ML13060A435
| ML13060A435 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 03/01/2013 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Flores R Luminant Generation Co |
| References | |
| Download: ML13060A435 (7) | |
See also: IR 05000445/2013007
Text
March 1, 2013
Rafael Flores, Senior Vice President
and Chief Nuclear Officer
Attention: Regulatory Affairs
Luminant Generation Company LLC
Comanche Peak Nuclear Power Plant
P.O. Box 1002
Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT - NOTIFICATION OF NRC
COMPONENT DESIGN BASES INSPECTION (05000445/2013007 AND
05000446/2013007) AND INITIAL REQUEST FOR INFORMATION
Dear Mr. Flores:
On May 20, 2013, the NRC will begin a triennial baseline Component Design Bases Inspection
at the Comanche Peak Nuclear Power Plant. A seven-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 three weeks of onsite inspection by the team. The inspection will consist of
five NRC inspectors and two contractors, of which six will focus on engineering and one on
operations. The current inspection schedule is as follows:
Onsite Information Gathering Visit: May 1 - 2, 2013
Preparation Week(s): May 13, 2013, and May 27, 2013, and June 10, 2013
Onsite Week(s): May 20, 2013, and June 3, 2013 and June 17, 2013
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
RE G IO N I V
1600 EAST LAMAR BLVD
ARLINGTON, TEXAS 76011-4511
R. Flores
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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 April 24, 2013. 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 Matthew Young. We understand that our licensing
engineer contact for this inspection is Gary Merka. If there are any questions about the
inspection or the requested materials, please contact the lead inspector by telephone at
817-200-1545 or by e-mail at Matt.Young@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 R. Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 05000445, 05000446
Enclosure: Component Design Bases Inspection Request for Information
R. Flores
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cc: Electronic Distribution for Comanche Peak Nuclear Power Plant
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Steven.Reynolds@nrc.gov)
DRP Director (Kriss.Kennedy@nrc.gov)
Acting DRP Deputy Director (Michael.Scott@nrc.gov)
Acting DRS Director (Tom.Blount@nrc.gov)
Acting DRS Deputy Director (Jeff.Clark@nrc.gov)
Senior Resident Inspector (John.Kramer@nrc.gov)
Resident Inspector (Brian.Tindell@nrc.gov)
Administrative Assistant (Phyllis.Holder@nrc.gov)
Branch Chief, DRP/A (Wayne.Walker@nrc.gov)
Senior Project Engineer, DRP/A (Matt.Young@nrc.gov)
Project Engineer, DRP/A (Jason.Dykert@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Balwant.Singal@nrc.gov)
Branch Chief, DRS/TSB (Ray.Kellar@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Technical Support Assistant (Loretta.Williams@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
OEMail Resource
RIV/ETA: OEDO (John.Cassidy@nrc.gov)
DRS/TSB STA (Dale.Powers@nrc.gov)
DOCUMENT NAME: R:\\_REACTORS\\CP 2013007 RFI CDBI
SUNSI Review
Initials: MRY
Non-Sensitive
Sensitive
Publicly Available
Non-Publicly Available
RI:EB1
C:EB1
MYoung
TFarnholtz
/RA/
/RA/
3/1/13
3/1/13
OFFICIAL RECORD COPY
- 1 -
Enclosure
Initial Request for Information
Component Design Bases Inspection
Comanche Peak Nuclear Power Plant
Inspection Report: 05000445/2013007, 05000446/2013007
Information Gathering Dates:
May 1 - 2, 2013
Inspection Dates:
May 20, 2013, and June 3, 2013 and June 17, 2013
Inspection Procedure:
IP 71111.21, Component Design Bases Inspection
Lead Inspector:
Matthew Young, Reactor Inspector
I.
Information Requested Prior to Information Gathering Visit (May 1, 2013)
The following information (Section I of this enclosure) should be sent to the Region IV
office in hard copy or electronic format (Certrec IMS preferred), to the attention of
Matthew Young by April 24, 2013, to facilitate the reduction in the items to be selected.
The team leader will provide the licensee the selected components for Section II by
May 2, 2013. The inspection team will finalize the selected list during the week of
May 13, 2013 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.
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Enclosure
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.).
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. Comanche Peak Nuclear Power 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.
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Enclosure
19. An electronic copy of the Design Bases Documents.
20. An electronic copy of the System Health notebooks.
II.
Information Requested to be Available on First Day of Preparation Week
(May 13, 2013)
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.
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Enclosure
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.
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:
Matthew Young
Reactor Inspector
817-200-1545
Matt.Young@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Matthew Young
1600 East Lamar Blvd.
Arlington, TX 76011-4511