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{{#Wiki_filter:May 22, 2017  
{{#Wiki_filter:UNITED STATES
  Mr. Eric Larson, Site Vice President  
                            NUCLEAR REGULATORY COMMISSION
Entergy Operations, Inc.  
                                              REGION IV
Grand Gulf Nuclear Station  
                                          1600 E. LAMAR BLVD
P.O. Box 756  
                                      ARLINGTON, TX 76011-4511
Port Gibson, MS 39150  
                                          May 22, 2017
SUBJECT: GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC DESIGN BASES ASSURANCE INSPECTION (05000416/2017007)
Mr. Eric Larson, Site Vice President
AND INITIAL REQUEST FOR INFORMATION  
Entergy Operations, Inc.
Dear Mr. Larson:  
Grand Gulf Nuclear Station
P.O. Box 756
On August 22, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial  
Port Gibson, MS 39150
baseline Design Bases Assurance Inspection at the Grand Gulf Nuclear Station. A six-person  
SUBJECT: GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC DESIGN BASES
              ASSURANCE INSPECTION (05000416/2017007) AND INITIAL REQUEST FOR
              INFORMATION
Dear Mr. Larson:
On August 22, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial
baseline Design Bases Assurance Inspection at the Grand Gulf Nuclear Station. A six-person
team will perform this inspection using NRC Inspection Procedure 71111.21M, Design Bases
Assurance Inspection.
The inspection focuses on components, modifications, 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 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 two weeks of on-site inspection by the team. The inspection will consist of
four NRC inspectors and two contractors, of which five will focus on engineering and one on
operations. The current inspection schedule is as follows:
        On-site Information Gathering Visit: August 22-24, 2017
        Preparation Week: August 28-September 1, 2017
        On-site Weeks: September 11-15 and September 25-29, 2017.
The purpose of the information gathering visit is to meet with members of your staff and to
identify potential risk-significant components, modifications, 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 on-site weeks, several days of time will be
needed on the plant-referenced simulator in order to facilitate the development 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.


team will perform this inspection using NRC Inspection Procedure 71111.21M, "Design Bases Assurance Inspection."
E. Larson                                        2
The inspection focuses on components, modifications, and operator actions that have high risk and low design margins. The samples reviewed during this inspection will be identified during  
Our experience with these inspections has shown that they are extremely resource intensive,
an information gathering visit and the subsequent in-office preparation week. In addition, a
both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact
number of operating experience issues will also be selected for review.
on the site and to ensure a productive inspection, we have enclosed a request for information
The inspection will include an information gathering site visit by the team leader and a senior
needed for the inspection. The request has been divided into two groups. The first group lists
reactor analyst, and two weeks of on-site inspection by the team.  The inspection will consist of
information necessary for the information gathering visit and for general preparation. This
four NRC inspectors and two contractors, of which five
information should be available to the regional office no later than August 14, 2017. Insofar as
will focus on engineering and one on operations. The current inspection schedule is as follows:
possible, this information should be provided electronically to the lead inspector. Since the
On-site Information Gathering Visit:  August 22-24, 2017
inspection will be concentrated on high risk/low margin components and modifications,
Preparation Week:  August 28-September 1, 2017
calculations associated with your list of high risk components and modifications should be
On-site Weeks:  September 11-15 and September 25-29, 2017.  
available to review during the information gathering visit to assist in our selection of components
based on available design margin.
The purpose of the information gathering visit is to meet with members of your staff and to identify potential risk-significant components, modifications, and operator actions.  The lead inspector will also request a tour of the plant with members of your operations staff and  
The second group of documents requested lists information necessary to aid the inspection
probabilistic safety assessment staff. During the on-site weeks, several days of time will be  
team in tracking issues identified as a result of the inspection. It is requested that this
needed on the plant-referenced simulator in order to facilitate the development of operator
information be provided to the lead inspector as the information is generated during the
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.
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 on-site 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
on-site 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 Wayne Sifre. We understand that our licensing
engineer contact for this inspection is Mr. S. Du Pont. If there are any questions about the
inspection or the requested materials, please contact the lead inspector by telephone at
817-200-1193 or by e-mail at Wayne.Sifre@nrc.gov.
This letter does not contain new or amended information collection requirements subject to
the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, control
number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget control
number.
In accordance with 10 CFR 2.390 of the NRCs 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).


  UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD ARLINGTON, TX 76011-4511 
E. Larson                                3
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.
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the
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
Public Electronic Reading Room).
information should be available to the regional office no later than August 14, 2017. Insofar as
                                          Sincerely,
possible, this information should be provided electronically to the lead inspector.  Since the
                                          /RA/
inspection will be concentrated on high risk/low margin components and modifications,  
                                          Thomas R. Farnholtz, Chief
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.
                                          Engineering Branch 1
                                          Division of Reactor Safety
Docket No. 50-416
License No. NPF-29
Enclosure:
Design Bases Assurance
Inspection Request for Information


                                  Initial Request for Information
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
                              Design Bases Assurance Inspection
the specific components and modifications have been selected. Additional requests by
                                    Grand Gulf Nuclear Station
inspectors will also be made throughout the on-site 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 on-site portions of the inspection. In order to facilitate the inspection, we request that a contact
Inspection Report:                05000416/2017007
individual be assigned to each inspector to ensure information requests, questions, and
Information Gathering Dates:      August 22-24, 2017
concerns are addressed in a timely manner.  
Inspection Dates:                September 11-15 and September 25-29, 2017
Inspection Procedure:            IP 71111.21M, Design Bases Assurance Inspection
Lead Inspector:                  Wayne Sifre, Senior Reactor Inspector
I.    Information Requested Prior to Information Gathering Visit (August 22, 2017)
      The following information (Section I of this enclosure) should be sent to the Region IV
      office in hard copy or electronic format (Certrec IMS preferred), to the attention of
      Wayne Sifre by August 14, 2017, to facilitate the reduction in the items to be selected for
      a final list during the preparation week, August 28, 2017. The inspection team will
      finalize its sample selections during the prep week and will provide an additional
      information request with specific items by sample. This information shall be made
      available by the first day of the onsite portion of the inspection. 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/or only hard
      copy formats are available, please inform the inspector(s), 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 (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. A list of the top 50 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.
                                                                                          Enclosure


6. Any pre-existing evaluation or list of components and associated calculations
The lead inspector for this inspection is Wayne Sifre.  We understand that our licensing engineer contact for this inspection is Mr. S. Du Pont.
    with low design margins.
  If there are any questions about the inspection or the requested materials, please contact the lead inspector by telephone at
7. A list of high LERF impact events and associated components.
 
8. A list of high risk maintenance rule systems/components and functions; based on
817-200-1193 or by e-mail at
    engineering or expert panel judgment.
Wayne.Sifre@nrc.gov.  This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).  Existing information collection requirements were approved by the O
9. A list of operating experience evaluations for the last 3 years.
ffice of Management and Budget, control number 3150-0011.  The NRC may not conduct or sponsor, and a person is not required to
10. A list of all time-critical operator actions in procedures.
respond to, a request for information or an information collection requirement unless the
11. A list of permanent and temporary modifications performed in the past five years
requesting document displays a currently valid Office of Management and Budget control
    to SSCs sorted by component identified in Item 1.
 
12. Post-modification testing, including performance characteristics affected,
number.  In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be
    assumptions, and acceptance criteria associated with modifications provided in
made available electronically for
    item 11.
public inspection in the NRC Public Document Room or from  the Publicly Available Records (PARS) component of NRC's document system (ADAMS). 
13. Documents associated with modifications listed in item 11. Specifically,
 
    calculations, specifications, vendor manuals, UFSAR, Technical Specifications
E. Larson 3
    and Bases updates.
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
14. Updated procedures and training plans associated with the modifications listed in
  Sincerely,    /RA/      Thomas R. Farnholtz, Chief  Engineering Branch 1
    item 11.
Division of Reactor Safety
15. Updated maintenance and surveillance activities and procedures associated with
    modifications listed in item 11.
Docket No. 50-416 License No. NPF-29
16. A list of current operator work arounds/burdens.
17. A list of the design calculations, which provide the design margin information for
Enclosure: 
    components included in Item 1. (Calculations for selected components should be
 
    available during the information gathering visit).
Design Bases Assurance 
18. List of root cause evaluations associated with component failures or design
Inspection Request for Information 
    issues initiated/completed in the last 5 years.
  Enclosure
19. A copy of the current management and engineering organizational charts.
Initial Request for Information
20. A copy of the Grand Gulf Nuclear Station IPEEE, if available electronically.
Design Bases Assurance Inspection Grand Gulf Nuclear Station
21. A list of any common-cause failures of components in the last 3 years.
 
22. An electronic copy of the Design Bases Documents.
Inspection Report:  05000416/2017007
23. An electronic copy of the System Health notebooks.
 
24. A copy of any internal/external self-assessments and associated corrective
    action documents generated in preparation for this inspection.
Information Gathering Dates: August 22-24, 2017
                                        2
 
Inspection Dates: September 11-15 and September 25-29, 2017
Inspection Procedure: IP 71111.21M, "Design Bases Assurance Inspection"
 
Lead Inspector: Wayne Sifre, Senior Reactor Inspector
  I. Information Requested Prior to Information Gathering Visit (August 22, 2017)
  The following information (Section I of this enclosure) should be sent to the Region IV office in hard copy or electronic format (Certrec IMS preferred), to the attention of Wayne Sifre by August 14, 2017, to facilitate the reduction in the items to be selected for
a final list during the preparation week, August 28, 2017.  The inspection team will
finalize its sample selections during the prep week and will provide an additional
information request with specific items by sample.  This information shall be made
available by the first day of the onsite portion of the inspection.  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/or only hard copy formats are available, please inform the inspector(s), 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 (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. A list of the top 50 cut-sets from your PRA. 
3. Copies of PRA "system notebooks," and the latest PRA summary document.
4. An excel spreadsheet of PRA human action basic events or risk ranking of operator actions from your site specific PSA sorted by RAW and FV.  Provide
copies of your human reliability worksheets for these items. 
5. If you have an external events or fire PSA model, provide the information requested in items 1-4 for external events and fire.
 
  2 6. Any pre-existing evaluation or list of components and associated calculations  
with low design margins.  
7. A list of high LERF impact events and associated components.  
8. A list of high risk maintenance rule systems/components and functions; based on engineering or expert panel judgment.  
9. A list of operating experience evaluations for the last 3 years.
10. A list of all time-critical operator actions in procedures.  
11. A list of permanent and temporary modifications performed in the past five years to SSCs sorted by component identified in Item 1.
12. Post-modification testing, including performance characteristics affected, assumptions, and acceptance criteria associated with modifications provided in  
 
item 11.
13. Documents associated with modifications listed in item 11. Specifically, calculations, specifications, vendor m
anuals, UFSAR, Technical Specifications and Bases updates.  
14. Updated procedures and training plans associated with the modifications listed in  
item 11. 15. Updated maintenance and surveillance activities and procedures associated with modifications listed in item 11.  
16. A list of current "operator work arounds/burdens."
17. A list of the design calculations, which provide the design margin information for components included in Item 1. (Calculations for selected components should be  
available during the information gathering visit).
18. List of root cause evaluations associated with component failures or design issues initiated/completed in the last 5 years.
19. A copy of the current management and engineering organizational charts.
20. A copy of the Grand Gulf Nuclear Station IPEEE, if available electronically.  
21. A list of any common-cause failures of components in the last 3 years.  
22. An electronic copy of the Design Bases Documents.  
23. An electronic copy of the System Health notebooks.  
24. A copy of any internal/external self-assessments and associated corrective action documents generated in preparation for this inspection.  
 
  3 25. A copy of engineering/operations related audits completed in the last 2 years.
26. Structures, systems, and components in the Maintenance Rule (a)(1) category.
27. Site top 10 issues list, if available.
28. Procedures used to accomplish operator actions associated with the basic events in your PRA.
29. A list of licensee contacts for the inspection team with phone numbers.
30. Electronic copies of the Technical Specifications, Technical Specifications Bases, and the Updated Final Safety Analysis Report.
31. One-line drawings of ECCS, Ultimate Heat Sink, Emergency Feedwater,  Safety-Related Electrical Systems.
II. Information Requested to be provided throughout the inspection.
  1. Copies of any corrective action documents generated as a result of the team's questions or queries during this inspection.
2. Calculations and drawings associated with selected components.
3. 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:
Wayne Sifre    Chad Stott    Nnaerika Okonkwo
Senior Reactor Inspector  Reactor Inspector  Reactor Inspector
817-200-1193    817-200-1526  817-200-1114 
 
Wayne.Sifre@nrc.gov  Chad.Stott@nrc.gov
  Nnaerika.Okonkwo@nrc.gov
  Sean Hedger Emergency Preparedness Inspector 
 
817-200-1556


            25. A copy of engineering/operations related audits completed in the last 2 years.
            26. Structures, systems, and components in the Maintenance Rule (a)(1) category.
            27. Site top 10 issues list, if available.
            28. Procedures used to accomplish operator actions associated with the basic
                events in your PRA.
            29. A list of licensee contacts for the inspection team with phone numbers.
            30. Electronic copies of the Technical Specifications, Technical Specifications Bases,
                and the Updated Final Safety Analysis Report.
            31. One-line drawings of ECCS, Ultimate Heat Sink, Emergency Feedwater,
                Safety-Related Electrical Systems.
II.    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. Calculations and drawings associated with selected components.
        3. 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:
Wayne Sifre                              Chad Stott                  Nnaerika Okonkwo
Senior Reactor Inspector                Reactor Inspector            Reactor Inspector
817-200-1193                            817-200-1526                817-200-1114
Wayne.Sifre@nrc.gov                      Chad.Stott@nrc.gov          Nnaerika.Okonkwo@nrc.gov
Sean Hedger
Emergency Preparedness Inspector
817-200-1556
Sean.Hedger@nrc.gov
Sean.Hedger@nrc.gov
    Mailing Address:  
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4511
                                                    3


U.S. NRC, Region IV
Attn:  Wayne Sifre
1600 East Lamar Blvd. Arlington, TX  76011-4511 


  ML17142A258  SUNSI Review   ADAMS:   Non-Publicly Available  Non-Sensitive Keyword: By: TFarnholtz  Yes    No Publicly Available Sensitive NRC-002 OFFICE SRI:EB1 C:EB1     NAME WSifre TFarnholtz     SIGNATURE /RA/ /RA/     DATE 5/16/17 5/19/17
ML17142A258
  SUNSI Review           ADAMS:           Non-Publicly Available  Non-Sensitive Keyword:
  By: TFarnholtz         Yes No       Publicly Available     Sensitive     NRC-002
OFFICE           SRI:EB1       C:EB1
NAME             WSifre       TFarnholtz
SIGNATURE       /RA/         /RA/
DATE             5/16/17       5/19/17
}}
}}

Latest revision as of 03:57, 30 October 2019

Notification of NRC Design Bases Assurance Inspection (05000416/2017007) and Initial Request for Information
ML17142A258
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 05/19/2017
From: Thomas Farnholtz
Region 4 Engineering Branch 1
To: Emily Larson
Entergy Operations
References
IR 2017007
Download: ML17142A258 (7)
v • d • e


See also: IR 05000416/2017007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD

ARLINGTON, TX 76011-4511

May 22, 2017

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 (05000416/2017007) AND INITIAL REQUEST FOR

INFORMATION

Dear Mr. Larson:

On August 22, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial

baseline Design Bases Assurance Inspection at the Grand Gulf Nuclear Station. A six-person

team will perform this inspection using NRC Inspection Procedure 71111.21M, Design Bases

Assurance Inspection.

The inspection focuses on components, modifications, 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 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 two weeks of on-site inspection by the team. The inspection will consist of

four NRC inspectors and two contractors, of which five will focus on engineering and one on

operations. The current inspection schedule is as follows:

On-site Information Gathering Visit: August 22-24, 2017

Preparation Week: August 28-September 1, 2017

On-site Weeks: September 11-15 and September 25-29, 2017.

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

identify potential risk-significant components, modifications, 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 on-site weeks, several days of time will be

needed on the plant-referenced simulator in order to facilitate the development 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 August 14, 2017. 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 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 on-site 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

on-site 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 Wayne Sifre. We understand that our licensing

engineer contact for this inspection is Mr. S. Du Pont. If there are any questions about the

inspection or the requested materials, please contact the lead inspector by telephone at

817-200-1193 or by e-mail at Wayne.Sifre@nrc.gov.

This letter does not contain new or amended information collection requirements subject to

the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, control

number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to

respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control

number.

In accordance with 10 CFR 2.390 of the NRCs 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).

E. Larson 3

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 No. 50-416

License No. NPF-29

Enclosure:

Design Bases Assurance

Inspection Request for Information

Initial Request for Information

Design Bases Assurance Inspection

Grand Gulf Nuclear Station

Inspection Report: 05000416/2017007

Information Gathering Dates: August 22-24, 2017

Inspection Dates: September 11-15 and September 25-29, 2017

Inspection Procedure: IP 71111.21M, Design Bases Assurance Inspection

Lead Inspector: Wayne Sifre, Senior Reactor Inspector

I. Information Requested Prior to Information Gathering Visit (August 22, 2017)

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

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

Wayne Sifre by August 14, 2017, to facilitate the reduction in the items to be selected for

a final list during the preparation week, August 28, 2017. The inspection team will

finalize its sample selections during the prep week and will provide an additional

information request with specific items by sample. This information shall be made

available by the first day of the onsite portion of the inspection. 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/or only hard

copy formats are available, please inform the inspector(s), 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 (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. A list of the top 50 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.

Enclosure

6. Any pre-existing evaluation or list of components and associated calculations

with low design margins.

7. A list of high LERF impact events and associated components.

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

engineering or expert panel judgment.

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

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

11. A list of permanent and temporary modifications performed in the past five years

to SSCs sorted by component identified in Item 1.

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

assumptions, and acceptance criteria associated with modifications provided in

item 11.

13. Documents associated with modifications listed in item 11. Specifically,

calculations, specifications, vendor manuals, UFSAR, Technical Specifications

and Bases updates.

14. Updated procedures and training plans associated with the modifications listed in

item 11.

15. Updated maintenance and surveillance activities and procedures associated with

modifications listed in item 11.

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

17. A list of the design calculations, which provide the design margin information for

components included in Item 1. (Calculations for selected components should be

available during the information gathering visit).

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

issues initiated/completed in the last 5 years.

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

20. A copy of the Grand Gulf Nuclear Station IPEEE, if available electronically.

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

22. An electronic copy of the Design Bases Documents.

23. An electronic copy of the System Health notebooks.

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

action documents generated in preparation for this inspection.

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

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

27. Site top 10 issues list, if available.

28. Procedures used to accomplish operator actions associated with the basic

events in your PRA.

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

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

and the Updated Final Safety Analysis Report.

31. One-line drawings of ECCS, Ultimate Heat Sink, Emergency Feedwater,

Safety-Related Electrical Systems.

II. 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. Calculations and drawings associated with selected components.

3. 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:

Wayne Sifre Chad Stott Nnaerika Okonkwo

Senior Reactor Inspector Reactor Inspector Reactor Inspector

817-200-1193 817-200-1526 817-200-1114

Wayne.Sifre@nrc.gov Chad.Stott@nrc.gov Nnaerika.Okonkwo@nrc.gov

Sean Hedger

Emergency Preparedness Inspector

817-200-1556

Sean.Hedger@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Wayne Sifre

1600 East Lamar Blvd.

Arlington, TX 76011-4511

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ML17142A258

SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword:

By: TFarnholtz Yes No Publicly Available Sensitive NRC-002

OFFICE SRI:EB1 C:EB1

NAME WSifre TFarnholtz

SIGNATURE /RA/ /RA/

DATE 5/16/17 5/19/17

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