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{{#Wiki_filter:December 16, 2008 | {{#Wiki_filter:UNITED S TATE S | ||
N UCLE AR REGU LATORY COMMI SS ION | |||
Grand Gulf Nuclear Station Entergy Operations, Inc. P.O. Box 756 Port Gibson, MS 39150 | R E GI ON I V | ||
612 E. LAMAR BLVD., SU ITE 40 0 | |||
SUBJECT: GRAND GULF NUCLEAR STATION | AR LIN GTON , TEXAS 7 6 01 1- 4125 | ||
December 16, 2008 | |||
James R. Douet, Vice President of Operations | |||
Grand Gulf Nuclear Station | |||
Inspection at the Grand Gulf Nuclear Station. | Entergy Operations, Inc. | ||
P.O. Box 756 | |||
gathering visit and during the subsequent in-office preparation week. | Port Gibson, MS 39150 | ||
SUBJECT: GRAND GULF NUCLEAR STATION - INFORMATION REQUEST FOR NRC | |||
seven NRC inspectors, of which six will focus on engineering and one on operations. | TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC | ||
INSPECTION REPORT 05000416/2009006 | |||
Dear Mr. Douet: | |||
On February 2, 2009, the NRC will begin a triennial baseline Component Design Bases | |||
Inspection at the Grand Gulf Nuclear Station. 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 January 19, 2009 | |||
Onsite weeks: February 2, February 16, and February 23, 2009 | |||
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. | |||
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 | |||
Entergy Operations, Inc. -2- | |||
information should be available to the regional office no later than January 27, 2009. Insofar as | |||
Entergy Operations, Inc. - 2 - | 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. | 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. | |||
necessary to aid the inspection team in tracking issues identified as a result of the inspection. | 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 A. Kopriva. We understand that our | |||
licensing engineer contact for this inspection is Mr. Dennis Coulter. If there are any questions | |||
about the inspection or the requested materials, please contact the lead inspector at (817) 860- | |||
8104 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 Farnholtz, Chief | |||
Engineering Branch 1 | |||
Division of Reactor Safety | |||
Docket: 50-416 | |||
License: NPF-29 | |||
Enclosure: | |||
Information Request For Grand Gulf Plant Component Design Bases Inspection. | |||
cc w/enclosure | |||
Senior Vice President | |||
Entergy Nuclear Operations | |||
P.O. Box 31995 | |||
Jackson, MS 39286-1995 | |||
Entergy Operations, Inc. -3- | |||
Senior Vice President and COO | |||
Entergy Operations, Inc. Attorney General | |||
P.O. Box 31995 Department of Justice | |||
Jackson, MS 39286-1995 State of Louisiana | |||
P.O. Box 94005 | |||
Vice President, Oversight Baton Rouge, LA 70804-9005 | |||
Entergy Services, Inc. | |||
P.O. Box 31995 Office of the Governor | |||
Jackson, MS 39286-1995 State of Mississippi | |||
Jackson, MS 39201 | |||
Chief, Energy and Transportation Branch | |||
Environmental Compliance and Attorney General | |||
Enforcement Division Asst. Attorney General | |||
Mississippi Department of State of Mississippi | |||
Environmental Quality P.O. Box 22947 | |||
P.O. Box 10385 Jackson, MS 39225-2947 | |||
Jackson, MS 39289-0385 | |||
State Health Officer | |||
President State Health Board | |||
Claiborne County P.O. Box 1700 | |||
Board of Supervisors Jackson, MS 39215 | |||
P.O. Box 339 | |||
Port Gibson, MS 39150 Associate General Counsel | |||
Entergy Nuclear Operations | |||
Senior Manager P.O. Box 31995 | |||
Nuclear Safety & Licensing Jackson, MS 39286-1995 | |||
Entergy Nuclear Operations | |||
P.O. Box 31995 Richard Penrod, Senior Environmental | |||
Jackson, MS 39286-1995 Scientist/State Liaison Officer | |||
Office of Environmental Services | |||
Manager, Licensing Northwestern State University | |||
Entergy Operations, Inc. Russell Hall, Room 201 | |||
Grand Gulf Nuclear Station Natchitoches, LA 71497 | |||
P.O. Box 756 | |||
Port Gibson, MS 39150 | |||
Entergy Operations, Inc. -4- | |||
Electronic distribution by RIV: | |||
Regional Administrator (Elmo.Collins@nrc.gov ) | |||
DRP Director (Dwight.Chamberlain@nrc.gov ) | |||
DRP Deputy Director (Anton.Vegel@nrc.gov ) | |||
DRS Director (Roy.Caniano@nrc.gov ) | |||
DRS Deputy Director (Troy.Pruett@nrc.gov ) | |||
Senior Resident Inspector (Rich.Smith@nrc.gov ) | |||
Resident Inspector (Andy.Barrett@nrc.gov ) | |||
Branch Chief, DRP/C (Geoffrey.Miller@nrc.gov ) | |||
Senior Project Engineer, DRP/C (Wayne.Walker@nrc.gov | |||
GG Site Secretary (Nancy.Spivey@nrc.gov ) | |||
Public Affairs Officer (Victor.Dricks@nrc.gov ) | |||
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov ) | |||
RITS Coordinator (Marisa.Herrera@nrc.gov) | |||
RC/ACES (Karla.Fuller@nrc.gov ) | |||
C. A. Carpenter, OE Cynthia.Carpenter@nrc.gov | |||
OEMAIL.Resource@nrc.gov | |||
Senior Enforcement Specialist (Mark.Haire@nrc.gov) | |||
Only inspection reports to the following: | |||
DRS STA (Dale.Powers@nrc.gov ) | |||
Mark Cox, OEDO RIV Coordinator (Mark.Cox@nrc.gov ) | |||
SUNSI Review Completed: _ __ ADAMS: Yes No Initials: _RAK_ | |||
Publicly Available Non-Publicly Available Sensitive Non-Sensitive | |||
R:\_REACTORS\GG\2009\GG2009-006RFI-RAK.doc ML | |||
SRI:DRS/EB1 C:DRS/EB1 | |||
RAKopriva TFarnholtz | |||
/RA/ /RA/ | |||
12/16/08 12/16/08 | |||
Entergy Operations, Inc. - 4 - | OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax | ||
DRS STA (Dale.Powers@nrc.gov ) Mark Cox, OEDO RIV Coordinator (Mark.Cox@nrc.gov ) | |||
/RA/ /RA/ | |||
INFORMATION REQUEST FOR GRAND GULF NUCLEAR STATION | |||
COMPONENT DESIGN BASES INSPECTION (CDBI) | |||
Inspection Report: 05000416/2009006 | |||
Information Gathering Dates: January 21-23, 2009 | |||
On-site Inspection Dates: February 2-6, 2009 and February 16-27, 2009 | |||
Inspection Procedure: IP 71111.21, Component Design Bases | |||
Inspection | |||
Lead Inspector/Team Leader: Ronald A. Kopriva | |||
817-860-8104 | |||
Ron.Kopriva@nrc.gov | |||
I. Information Requested Prior to the information Gathering Visit | |||
The following information is requested by January 27, 2009, 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. Grand Gulf Nuclear Station 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- Enclosure | |||
II. Information Requested to be Available on First Day of Inspection (February | |||
2, 2009) | |||
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- Enclosure | |||
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 | ||
Ronald A. Kopriva Senior Reactor Inspector (817) 860-8104 Ron.Kopriva@nrc.gov | Procurement documents for components selected | ||
Plant procedures (normal, abnormal, emergency, surveillance, etc.) | |||
Mailing Address | Technical Specifications | ||
Updated Final Safety Analysis Report | |||
Vendor manuals | |||
Inspector Contact Information: | |||
Ronald A. Kopriva | |||
Senior Reactor Inspector | |||
(817) 860-8104 | |||
Ron.Kopriva@nrc.gov | |||
Mailing Address: | |||
US NRC, Region IV | |||
Attn: Ronald A. Kopriva | |||
612 East Lamar Blvd., Ste 400 | |||
Arlington, TX 76011 | |||
-4- Enclosure | |||
}} | }} |
Latest revision as of 11:16, 14 November 2019
ML083570174 | |
Person / Time | |
---|---|
Site: | Grand Gulf |
Issue date: | 12/16/2008 |
From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
To: | Douet J Entergy Operations |
References | |
IR-09-006 | |
Download: ML083570174 (8) | |
See also: IR 05000416/2009006
Text
UNITED S TATE S
N UCLE AR REGU LATORY COMMI SS ION
R E GI ON I V
612 E. LAMAR BLVD., SU ITE 40 0
AR LIN GTON , TEXAS 7 6 01 1- 4125
December 16, 2008
James R. Douet, Vice President of Operations
Grand Gulf Nuclear Station
Entergy Operations, Inc.
P.O. Box 756
Port Gibson, MS 39150
SUBJECT: GRAND GULF NUCLEAR STATION - INFORMATION REQUEST FOR NRC
TRIENNIAL BASELINE COMPONENT DESIGN BASES INSPECTION NRC
INSPECTION REPORT 05000416/2009006
Dear Mr. Douet:
On February 2, 2009, the NRC will begin a triennial baseline Component Design Bases
Inspection at the Grand Gulf Nuclear Station. 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 January 19, 2009
Onsite weeks: February 2, February 16, and February 23, 2009
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.
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
Entergy Operations, Inc. -2-
information should be available to the regional office no later than January 27, 2009. 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 A. Kopriva. We understand that our
licensing engineer contact for this inspection is Mr. Dennis Coulter. If there are any questions
about the inspection or the requested materials, please contact the lead inspector at (817) 860-
8104 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 Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-416
License: NPF-29
Enclosure:
Information Request For Grand Gulf Plant Component Design Bases Inspection.
cc w/enclosure
Senior Vice President
Entergy Nuclear Operations
P.O. Box 31995
Jackson, MS 39286-1995
Entergy Operations, Inc. -3-
Senior Vice President and COO
Entergy Operations, Inc. Attorney General
P.O. Box 31995 Department of Justice
Jackson, MS 39286-1995 State of Louisiana
P.O. Box 94005
Vice President, Oversight Baton Rouge, LA 70804-9005
Entergy Services, Inc.
P.O. Box 31995 Office of the Governor
Jackson, MS 39286-1995 State of Mississippi
Jackson, MS 39201
Chief, Energy and Transportation Branch
Environmental Compliance and Attorney General
Enforcement Division Asst. Attorney General
Mississippi Department of State of Mississippi
Environmental Quality P.O. Box 22947
P.O. Box 10385 Jackson, MS 39225-2947
Jackson, MS 39289-0385
State Health Officer
President State Health Board
Claiborne County P.O. Box 1700
Board of Supervisors Jackson, MS 39215
P.O. Box 339
Port Gibson, MS 39150 Associate General Counsel
Entergy Nuclear Operations
Senior Manager P.O. Box 31995
Nuclear Safety & Licensing Jackson, MS 39286-1995
Entergy Nuclear Operations
P.O. Box 31995 Richard Penrod, Senior Environmental
Jackson, MS 39286-1995 Scientist/State Liaison Officer
Office of Environmental Services
Manager, Licensing Northwestern State University
Entergy Operations, Inc. Russell Hall, Room 201
Grand Gulf Nuclear Station Natchitoches, LA 71497
P.O. Box 756
Port Gibson, MS 39150
Entergy Operations, Inc. -4-
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov )
DRP Director (Dwight.Chamberlain@nrc.gov )
DRP Deputy Director (Anton.Vegel@nrc.gov )
DRS Director (Roy.Caniano@nrc.gov )
DRS Deputy Director (Troy.Pruett@nrc.gov )
Senior Resident Inspector (Rich.Smith@nrc.gov )
Resident Inspector (Andy.Barrett@nrc.gov )
Branch Chief, DRP/C (Geoffrey.Miller@nrc.gov )
Senior Project Engineer, DRP/C (Wayne.Walker@nrc.gov
GG Site Secretary (Nancy.Spivey@nrc.gov )
Public Affairs Officer (Victor.Dricks@nrc.gov )
Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov )
RITS Coordinator (Marisa.Herrera@nrc.gov)
RC/ACES (Karla.Fuller@nrc.gov )
C. A. Carpenter, OE Cynthia.Carpenter@nrc.gov
OEMAIL.Resource@nrc.gov
Senior Enforcement Specialist (Mark.Haire@nrc.gov)
Only inspection reports to the following:
DRS STA (Dale.Powers@nrc.gov )
Mark Cox, OEDO RIV Coordinator (Mark.Cox@nrc.gov )
SUNSI Review Completed: _ __ ADAMS: Yes No Initials: _RAK_
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
R:\_REACTORS\GG\2009\GG2009-006RFI-RAK.doc ML
SRI:DRS/EB1 C:DRS/EB1
RAKopriva TFarnholtz
/RA/ /RA/
12/16/08 12/16/08
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INFORMATION REQUEST FOR GRAND GULF NUCLEAR STATION
COMPONENT DESIGN BASES INSPECTION (CDBI)
Inspection Report: 05000416/2009006
Information Gathering Dates: January 21-23, 2009
On-site Inspection Dates: February 2-6, 2009 and February 16-27, 2009
Inspection Procedure: IP 71111.21, Component Design Bases
Inspection
Lead Inspector/Team Leader: Ronald A. Kopriva
817-860-8104
Ron.Kopriva@nrc.gov
I. Information Requested Prior to the information Gathering Visit
The following information is requested by January 27, 2009, 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. Grand Gulf Nuclear Station 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- Enclosure
II. Information Requested to be Available on First Day of Inspection (February
2, 2009)
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- Enclosure
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 A. Kopriva
Senior Reactor Inspector
(817) 860-8104
Ron.Kopriva@nrc.gov
Mailing Address:
US NRC, Region IV
Attn: Ronald A. Kopriva
612 East Lamar Blvd., Ste 400
Arlington, TX 76011
-4- Enclosure