ML20054C426
| ML20054C426 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/20/2020 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Vazquez S Entergy Operations |
| Gaddy V | |
| References | |
| IR 2020012 | |
| Download: ML20054C426 (7) | |
See also: IR 05000382/2020012
Text
February 20, 2020
Mr. Sergio Vazquez
Site Vice President
Entergy Operations, Inc.
17265 River Road
Killona, LA 70057
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION
OF NRC DESIGN BASES ASSURANCE INSPECTION (TEAMS)
(05000382/2020012) AND INITIAL REQUEST FOR INFORMATION
Dear Mr. Vazquez:
On May 4, 2020, the Nuclear Regulatory Commission (NRC) will begin a triennial baseline
component design bases inspection at the Waterford Steam Electric Station, Unit 3. 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. In addition, a number of operating
experience issues will also be selected for review during the in-office preparation week.
The inspection will include an information gathering site visit by the team leader and 2 weeks of
onsite inspection by the team. The inspection will consist of three NRC inspectors and two NRC
contractors, who will focus on engineering, and one NRC inspector who will focus on
operations. The current inspection schedule is as follows:
Onsite Information Gathering Visit: April 13-17, 2020
Preparation Week: April 27 - May 1, 2020
Onsite Weeks: May 4-8 and May 18-22, 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 onsite weeks, several days will be needed on the plant-referenced simulator in
S. Vazquez
2
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.
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 April 1, 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 document requests 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 Mr. Ronald Kopriva, senior reactor inspector. We
understand that our licensing engineer contact for this inspection is Mr. Remy DeVoe. If there
are any questions about the inspection or the requested materials, please contact the lead
inspector by telephone at 817-200-1104 or by e-mail at Ron.Kopriva@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.
S. Vazquez
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,
/RA/
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 05000382
License No. NPF-38
Enclosure:
Initial Request for Information
Design Bases Assurance Inspection (Teams)
SUNSI Review:
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: RAK
Yes No
Publicly Available
Sensitive
OFFICE
SRI:EB1
C:EB1
NAME
RKopriva
VGaddy
SIGNATURE
/RA/
/RA/
DATE
02/20/2020
02/20/2020
Enclosure
Initial Request for Information
Design Bases Assurance Inspection (Teams)
Waterford Steam Electric Station, Unit 3
Inspection Report: 05000382/2020012
EPID ID:
I-2020-012-0004
Information Gathering Date:
April 13-17, 2020
Inspection Dates:
May 4-8 and May 18-22, 2020
Inspection Procedure:
IP 71111, Attachment 21M, Design Bases Assurance
Inspection (Teams)
Lead Inspector:
Ronald A. Kopriva, Senior Reactor Inspector
I.
Information Requested Prior to Information Gathering Visit (April 13, 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
Ronald A. Kopriva, senior reactor inspector, by April 1, 2020. 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
pressurized 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 Birnbaum 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 Birnbaum. 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. Lists of permanent and temporary modifications performed in the past 5 years to
structures, systems, and components sorted by component identified in Item 1.
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. A copy of the Top Ten Issues list, if available.
11. Any pre-existing list of components and associated calculations with low design
margins.
12. A List of root cause evaluations associated with component failures or design issues
initiated/completed in the last 5 years.
13. A list of any common-cause failures of components in the last 3 years.
14. A list of operating experience evaluations for the last 3 years.
15. A list of all time-critical operator actions in procedures.
16. A list of current operator work arounds/burdens.
17. Procedures, including emergency and abnormal, used to accomplish operator
actions associated with the basic events credited in your PRA.
18. Electronic copies of quality assurance program manual, corrective action program,
and engineering design change procedures.
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,
Technical Requirements Manual, 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 systems, ultimate heat sink,
emergency safety features, and safety-related electrical systems.
24. A copy of plant systems equipment identifier key or procedure.
3
25. A copy of condition reports associated with inspection findings from the previous
NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).
26. A list of licensee contacts for the inspection team with phone numbers.
27. 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. Documentation associated with modifications selected from Item I.6, 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, emergency, and abnormal procedures associated with
the modifications.
d. 10 CFR 50.59 applicability determination, screening, and safety evaluation.
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:
Ronald A. Kopriva
Senior Reactor Inspector
817-200-1104
Ron.Kopriva@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Ronald A. Kopriva
1600 East Lamar Blvd.
Arlington, TX 76011-4511