ML14027A279: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:       January 27, 2014   
{{#Wiki_filter:January 27, 2014  
    
Mr. Adam C. Heflin, Senior Vice  
Mr. Adam C. Heflin, Senior Vice  
President and Chief Nuclear Officer  
President and Chief Nuclear Officer  
Union Electric Company P.O. Box 620 Fulton, MO 65251  
Union Electric Company P.O. Box 620 Fulton, MO 65251  
   
   
SUBJECT: CALLAWAY PLANT - INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION REPORT 05000483/2014007
   
   
SUBJECT: CALLAWAY PLANT - INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION REPORT 05000483/2014007 
Dear Mr. Heflin:  
Dear Mr. Heflin:  
   
   
On April 14, 2014, the NRC will begin a triennial baseline Component Design Bases Inspection at the Callaway Plant.  A seven-person team will perform this inspection using NRC Inspection Procedure 71111.21, "Component Design Bases Inspection."  
On April 14, 2014, the NRC will begin a triennial baseline Component Design Bases Inspection at the Callaway Plant.  A seven-person team will perform this inspection using NRC Inspection Procedure 71111.21, "Component Design Bases Inspection."  
   
   
The inspection focuses on components and operator actions that have high risk and low design  
The inspection focuses on components and operator actions that have high risk and low design  
margins.  The samples reviewed during this inspection will be identified during an information gathering visit and during the subsequent in-office preparation week.  In addition, a number of operating experience issues will also be selected for review.   
margins.  The samples reviewed during this inspection will be identified during an information gathering visit and during the subsequent in-office preparation week.  In addition, a number of operating experience issues will also be selected for review.   
   
   
The inspection will include an information gathering site visit by the team leader and a senior  
The inspection will include an information gathering site visit by the team leader and a senior  
reactor analyst, and 3-weeks of onsite inspection by the team.  The inspection will consist of seven NRC inspectors, of which six will focus on engineering and one on operations.  The current inspection schedule is as follows:  
reactor analyst, and 3-weeks of onsite inspection by the team.  The inspection will consist of seven NRC inspectors, of which six will focus on engineering and one on operations.  The current inspection schedule is as follows:  
  Onsite information gathering visit: Week of March 24, 2014 Onsite weeks: First On-Site Week - April 14-18, 2014  
  Onsite information gathering visit: Week of March 24, 2014 Onsite weeks: First On-Site Week - April 14-18, 2014  
   Second On-Site Week -  April 28 - May 2, 2014  Third On-Site Week - May 12-16, 2014  The purpose of the information gathering visit is to meet with members of your staff to identify  
   Second On-Site Week -  April 28 - May 2, 2014  Third On-Site Week - May 12-16, 2014  
  The purpose of the information gathering visit is to meet with members of your staff to identify  
potential risk-significant components and operator actions.  The lead inspector will also request  
potential risk-significant components and operator actions.  The lead inspector will also request  
a tour of the plant with members of your operations staff and probabilistic safety assessment staff.  Additional information and documentation needed to support the inspection will be identified, including interviews with engineering managers, engineers, and probabilistic safety  
a tour of the plant with members of your operations staff and probabilistic safety assessment staff.  Additional information and documentation needed to support the inspection will be identified, including interviews with engineering managers, engineers, and probabilistic safety  
assessment staff.   
assessment staff.   
  UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV1600 EAST LAMAR BLVDARLINGTON, TEXAS 76011-4511  
  UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV1600 EAST LAMAR BLVDARLINGTON, TEXAS 76011-4511  
A. Heflin  - 2 -  Our experience with these inspections has shown they are extremely resource intensive, both for the NRC inspectors and the licensee staff.  In order to minimize the inspection impact on the site and to ensure a productive inspection, we have enclosed a request for information needed  
A. Heflin  - 2 -  
   Our experience with these inspections has shown they are extremely resource intensive, both for the NRC inspectors and the licensee staff.  In order to minimize the inspection impact on the site and to ensure a productive inspection, we have enclosed a request for information needed  
for the inspection.  The request has been divided into three groups.  The first group lists  
for the inspection.  The request has been divided into three groups.  The first group lists  
information necessary for the information gathering visit and for general preparation.  This  
information necessary for the information gathering visit and for general preparation.  This  
information should be available to the regional office no later than March 17, 2014.  Insofar as  
information should be available to the regional office no later than March 17, 2014.  Insofar as  
possible, this information should be provided electronically to the lead inspector.  Since the inspection will be concentrated on high risk/low margin components, calculations associated with your list of high risk components should be available to review during the information  
possible, this information should be provided electronically to the lead inspector.  Since the inspection will be concentrated on high risk/low margin components, calculations associated with your list of high risk components should be available to review during the information  
gathering visit to assist in our selection of components based on available design margin.  
gathering visit to assist in our selection of components based on available design margin.
The second group of documents requested are those items that the team will need access to when onsite and after the inspection samples are selected. The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection.  It  
The second group of documents requested are those items that the team will need access to when onsite and after the inspection samples are selected. The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection.  It  
is requested that this information be provided to the lead inspector as the information is  
is requested that this information be provided to the lead inspector as the information is  
Line 50: Line 62:
completed in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.  In order to facilitate the inspection, we request that a contact individual be assigned to each inspector to ensure information requests,  
completed in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.  In order to facilitate the inspection, we request that a contact individual be assigned to each inspector to ensure information requests,  
questions, and concerns are addressed in a timely manner.   
questions, and concerns are addressed in a timely manner.   
   
   
The lead inspector for this inspection is Mr. Ronald Kopriva.  We understand that our licensing engineer contact for this inspection is Mr. Steve Petzel.  If there are any questions about the inspection or the requested materials, please contact the lead inspector at (817) 200-1104 or via e-mail at Ron.Kopriva@nrc.gov.   
The lead inspector for this inspection is Mr. Ronald Kopriva.  We understand that our licensing engineer contact for this inspection is Mr. Steve Petzel.  If there are any questions about the inspection or the requested materials, please contact the lead inspector at (817) 200-1104 or via  
e-mail at Ron.Kopriva@nrc.gov
.   
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be  
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be  
made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).  ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).  
made available electronically for  
public inspection in the NRC Pub
lic Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).  ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).  
 
   
   
       Sincerely,  
       Sincerely,  
   
   
       /RA/  Thomas R. Farnholtz, Chief      Engineering Branch 1 Division of Reactor Safety  Docket:  50-483  
       /RA/  
  Thomas R. Farnholtz, Chief      Engineering Branch 1  
Division of Reactor Safety  
  Docket:  50-483  
License: NPF-30  
License: NPF-30  
   
   
Enclosure:   
Enclosure:   
Component Design Basis Inspection   Document Request   
Component Design Basis Inspection
  Document Request  
   
cc w/ enclosure:  Electronic Distribution for Callaway Plant   
cc w/ enclosure:  Electronic Distribution for Callaway Plant   
A. Heflin - 3 -    ADAMS ACCESSION NUMBER:  ML14027A279 SUNSI Rev Compl.  Yes  No ADAMS  Yes  No Reviewer Initials TRFPublicly Avail  Yes  No Sensitive  Yes No Sens. Type Initials TRFRIV:SRI:DRS/EB1 BC/EB1    RKopriva TFarnholtz    /RA/  TRF for /RA/    01/23/2014 01/23/2014   OFFICIAL RECORD COPY  T=Telephone          E=E-mail        F=Fax 
 
  - 1 - Enclosure INFORMATION REQUEST FOR CALLAWAY PLANT  COMPONENT DESIGN BASES (CDBI) INSPECTION   
  ML14027A279
  Inspection Report:    05000483/2014007   
  SUNSI Rev Compl.  Yes  No ADAMS  Yes  No Reviewer Initials TRFPublicly Avail  Yes  No Sensitive  Yes No Sens. Type Initials TRFRIV:SRI:DRS/EB1 BC/EB1    RKopriva TFarnholtz    /RA/  TRF for  
Information Gathering Dates: March 24-28, 2014   
/RA/    01/23/2014 01/23/2014    
On-site Inspection Dates:  First Week  - April 14-18, 2014       Second Week -  April 28 - May 2, 2014      Third Week  - May 12-16, 2014  
  - 1 - Enclosure INFORMATION REQUEST FOR CALLAWAY PLANT  COMPONENT DESIGN BASES (CDBI) INSPECTION  
    
  Inspection Report:    05000483/2014007  
   
Information Gathering Dates: March 24-28, 2014  
   
On-site Inspection Dates:  First Week  - April 14-18, 2014
    Second Week -  April 28 - May 2, 2014      Third Week  - May 12-16, 2014  
 
   
   
Inspection Procedure:  IP 71111.21, "Component Design Bases Inspection"  Lead Inspector/Team Leader: Ronald Kopriva      817-200-1104  
Inspection Procedure:  IP 71111.21, "Component Design Bases Inspection"  
  Lead Inspector/Team Leader: Ronald Kopriva      817-200-1104  
     Ron.Kopriva@nrc.gov  
     Ron.Kopriva@nrc.gov  
   I. Information Requested Prior to the information Gathering Visit The following information is requested by March 17, 2014, or sooner, to facilitate  
 
   I. Information Requested Prior to the information Gathering Visit
  The following information is requested by March 17, 2014, or sooner, to facilitate  
inspection preparation.  If you have any questions regarding this information,  
inspection preparation.  If you have any questions regarding this information,  
pleased call the lead inspector as soon as possible.  (Please provide the information electronically in "pdf" files, Excel, or other searchable formats.  The information should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use.  Information in "lists" should contain enough information to  
pleased call the lead inspector as soon as possible.  (Please provide the information electronically in "pdf" files, Excel, or other searchable formats.  The information should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use.  Information in "lists" should contain enough information to  
be easily understood by someone who has knowledge of boiling water reactor  
be easily understood by someone who has knowledge of boiling water reactor  
technology.)  1. An excel spreadsheet of equipment basic events (with definitions) including importance measures sorted by risk achievement worth (RAW) and Fussell-Vesely (FV) from your internal events probabilistic risk  
 
technology.)  
   1. An excel spreadsheet of equipment basic events (with definitions) including importance measures sorted by risk achievement worth (RAW) and Fussell-Vesely (FV) from your internal events probabilistic risk  
assessment (PRA).  Include basic events with RAW value of 1.3 or  
assessment (PRA).  Include basic events with RAW value of 1.3 or  
greater.   2. Provide a list of the top 500 cut-sets from your PRA.  
 
  3. Copies of PRA "system notebooks," and the latest PRA summary document.  4. An excel spreadsheet of PRA human action basic events or risk ranking of operator actions from your site specific PSA sorted by RAW and FV.   
greater.
Provide copies of your human reliability worksheets for these items.  
2. Provide a list of the top 500 cut-sets from your PRA.
  5. If you have an external events or fire PSA model, provide the information requested in items 1-4 for external events and fire.   
  3. Copies of PRA "system notebooks," and the latest PRA summary  
document.  
   4. An excel spreadsheet of PRA human action basic events or risk ranking of operator actions from your site specific PSA sorted by RAW and FV.   
Provide copies of your human reliability worksheets for these items.
  5. If you have an external events or fire PSA model, provide the information requested in items 1-4 for external events and fire.  
    
   - 2 -  6.  Any pre-existing evaluation or list of components and associated calculations with low design margins, (i.e., pumps closest to the design  
   - 2 -  6.  Any pre-existing evaluation or list of components and associated calculations with low design margins, (i.e., pumps closest to the design  
limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal, etc.).   
limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal, etc.).  
  7.  List of high risk maintenance rule systems/components and functions; based on engineering or expert panel judgment.   
   
  8. A list of operating experience evaluations for the last 2 years.     9.  A list of all time-critical operator actions in procedures.  
  7.  List of high risk maintenance rule systems/components and functions; based on engineering or expert panel judgment.  
   
  8. A list of operating experience evaluations for the last 2 years.  
  9.  A list of all time-critical operator actions in procedures.  
 
10. A list of permanent and temporary modifications sorted by component identified in Item 1. 
  11.  List of current "operator work arounds/burdens."
 
   
   
  10. A list of permanent and temporary modifications sorted by component identified in Item 1.    11.  List of current "operator work arounds/burdens."
  12. A list of the design calculations, which provide the design margin information for components included in Item 1.  (Calculations should be available during the information gathering visit.)
   
   
12. A list of the design calculations, which provide the design margin information for components included in Item 1.  (Calculations should be available during the information gathering visit.) 
  13.  List of root cause evaluations associated with component failures or design issues initiated/completed in the last 5 years.
  13.  List of root cause evaluations associated with component failures or design issues initiated/completed in the last 5 years.  
  14.  Current management and engineering organizational charts.   15. Callaway Plant IPEEE, if available electronically.  
  14.  Current management and engineering organizational charts.
  15. Callaway Plant IPEEE, if available electronically.  
 
   
   
  16. Mechanical piping drawings for:  
  16. Mechanical piping drawings for:  
   Engineered safety features  Emergency core cooling Systems  
   Engineered safety features  Emergency core cooling Systems  
   Emergency diesel generators  
   Emergency diesel generators  
   
   
  17 Electrical one-line drawings for:  
  17 Electrical one-line drawings for:  
     Offsite power/switchyard supplies  Normal ac power systems  
     Offsite power/switchyard supplies  Normal ac power systems  
   Emergency ac/dc power systems including    120Vac power, and    125Vdc/24Vdc safety class systems  
   Emergency ac/dc power systems including    120Vac power, and    125Vdc/24Vdc safety class systems  
  18. List of any common-cause failures of components in the last 3 years.  
  18. List of any common-cause failures of components in the last 3 years.  
19. An electronic copy of the Design Bases Documents.
20. An electronic copy of the System Health notebooks. 
  - 3 -  II.  Information Requested to be Available on First Day of Inspection
(April 14, 2014)
 
1. List of condition reports (corrective action documents) associated with each of the selected components for the last 5 years.
   
   
19. An electronic copy of the Design Bases Documents.  20. An electronic copy of the System Health notebooks. 
  2. The corrective maintenance history associated with each of the selected components for the last 2 years.
  - 3 -  II.  Information Requested to be Available on First Day of Inspection (April 14, 2014) 
  3. Copies of calculations associated with each of the selected components (if not previously provided), excluding data files.  Please review the  
1. List of condition reports (corrective action documents) associated with each of the selected components for the last 5 years. 
  2. The corrective maintenance history associated with each of the selected components for the last 2 years.   3. Copies of calculations associated with each of the selected components (if not previously provided), excluding data files.  Please review the  
calculations and also provide copies of reference material (such as  
calculations and also provide copies of reference material (such as  
drawings, engineering requests, and vendor letters).  4. Copies of operability evaluations associated with each of the selected components and plans for restoring operability, if applicable.  
drawings, engineering requests, and vendor letters).  
  5. Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable.  6. Copies of any open temporary modifications associated with each of the selected components, if applicable.   
   4. Copies of operability evaluations associated with each of the selected components and plans for restoring operability, if applicable.
  7. Trend data on the selected electrical/mechanical components' performance for last 3 years (for example, pumps' performance including in-service testing, other vibration monitoring, oil sample results, etc., as applicable).   
  8.  A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection.   9. A copy of engineering/operations related audits completed in the last 2 years.   
  5. Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable.  
  10. List of motor operated valves (MOVs) in the program, design margin and risk ranking.  11. List of air operated valves (AOVs) in the valve program, design and risk ranking.   
   6. Copies of any open temporary modifications associated with each of the selected components, if applicable.  
  12. Structure, system and components in the Maintenance Rule (a)(1) category.   
   
  7. Trend data on the selected electrical/mechanical components'  
performance for last 3 years (for example, pumps' performance including in-service testing, other vibration monitoring, oil sample results, etc., as applicable).  
   
  8.  A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection.
  9. A copy of engineering/operations related audits completed in the last  
2 years.  
   
  10. List of motor operated valves (MOVs) in the program, design margin and risk ranking.  
   11. List of air operated valves (AOVs) in the valve program, design and risk ranking.  
   
  12. Structure, system and components in the Maintenance Rule (a)(1)  
category.  
   
  13.  Site top 10 issues list.  
  13.  Site top 10 issues list.  
14. Procedures used to accomplish operator actions associated with the
basic events in your PRA.
  15.  List of licensee contacts for the inspection team with pager or phone
numbers. 
  - 4 -  III. 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.
   
   
14. Procedures used to accomplish operator actions associated with the basic events in your PRA.  15.  List of licensee contacts for the inspection team with pager or phone numbers. 
  - 4 -  III. 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  
  2. Copies of the list of questions submitted by the team members and the status/resolution of the information requested (provide daily during the  
inspection to each team member).  3. Reference materials (available electronically and as needed during all onsite weeks):   
inspection to each team member).  
   3. Reference materials (available electronically and as needed during all  
onsite weeks):  
   
   General set of plant drawings  IPE/PRA report  Procurement documents for components selected  Plant procedures (normal, abnormal, emergency, surveillance, etc.)  
   General set of plant drawings  IPE/PRA report  Procurement documents for components selected  Plant procedures (normal, abnormal, emergency, surveillance, etc.)  
   Technical Specifications  
   Technical Specifications  
   Updated Final Safety Analysis Report  
   Updated Final Safety Analysis Report  
   Vendor manuals   
   Vendor manuals  
Inspector Contact Information:   
    
Inspector Contact Information
:   
Ronald Kopriva  
Ronald Kopriva  
Senior Reactor Inspector (817) 200-1104 Ron.Kopriva@nrc.gov  
Senior Reactor Inspector  
(817) 200-1104 Ron.Kopriva@nrc.gov  
 
   
   
Mailing Address:  RONALD KOPRIVA US NRC, REGION IV  
Mailing Address
:  RONALD KOPRIVA US NRC, REGION IV  
 
1600 E LAMAR BLVD  
1600 E LAMAR BLVD  
ARLINGTON TX  76011
ARLINGTON TX  76011
 
}}
}}

Revision as of 01:10, 3 July 2018

Callaway, Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000483-14-007
ML14027A279
Person / Time
Site: Callaway Ameren icon.png
Issue date: 01/27/2014
From: Thomas Farnholtz
Region 4 Engineering Branch 1
To: Heflin A C
Union Electric Co
References
IR-14-007
Download: ML14027A279 (7)
v • d • e


See also: IR 05000483/2014007

Text

January 27, 2014

Mr. Adam C. Heflin, Senior Vice

President and Chief Nuclear Officer

Union Electric Company P.O. Box 620 Fulton, MO 65251

SUBJECT: CALLAWAY PLANT - INFORMATION REQUEST FOR NRC TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC INSPECTION REPORT 05000483/2014007

Dear Mr. Heflin:

On April 14, 2014, the NRC will begin a triennial baseline Component Design Bases Inspection at the Callaway Plant. A seven-person team will perform this inspection using NRC Inspection Procedure 71111.21, "Component Design Bases Inspection."

The inspection focuses on components and operator actions that have high risk and low design

margins. The samples reviewed during this inspection will be identified during an information gathering visit and during the subsequent in-office preparation week. In addition, a number of operating experience issues will also be selected for review.

The inspection will include an information gathering site visit by the team leader and a senior

reactor analyst, and 3-weeks of onsite inspection by the team. The inspection will consist of seven NRC inspectors, of which six will focus on engineering and one on operations. The current inspection schedule is as follows:

Onsite information gathering visit: Week of March 24, 2014 Onsite weeks: First On-Site Week - April 14-18, 2014

Second On-Site Week - April 28 - May 2, 2014 Third On-Site Week - May 12-16, 2014

The purpose of the information gathering visit is to meet with members of your staff to identify

potential risk-significant components and operator actions. The lead inspector will also request

a tour of the plant with members of your operations staff and probabilistic safety assessment staff. Additional information and documentation needed to support the inspection will be identified, including interviews with engineering managers, engineers, and probabilistic safety

assessment staff.

UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION IV1600 EAST LAMAR BLVDARLINGTON, TEXAS 76011-4511

A. Heflin - 2 -

Our experience with these inspections has shown they are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection, we have enclosed a request for information needed

for the inspection. The request has been divided into three groups. The first group lists

information necessary for the information gathering visit and for general preparation. This

information should be available to the regional office no later than March 17, 2014. Insofar as

possible, this information should be provided electronically to the lead inspector. Since the inspection will be concentrated on high risk/low margin components, calculations associated with your list of high risk components should be available to review during the information

gathering visit to assist in our selection of components based on available design margin.

The second group of documents requested are those items that the team will need access to when onsite and after the inspection samples are selected. The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It

is requested that this information be provided to the lead inspector as the information is

generated during the inspection. It is important that all of these documents are up to date and

completed in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. In order to facilitate the inspection, we request that a contact individual be assigned to each inspector to ensure information requests,

questions, and concerns are addressed in a timely manner.

The lead inspector for this inspection is Mr. Ronald Kopriva. We understand that our licensing engineer contact for this inspection is Mr. Steve Petzel. If there are any questions about the inspection or the requested materials, please contact the lead inspector at (817) 200-1104 or via

e-mail at Ron.Kopriva@nrc.gov

.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be

made available electronically for

public inspection in the NRC Pub

lic Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html

(the Public Electronic Reading Room).

Sincerely,

/RA/

Thomas R. Farnholtz, Chief Engineering Branch 1

Division of Reactor Safety

Docket: 50-483

License: NPF-30

Enclosure:

Component Design Basis Inspection

Document Request

cc w/ enclosure: Electronic Distribution for Callaway Plant

ML14027A279

SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials TRFPublicly Avail Yes No Sensitive Yes No Sens. Type Initials TRFRIV:SRI:DRS/EB1 BC/EB1 RKopriva TFarnholtz /RA/ TRF for

/RA/ 01/23/2014 01/23/2014

- 1 - Enclosure INFORMATION REQUEST FOR CALLAWAY PLANT COMPONENT DESIGN BASES (CDBI) INSPECTION

Inspection Report: 05000483/2014007

Information Gathering Dates: March 24-28, 2014

On-site Inspection Dates: First Week - April 14-18, 2014

Second Week - April 28 - May 2, 2014 Third Week - May 12-16, 2014

Inspection Procedure: IP 71111.21, "Component Design Bases Inspection"

Lead Inspector/Team Leader: Ronald Kopriva 817-200-1104

Ron.Kopriva@nrc.gov

I. Information Requested Prior to the information Gathering Visit

The following information is requested by March 17, 2014, or sooner, to facilitate

inspection preparation. If you have any questions regarding this information,

pleased call the lead inspector as soon as possible. (Please provide the information electronically in "pdf" files, Excel, or other searchable formats. The information should contain descriptive names, and be indexed and hyperlinked to facilitate ease of use. Information in "lists" should contain enough information to

be easily understood by someone who has knowledge of boiling water reactor

technology.)

1. An excel spreadsheet of equipment basic events (with definitions) including importance measures sorted by risk achievement worth (RAW) and Fussell-Vesely (FV) from your internal events probabilistic risk

assessment (PRA). Include basic events with RAW value of 1.3 or

greater.

2. Provide a list of the top 500 cut-sets from your PRA.

3. Copies of PRA "system notebooks," and the latest PRA summary

document.

4. An excel spreadsheet of PRA human action basic events or risk ranking of operator actions from your site specific PSA sorted by RAW and FV.

Provide copies of your human reliability worksheets for these items.

5. If you have an external events or fire PSA model, provide the information requested in items 1-4 for external events and fire.

- 2 - 6. Any pre-existing evaluation or list of components and associated calculations with low design margins, (i.e., pumps closest to the design

limit for flow or pressure, diesel generator close to design required output, heat exchangers close to rated design heat removal, etc.).

7. List of high risk maintenance rule systems/components and functions; based on engineering or expert panel judgment.

8. A list of operating experience evaluations for the last 2 years.

9. A list of all time-critical operator actions in procedures.

10. A list of permanent and temporary modifications sorted by component identified in Item 1.

11. List of current "operator work arounds/burdens."

12. A list of the design calculations, which provide the design margin information for components included in Item 1. (Calculations should be available during the information gathering visit.)

13. List of root cause evaluations associated with component failures or design issues initiated/completed in the last 5 years.

14. Current management and engineering organizational charts.

15. Callaway Plant IPEEE, if available electronically.

16. Mechanical piping drawings for:

Engineered safety features Emergency core cooling Systems

Emergency diesel generators

17 Electrical one-line drawings for:

Offsite power/switchyard supplies Normal ac power systems

Emergency ac/dc power systems including 120Vac power, and 125Vdc/24Vdc safety class systems

18. List of any common-cause failures of components in the last 3 years.

19. An electronic copy of the Design Bases Documents.

20. An electronic copy of the System Health notebooks.

- 3 - II. Information Requested to be Available on First Day of Inspection

(April 14, 2014)

1. List of condition reports (corrective action documents) associated with each of the selected components for the last 5 years.

2. The corrective maintenance history associated with each of the selected components for the last 2 years.

3. Copies of calculations associated with each of the selected components (if not previously provided), excluding data files. Please review the

calculations and also provide copies of reference material (such as

drawings, engineering requests, and vendor letters).

4. Copies of operability evaluations associated with each of the selected components and plans for restoring operability, if applicable.

5. Copies of selected operator work-around evaluations associated with each of the selected components and plans for resolution, if applicable.

6. Copies of any open temporary modifications associated with each of the selected components, if applicable.

7. Trend data on the selected electrical/mechanical components'

performance for last 3 years (for example, pumps' performance including in-service testing, other vibration monitoring, oil sample results, etc., as applicable).

8. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for the inspection.

9. A copy of engineering/operations related audits completed in the last

2 years.

10. List of motor operated valves (MOVs) in the program, design margin and risk ranking.

11. List of air operated valves (AOVs) in the valve program, design and risk ranking.

12. Structure, system and components in the Maintenance Rule (a)(1)

category.

13. Site top 10 issues list.

14. Procedures used to accomplish operator actions associated with the

basic events in your PRA.

15. List of licensee contacts for the inspection team with pager or phone

numbers.

- 4 - III. 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 (available electronically and as needed during all

onsite weeks):

General set of plant drawings IPE/PRA report Procurement documents for components selected Plant procedures (normal, abnormal, emergency, surveillance, etc.)

Technical Specifications

Updated Final Safety Analysis Report

Vendor manuals

Inspector Contact Information

Ronald Kopriva

Senior Reactor Inspector

(817) 200-1104 Ron.Kopriva@nrc.gov

Mailing Address

RONALD KOPRIVA US NRC, REGION IV

1600 E LAMAR BLVD

ARLINGTON TX 76011

Retrieved from "https://kanterella.com/w/index.php?title=ML14027A279&oldid=796441"