ML20199M235: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 14: Line 14:
| page count = 7
| page count = 7
}}
}}
See also: [[followed by::IR 05000416/2020012]]
See also: [[see also::IR 05000416/2020012]]


=Text=
=Text=
{{#Wiki_filter:July 17, 2020
{{#Wiki_filter:July 17, 2020  
Mr. Eric Larson, Site Vice President
Entergy Operations, Inc.
Grand Gulf Nuclear Station
Mr. Eric Larson, Site Vice President  
P.O. Box 756
Entergy Operations, Inc.  
Port Gibson, MS 39150
Grand Gulf Nuclear Station  
SUBJECT:         GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC DESIGN
P.O. Box 756  
                BASES ASSURANCE INSPECTION (TEAMS) (INSPECTION
Port Gibson, MS 39150  
                REPORT 05000416/2020012) AND INITIAL REQUEST FOR INFORMATION
Dear Mr. Larson:
SUBJECT:  
On September 8, 2020, the Nuclear Regulatory Commission (NRC) will begin a triennial
GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC DESIGN  
baseline component design bases inspection at the Grand Gulf Nuclear Station. A six-person
BASES ASSURANCE INSPECTION (TEAMS) (INSPECTION  
team will perform this inspection using NRC Inspection Procedure 71111, Attachment 21M,
REPORT 05000416/2020012) AND INITIAL REQUEST FOR INFORMATION  
Design Bases Assurance Inspection (Teams).
The inspection focuses on the maintenance of component design bases and modifications
Dear Mr. Larson:  
made to structures, systems, and components. The samples reviewed during this inspection
will be identified during an information gathering visit and during the subsequent in-office
On September 8, 2020, the Nuclear Regulatory Commission (NRC) will begin a triennial  
preparation week. In addition, a number of operating experience issues will also be selected for
baseline component design bases inspection at the Grand Gulf Nuclear Station. A six-person  
review.
team will perform this inspection using NRC Inspection Procedure 71111, Attachment 21M,  
The inspection will include an information gathering site visit by the team leader and two weeks
Design Bases Assurance Inspection (Teams).  
of onsite inspection by the team. The inspection will consist of five NRC inspectors,
one full- time contractor, and one part-time contractor (electrical support). The current
The inspection focuses on the maintenance of component design bases and modifications  
inspection schedule is as follows:
made to structures, systems, and components. The samples reviewed during this inspection  
        Remote Information Gathering Visit: September 8, 2020
will be identified during an information gathering visit and during the subsequent in-office  
        Preparation Week: September 14-18, 2020
preparation week. In addition, a number of operating experience issues will also be selected for  
        Onsite Weeks: September 21-25, and October 5-9, 2020
review.
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
The inspection will include an information gathering site visit by the team leader and two weeks  
a tour of the plant with members of your operations staff and probabilistic safety assessment
of onsite inspection by the team. The inspection will consist of five NRC inspectors,
staff. During the inspection, up to 16 hours will be needed on the plant-referenced simulator in
one full- time contractor, and one part-time contractor (electrical support). The current  
order to facilitate the development and inspection of operator action-based scenarios.
inspection schedule is as follows:  
Additional information and documentation needed to support the inspection will be identified
during the inspection, including interviews with engineering managers, engineers, and
Remote Information Gathering Visit: September 8, 2020  
probabilistic safety assessment staff.
Preparation Week: September 14-18, 2020  
Onsite Weeks: September 21-25, and October 5-9, 2020  
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. During the inspection, up to 16 hours will be needed on the plant-referenced simulator in  
order to facilitate the development and inspection of operator action-based scenarios.
Additional information and documentation needed to support the inspection will be identified  
during the inspection, including interviews with engineering managers, engineers, and  
probabilistic safety assessment staff.


E. Larson                                         2
Our experience with these inspections has shown that they are extremely resource intensive,
E. Larson  
both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact
2  
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 two 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 September 4, 2020, unless
Our experience with these inspections has shown that they are extremely resource intensive,  
otherwise stated. If possible, this information should be provided electronically to the lead
both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact  
inspector. Since the inspection will be concentrated on high risk/low margin components and
on the site and to ensure a productive inspection, we have enclosed a request for information  
modifications, calculations associated with your list of high risk components and modifications
needed for the inspection. The request has been divided into two groups. The first group lists  
should be available to review during the information gathering visit to assist in our selection of
information necessary for the information gathering visit and for general preparation. This  
components based on available design margin.
information should be available to the regional office no later than September 4, 2020, unless  
The second group of documents requested lists information necessary to aid the inspection
otherwise stated. If possible, this information should be provided electronically to the lead  
team in tracking issues identified as a result of the inspection. It is requested that this
inspector. Since the inspection will be concentrated on high risk/low margin components and  
information be provided to the lead inspector as the information is generated during the
modifications, calculations associated with your list of high risk components and modifications  
inspection. An additional request will be made by the team during the preparation week once
should be available to review during the information gathering visit to assist in our selection of  
the specific components and modifications have been selected. Additional requests by
components based on available design margin.
inspectors will also be made throughout the onsite weeks for specific documents needed to
complete the review. It is important that all of these documents are up-to date and complete in
The second group of documents requested lists information necessary to aid the inspection  
order to minimize the number of additional documents requested during the preparation and/or
team in tracking issues identified as a result of the inspection. It is requested that this  
onsite portions of the inspection. In order to facilitate the inspection, we request that a contact
information be provided to the lead inspector as the information is generated during the  
individual be assigned to each inspector to ensure information requests, questions, and
inspection. An additional request will be made by the team during the preparation week once  
concerns are addressed in a timely manner.
the specific components and modifications have been selected. Additional requests by  
The lead inspector for this inspection is Gerond A. George, Senior Reactor Inspector. If there
inspectors will also be made throughout the onsite weeks for specific documents needed to  
are any questions about the inspection or the requested materials, please contact the lead
complete the review. It is important that all of these documents are up-to date and complete in  
inspector by telephone at 817-200-1562 or by e-mail at Gerond.George@nrc.gov.
order to minimize the number of additional documents requested during the preparation and/or  
PAPERWORK REDUCTION ACT STATEMENT
onsite portions of the inspection. In order to facilitate the inspection, we request that a contact  
This letter contains mandatory information collections that are subject to the Paperwork
individual be assigned to each inspector to ensure information requests, questions, and  
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)
concerns are addressed in a timely manner.  
approved these information collections (approval number 3150-0011). Send comments
regarding this information collection to the Information Services Branch, Office of the Chief
The lead inspector for this inspection is Gerond A. George, Senior Reactor Inspector. If there  
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,
are any questions about the inspection or the requested materials, please contact the lead  
DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office
inspector by telephone at 817-200-1562 or by e-mail at Gerond.George@nrc.gov.
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and
Budget, Washington, DC 20503.
PAPERWORK REDUCTION ACT STATEMENT
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request
This letter contains mandatory information collections that are subject to the Paperwork  
for information or an information collection requirement unless the requesting document
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)  
displays a currently valid OMB control number.
approved these information collections (approval number 3150-0011). Send comments  
regarding this information collection to the Information Services Branch, Office of the Chief  
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,  
DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office  
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and  
Budget, Washington, DC 20503.  
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct nor 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 OMB control number.  


E. Larson                                         3
This letter, its enclosure, and your response (if any) will be made available for public inspection
E. Larson  
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
3  
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
                                                Sincerely,
                                                Vincent G.    Digitally signed by
This letter, its enclosure, and your response (if any) will be made available for public inspection  
                                                                Vincent G. Gaddy
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document  
                                                Gaddy          Date: 2020.07.17 13:49:10
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for  
                                                                -05'00'
Withholding.  
                                                Vincent G. Gaddy, Chief
                                                Engineering Branch 1
Sincerely,  
                                                Division of Reactor Safety
Docket No. 05000416
License No. NPF-29
Enclosure:
Design Bases Assurance Inspection
Vincent G. Gaddy, Chief  
(Teams) Request for Information
Engineering Branch 1  
cc w/ encl: Distribution via LISTSERV
Division of Reactor Safety  
Docket No. 05000416  
License No. NPF-29  
Enclosure:  
Design Bases Assurance Inspection
(Teams) Request for Information  
cc w/ encl: Distribution via LISTSERV  
Vincent G.
Gaddy
Digitally signed by
Vincent G. Gaddy
Date: 2020.07.17 13:49:10
-05'00'




ML20199M235
  ML20199M235  
  SUNSI Review:         ADAMS:           Non-Publicly Available  Non-Sensitive Keyword:
  SUNSI Review:  
  By: GAG               Yes  No        Publicly Available     Sensitive     NRC-002
ADAMS:  
OFFICE         SRI:EB1       C:EB1
Non-Publicly Available  
  NAME           GAGeorge     VGGaddy
  Non-Sensitive  
  SIGNATURE     /RA/         /RA/
Keyword:
  DATE           07/15/2020   07/17/2020
By: GAG  
                                     
Yes     No
                                  Initial Request for Information
  Publicly Available  
                          Design Bases Assurance Inspection (Teams)
Sensitive
                                    Grand Gulf Nuclear Station
NRC-002  
Inspection Report:                      05000416/2020012
OFFICE  
EPID ID:                                I-2020-012-0015
SRI:EB1  
Information Gathering Date:              September 8, 2020
C:EB1  
Inspection Dates:                        September 21-25, and October 5-9, 2020
   
Inspection Procedure:                    IP 71111, Attachment 21M, Design Bases Assurance
                                        Inspection (Teams)
Lead Inspector:                          Gerond A. George, Senior Reactor Inspector
I.    Information Requested Prior to Information Gathering Visit (September 4, 2020)
NAME  
      The following information (Section I of this enclosure) should be sent to the Region IV
GAGeorge  
      office in hard copy or electronic format (electronic database preferred), to the attention of
VGGaddy  
      Gerond A. George, Senior Reactor Inspector, by September 4, 2020, to facilitate the
   
      reduction in the items to be selected for a final list. The inspection team will finalize the
      selected list during the prep week using the additional documents requested in Section II
      of this enclosure. The specific items selected from the lists shall be available and ready
      for review on the day indicated in this request. *Please provide requested
SIGNATURE  
      documentation electronically in pdf files, Excel, or other searchable formats, if possible.
/RA/  
      The information should contain descriptive names and be indexed and hyperlinked to
/RA/  
      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. If
      requested documents are large and only hard copy formats are available, please inform
      the inspector and provide subject documentation during the first day of the onsite
      inspection.
DATE  
      1. An Excel spreadsheet of equipment basic events (with definitions), including
07/15/2020  
            importance measures sorted by risk achievement worth and Fussell-Vesely from
07/17/2020  
            your internal events probabilistic risk assessment. Include basic events with risk
            achievement worth value of 1.3 or greater.
      2. A list of the top 50 cut-sets from your PRA.
      3. Copies of probabilistic risk assessment system notebooks and the latest
            probabilistic risk assessment summary document.
      4. An Excel spreadsheet of probabilistic risk assessment human action basic events or
            risk ranking of operator actions from your site-specific PSA sorted by risk
            achievement worth and Fussell-Vesely. Provide copies of your human reliability
            worksheets for these items.
                                                                                  Enclosure


5. If you have an external events or fire PSA model, provide the information requested
    in items 1-4 for external events and fire.
6. A list of high large early release frequency impact events and associated
    components.
Enclosure
7. Structures, systems, and components in the Maintenance Rule (a)(1) category.
Initial Request for Information
8. A list of high risk maintenance rule systems/components and functions; based on
Design Bases Assurance Inspection (Teams)
    engineering or expert panel judgment.
Grand Gulf Nuclear Station
9. Site top 10 issues list, if available.
10. Any pre-existing list of components and associated calculations with low design
    margins.
Inspection Report: 
11. A list of operating experience evaluations for the last 3 years.
05000416/2020012
12. A list of all time-critical operator actions in procedures.
13. A list of current operator work arounds/burdens.
14. Procedures, including emergency and abnormal, used to accomplish operator
EPID ID:
    actions associated with the basic events credited in your PRA.
15. Lists of permanent and temporary modifications performed in the past 5 years to
    structures, systems, and components sorted by component identified in Item 1.
16. List of root cause evaluations associated with component failures or design issues
I-2020-012-0015
    initiated/completed in the last 5 years.
17. A list of any common-cause failures of components in the last 3 years.
Information Gathering Date: 
18. A copy of any internal/external self-assessments and associated corrective action
September 8, 2020
    documents generated in preparation for this inspection.
19. A copy of engineering/operations-related audits completed in the last 2 years.
Inspection Dates:
20. Electronic copies of the Technical Specifications, Technical Specifications Bases,
September 21-25, and October 5-9, 2020
    and the Final Safety Analysis Report, as updated.
21. A copy of the Individual Plant Examination of External Events, if available
Inspection Procedure:
    electronically.
IP 71111, Attachment 21M, Design Bases Assurance
22. One-line drawings of emergency core cooling system, ultimate heat sink, emergency
Inspection (Teams)  
    feedwater, safety-related electrical systems.
23. A copy of condition reports associated with inspection findings from the previous
Lead Inspector:
    NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).
24. A list of licensee contacts for the inspection team with phone numbers.
                                              2
Gerond A. George, Senior Reactor Inspector
I.  
Information Requested Prior to Information Gathering Visit (September 4, 2020)
The following information (Section I of this enclosure) should be sent to the Region IV
office in hard copy or electronic format (electronic database preferred), to the attention of  
Gerond A. George, Senior Reactor Inspector, by September 4, 2020, to facilitate the  
reduction in the items to be selected for a final list.  The inspection team will finalize the
selected list during the prep week using the additional documents requested in Section II
of this enclosure. The specific items selected from the lists shall be available and ready
for review on the day indicated in this request. *Please provide requested
documentation electronically in pdf files, Excel, or other searchable formats, if possible.
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. If
requested documents are large and only hard copy formats are available, please inform
the inspector and provide subject documentation during the first day of the onsite
inspection.  
1. An Excel spreadsheet of equipment basic events (with definitions), including
importance measures sorted by risk achievement worth and Fussell-Vesely from
your internal events probabilistic risk assessment.  Include basic events with risk
achievement worth value of 1.3 or greater.
2. A list of the top 50 cut-sets from your PRA. 
3. Copies of probabilistic risk assessment system notebooks and the latest
probabilistic risk assessment summary document.  
4. An Excel spreadsheet of probabilistic risk assessment human action basic events or
risk ranking of operator actions from your site-specific PSA sorted by risk
achievement worth and Fussell-Vesely. Provide copies of your human reliability
worksheets for these items.


        25. A copy of the current management and engineering organizational charts.
II.     Information Requested to be provided throughout the inspection.
        1. Electronic copies of the design bases documents for selected components and
2
            modifications.
        2. Electronic copies of the system health notebooks for selected components and
            modifications.
5. If you have an external events or fire PSA model, provide the information requested
        3. A list of the design calculations that provide the design margin information for
in items 1-4 for external events and fire.
            selected components. (Calculations for selected components should be available
            during the information gathering visit.)
6. A list of high large early release frequency impact events and associated
        4. Calculations and drawings associated with selected components.
components.
        5. Modification documentation associated with modifications selected from Item I.15,
            this includes:
7. Structures, systems, and components in the Maintenance Rule (a)(1) category.
                    a. Post-modification testing, including performance characteristics affected,
                        assumptions, and acceptance criteria associated with modifications
8. A list of high risk maintenance rule systems/components and functions; based on
                        selected.
engineering or expert panel judgment.
                    b. Updated maintenance and surveillance procedures associated with
                        modifications.
9. Site top 10 issues list, if available.
                    c. Updated operation procedures and training plans associated with the
                        modifications.
10. Any pre-existing list of components and associated calculations with low design
        6. Copies of any corrective action documents generated as a result of the teams
margins.
            questions or queries during this inspection.
        7. Copies of the list of questions submitted by the team members and the
11. A list of operating experience evaluations for the last 3 years. 
            status/resolution of the information requested (provide daily during the inspection to
            each team member).
12. A list of all time-critical operator actions in procedures.
Inspector Contact Information:
Gerond A. George
13. A list of current operator work arounds/burdens.
Senior Reactor Inspector
817-200-1562
14. Procedures, including emergency and abnormal, used to accomplish operator
Gerond.George@nrc.gov
actions associated with the basic events credited in your PRA.
Mailing Address:
U.S. NRC, Region IV
15. Lists of permanent and temporary modifications performed in the past 5 years to
ATTN: Gerond A. George
structures, systems, and components sorted by component identified in Item 1. 
1600 East Lamar Blvd.
16. List of root cause evaluations associated with component failures or design issues
initiated/completed in the last 5 years. 
17. A list of any common-cause failures of components in the last 3 years.
18. A copy of any internal/external self-assessments and associated corrective action
documents generated in preparation for this inspection.
19. A copy of engineering/operations-related audits completed in the last 2 years.
20. Electronic copies of the Technical Specifications, Technical Specifications Bases,
and the Final Safety Analysis Report, as updated.
21. A copy of the Individual Plant Examination of External Events, if available
electronically.
22. One-line drawings of emergency core cooling system, ultimate heat sink, emergency
feedwater, safety-related electrical systems.
23. A copy of condition reports associated with inspection findings from the previous
NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).
24. A list of licensee contacts for the inspection team with phone numbers.
 
3
25. A copy of the current management and engineering organizational charts.
II.  
Information Requested to be provided throughout the inspection.  
1. Electronic copies of the design bases documents for selected components and  
modifications.
2. Electronic copies of the system health notebooks for selected components and  
modifications.
3. A list of the design calculations that provide the design margin information for  
selected components. (Calculations for selected components should be available  
during the information gathering visit.)  
4. Calculations and drawings associated with selected components.  
5. Modification documentation associated with modifications selected from Item I.15,  
this includes:  
a. Post-modification testing, including performance characteristics affected,  
assumptions, and acceptance criteria associated with modifications  
selected.  
b. Updated maintenance and surveillance procedures associated with  
modifications.  
c. Updated operation procedures and training plans associated with the  
modifications.  
6. Copies of any corrective action documents generated as a result of the teams  
questions or queries during this inspection.  
7. 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).  
Inspector Contact Information:  
Gerond A. George  
Senior Reactor Inspector  
817-200-1562  
Gerond.George@nrc.gov  
Mailing Address:  
U.S. NRC, Region IV  
ATTN: Gerond A. George  
1600 East Lamar Blvd.  
Arlington, TX 76011-4511
Arlington, TX 76011-4511
                                                  3
}}
}}

Latest revision as of 02:30, 24 May 2025

Notification of NRC Design Bases Assurance Inspection (Teams) (Inspection Report 05000416/2020012) and Initial Request for Information
ML20199M235
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/17/2020
From: Vincent Gaddy
Region 4 Engineering Branch 1
To: Emily Larson
Entergy Operations
References
IR 2020012
Download: ML20199M235 (7)
v • d • e


See also: IR 05000416/2020012

Text

July 17, 2020

Mr. Eric Larson, Site Vice President

Entergy Operations, Inc.

Grand Gulf Nuclear Station

P.O. Box 756

Port Gibson, MS 39150

SUBJECT:

GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC DESIGN

BASES ASSURANCE INSPECTION (TEAMS) (INSPECTION

REPORT 05000416/2020012) AND INITIAL REQUEST FOR INFORMATION

Dear Mr. Larson:

On September 8, 2020, the Nuclear Regulatory Commission (NRC) will begin a triennial

baseline component design bases inspection at the Grand Gulf Nuclear Station. A six-person

team will perform this inspection using NRC Inspection Procedure 71111, Attachment 21M,

Design Bases Assurance Inspection (Teams).

The inspection focuses on the maintenance of component design bases and modifications

made to structures, systems, and components. 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 two weeks

of onsite inspection by the team. The inspection will consist of five NRC inspectors,

one full- time contractor, and one part-time contractor (electrical support). The current

inspection schedule is as follows:

Remote Information Gathering Visit: September 8, 2020

Preparation Week: September 14-18, 2020

Onsite Weeks: September 21-25, and October 5-9, 2020

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. During the inspection, up to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> will be needed on the plant-referenced simulator in

order to facilitate the development and inspection of operator action-based scenarios.

Additional information and documentation needed to support the inspection will be identified

during the inspection, including interviews with engineering managers, engineers, and

probabilistic safety assessment staff.

E. Larson

2

Our experience with these inspections has shown that 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 two 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 September 4, 2020, unless

otherwise stated. If possible, this information should be provided electronically to the lead

inspector. Since the inspection will be concentrated on high risk/low margin components and

modifications, calculations associated with your list of high risk components and modifications

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 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. An additional request will be made by the team during the preparation week once

the specific components and modifications have been selected. Additional requests by

inspectors will also be made throughout the onsite weeks for specific documents needed to

complete the review. 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

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 Gerond A. George, Senior Reactor Inspector. If there

are any questions about the inspection or the requested materials, please contact the lead

inspector by telephone at 817-200-1562 or by e-mail at Gerond.George@nrc.gov.

PAPERWORK REDUCTION ACT STATEMENT

This letter contains mandatory information collections that are subject to the Paperwork

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)

approved these information collections (approval number 3150-0011). Send comments

regarding this information collection to the Information Services Branch, Office of the Chief

Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,

DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office

of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and

Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION

The NRC may not conduct nor 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 OMB control number.

E. Larson

3

This letter, its enclosure, and your response (if any) will be made available for public inspection

and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document

Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for

Withholding.

Sincerely,

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 05000416

License No. NPF-29

Enclosure:

Design Bases Assurance Inspection

(Teams) Request for Information

cc w/ encl: Distribution via LISTSERV

Vincent G.

Gaddy

Digitally signed by

Vincent G. Gaddy

Date: 2020.07.17 13:49:10

-05'00'

ML20199M235

SUNSI Review:

ADAMS:

Non-Publicly Available

Non-Sensitive

Keyword:

By: GAG

Yes No

Publicly Available

Sensitive

NRC-002

OFFICE

SRI:EB1

C:EB1

NAME

GAGeorge

VGGaddy

SIGNATURE

/RA/

/RA/

DATE

07/15/2020

07/17/2020

Enclosure

Initial Request for Information

Design Bases Assurance Inspection (Teams)

Grand Gulf Nuclear Station

Inspection Report: 05000416/2020012

EPID ID:

I-2020-012-0015

Information Gathering Date:

September 8, 2020

Inspection Dates:

September 21-25, and October 5-9, 2020

Inspection Procedure:

IP 71111, Attachment 21M, Design Bases Assurance

Inspection (Teams)

Lead Inspector:

Gerond A. George, Senior Reactor Inspector

I.

Information Requested Prior to Information Gathering Visit (September 4, 2020)

The following information (Section I of this enclosure) should be sent to the Region IV

office in hard copy or electronic format (electronic database preferred), to the attention of

Gerond A. George, Senior Reactor Inspector, by September 4, 2020, to facilitate the

reduction in the items to be selected for a final list. The inspection team will finalize the

selected list during the prep week using the additional documents requested in Section II

of this enclosure. The specific items selected from the lists shall be available and ready

for review on the day indicated in this request. *Please provide requested

documentation electronically in pdf files, Excel, or other searchable formats, if possible.

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. If

requested documents are large and only hard copy formats are available, please inform

the inspector and provide subject documentation during the first day of the onsite

inspection.

1. An Excel spreadsheet of equipment basic events (with definitions), including

importance measures sorted by risk achievement worth and Fussell-Vesely from

your internal events probabilistic risk assessment. Include basic events with risk

achievement worth value of 1.3 or greater.

2. A list of the top 50 cut-sets from your PRA.

3. Copies of probabilistic risk assessment system notebooks and the latest

probabilistic risk assessment summary document.

4. An Excel spreadsheet of probabilistic risk assessment human action basic events or

risk ranking of operator actions from your site-specific PSA sorted by risk

achievement worth and Fussell-Vesely. Provide copies of your human reliability

worksheets for these items.

2

5. If you have an external events or fire PSA model, provide the information requested

in items 1-4 for external events and fire.

6. A list of high large early release frequency impact events and associated

components.

7. Structures, systems, and components in the Maintenance Rule (a)(1) category.

8. A list of high risk maintenance rule systems/components and functions; based on

engineering or expert panel judgment.

9. Site top 10 issues list, if available.

10. Any pre-existing list of components and associated calculations with low design

margins.

11. A list of operating experience evaluations for the last 3 years.

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

13. A list of current operator work arounds/burdens.

14. Procedures, including emergency and abnormal, used to accomplish operator

actions associated with the basic events credited in your PRA.

15. Lists of permanent and temporary modifications performed in the past 5 years to

structures, systems, and components sorted by component identified in Item 1.

16. List of root cause evaluations associated with component failures or design issues

initiated/completed in the last 5 years.

17. A list of any common-cause failures of components in the last 3 years.

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

documents generated in preparation for this inspection.

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

20. Electronic copies of the Technical Specifications, Technical Specifications Bases,

and the Final Safety Analysis Report, as updated.

21. A copy of the Individual Plant Examination of External Events, if available

electronically.

22. One-line drawings of emergency core cooling system, ultimate heat sink, emergency

feedwater, safety-related electrical systems.

23. A copy of condition reports associated with inspection findings from the previous

NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).

24. A list of licensee contacts for the inspection team with phone numbers.

3

25. A copy of the current management and engineering organizational charts.

II.

Information Requested to be provided throughout the inspection.

1. Electronic copies of the design bases documents for selected components and

modifications.

2. Electronic copies of the system health notebooks for selected components and

modifications.

3. A list of the design calculations that provide the design margin information for

selected components. (Calculations for selected components should be available

during the information gathering visit.)

4. Calculations and drawings associated with selected components.

5. Modification documentation associated with modifications selected from Item I.15,

this includes:

a. Post-modification testing, including performance characteristics affected,

assumptions, and acceptance criteria associated with modifications

selected.

b. Updated maintenance and surveillance procedures associated with

modifications.

c. Updated operation procedures and training plans associated with the

modifications.

6. Copies of any corrective action documents generated as a result of the teams

questions or queries during this inspection.

7. 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).

Inspector Contact Information:

Gerond A. George

Senior Reactor Inspector

817-200-1562

Gerond.George@nrc.gov

Mailing Address:

U.S. NRC, Region IV

ATTN: Gerond A. George

1600 East Lamar Blvd.

Arlington, TX 76011-4511

Retrieved from "https://kanterella.com/w/index.php?title=ML20199M235&oldid=5487814"