ML15345A263: Difference between revisions

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  SUBJECT:  LASALLE COUNTY STATION, UNITS 1 AND 2
  SUBJECT:  LASALLE COUNTY STATION, UNITS 1 AND 2
  - REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
  - REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION
; INSPECTION REPORT 05000373/2016007; 05000374/2016007 Dear Mr. Hanson: On April 11, 2016
; INSPECTION REPORT 05000 373/20 1 6007; 05000 374/20 1 6007 Dear Mr. Hanson: On April 11, 2016
, the U. S. Nuclear Regulatory Commission (NRC) will begin a  
, the U. S. Nuclear Regulatory Commission (NRC) will begin a  
triennial baseline Component Design Bases Inspection (CDBI) at
triennial baseline Component Design Bases Inspection (CDBI) at
  the LaSalle County Station, Units 1  
  the La Salle County Station, Units 1  
and 2.  This inspection will be performed in accordance with NRC Baseline Inspection Procedure
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
71111.21.
The CDBI focuses on the design, maintenance, and operation of risk
-significant components
-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
  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
Line 45: Line 43:
  and one on operations.  The current inspection schedule is as follows:   
  and one on operations.  The current inspection schedule is as follows:   
  Onsite weeks:
  Onsite weeks:
  April 11  
  April 11 - 15, 2016; April 25 - 29, 2016; and  May 9 - 13, 2016.   
- 15, 2016; April 25  
B. Hanson -2- The team will be preparing for the inspection, mainly during the week of
- 29, 2016; and  May 9 - 13, 2016.   
B. Hanson
-2- The team will be preparing for the inspection, mainly during the week of
  April 4 - 8, 2016, as discussed in the enclosure.
  April 4 - 8, 2016, as discussed in the enclosure.
  Experience with previous baseline design inspections of similar depth and length has shown that this type of inspection is
  Experience with previous baseline design inspections of similar depth and length has shown that th is 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.
  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
  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
-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.  Insofar as possible, this information should be provided electronically to the lead inspector.  The information request has been divided into three groups:
  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
   The first group lists information necessary for our initial inspection scoping activities.  This information should be provide d to the lead inspector no later than
  February 29, 2016.  By March 11, 2016, the lead inspector will communicate the initial selected set of approximately  
  February 29, 2016.  By March 11, 2016, the lead inspector will communicate the initial selected set of approximately  
20 components
2 0 components
.  The second group of documents requested is
.  The second group of documents requested is
  those items needed to support our in
  those items needed to support our in
Line 71: Line 66:
  Dwi Murray
  Dwi Murray
  of your organization.  If there are any questions about the inspection or the material requested in the enclosure, please contact  
  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
the lead inspector at (630) 829-9739 , or via e-mail at Nestor.Feliz
-9739, or via e-mail at Nestor.Feliz
-Adorno@nrc.gov
-Adorno@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.
. 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.    
 
B. Hanson -3- In accordance with Title 10 of the Code of Federal Regulations
B. Hanson
-3- 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  
  (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 inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the
of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the
Line 84: Line 76:
-rm/adams.html
-rm/adams.html
  (the Public Electronic Reading Room).
  (the Public Electronic Reading Room).
  Sincerely,  /RA/  Christine A. Lipa, Chief Engineering Branch 2
  Sincerel y,  /RA/  Christine A. Lipa , Chie f Engineering Branch 2
   
   
Division of Reactor Safety  
Division of Reactor Safety  
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COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION
  Enclosure
  Enclosure Inspection Report:
Inspection Report:
  05000 373/20 1 6007; 05000 374/20 1 6007 Inspection Dates:
  05000373/2016007; 05000374/2016007 Inspection Dates:
  April 11 - 15, 2016; April 25 - 29, 2016; and  May 9 - 13, 2016. Inspection Procedure:
  April 11  
- 15, 2016;
April 25 - 29, 2016; and  May 9 - 13, 2016. Inspection Procedure:
  IP 71111.21 "Component Design Bases Inspection"
  IP 71111.21 "Component Design Bases Inspection"
  Lead Inspector:
  Lead Inspector:
  Néstor J. Féliz
  Néstor J. Féliz
-Adorno, Senior Reactor Engineer, DRS
-Adorno , Senior Reactor Engineer, DRS
   (630) 829
   (630) 829-9739 Nestor.Feliz
-9739 Nestor.Feliz
-Adorno@nrc.gov
-Adorno@nrc.gov
  I. Information Requested Prior to the Onsite Information Gathering/Inspection Week
  I. Information Requested Prior to the Onsite Information Gathering/Inspection Week
  The following
  The following information is requested by
information is requested by
  February 29, 2016 , or sooner, to facilitate inspection
  February 29, 2016, or sooner, to facilitate inspection
  preparation.  If you have any questions regarding this information, please call the team leader as soon as possible.  Unless stated otherwise, please provide the information electronically in "pdf" files, Excel, or other searchable formats, preferably  
  preparation.  If you have any questions regarding this information, please call the team leader as soon as possible.  Unless stated otherwise, please provide the information electronically in "pdf" files, Excel, or other searchable formats, preferably  
on some portable electronic media (e.g., CD-ROM, DVD, 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  
on some portable electronic media (e.g., CD-ROM, DVD, 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
understood by someone who has knowledge of light water reactor technology.
of light water reactor technology.
  1. Risk-ranking of top  
  1. Risk-ranking of top  
250 components from your site specific probabilistic safety analysis (PSA) sorted by Risk
2 50 components from your site specific probabilistic safety analysis (PSA) sorted by Risk
-Achievement Worth (RAW).  Include values for Birnbaum Importance, Risk
-Achievement Worth (RAW).  Include values for Birnbaum Importance, Risk
-Reduction Worth, and Fussell
-Reduction Worth, and Fussell
-Veseley (as applicable).
-Veseley (as applicable).
  2. Risk-ranking of top 100 containment
  2. Risk-ranking of top 100 containment
-related components (i.e. ,Large Early Release Frequency
-related components (i.e. ,Large Early Release Frequency) from your site specific PSA sorted by
) from your site specific PSA sorted by
  RAW. 3. Provide a list of the top 200 cut
  RAW. 3. Provide a list of the top 200 cut
-sets from your PSA.
-sets from your PSA.
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  7. Provide copies of the emergency operating procedures
  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)
. 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
. 9. Electronic copy of the site Individual Plant Examination of External Events , if available.
, if available.
    
    
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION
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  in the Motor-Operated Valve
  in the Motor-Operated Valve
  and Air-Operated Valve Programs
  and Air-Operated Valve Programs
.  Identify the basis for how the margin was determined. 12. List of high
.  Identify the basis for how the margin was determin ed. 12. List of high
-risk Maintenance Rule systems/components based on engineering  
-risk Maintenance Rule systems/components based on engineering  
or expert panel judgment
or expert panel judgment
  (i.e., those systems/components not identified in the  
  (i.e., those systems/components not identified in the  
PSA). 13. Structures, systems, and components in the Maintenance Rule (a)(1) category
P S A). 13. Structures, systems, and components in the Maintenance Rule (a)(1) category
  for the last  
  for the last  
3 years. 14. Site top ten issues list (if applicable)
3 years. 14. Site top ten issues list (if applicable)
Line 171: Line 155:
  for the last  
  for the last  
10 years.  Identify frequency of preventive maintenance activities.
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)
  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
.  Pipe stress calculations
  are excluded from this request.
  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.
  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,
  5. A list of modifications, including equivalency evaluations and setpoint changes, associated with each of the selected components
associated with each of the selected components
.  This list should include a descriptive paragraph on the
.  This list should include a descriptive paragraph on the
  purpose of the modification.  Please ensure this list only includes design completed (not canceled) modifications.
  purpose of the modification.  Please ensure this list only includes design completed (not canceled) modifications.
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COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION
COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION
  4 III. Additional Information to
  4 III. Additional Information to
  be Provided on April 11, 2016,
  be Provided on April 11, 2016, On site (for final selected components)  
Onsite (for final selected components)  
  1. During the in
  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
-office preparation activities, the team will be making final selections and may identify additional information needed to support the inspection.  The lead inspector will
Line 210: Line 191:
  members and the status/resolution of the information requested (provide daily during the inspection  
  members and the status/resolution of the information requested (provide daily during the inspection  
to each team member)
to each team member)
. 3. Reference materials
. 3. Reference materials.  (make available if needed during all on
.  (make available if needed during all on
-site weeks):
-site weeks):
   Individual Plant Examination/Probabilistic Risk Assessment  
   Individual Plant Examination/Probabilistic Risk Assessment  
Line 219: Line 199:
  If you have questions regarding the information requested, please contact the lead inspector.
  If you have questions regarding the information requested, please contact the lead inspector.
    
    
   B. Hanson
   B. Hanson -3- In accordance with Title 10 of the Code of Federal Regulations
-3- 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  
  (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 inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide
of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide
Line 226: Line 205:
-rm/adams.html
-rm/adams.html
  (the Public Electronic Reading Room).
  (the Public Electronic Reading Room).
  Sincerely,
  Sincerely, /RA/  Christine A. Lipa, Chie f Engineering Branch 2
  /RA/  Christine A. Lipa, Chief Engineering Branch 2
   
   
Division of Reactor Safety  
Division of Reactor Safety  
Line 252: Line 230:
   Publicly Available
   Publicly Available
   Non-Publicly Available
   Non-Publicly Available
   Sensitive
   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
  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 NFeliz-Adorno:cl CLipa  DATE 12/10/15 12/10/15  OFFICIAL RECORD COPY
  OFFICE RIII  RIII  RIII  RIII  NAME NFeliz-Adorno:cl
CLipa  DATE 12/10/15 12/10/15  OFFICIAL RECORD COPY
}}
}}

Revision as of 18:21, 8 July 2018

Ltr 12/10/15 LaSalle County Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Component Design Bases Inspection; Inspection Report 05000373/2016007; 05000374/2016007 (Nja)
ML15345A263
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/10/2015
From: Lipa C A
NRC/RGN-III/DRS/EB2
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2016007
Download: ML15345A263 (8)


See also: IR 05000373/2016007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III 2443 WARRENVILLE RD. SUIT

E 210 LISLE, IL 60532

-4352 December 10, 2015

Mr. Bryan C. Hanson

Senior VP, Exelon Generation Company, LLC

President and CNO, Exelon Nuclear

4300 Winfield Road

Warrenville, IL 60555

SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2

- REQUEST FOR INFORMATION FOR AN NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION

INSPECTION REPORT 05000 373/20 1 6007; 05000 374/20 1 6007 Dear Mr. Hanson
On April 11, 2016

, the U. S. Nuclear Regulatory Commission (NRC) will begin a

triennial baseline Component Design Bases Inspection (CDBI) at

the La Salle County 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 you

r simulator staff to validate scenarios, simulator time, and a crew to perform the actions which would most likely occur during the second onsite 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 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:

April 11 - 15, 2016; April 25 - 29, 2016; and May 9 - 13, 2016.

B. Hanson -2- The team will be preparing for the inspection, mainly during the week of

April 4 - 8, 2016, as discussed in the enclosure.

Experience with previous baseline design inspections of similar depth and length has shown that th is 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 onsite 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 provide d to the lead inspector no later than

February 29, 2016. By March 11, 2016, the lead inspector will communicate the initial selected set of approximately

2 0 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 March 30, 2016. During the inoffice 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 April 11, 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

Néstor J. Féliz

-Adorno. We understand that our licensing contact for this inspection is

Dwi Murray

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) 829-9739 , or via e-mail at Nestor.Feliz

-Adorno@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.

B. Hanson -3- 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 inspection in the NRC's 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).

Sincerel y, /RA/ Christine A. Lipa , Chie f Engineering Branch 2

Division of Reactor Safety

Docket Nos. 50

-373; 50-374 License Nos. NPF

-11; NPF-18 Enclosure:

Information Request for

CDBI cc: Distribution via LISTSERV

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION

Enclosure Inspection Report:

05000 373/20 1 6007; 05000 374/20 1 6007 Inspection Dates:

April 11 - 15, 2016; April 25 - 29, 2016; and May 9 - 13, 2016. Inspection Procedure:

IP 71111.21 "Component Design Bases Inspection"

Lead Inspector:

Néstor J. Féliz

-Adorno , Senior Reactor Engineer, DRS

(630) 829-9739 Nestor.Feliz

-Adorno@nrc.gov

I. Information Requested Prior to the Onsite Information Gathering/Inspection Week

The following information is requested by

February 29, 2016 , or sooner, to facilitate inspection

preparation. If you have any questions regarding this information, please call the team leader as soon as possible. Unless stated otherwise, please provide the information electronically in "pdf" files, Excel, or other searchable formats, preferably

on some portable electronic media (e.g., CD-ROM, DVD, 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

2 50 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 P

SA 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.

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION

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 determin ed. 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

P S A). 13. Structures, systems, and components 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 Piping and Instrumentation Drawing

s (P&IDs), including the table of content

(if available).

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

Available by

March 30, 2016, (will be reviewed by the team in the Regional office during the week of April 4 - 8, 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.

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION

3 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). 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: Pumps: comprehensive test, quarterly test, flow balance, etc.

Valves: stroke time testing, diagnostic testing, leak testing, interlocks, etc. Heat Exchangers/room coolers

thermal performance, clean/inspect, fan flows, etc.

Acceptance criteria basis calculations should also be included.

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

COMPONENT DESIGN BASES INSPECTION REQUEST FOR INFORMATION

4 III. Additional Information to

be Provided on April 11, 2016, 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 April 4 - 8, 2016. 2. Schedule of any testing/maintenance activities to be conducted on the selected components during the three onsite inspection weeks.

3. One complete set of P&IDs (paper copies)

. IV. Information Requested to be Provided Throughout the Inspection

1. Copies of any corrective action documents generated as a result of the team's 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. (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- 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 inspection in the NRC's 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, Chie f Engineering Branch 2

Division of Reactor Safety

Docket Nos. 50

-373; 50-374 License Nos. NPF

-11; NPF-18 Enclosure:

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