ML21077A016
| ML21077A016 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/22/2021 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Dinelli J |
| References | |
| IR 2021010 | |
| Download: ML21077A016 (7) | |
See also: IR 05000313/2021010
Text
March 22, 2021
Mr. John Dinelli, Site Vice President
Arkansas Nuclear One
Entergy Operations, Inc.
N-TSB-58
1448 S.R. 333
Russellville, AR 72802-0967
SUBJECT:
ARKANSAS NUCLEAR ONE - NOTIFICATION OF NRC DESIGN BASES
ASSURANCE INSPECTION (TEAM) (05000313/2021010 AND
05000368/2021010) AND INITIAL REQUEST FOR INFORMATION
Dear Mr. Dinelli:
On May 17, 2021, U.S. Nuclear Regulatory Commission (NRC) staff will begin a triennial
baseline Design Bases Assurance Inspection at Arkansas Nuclear One. A team of five
inspectors will perform this inspection using NRC Inspection Procedure 71111.21M, Design
Bases Assurance Inspection (Team).
This inspection of component design bases and modifications made to structures, systems, and
components (SSCs) verifies that plant components are maintained within their design basis.
This inspection also provides monitoring of the capability of the selected components and
operator actions to perform their design bases functions. Additionally, this inspection verifies
that risk significant issues resulting from generic communications have been adequately
addressed.
This inspection requires a review of 8-12 risk informed samples and 1-3 operating experience
samples. Risk informed samples will consist of 4-6 components and 4-6 modifications. The
samples reviewed during this inspection will be identified during an information gathering visit
and/or during the subsequent in-office preparation week.
The inspection will include an information gathering site visit by the lead inspector and two
weeks of onsite inspection by the entire team. The current inspection schedule is as follows:
Onsite Information Gathering Visit: May 17-20, 2021
Inspection Preparation Weeks: June 1-4 and June 21-25, 2021
Onsite Inspection Weeks: June 14-18 and June 28 - July 2, 2021
Our experience with these inspections has shown that they are extremely resource intensive,
both for the NRC inspectors and the licensee staff. To minimize the inspection impact on the
site and to ensure an efficient inspection, we have enclosed an initial request for information
needed for the inspection. The request has been divided into three groups. Generally, the first
group lists information necessary for the information gathering visit and for overall preparation;
the second group of information lists information necessary for sample-specific inspection
J. Dinelli
2
preparation; and the third group lists information necessary throughout the remainder of the
inspection. This information should be provided electronically by the dates listed in the
enclosure (and should also be sorted in a consistent manner). If this is not possible, please
inform the lead inspector as soon as practicable. Additionally, it is important that this
information is 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. Finally, we request
that a contact individual be assigned to each inspector to ensure information requests,
questions, and concerns are addressed in a timely manner.
As stated, the first group of information is intended to aid the lead inspector during the
information gathering visit to identify potential risk-significant SSCs, operator actions, operating
experience, and modification samples. 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/or documentation needed to support the inspection may be identified during the
visit, including interviews with engineering managers, engineers, and probabilistic safety
assessment staff. Between the information gathering visit and the initial preparation, the lead
inspector will choose the inspection samples and communicate them to your staff. Please note
that the team may make changes to the sample selections during the preparation week.
Similarly, the second group of information is intended to provide sample-specific information to
the inspection team. Please note that the inspection team may identify additional information
and/or documentation needed to support the inspection during the initial preparation week. This
information will be communicated by the lead inspector as soon as practicable. This information
may include requests for plant tours, interviews with staff, etc. during the onsite portions of the
inspection.
Finally, the third 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. Please also note that additional requests by inspectors will also be made throughout
the onsite weeks for specific documents needed to complete the review, which may also include
additional plant tours, interviews with staff, etc.
The lead inspector for this inspection is Wayne Sifre. We understand that our licensing
engineer contact for this inspection is Ms. Natalie Mosher. 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.
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.
J. Dinelli
3
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.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390 of the NRC's
"Rules of Practice and Procedure," 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
component of NRCs document system Agencywide Documents Access and Management
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,
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-313 and 50-368
Enclosure: Design Bases Assurance
Inspection (Team) Initial Request for Information
cc: Electronic Distribution via LISTSERV
Vincent G.
Gaddy
Digitally signed by Vincent G.
Gaddy
Date: 2021.03.22 09:20:36
-05'00'
SUNSI Review:
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: WCS
Yes No
Publicly Available
Sensitive
OFFICE
SRI:EB1
C:EB1
NAME
WSifre
VGaddy
SIGNATURE
/RA/
/RA/
DATE
3/22/2021
3/22/2021
Enclosure
Initial Request for Information
Design Bases Assurance Inspection (Team)
Arkansas Nuclear One
Inspection Report: 05000313/2021010 and 05000368/2021010
EPID ID:
I-2021-010-0021
Information Gathering Dates:
May 17-20, 2021
Inspection Dates:
June 14-18 and June 28 - July 2, 2021
Inspection Procedure:
IP 71111.21M, Design Bases Assurance Inspection
(Team)
Lead Inspector:
Wayne Sifre, Senior Reactor Inspector
I.
Information Requested for the Information Gathering Visit (May 17, 2021)
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.
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, if available, of low design margin components.
7. A list of high large early release frequency impact events and associated components.
8. Structures, systems, and components in the Maintenance Rule (a)(1) category.
9. A list of high-risk maintenance rule systems/components and functions; based on
engineering or expert panel judgment.
10. Site top 10 issues list, if available.
2
11. Any pre-existing list of components and associated calculations with low design
margins.
12. A list of operating experience evaluations for the last 3 years.
13. A list of all time-critical or time-sensitive operator actions in procedures.
14. A list of current operator work arounds/burdens.
15. Procedures, including emergency and abnormal, used to accomplish operator
actions associated with the basic events credited in your PRA.
16. Lists of permanent and temporary modifications performed in the past 5 years to
structures, systems, and components sorted by component identified in Item 1.
17. List of root cause evaluations associated with component failures or design issues
initiated/completed in the last 5 years.
18. A list of any common-cause failures of components in the last 3 years.
19. A copy of any internal/external self-assessments and associated corrective action
documents generated in preparation for this inspection.
20. A copy of engineering/operations-related audits completed in the last 2 years.
21. Electronic copies of the Technical Specifications, Technical Specifications Bases,
and the Final Safety Analysis Report, as updated.
22. A copy of the Individual Plant Examination of External Events, if available
electronically.
23. One-line drawings of emergency core cooling system, ultimate heat sink, emergency
feedwater, safety-related electrical systems.
24. A copy of condition reports associated with inspection findings from the previous
NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).
25. A list of licensee contacts for the inspection team with phone numbers.
26. A copy of the current management and engineering organizational charts.
II.
Information Requested for the Inspection Preparation Week (June 1, 2021)
1. Electronic copies of the design bases documents (or system descriptions) for selected
components and modifications.
2. Electronic copies of the system health notebooks for selected components and
modifications.
3. A list of relevant design calculations.
3
4. Calculations and drawings associated with selected components.
5. Modification documentation associated with modifications selected. 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.
III.
Information Requested Throughout Inspection (June 14, 2021)
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).
Inspector Contact Information:
Senior Reactor Inspector
817-200-1193
wayne.sifre@nrc.gov
Senior Reactor Inspector
817-200-1558
james.drake@nrc.gov
Senior Resident Inspector
817-200-1957
Timothy.steadham@nrc.gov
Reactor Inspector
817-200-1114
nnaerika.okonkwo@nrc.gov
Reactor Inspector
817-200-1534
dustin.reinert@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4511