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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES
NUCLEAR REGULATORY COMMISSION
                          NUCLEAR REGULATORY COMMISSION
REGION III
                                            REGION III
2443 WARRENVILLE ROAD, SUITE 210
                                2443 WARRENVILLE ROAD, SUITE 210
LISLE, IL 60532
                                        LISLE, IL 60532-4352
-4352 February 7, 2013
                                          February 7, 2013
  Mr. Michael J. Pacilio
Mr. Michael J. Pacilio
Senior Vice President, Exelon Generation Company, LLC
Senior Vice President, Exelon Generation Company, LLC
    President and Chief Nuclear Officer, Exelon Nuclear
  President and Chief Nuclear Officer, Exelon Nuclear
4300 Winfield Road
4300 Winfield Road
Warrenville , IL 60555 SUBJECT: CLINTON POWER STATIO
Warrenville, IL 60555
N REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION INSPECTION
SUBJECT:         CLINTON POWER STATION REQUEST FOR INFORMATION FOR AN NRC
REPORT 05000461/201300
                TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
8 Dear Mr. Pacilio: On May 20, 2013
                INSPECTION REPORT 05000461/2013008
, the U. S. Nuclear Regulatory Commission (NRC) will begin a  
Dear Mr. Pacilio:
triennial baseline Component Design Bases Inspection (CDBI) at Clinton Power Station
On May 20, 2013, the U. S. Nuclear Regulatory Commission (NRC) will begin a triennial
. A team of six inspectors will perform this
baseline Component Design Bases Inspection (CDBI) at Clinton Power Station. A team of six
3-week inspection. This inspection will be performed in accordance with NRC Baseline Inspection Procedure (IP) 71111.21.
inspectors will perform this 3-week inspection. This inspection will be performed in accordance
The CDBI focuses on the design, maintenance, and operation of risk
with NRC Baseline Inspection Procedure (IP) 71111.21.
-significant components
The CDBI focuses on the design, maintenance, and operation of risk-significant components
associated with one or more accident scenario. The components to be reviewed during this baseline inspection will be identified during the in-office preparation week that occurs prior to the first on-site inspection
associated with one or more accident scenario. The components to be reviewed during this
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 you
baseline inspection will be identified during the inoffice preparation week that occurs prior to the
r 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.
first on-site inspection week. In addition, operating experience issues, associated with the
  The inspection will include three weeks on-site. The inspection team will consist of
component samples, will also be selected for review. The inspection team may request
six NRC inspectors, of which five will focus on engineering/maintenance
scenarios to be performed on the simulator. This request would require support from your
and one on operations. The current inspection schedule is as follows:
simulator staff to validate scenarios, simulator time, and a crew to perform the actions which
  On-site weeks:
would most likely occur during the second on-site week. The team will work closely with your
May 20 - 24, 2013;   June 3 - 7, 2013; and   June 17 - 21, 2013. The team will be preparing for the inspection, mainly during the week of May 13, 2013, as discussed in the attached enclosure.
staff early on during the inspection process to ensure this activity can be accomplished with
Experience with previous baseline design inspections of similar depth and length has shown that th is type of inspection is
minimal impact.
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  
The inspection will include three weeks on-site. The inspection team will consist of six NRC
inspection for both parties, we have enclosed a request for information needed for the inspection.  
inspectors, of which five will focus on engineering/maintenance and one on operations. The
  M. Pacilio
current inspection schedule is as follows:
    -2- 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
*    On-site weeks:     May 20 - 24, 2013;
-site portions of
                        June 3 - 7, 2013; and
the inspection. Insofar as possible, this information should be provided electronically to the lead  
                        June 17 - 21, 2013.
inspector. The information request has been divided into three groups:
The team will be preparing for the inspection, mainly during the week of May 13, 2013, as
  The first group lists information necessary for our initial inspection scoping activities.
discussed in the attached enclosure.
This information should be provided to the lead inspector no later than April 9, 2013. By April 19, 2013, the lead inspector will communicate the initial selected set of approximately  
Experience with previous baseline design inspections of similar depth and length has shown
20 components.  
that this type of inspection is extremely resource intensive, both for the NRC inspectors and the
  The second group of documents requested is
licensee staff. In order to minimize the inspection impact on the site and to ensure a productive
those items needed to support our in
inspection for both parties, we have enclosed a request for information needed for the
-office preparation activities. This set of documents, including the calculations associated with the initial selected components, should be provided to the lead inspector
inspection.
at the Regional Office no later than May 8, 2013. During the in
 
-office preparation activities, the team may identify additional information needed to support the inspection.
M. Pacilio                                     -2-
  The last group includes the additional information above
It is important that all of these documents are up to date and complete in order to minimize the
, as well as plant specific reference material. This information should be available to the team onsite on May 20, 2013. It is also requested that corrective action documents and/or questions developed during the  
number of additional documents requested during the preparation and/or the on-site portions of
inspection be provided to the lead inspector as the documents are generated.
the inspection. Insofar as possible, this information should be provided electronically to the lead
The lead inspector for this inspection is Andrew Dunlop. We understand
inspector. The information request has been divided into three groups:
that our licensing contact for this inspection is Ron Frantz
*    The first group lists information necessary for our initial inspection scoping activities.
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) 829-9726 or via e
    This information should be provided to the lead inspector no later than April 9, 2013. By
-mail at andrew.dunlop@nrc.gov
    April 19, 2013, the lead inspector will communicate the initial selected set of approximately
. 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
    20 components.
-
*    The second group of documents requested is those items needed to support our in-office
0011. The NRC may not conduct or sponsor, and a person is not required to respond to a request for information
    preparation activities. This set of documents, including the calculations associated with the
, or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.  
    initial selected components, should be provided to the lead inspector at the Regional Office
  M. Pacilio
    no later than May 8, 2013. During the in-office preparation activities, the team may identify
      -2- In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records Systems (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
    additional information needed to support the inspection.
-rm/adams.html
*    The last group includes the additional information above, as well as plant specific reference
(the Public Electronic
    material. This information should be available to the team onsite on May 20, 2013. It is also
Reading Room).
    requested that corrective action documents and/or questions developed during the
Sincerely,   /RA/ Ann Marie Stone, Chie f Engineering Branch 2
    inspection be provided to the lead inspector as the documents are generated.
Division of Reactor Safety  
The lead inspector for this inspection is Andrew Dunlop. We understand that our licensing
Docket No. 50
contact for this inspection is Ron Frantz of your organization. If there are any questions about
-461 License No. NPF-62 Enclosure:
the inspection or the material requested in the enclosure, please contact the lead inspector at
Component Design Bases Inspection Request for Information Documents
(630) 829-9726 or via e-mail at andrew.dunlop@nrc.gov.
cc w/encl:
This letter does not contain new or amended information collection requirements subject to the
Distribution via ListServŽ 
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.
 
M. Pacilio                                             -2-
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records Systems (PARS) component of NRCs document
system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
                                              Sincerely,
                                              /RA/
                                              Ann Marie Stone, Chief
                                              Engineering Branch 2
                                              Division of Reactor Safety
Docket No. 50-461
License No. NPF-62
Enclosure:     Component Design Bases Inspection Request for Information Documents
cc w/encl:     Distribution via ListServ'
 
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
  Enclosure 1 Inspection Report:
Inspection Report:               05000461/2013008
  05000461/201300
Inspection Dates:               May 20 - 24, 2013;
8 Inspection Dates:
                                June 3 - 7, 2013; and
    June 3 - 7, 2013; and   May 20 - 24, 2013;    June 17 - 21, 2013. Inspection Procedure:
                                June 17 - 21, 2013.
Inspection  
Inspection Procedure:           Inspection Procedure 71111.21 Component Design Bases
Procedure 71111.21 "Component Design Bases
                                Inspection
      Inspection"
Lead Inspector:                 Andrew Dunlop, Senior Reactor Engineer, DRS
Lead Inspector:(630) 829-97 26  Andrew Dunlop
                                (630) 829-9726
, Senior Reactor Engineer, DRS
                                andrew.dunlop@nrc.gov
      andrew.dunlop@nrc.gov
I.     Information Requested Prior to the On-site Information Gathering/Inspection Week
I. Information Requested Prior to the On
      The following information is requested by April 9, 2013, or sooner, to facilitate inspection
-site Information Gathering/Inspection Week
      preparation. If you have any questions regarding this information, please call the team
The following information is requested by April 9, 2013 , 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
      leader as soon as possible. (Please provide the information electronically in pdf files,
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).
      Excel, or other searchable formats, preferably on some portable electronic media (e.g.,
1. Risk-ranking of top 2 50 components from your site specific probabilistic safety
      CDROM, DVD, flash drive, etc.). The portable electronic media should contain
analysis (PSA) sorted by Risk
      descriptive names, and be indexed and hyperlinked to facilitate ease of use. Information
-Achievement Worth (RAW). Include values for Birnbaum Importance, Risk
      in lists should contain enough information to be easily understood by someone who
-Reduction Worth (RRW), and Fussell
      has knowledge of light water reactor technology).
-Veseley (FV)
      1.       Risk-ranking of top 250 components from your site specific probabilistic safety
(as applicable)
                analysis (PSA) sorted by Risk-Achievement Worth (RAW). Include values for
. 2. Risk-ranking of top  
                Birnbaum Importance, Risk-Reduction Worth (RRW), and Fussell-Veseley (FV)
10 0 containment-related components from your site specific PSA sorted by
                (as applicable).
Large Early Release Frequency (LERF).
      2.       Risk-ranking of top 100 containment-related components from your site specific
3. Provide a list of the top 200 cut
                PSA sorted by Large Early Release Frequency (LERF).
-sets from your PSA
      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 P
      4.       Provide a list of the top 100 cut-sets for each initiator modeled in the PSA that
SA that contributes more than 5 percent to the baseline plant core damage frequency (CDF). 5. Copies of PSA "system notebooks" and latest PSA summary document.
                contributes more than 5 percent to the baseline plant core damage frequency
6. List of time critical operator actions. Identify those actions that do not have job performance measures (JPMs).
                (CDF).
7. Provide copies of the emergency operating procedures
      5.       Copies of PSA system notebooks and latest PSA summary document.
(EOPs).  
      6.       List of time critical operator actions. Identify those actions that do not have job
                performance measures (JPMs).
      7.       Provide copies of the emergency operating procedures (EOPs).
                                                    1                                  Enclosure
 
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
  Enclosure 2 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)
    8.   If you have an External Events or Fire PSA Model, provide the information
. 9. Electronic copy of the site IPEEE, if available.
        requested in Items 1 and 2 for external events and fire. Provide narrative
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  
        description of each coded event (including fire, flood zone description).
pressure, diesel generator close to design required output, heat
    9.   Electronic copy of the site IPEEE, if available.
exchangers close to rated design heat removal etc.)
    10. Any pre-existing evaluation or list of components and associated calculations
. 11. List of available design (setup) margins in both the  
        with low design margins, (i.e., pumps closest to the design limit for flow or
open and closed direction (identify safety
        pressure, diesel generator close to design required output, heat exchangers
-related direction) for valves in the motor
        close to rated design heat removal etc.).
-operated valve (MOV) and air-operated valve (AOV) programs
    11. List of available design (setup) margins in both the open and closed direction
. Identify the basis for how the margin was determined.
        (identify safety-related direction) for valves in the motor-operated valve (MOV)
12. List of high risk Maintenance Rule systems/components based on engineering or  
        and air-operated valve (AOV) programs. Identify the basis for how the margin
expert panel judgment
        was determined.
(i.e., those systems/components not identified in the PRA). 13. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1)  
    12. List of high risk Maintenance Rule systems/components based on engineering or
category for the last  
        expert panel judgment (i.e., those systems/components not identified in the
3 years. 14. Site top ten issues list (if applicable)
        PRA).
. 15. A list of operating experience evaluations for the last  
    13. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1)
3 years. 16. Information of any common cause failure of components experienced in the last 5 years at your facility
        category for the last 3 years.
. 17. List of Root Cause Evaluations associated with component failures or design issues initiated/completed in the last  
    14. Site top ten issues list (if applicable).
5 years. 18. List of open operability evaluations.
    15. A list of operating experience evaluations for the last 3 years.
19. List of components/systems considered operable but degraded/nonconforming.
    16. Information of any common cause failure of components experienced in the last
20. Current management and engineering organizational chart
        5 years at your facility.
. 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).
    17. List of Root Cause Evaluations associated with component failures or design
23. Electronic copy of P&IDs (if available).  
        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 P&IDs (if available).
                                            2                                Enclosure
 
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
  Enclosure 3 II. Information Requested (for the approx.
II. Information Requested (for the approx. 20 selected components) to be Available
20 selected components) to be  
    by May 8, 2013, (will be reviewed by the team in the Regional Office during the
Available by May 8, 2013, (will be reviewed by the team in the Regional  
    week of May 13, 2013).
Office during the week of May 13, 2013).   This information
    This information should be separated for each selected component, especially if
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
    provided electronically (e.g., folder with component name that includes calculations,
.). 1. List of condition reports (corrective action documents) associated with each of  
    condition reports, maintenance history, etc.).
the selected components for the last  
    1.     List of condition reports (corrective action documents) associated with each of
4 years. 2. The maintenance history  
            the selected components for the last 4 years.
(corrective, preventive, and elective)
    2.     The maintenance history (corrective, preventive, and elective) associated with
associated with each of the selected components for the last  
            each of the selected components for the last 10 years. Identify frequency of
10 years. Identify frequency of
            preventive maintenance activities.
preventive maintenance activities.
    3.     Copies of calculations associated with each of the selected components (if not
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
            previously provided), excluding data files. Please review the calculations and
drawings, engineering requests, and vendor letters)
            also provide copies of important referenced material (such as drawings,
. 4. System Health Reports, System Descriptions, Design Basis Documents, and/or Training Lesson Plans that are associated with each of the selected components.
            engineering requests, and vendor letters).
5. A list of modifications, including equivalency evaluations and setpoint changes, associated with each of the selected components
    4.     System Health Reports, System Descriptions, Design Basis Documents, and/or
. This list should include a descriptive paragraph on the purpose of the modification. Please ensure this list only includes design completed (not canceled) modifications.
            Training Lesson Plans that are associated with each of the selected components.
6. Copies of operability evaluations (open/closed for last  
    5.     A list of modifications, including equivalency evaluations and setpoint changes,
3 years) associated with each of the selected components and plans for restoring operability, if applicable
            associated with each of the selected components. This list should include a
. 7. Copies of selected operator work
            descriptive paragraph on the purpose of the modification. Please ensure this list
-around evaluations associated with each of the selected components and plans for resolution, if applicable.
            only includes design completed (not canceled) modifications.
8. Copies of any open temporary modifications associated with each of the selected components, if applicable.
    6.     Copies of operability evaluations (open/closed for last 3 years) associated with
9. Trend data on the selected electrical/mechanical components' performance for  
            each of the selected components and plans for restoring operability, if applicable.
last 3 years (For example, pumps' performance including in
    7.     Copies of selected operator work-around evaluations associated with each of the
-service testing, other vibration monitoring, oil sample results, etc., for valves: stroke time and leak rate results, etc.
            selected components and plans for resolution, if applicable.
). 10. Copy of latest completed surveillance tests for each component (for example, for pumps this would include: comprehensive test, quarterly test, flow balance, etc. for valves: stroke time testing, diagnostic testing, leak testing, etc.). Acceptance criteria basis calculations should also be included.
    8.     Copies of any open temporary modifications associated with each of the selected
11. Provide copies of the normal and abnormal operating procedures associated with  
            components, if applicable.
the selected components
    9.     Trend data on the selected electrical/mechanical components performance for
and selected scenarios
            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.     Copy of latest completed surveillance tests for each component (for example, for
            pumps this would include: comprehensive test, quarterly test, flow balance, etc.
            for valves: stroke time testing, diagnostic testing, leak testing, etc.). Acceptance
            criteria basis calculations should also be included.
    11.     Provide copies of the normal and abnormal operating procedures associated with
            the selected components and selected scenarios.
                                              3                                  Enclosure
 
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS
  Enclosure 4 12. A copy of any internal/external self
        12.   A copy of any internal/external self-assessments and associated corrective
-assessments and associated corrective action documents generated in preparation for the inspection
              action documents generated in preparation for the inspection.
. 13. A copy of engineering/operations related audits completed in the last  
        13.   A copy of engineering/operations related audits completed in the last 2 years.
2 years. III. Additional Information to be  
III.   Additional Information to be Provided on May 20, 2013, On-Site (for final selected
Provided on May 20, 2013, On-Site (for final selected components)  
        components)
1. During the in
        1.     During the in-office preparation activities, the team will be making final selections
-office preparation activities, the team will be making final selections  
              and may identify additional information needed to support the inspection. The
and may identify additional information needed to support the inspection. The lead inspector will provide a list of
              lead inspector will provide a list of the additional information needed during the
the additional information needed during the week of May 13, 2013. 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the three onsite inspection weeks.  
              week of May 13, 2013.
  IV. Information Requested to be Provided Throughout the Inspection
        2.     Schedule of any testing/maintenance activities to be conducted on the selected
1. Copies of any corrective action documents generated as a result of the team's questions or queries during this inspection
              components during the three onsite inspection weeks.
. 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)
IV.     Information Requested to be Provided Throughout the Inspection
. 3. One complete set of P&IDs (paper copies)
        1.     Copies of any corrective action documents generated as a result of the teams
. 4. Reference materials. (make available if needed during all on
              questions or queries during this inspection.
-site weeks):
        2.     Copies of the list of questions submitted by the team members and the
   IPE/PRA report
              status/resolution of the information requested (provide daily during the inspection
Procurement documents for components selected (verify retrievable);
              to each team member).
   Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
        3.     One complete set of P&IDs (paper copies).
   Vendor manuals.
        4.     Reference materials. (make available if needed during all on-site weeks):
If you have questions regarding the information requested, please contact the lead inspector.  
              *   IPE/PRA report;
    M. Pacilio
              *  Procurement documents for components selected (verify retrievable);
      -2- In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public
              *   Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
inspection in the NRC Public Document Room or from the Publicly Available Records Systems (PARS) component of NRC's document  
              *   Vendor manuals.
system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
If you have questions regarding the information requested, please contact the lead inspector.
-rm/adams.html
                                                  4                                Enclosure
(the Public Electronic Reading Room).
 
Sincerely, /RA/
M. Pacilio                                                                             -2-
Ann Marie Stone, Chie f Engineering Branch 2
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
Division of Reactor Safety  
enclosure will be available electronically for public inspection in the NRC Public Document
Docket No. 50
Room or from the Publicly Available Records Systems (PARS) component of NRCs document
-461 License No. NPF-62 Enclosure:
system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-
Component Design Bases Inspection Request for Information Documents
rm/adams.html (the Public Electronic Reading Room).
cc w/encl:
                                                                          Sincerely,
Distribution via ListServŽ
                                                                          /RA/
Docket No.  
                                                                          Ann Marie Stone, Chief
50-461 License No. NPF
                                                                          Engineering Branch 2
-62 Enclosure:
                                                                          Division of Reactor Safety
Information Request for Component Design Bases Inspection (CDBI)
Docket No. 50-461
cc w/encl:
License No. NPF-62
Distribution via ListServŽ
Enclosure:               Component Design Bases Inspection Request for Information Documents
DISTRIBUTIONJohn Cassidy
cc w/encl:               Distribution via ListServ'
: RidsNrrDorlLpl3
Docket No. 50-461
-2 Resource
License No. NPF-62
RidsNrrPMClinton Resource
Enclosure:               Information Request for Component Design Bases Inspection (CDBI)
RidsNrrDirsIrib Resource
cc w/encl:               Distribution via ListServ'
Chuck Casto
DISTRIBUTION:
Cynthia Pederson
John Cassidy
Steven Orth
RidsNrrDorlLpl3-2 Resource
Allan Barker
RidsNrrPMClinton Resource
Carole Ariano
RidsNrrDirsIrib Resource
Chuck Casto
Cynthia Pederson
Steven Orth
Allan Barker
Carole Ariano
Christine Lipa
Christine Lipa
Linda Linn
Linda Linn
DRSIII DRPIII Tammy Tomczak
DRSIII
  DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress
DRPIII
\Ltr. 020713
Tammy Tomczak
Clinton CDBI
DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\Ltr. 020713                                     Clinton CDBI RFI AXD.docx
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Revision as of 22:36, 4 November 2019

Ltr 02/07/13 Clinton Power Station Request for Information for an NRC Triennial Baseline Component Design Bases Inspection Report 05000461-13-008
ML13038A312
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/07/2013
From: Ann Marie Stone
NRC/RGN-III/DRS/EB2
To: Pacilio M
Exelon Generation Co, Exelon Nuclear
References
IR-13-008
Download: ML13038A312 (8)


See also: IR 05000461/2013008

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE ROAD, SUITE 210

LISLE, IL 60532-4352

February 7, 2013

Mr. Michael J. Pacilio

Senior Vice President, Exelon Generation Company, LLC

President and Chief Nuclear Officer, Exelon Nuclear

4300 Winfield Road

Warrenville, IL 60555

SUBJECT: CLINTON POWER STATION REQUEST FOR INFORMATION FOR AN NRC

TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION

INSPECTION REPORT 05000461/2013008

Dear Mr. Pacilio:

On May 20, 2013, the U. S. Nuclear Regulatory Commission (NRC) will begin a triennial

baseline Component Design Bases Inspection (CDBI) at Clinton Power Station. A team of six

inspectors will perform this 3-week inspection. This inspection will be performed in accordance

with NRC Baseline Inspection Procedure (IP) 71111.21.

The CDBI focuses on the design, maintenance, and operation of risk-significant components

associated with one or more accident scenario. The components to be reviewed during this

baseline inspection will be identified during the inoffice preparation week that occurs prior to the

first on-site 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 three weeks on-site. 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:

  • On-site weeks: May 20 - 24, 2013;

June 3 - 7, 2013; and

June 17 - 21, 2013.

The team will be preparing for the inspection, mainly during the week of May 13, 2013, as

discussed in the attached enclosure.

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.

M. Pacilio -2-

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 April 9, 2013. By

April 19, 2013, the lead inspector will communicate the initial selected set of approximately

20 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 May 8, 2013. 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 May 20, 2013. 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 Andrew Dunlop. We understand that our licensing

contact for this inspection is Ron Frantz 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) 829-9726 or via e-mail at andrew.dunlop@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.

M. Pacilio -2-

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its

enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records Systems (PARS) component of NRCs document

system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50-461

License No. NPF-62

Enclosure: Component Design Bases Inspection Request for Information Documents

cc w/encl: Distribution via ListServ'

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS

Inspection Report: 05000461/2013008

Inspection Dates: May 20 - 24, 2013;

June 3 - 7, 2013; and

June 17 - 21, 2013.

Inspection Procedure: Inspection Procedure 71111.21 Component Design Bases

Inspection

Lead Inspector: Andrew Dunlop, Senior Reactor Engineer, DRS

(630) 829-9726

andrew.dunlop@nrc.gov

I. Information Requested Prior to the On-site Information Gathering/Inspection Week

The following information is requested by April 9, 2013, 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 (RRW), and Fussell-Veseley (FV)

(as applicable).

2. Risk-ranking of top 100 containment-related components from your site specific

PSA sorted by Large Early Release Frequency (LERF).

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

(CDF).

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 (JPMs).

7. Provide copies of the emergency operating procedures (EOPs).

1 Enclosure

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS

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 IPEEE, if available.

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 (MOV)

and air-operated valve (AOV) 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

PRA).

13. Structures, systems, and components (SSCs) in the Maintenance Rule (a)(1)

category for the last 3 years.

14. Site top ten 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 P&IDs (if available).

2 Enclosure

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS

II. Information Requested (for the approx. 20 selected components) to be Available

by May 8, 2013, (will be reviewed by the team in the Regional Office during the

week of May 13, 2013).

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 4 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.

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).

4. System Health Reports, System Descriptions, Design Basis Documents, and/or

Training Lesson Plans that are 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. Copy of latest completed surveillance tests for each component (for example, for

pumps this would include: comprehensive test, quarterly test, flow balance, etc.

for valves: stroke time testing, diagnostic testing, leak testing, etc.). Acceptance

criteria basis calculations should also be included.

11. Provide copies of the normal and abnormal operating procedures associated with

the selected components and selected scenarios.

3 Enclosure

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION DOCUMENTS

12. A copy of any internal/external self-assessments and associated corrective

action documents generated in preparation for the inspection.

13. A copy of engineering/operations related audits completed in the last 2 years.

III. Additional Information to be Provided on May 20, 2013, On-Site (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 May 13, 2013.

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):

  • IPE/PRA report;
  • Plant procedures (normal, abnormal, emergency, surveillance, etc.); and
  • Vendor manuals.

If you have questions regarding the information requested, please contact the lead inspector.

4 Enclosure

M. Pacilio -2-

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its

enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records Systems (PARS) component of NRCs document

system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Ann Marie Stone, Chief

Engineering Branch 2

Division of Reactor Safety

Docket No. 50-461

License No. NPF-62

Enclosure: Component Design Bases Inspection Request for Information Documents

cc w/encl: Distribution via ListServ'

Docket No. 50-461

License No. NPF-62

Enclosure: Information Request for Component Design Bases Inspection (CDBI)

cc w/encl: Distribution via ListServ'

DISTRIBUTION:

John Cassidy

RidsNrrDorlLpl3-2 Resource

RidsNrrPMClinton Resource

RidsNrrDirsIrib Resource

Chuck Casto

Cynthia Pederson

Steven Orth

Allan Barker

Carole Ariano

Christine Lipa

Linda Linn

DRSIII

DRPIII

Tammy Tomczak

DOCUMENT NAME: G:\DRSIII\DRS\Work in Progress\Ltr. 020713 Clinton CDBI RFI AXD.docx

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

NAME ADunlop:ls AMStone

DATE 02/05/13 02/07/13

OFFICIAL RECORD COPY