ML091520658
| ML091520658 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 06/01/2009 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Bannister D Omaha Public Power District |
| References | |
| IR-09-006, FOIA/PA-2014-0210 | |
| Download: ML091520658 (8) | |
See also: IR 05000285/2009006
Text
June 1, 2009
David J. Bannister, Vice President
and Chief Nuclear Officer
Omaha Public Power District
Fort Calhoun Station FC-2-4
P. O. Box 550
Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION-INITIAL INFORMATION REQUEST FOR NRC
TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC
INSPECTION REPORT 05000285/2009006
Dear Mr. Bannister:
On August 3, the NRC will begin a triennial baseline Component Design Bases Inspection at the
Fort Calhoun. 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
four NRC inspectors and two contractors, of which three will focus on engineering and one on
operations. The current inspection schedule is as follows:
Onsite information gathering visit: August 3-8, 2009
Preparation Week: August 17-21, 2009
Onsite weeks: August 24-29, 2009; September 8-18, 2009
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. During the onsite weeks, several days of time will be needed on the plant-referenced
simulator in order to facilitate the development of operator action-based scenarios. Additional
information and documentation needed to support the inspection will be identified during the
inspection, including interviews with engineering managers, engineers, and probabilistic safety
assessment staff.
UNITED STATES
NUCLEAR REGULATORY COMMISSION
R E GI ON IV
612 E. LAMAR BLVD., SUITE 400
ARLINGTON, TEXAS 76011-4005
Omaha Public Power District
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Our experience with these inspections has shown that 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 July 20, 2009. Insofar as
possible, this information should be provided electronically to the lead inspector. Since the
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 is those items that the team will need access to
during the preparation week in order to finalize the samples to be inspected. 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. Additional requests by inspectors will be made
throughout all three onsite weeks for specific documents needed to complete the review of that
component/selection. 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 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 Gerond A. George. We understand that our licensing
engineer contact for this inspection is Erick Matzke. If there are any questions about the
inspection or the requested materials, please contact the lead inspector at (817) 276-6562 or via
e-mail at Gerond.George@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/
Thomas Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-285
License: DPR-40
Enclosure:
Component Design Basis Inspection
Document Request
cc w/enclosure:
Omaha Public Power District
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Jeffrey A. Reinhart
Site Vice President
Omaha Public Power District
Fort Calhoun Station FC-2-4 Adm
P.O. Box 550
Fort Calhoun, NE 68023-0550
Mr. Thomas C. Matthews
Manager - Nuclear Licensing
Omaha Public Power District
Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550
Fort Calhoun, NE 68023-0550
Winston & Strawn
Attn: David A. Repke, Esq.
1700 K Street, NW
Washington, DC 20006-3817
Chairman
Washington County Board of Supervisors
P.O. Box 466
Blair, NE 68008
Ms. Julia Schmitt, Manager
Radiation Control Program
Nebraska Health & Human Services R & L
Public Health Assurance
301 Centennial Mall, South
P.O. Box 95007
Lincoln, NE 68509-5007
Ms. Melanie Rasmussen
Radiation Control Program Officer
Bureau of Radiological Health
Iowa Department of Public Health
Lucas State Office Building, 5th Floor
321 East 12th Street
Des Moines, IA 50319
Chief, Technological Hazards Branch
FEMA, Region VII
9221 Ward Parkway
Suite 300
Kansas City, MO 64114-3372
Omaha Public Power District
- 4 -
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov )
Deputy Regional Administrator (Chuck.Casto@nrc.gov )
DRP Director (Dwight.Chamberlain@nrc.gov)
DRP Deputy Director (Anton.Vegel@nrc.gov )
DRS Director (Roy.Caniano@nrc.gov )
DRS Deputy Director (Troy.Pruett@nrc.gov)
Senior Resident Inspector (John.Hanna@nrc.gov)
Resident Inspector (John.Kirkland@nrc.gov )
Branch Chief, DRP/E (Jeff.Clark@nrc.gov)
FCS Site Secretary (Berni.Madison@nrc.gov )
Senior Project Engineer, DRP/E (George.Replogle@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov )
RITS Coordinator (Marisa.Herrera@nrc.gov )
Regional Counsel (Karla.Fuller@nrc.gov)
D. Norkin, NRR CDBI Coordinator (Donald.Norkin@nrc.gov)
OEMail Resource
SUNSI Review Completed: _Yes_ ADAMS: Yes No Initials: _GAG_____
Publicly Available Non-Publicly Available
Sensitive Non-Sensitive
RIV:RI:DRS/EB1
DRS/EB2
DRS/PSB2
SRI/EB1
BC/EB1
GAGeorge
GTutak
PGoldberg
KClayton
TFarnholtz
/RA/
/RA/
/RA/
/RA/
/RA/
05/19/2009
05/19/2009
05/20/2009
06/01/2009
06/01/2009
OFFICIAL RECORD COPY
T=Telephone E=E-mail F=Fax
- 1 -
Enclosure
INFORMATION REQUEST FOR FORT CALHOUN STATION COMPONENT DESIGN BASES
(CDBI) INSPECTION
Inspection Report: 05000285/2009006
Information Gathering Dates:
August 3-8, 2009
On-site Inspection Dates:
August 24-28, 2009; September 8-18, 2009
Inspection Procedure:
IP 71111.21, Component Design Bases Inspection
Lead Inspector/Team Leader:
Gerond A. George
817-276-6562
Gerond.George@nrc.gov
I.
Information Requested Prior to the information Gathering Visit (August 3, 2009)
The following information (Section I of this enclosure) should be sent to the Region IV
office in hard copy or electronic format (ims.certrec.com preferred), in care of Gerond A.
George, July 20, 2009, to facilitate the reduction in the items to be selected for a final list
during the preparation week of August 10, 2009. The inspection team will finalize the
selected list during the prep week using the additional documents requested in Section II
of this enclosure. The specific items selected from the lists shall be available and ready
for review on the day indicated in this request. *Please provide requested documentation
electronically in pdf files, Excel, or other searchable formats, if possible. 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 pressurized water reactor
technology. If requested documents are large and only hard copy formats are available,
please inform the inspector(s), and provide subject documentation during the first day of
the onsite inspection.
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.
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Enclosure
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.).
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.
Fort Calhoun Station 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 Preparation Week (August
17, 2009)
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.
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.
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Enclosure
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:
Gerond A. George
Senior Reactor Inspector
(817) 276-6562
Gerond.george@nrc.gov
Mailing Address:
US NRC, Region IV
Attn: Gerond A. George
612 East Lamar Blvd, Ste 400
Arlington, TX 76011