ML072350335
| ML072350335 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/22/2007 |
| From: | William Jones Division of Reactor Safety IV |
| To: | Sheppard J South Texas |
| References | |
| IR-07-007 | |
| Download: ML072350335 (10) | |
See also: IR 05000498/2007007
Text
UNITED STATES
NU CLE AR RE GU LATOR Y C O M M I S S I O N
R EGI ON I V
611 R YAN PLAZA D R IV E, SU ITE 400
AR LI N GTON , TEXAS 76011-4005
August 22, 2007
James J. Sheppard, President and
Chief Executive Officer
STP Nuclear Operating Company
P.O. Box 289
Wadsworth, TX 77483
SUBJECT: SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION, UNITS 1
and 2 - INFORMATION REQUEST FOR AN NRC BIENNIAL BASELINE
COMPONENT DESIGN BASES INSPECTION 05000498/2007007;
AND 05000499/2007007
Dear Mr. Sheppard:
On September 24, 2007, the NRC will begin a biennial baseline Component Design Bases
Inspection at the South Texas Project Electric Generating Station, Units 1 and 2. A team of six
inspectors plus a team leader, 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.
The Component Design Bases Inspection focuses on components that have high risk and low
design 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 and operating experience issues
associated with the component samples will also be selected for review.
The inspection will include 4-weeks onsite, including the information gathering site visit and
3-weeks of onsite inspection. 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 September 4, 2007
Onsite weeks: September 24, 2007, October 15 and October 22, 2007
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 a member of your probabilistic risk analyst or operations staff. Additional
information and documentation needed to support the inspection will also be identified. A
Region IV senior reactor analyst will accompany the lead inspector 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.
STP Nuclear Operating Company 2
Experience with previous baseline design inspections of similar depth and length has shown
that these types 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, 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 by no later than August 29, 2007. 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 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 being requested is those items that the team will need access
to while onsite and after components 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. Wayne Sifre. We understand that our licensing
engineer contact for this inspection is Mr. Jim Morris of your organization. If there are any
questions about the inspection or the requested materials, please contact the lead inspector
at (817) 860-8193 or via e-mail at wcs@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 Agencywide Documents Access
and Management System (ADAMS). ADAMS is accessible from the Electronic Reading Room
page of the NRCs public 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
Dockets: 50-498; 50-499
STP Nuclear Operating Company 3
cc w/enclosure:
E. D. Halpin
Site Vice President
STP Nuclear Operating Company
P.O. Box 289
Wadsworth, TX 77483
Ken Coates
Plant General Manager
STP Nuclear Operating Company
P.O. Box 289
Wadsworth, TX 77483
S. M. Head, Manager, Licensing
STP Nuclear Operating Company
P.O. Box 289, Mail Code: N5014
Wadsworth, TX 77483
C. T. Bowman
General Manager, Oversight
STP Nuclear Operating Company
P.O. Box 289
Wadsworth, TX 77483
Marilyn Kistler
Sr. Staff Specialist, Licensing
STP Nuclear Operating Company
P.O. Box 289, Mail Code 5014
Wadsworth, TX 77483
C. M. Canady
City of Austin
Electric Utility Department
721 Barton Springs Road
Austin, TX 78704
J. J. Nesrsta/R. K. Temple/
E. Alercon/Kevin Pollo
City Public Service Board
P.O. Box 1771
San Antonio, TX 78296
Jon C. Wood
Cox Smith Matthews
112 E. Pecan, Suite 1800
San Antonio, TX 78205
STP Nuclear Operating Company 4
A. H. Gutterman, Esq.
1111 Pennsylvania Avenue NW
Washington, DC 20004
Institute of Nuclear Power Operations (INPO)Records Center
700 Galleria Parkway SE, Suite 100
Atlanta, GA 30339
Director, Division of Compliance & Inspection
Bureau of Radiation Control
Texas Department of State Health Services
1100 West 49th Street
Austin, TX 78756
Brian Almon
Public Utility Commission
William B. Travis Building
P.O. Box 13326
1701 North Congress Avenue
Austin, TX 78701-3326
Environmental and Natural
Resources Policy Director
P.O. Box 12428
Austin, TX 78711-3189
Judge, Matagorda County
Matagorda County Courthouse
1700 Seventh Street
Bay City, TX 77414
Terry Parks, Chief Inspector
Texas Department of Licensing
and Regulation
Boiler Program
P.O. Box 12157
Austin, TX 78711
Susan M. Jablonski
Office of Permitting, Remediation and Registration
Texas Commission on Environmental Quality
MC-122, P.O. Box 13087
Austin, TX 78711-3087
Ted Enos
4200 South Hulen
Suite 422
Fort Worth, TX 76109
STP Nuclear Operating Company 5
Steve Winn/Christine Jacobs/
Eddy Daniels/Marty Ryan
NRC Energy, Inc.
211 Carnegie Center
Princeton, NJ 08540
Lisa R. Hammond, Chief
Technological Hazards Branch
National Preparedness Division
FEMA Region VI
800 N. Loop 288
Denton, TX 76209
STP Nuclear Operating Company 6
Electronic distribution by RIV:
Regional Administrator (BSM1)
DRP Director (ATH)
DRS Director (DDC)
DRS Deputy Director (RJC1)
Senior Resident Inspector (JLD5)
Branch Chief, DRP/A (CEJ1)
Senior Project Engineer, DRP/A (TRF)
Team Leader, DRP/TSS (CJP)
RITS Coordinator (MSH3)
SUNSI Review Completed: __Y____ADAMS: # Yes G No Initials: __WCS____
- Publicly Available G Non-Publicly Available G Sensitive # Non-Sensitive
SRI:EB1 C:EB1
WCSifre/lmb WBJones
/RA/ /Ra/
08/22/2007 08/22/2007
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INFORMATION REQUEST FOR COOPER NUCLEAR STATION
COMPONENT DESIGN BASES INSPECTION (CDBI)
Inspection Report: 05000498/2007007; 05000499/2007007
Information Gathering Dates: September 4-5, 2007
On-site Inspection Dates: September 24-28, 2007, October 15-26, 2007.
Inspection Procedure: IP 71111.21, Component Design Bases Inspection
Lead Inspector/Team Leader: Wayne C. Sifre
817-860-8193
wcs@nrc.gov
I. Information Requested Prior to the information Gathering Visit
The following information is requested by September 29, 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. 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).
1. An excel spreadsheet of equipment basic events (with definitions) including
importance measures (RAW, FV) from your internal events probabilistic risk
assessment (PRA), including risk ranking of top 50 components from your site
specific PRA 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 PRA
3. Copies of PRA system notebooks
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 1-3 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.).
1 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. Any pre-existing evaluation or list of components and calculations with low
design margins (i.e. pumps closest to the design limit for flow or pressure, diesel
generators close to design required output, heat exchangers close to rated
design heat removal etc.)
10. A list of permanent and temporary modifications sorted by component identified
in Item 1.
11. Information of any common cause failure of components experienced in the last
5 years at your facility.
12. List of current operator workarounds.
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).
14. List of root cause evaluations associate with component failures or design issues
initiated/completed in the last 5 years.
15. Current management and engineering organizational charts.
16. South Texas Project IPEEE, if available electronically.
17. Mechanical piping drawings for:
Engineered Safety Features
Emergency core cooling Systems
18. Electrical one-line drawings for:
Off-site power/switchyard supplies
Normal ac power systems
Emergency ac/dc power systems including, 120Vac power, and
125Vdc/24Vdc safety class systems
19. List of any common-cause failures of components in the last 3 years.
2 Enclosure
II. Information Requested to be Available on the First Day of Inspection (September
24, 2007)
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 component (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 workaround evaluations associated with each of he
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 valve program , design margin and
risk ranking.
11. List of air-operated valves (AOVs) in the valve program, design and risk ranking.
12. SSCs in the maintenance rule (a)(1) category.
13. Site top ten issues list.
14. Provide list of PRA assumptions regarding operator actions and the associated
procedures.
15. List of licensee contacts for the inspection team with pager or phone numbers.
3 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 on-site
weeks):
General set of plant drawings
- IPE/PRA report
- Procurement documents for components selected
- Plant procedures (normal, abnormal, emergency, surveillance, etc.)
- Technical specifications
- Vendor manuals
4 Enclosure