ML081580079
| ML081580079 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/05/2008 |
| From: | William Jones Region 4 Engineering Branch 1 |
| To: | Naslund C AmerenUE |
| References | |
| IR-08-008 | |
| Download: ML081580079 (9) | |
See also: IR 05000483/2008008
Text
June 5, 2008
Charles D. Naslund, Senior Vice
President and Chief Nuclear Officer
AmerenUE
P.O. Box 620
Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT - INFORMATION REQUEST FOR NRC TRIENNIAL
BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION
REPORT 05000483/2008008
Dear Mr. Naslund:
On July 28, 2008, the Nuclear Regulatory Commission will begin a triennial baseline
Component Design Bases Inspection at the Callaway Plant. 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 six
NRC inspectors, of which five will focus on engineering and one on operations. The current
inspection schedule is as follows:
Onsite information gathering visit: Week of July 14, 2008
Onsite weeks: July 28, August 11, and August 18, 2008
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. Additional information and documentation needed to support the inspection will be
identified, including interviews with engineering managers, engineers, and probabilistic safety
assessment staff.
Our experience with these inspections has shown 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 June 18, 2008. Insofar as
possible, this information should be provided electronically to the lead inspector. Since the
UNITED STATES
NUCLEAR REGULATORY COMMISSION
R E GI ON I V
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, TEXAS 76011-4125
AmerenUE
- 2 -
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 are those items that the team will need access to
when onsite and after the inspection samples are selected. 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
completed 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 Mr. Ronald A. Kopriva. We understand that our
licensing engineer contact for this inspection is Mr. Steve Petzel. If there are any questions
about the inspection or the requested materials, please contact the lead inspector at
(817) 860-8104 or via e-mail at ron.kopriva@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/
William B. Jones, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-483
License: NPF-30
Enclosure:
Component Design Basis Inspection
Document Request
AmerenUE
- 3 -
John ONeill, Esq.
Pillsbury Winthrop Shaw Pittman LLP
2300 N. Street, N.W.
Washington, DC 20037
Scott A. Maglio, Assistant Manager
Regulatory Affairs
AmerenUE
P.O. Box 620
Fulton, MO 65251
Missouri Public Service Commission
Governors Office Building
200 Madison Street
P.O. Box 360
Jefferson City, MO 65102-0360
H. Floyd Gilzow
Deputy Director for Policy
Missouri Department of Natural Resources
P. O. Box 176
Jefferson City, MO 65102-0176
Rick A. Muench, President and
Chief Executive Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
Kathleen Smith, Executive Director and
Kay Drey, Representative
Board of Directors Missouri Coalition
for the Environment
6267 Delmar Boulevard, Suite 2E
St. Louis City, MO 63130
Lee Fritz, Presiding Commissioner
Callaway County Courthouse
10 East Fifth Street
Fulton, MO 65251
Les H. Kanuckel, Manager
Quality Assurance
AmerenUE
P.O. Box 620
Fulton, MO 65251
AmerenUE
- 4 -
Director, Missouri State Emergency
Management Agency
P.O. Box 116
Jefferson City, MO 65102-0116
Scott Clardy, Director
Section for Environmental Public Health
Missouri Department of Health and
Senior Services
P.O. Box 570
Jefferson City, MO 65102-0570
Luke H. Graessle, Manager
Regulatory Affairs
AmerenUE
P.O. Box 620
Fulton, MO 65251
Thomas B. Elwood, Supervising Engineer
Regulatory Affairs and Licensing
AmerenUE
P.O. Box 620
Fulton, MO 65251
Certrec Corporation
4200 South Hulen, Suite 422
Fort Worth, TX 76109
Keith G. Henke, Planner III
Division of Community and Public Health
Office of Emergency Coordination
Missouri Department of Health and
Senior Services
930 Wildwood,
P.O. Box 570
Jefferson City, MO 65102
Technical Services Branch Chief
FEMA Region VII
2323 Grand Boulevard, Suite 900
Kansas City, MO 64108-2670
Ronald L. McCabe, Chief
Technological Hazards Branch
National Preparedness Division
DHS/FEMA
9221 Ward Parkway
Suite 300
Kansas City, MO 64114-3372
AmerenUE
- 5 -
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov )
DRP Director (Dwight.Chamberlain@nrc.gov )
DRS Director (Roy.Caniano@nrc.gov )
DRS Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (David.Dumbacher@nrc.gov)
Branch Chief, DRP/B (Vincent.Gaddy@nrc.gov)
Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov )
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov )
RITS Coordinator (Marisa.Herrera@nrc.gov )
DRS STA (Dale.Powers@nrc.gov )
J. Adams, OEDO RIV Coordinator (John.Adams@nrc.gov)
P. Lougheed, OEDO RIV Coordinator (Patricia.Lougheed@nrc.gov )
ROPreports
CWY Site Secretary (Dawn.Yancey@nrc.gov )
SUNSI Review Completed: ___WBJ
ADAMS: Yes
Initials: __WBJ____
Publicly Available
Non-Sensitive
S:DRS\\REPORTS\\CW 2008008 ltr-RAK ML081580079
RIV:RI:DRS/EB1
BC/EB1
RAKopriva (rak1)
WBJones
/RA/
/RA/
05/09/08
06/5/08
OFFICIAL RECORD COPY
T=Telephone E=E-mail F=Fax
- 1 -
Enclosure
INFORMATION REQUEST FOR CALLAWAY PLANT STATION COMPONENT DESIGN
BASES (CDBI) INSPECTION
Inspection Report: 05000453/2008008
Information Gathering Dates:
July 16-18, 2008
On-site Inspection Dates:
July 28 through August 11
August 11 - 22, 2008
Inspection Procedure:
IP 71111.21, Component Design Bases Inspection
Lead Inspector/Team Leader:
Ronald A. Kopriva
817-860-8104
Ron.Kopriva@nrc.gov
I.
Information Requested Prior to the information Gathering Visit
The following information is requested by June 18, 2008, or sooner, to facilitate
inspection preparation. If you have any questions regarding this information, pleased
call the lead inspector as soon as possible. (Please provide the information
electronically in pdf files, Excel, or other searchable formats. 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 boiling water reactor technology).
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.
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.).
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Enclosure
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.
Calloway Plant 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.
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Enclosure
II.
Information Requested to be Available on First Day of Inspection (July 28,
2008)
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.
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Enclosure
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:
Ronald A. Kopriva
Senior Reactor Inspector
(817) 860-8104
Ron.Kopriva@nrc.gov
Mailing Address:
US NRC, Region IV
Attn: Ronald A. Kopriva
612 East Lamar Blvd.
Arlington, TX 76011-4005