Nelson, President
Minnesota Environmental Control Citizens
Association (MECCA)
Commissioner, Minnesota Pollution Control Agency
D. Gruber, Auditor/Treasurer,
Wright County Government Center
Commissioner, Minnesota Department of Commerce
Manager - Environmental Protection Division
Minnesota Attorney Generals Office
DOCUMENT NAME:C:\\MyFiles\\Roger\\ML060670336.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
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NAME
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DATE
3/07/06
3/07/06
3/07/06
3/07/06
OFFICIAL RECORD COPY
J. Conway
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ADAMS Distribution:
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INFORMATION REQUEST FOR MONTICELLO NUCLEAR GENERATING PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
1
Inspection Report: 05000263/2006009(DRS)
Information Gathering
Dates:
May 8-12, 2006
Inspection Dates:
May 22-26, 2006, June 5-9, 2006, and June 19-23, 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 April 24, 2006, 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 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. Provide narrative
description of each coded event (including fire, flood zone description);
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 available design margins for valves in the motor-operated valve (MOV)
and air-operated valve (AOV) programs;
INFORMATION REQUEST FOR MONTICELLO NUCLEAR GENERATING PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
2
7.
List of high risk Maintenance Rule systems/components based on engineering
or expert panel judgement;
8.
Structures, systems, and components (SSCs) in the Maintenance
Rule (a)(1) category;
9.
Site top ten issues list (if applicable);
10.
A list of operating experience evaluations for the last 3 years;
11.
A list of modifications sorted by the components identified in item 1;
12.
Information of any common cause failure of components experienced in the last
5 years at your facility;
13.
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. The team will attempt to narrow down the list of
components that will be reviewed prior to the information gathering visit such
that you will be able to focus your resources for document retrieval to those
components.);
14.
List of Root Cause Evaluations associated with component failures or design
issues initiated/completed in the last 5 years; and
15.
Current management and engineering organizational chart.
II.
Information Requested to be Available after Selection of Components
(Week of May 22, 2006)
1.
List of condition reports (corrective action documents) associated with each of
the selected components for the last 4 years;
2.
The corrective maintenance history associated with each of the selected
components for the last 4 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;
INFORMATION REQUEST FOR MONTICELLO NUCLEAR GENERATING PLANT
COMPONENT DESIGN BASES INSPECTION (CDBI)
Enclosure
3
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;
and
10.
Provide list of PRA assumptions regarding operator actions and the associated
procedures.
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.
One complete set of P&IDs and one line electrical drawings (paper copies); and
4.
Reference materials (make available if needed during all on-site weeks):
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.