ML15328A502
| ML15328A502 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/24/2015 |
| From: | Christine Lipa NRC/RGN-III/DRS/EB2 |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| IR 2016008 | |
| Download: ML15328A502 (8) | |
See also: IR 05000456/2016008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
November 24, 2015
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR INFORMATION FOR
AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION;
INSPECTION REPORT 05000456/2016008; 05000457/2016008.
Dear Mr. Hanson:
On February 22, 2016, the U. S. Nuclear Regulatory Commission (NRC) will begin a
Triennial Baseline Component Design Bases Inspection (CDBI) at the Braidwood Station,
Units 1 and 2. This inspection will be performed in accordance with NRC Baseline Inspection
Procedure 71111.21.
The CDBI focuses on the design, maintenance, and operation of risk-significant components
associated with one or more accident scenario or systems. The components to be reviewed
during this baseline inspection will be identified during the in-office preparation week that occurs
prior to the first onsite inspection week. In addition, operating experience issues, associated
with the component samples, will also be selected for review. The inspection team may request
scenarios to be performed on the simulator. This request would require support from your
simulator staff to validate scenarios, simulator time, and a crew to perform the actions which
would most likely occur during the second on-site week. The team will work closely with your
staff early on during the inspection process to ensure this activity can be accomplished with
minimal impact.
The inspection will include 3 weeks onsite. The inspection team will consist of six NRC
inspectors, of which five will focus on engineering/maintenance and one on operations.
The current inspection schedule is as follows:
Onsite weeks:
February 22 - 26, 2016;
March 7 - 11, 2016; and
March 21 - 25, 2016.
The team will be preparing for the inspection, mainly during the week of February 15, 2016,
as discussed in the attached enclosure.
B. Hanson
-2-
Experience with previous baseline design inspections of similar depth and length has shown
that this type of inspection is 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.
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. Insofar as possible, this information should be provided electronically to the lead
inspector. The information request has been divided into three groups:
The first group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector no later than January 18, 2016.
By January 25, 2016, the lead inspector will communicate the initial selected set of
approximately 15 components.
The second group of documents requested is those items needed to support our
in-office preparation activities. This set of documents, including the calculations
associated with the initial selected components, should be provided to the lead inspector
at the Regional Office no later than February 5, 2016. During the in-office preparation
activities, the team may identify additional information needed to support the inspection.
The last group includes the additional information above as well as plant specific
reference material. This information should be available to the team onsite on
February 22, 2016. It is also requested that corrective action documents and/or
questions developed during the inspection be provided to the lead inspector as the
documents are generated.
The lead inspector for this inspection is Mr. Benny Jose. We understand that our licensing
contact for this inspection is Mr. Richard Schliessmann 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) 829-9756, or via e-mail at Benny.Jose@nrc.gov.
This letter does not contain new or amended information collection requirements subject to
the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information
collection requirements were approved by the Office of Management and Budget, Control
Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget Control
Number.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
B. Hanson
-3-
inspection in the NRCs Public Document Room or from the Publicly Available Records
(PARS)component of the NRC's Agencywide Documents Access and Management 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/
Christine A. Lipa, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-456; 50-457
Enclosure:
Information Request for Component Design Bases Inspection
cc w/encl: Distribution via LISTSERV
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
Enclosure
Inspection Report: 05000456/2016008; 05000457/2016008
Inspection Dates:
February 22 - 26, 2016;
March 7-11, 2016; and
March 21-25, 2016.
Inspection Procedure:
IP 71111.21 Component Design Bases Inspection
Lead Inspector:
Benny Jose, Senior Reactor Engineer, DRS
(630) 829-9756
Benny.Jose@nrc.gov
I.
Information Requested Prior to the Onsite Information Gathering/Inspection Week
The following information is requested by January 18, 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 some portable electronic media
(e.g., CDROM, DVD, flash drive, etc.). The portable electronic media 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 light water reactor technology).
1. Risk-ranking of top 250 components from your site specific Probabilistic Safety
Analysis (PSA) sorted by Risk-Achievement Worth (RAW). Include values for
Birnbaum Importance, Risk-Reduction Worth, and Fussell-Veseley (as applicable).
2. Risk-ranking of top 100 containment-related components (i.e., Large Early Release
Frequency) from your site specific PSA sorted by RAW.
3. Provide a list of the top 200 cut-sets from your PSA.
4. Provide a list of the top 100 cut-sets for each initiator modeled in the PSA that
contributes more than 5 percent to the baseline plant core damage frequency.
5. Copies of PSA system notebooks, and latest PSA summary document.
6. List of time critical operator actions. Identify those actions that do not have job
performance measures.
7. Provide copies of the emergency operating procedures.
8. 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).
9. Electronic copy of the site Individual Plant Examination of External Events, if
available.
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
2
10. 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.).
11. List of available design (setup) margins in both the open and closed direction
(identify safety-related direction) for valves in the Motor-Operated Valve and
Air-Operated Valve Programs. Identify the basis for how the margin was determined.
12. List of high-risk Maintenance Rule systems/components based on engineering or
expert panel judgment (i.e., those systems/components not identified in the PSA).
13. Structures, systems, and components in the Maintenance Rule (a)(1) category for
the last 3 years.
14. Site top 10 issues list (if applicable).
15. A list of operating experience evaluations for the last 3 years.
16. Information of any common cause failure of components experienced in the last
5 years at your facility.
17. List of Root Cause Evaluations associated with component failures or design issues
initiated/completed in the last 5 years.
18. List of open operability evaluations.
19. List of components/systems considered operable but degraded/nonconforming.
20. Current management and engineering organizational chart.
21. Electronic copies of Updated Final Safety Analysis Report, Technical Specifications,
Technical Specifications Bases, and Technical Requirements Manual.
22. Major one line electrical drawings (ac and dc) and key diagrams (paper copies).
23. Electronic copy of Piping and Instrumentation Drawings (P&IDs) (if available).
II.
Information Requested (for the approximate 15 selected components) to be
Available by February 5, 2016, (will be reviewed by the team in the Regional
office during the week of February 15, 2016).
This information should be separated for each selected component, especially if
provided electronically (e.g., folder with component name that includes calculations,
condition reports, maintenance history, etc.).
1. List of condition reports (corrective action documents) associated with each of the
selected components for the last 6 years.
2. The maintenance history (corrective, preventive, and elective) associated with each
of the selected components for the last 10 years. Identify frequency of preventive
maintenance activities.
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
3
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 important referenced material (such as drawings, engineering
requests, and vendor letters). [Pipe stress calculations are excluded from this
request]
4. System Health Reports, System Descriptions, Design Basis Documents, and/or
Training Lesson Plans associated with each of the selected components.
5. A list of modifications, including equivalency evaluations and setpoint changes,
associated with each of the selected components. This list should include a
descriptive paragraph on the purpose of the modification. Please ensure this
list only includes design completed (not canceled) modifications.
6. Copies of operability evaluations (open/closed for last 3 years) associated with each
of the selected components and plans for restoring operability, if applicable.
7. Copies of selected operator work-around evaluations associated with each of the
selected components and plans for resolution, if applicable.
8. Copies of any open temporary modifications associated with each of the selected
components, if applicable.
9. 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., for valves: stroke time and leak rate
results, etc.).
10. Provide copies of the normal and abnormal operating procedures associated with the
selected components and selected scenarios.
11. A copy of any internal/external self-assessments and associated corrective action
documents generated in preparation for the inspection.
12. Copy of latest completed tests and surveillances for each component, for example:
13. Pumps: comprehensive test, quarterly test, flow balance, etc.
14. Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc.
15. Heat Exchangers/room coolers: thermal performance, clean/inspect, fan flows, etc.
16. Acceptance criteria basis calculations should also be included.
17. A copy of engineering/operations related audits completed in the last 2 years.
III.
Additional Information to be Provided on February 22, 2016, Onsite (for final
selected components)
1. During the in-office preparation activities, the team will be making final selections
and may identify additional information needed to support the inspection. The lead
inspector will provide a list of the additional information needed during the week of
February 15, 2016.
INFORMATION REQUEST FOR COMPONENT DESIGN BASES INSPECTION
4
2. Schedule of any testing/maintenance activities to be conducted on the selected
components during the three onsite inspection weeks.
IV.
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 (paper copies).
4. Reference materials. (make available if needed during all on-site weeks):
Individual Plant Examination/Probabilistic Risk Assessment Report;
Procurement documents for components selected (verify retrievable);
Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
Vendor manuals.
If you have questions regarding the information requested, please contact the lead inspector.
B. Hanson
-3-
inspection in the NRCs Public Document Room or from the Publicly Available Records
(PARS)component of the NRC's Agencywide Documents Access and Management 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/
Christine A. Lipa, Chief
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-456; 50-457
Enclosure:
Information Request for Component Design Bases Inspection
cc w/encl: Distribution via LISTSERV
DISTRIBUTION w/encl:
RidsNrrDorlLpl3-2 Resource
RidsNrrPMBraidwood Resource
RidsNrrDirsIrib Resource
Cynthia Pederson
DRPIII
DRSIII
ADAMS Accession Number ML15328A502
Publicly Available
Non-Publicly Available
Sensitive
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
RIII
RIII
RIII
RIII
NAME
BJose:cl
CLipa
DATE
11/24/15
11/24/15
OFFICIAL RECORD COPY