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{{Adams | |||
| number = ML14027A279 | |||
| issue date = 01/27/2014 | |||
| title = Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000483-14-007 | |||
| author name = Farnholtz T | |||
| author affiliation = NRC/RGN-IV/DRS/EB-1 | |||
| addressee name = Heflin A | |||
| addressee affiliation = Union Electric Co | |||
| docket = 05000483 | |||
| license number = NPF-030 | |||
| contact person = | |||
| document report number = IR-14-007 | |||
| document type = Inspection Plan, Letter | |||
| page count = 7 | |||
}} | |||
See also: [[see also::IR 05000483/2014007]] | |||
=Text= | |||
{{#Wiki_filter:UNITE D S TATE S | |||
NUC LEAR RE GULATOR Y C OMMI S SI ON | |||
R E G IO N I V | |||
1600 EAST LAMAR BLVD | |||
AR L I NGTON , TEXAS 7 601 1- 4511 | |||
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. | |||
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 Public Document Room or from | |||
the Publicly Available Records (PARS) component of NRCs document system (ADAMS). | |||
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the | |||
Public Electronic Reading Room). | |||
Sincerely, | |||
/RA/ | |||
Thomas R. Farnholtz, Chief | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket: 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 TRF | |||
Publicly Avail Yes No Sensitive Yes No Sens. Type Initials TRF | |||
RIV:SRI:DRS/EB1 BC/EB1 | |||
RKopriva TFarnholtz | |||
/RA/ TRF for /RA/ | |||
01/23/2014 01/23/2014 | |||
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. | |||
-1- Enclosure | |||
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. | |||
-2- | |||
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. | |||
-3- | |||
III. Information Requested to be provided throughout the inspection. | |||
1. Copies of any corrective action documents generated as a result of the | |||
teams questions or queries during this inspection. | |||
2. Copies of the list of questions submitted by the team members and the | |||
status/resolution of the information requested (provide daily during the | |||
inspection to each team member). | |||
3. Reference materials (available electronically and as needed during all | |||
onsite weeks): | |||
General set of plant drawings | |||
IPE/PRA report | |||
Procurement documents for components selected | |||
Plant procedures (normal, abnormal, emergency, surveillance, etc.) | |||
Technical Specifications | |||
Updated Final Safety Analysis Report | |||
Vendor manuals | |||
Inspector Contact Information: | |||
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 | |||
-4- | |||
}} |
Latest revision as of 10:09, 4 November 2019
ML14027A279 | |
Person / Time | |
---|---|
Site: | Callaway ![]() |
Issue date: | 01/27/2014 |
From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
To: | Heflin A Union Electric Co |
References | |
IR-14-007 | |
Download: ML14027A279 (7) | |
See also: IR 05000483/2014007
Text
UNITE D S TATE S
NUC LEAR RE GULATOR Y C OMMI S SI ON
R E G IO N I V
1600 EAST LAMAR BLVD
AR L I NGTON , TEXAS 7 601 1- 4511
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.
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 Public Document Room or from
the Publicly Available Records (PARS) component of NRCs document system (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the
Public Electronic Reading Room).
Sincerely,
/RA/
Thomas R. Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-483
License: NPF-30
Enclosure:
Component Design Basis Inspection
Document Request
cc w/ enclosure: Electronic Distribution for Callaway Plant
SUNSI Rev Compl. Yes No ADAMS Yes No Reviewer Initials TRF
Publicly Avail Yes No Sensitive Yes No Sens. Type Initials TRF
RIV:SRI:DRS/EB1 BC/EB1
RKopriva TFarnholtz
/RA/ TRF for /RA/
01/23/2014 01/23/2014
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.
-1- Enclosure
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
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.
-2-
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.
-3-
III. Information Requested to be provided throughout the inspection.
1. Copies of any corrective action documents generated as a result of the
teams questions or queries during this inspection.
2. Copies of the list of questions submitted by the team members and the
status/resolution of the information requested (provide daily during the
inspection to each team member).
3. Reference materials (available electronically and as needed during all
onsite weeks):
General set of plant drawings
IPE/PRA report
Procurement documents for components selected
Plant procedures (normal, abnormal, emergency, surveillance, etc.)
Technical Specifications
Updated Final Safety Analysis Report
Vendor manuals
Inspector Contact Information:
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
-4-