ML22187A036
| ML22187A036 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/11/2022 |
| From: | Vincent Gaddy NRC/RGN-IV/DORS/EB1 |
| To: | Ferrick J Entergy Operations |
| References | |
| IR 2022013 | |
| Download: ML22187A036 (9) | |
See also: IR 05000382/2022013
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION IV
1600 E. LAMAR BLVD.
ARLINGTON, TX 76011-4511
July 11, 2022
Mr. John Ferrick, 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 (PROGRAMS) (05000382/2022013)
AND REQUEST FOR INFORMATION
Dear Mr. Ferrick:
On September 19, 2022, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Waterford Steam Electric Plant Station, Unit 3. A three-person team will
perform this inspection using NRC Inspection Procedure 71111, Attachment 21N.02,
Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements,
dated October 9, 2020.
This inspection will evaluate the reliability, functional capability, and design basis of
risk-significant power-operated valves as required by 10 CFR 50.55a and applicable
10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Waterford
Steam Electric Plant Station, Unit 3 operating license. Additionally, the team will perform an
inspection of the documentation files to verify that the plant activities associated with safety-
related motor-operated valves meet your commitments to Generic Letter (GL) 89-10,
Safety-Related Motor-Operated Valve Testing and Surveillance, and GL 96-05, "Periodic
Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." In
conducting this inspection, the team will select power-operated valves used to prevent and
mitigate the consequences of a design basis accident.
The inspection will include an information gathering site visit by the team leader and two weeks
of onsite inspection by the team. The inspection team will consist of three NRC inspectors. The
current inspection schedule is as follows:
Onsite Information Gathering Visit: August 8, 2022
Preparation Week: September 12, 2022
Onsite Weeks: September 19, 2022, and October 3, 2022
J. Ferrick
- 2 -
The purpose of the information gathering visit is to meet with members of your staff to become
familiar with the power-operated valve activities at Waterford Steam Electric Plant Station, Unit
3. The lead inspector will request a meeting with your personnel to discuss the site
power-operated valve procedures. Additionally, the lead inspector will request a discussion with
your staff to become familiar with the regulations and standards applicable to power-operated
valves at the site. Additional information and documentation needed to support the inspection
will be identified during the inspection, including interviews with engineering managers and
engineers.
To minimize the inspection impact on the site and to ensure a productive inspection, we have
enclosed a request for information needed prior to the inspection. This information should be
made available to the lead inspector during the August 8, 2022, visit. Since the inspection will
be concentrated on safety-related and risk-significant power-operated valves, a list of such
power-operated valves should be available to review during and following the information
gathering visit to assist in our selection of appropriate power-operated valves to review.
Additional requests by inspectors will be made during the onsite weeks for specific documents
needed to complete the review of specific power-operated valves and associated activities. It is
important that all documentation is up-to-date and complete in order to minimize the number of
additional documents requested during the preparation and/or the onsite portions of the
inspection. In order to facilitate the inspection, we request that a contact individual be assigned
to each inspector to ensure information requests, questions, and concerns are addressed in a
timely manner.
The lead inspector for this inspection is Mr. Wes Cullum. We understand that our licensing
contact for this inspection is Mr. Jeff Bradley. If there are any questions about the inspection or
the requested materials, please contact the lead inspector by telephone at 817-200-1563 or by
e-mail at Wes.Cullum@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.
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 Title 10 of the Code of Federal Regulations 2.390, Public
Inspections, Exemptions, Requests for Withholding.
J. Ferrick
- 3 -
Sincerely,
Vincent Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No:05000382
License No: NPF-38
Enclosures:
Request for Information and
Valves of Interest
cc w/ encl: Distribution via LISTSERV
Signed by Gaddy, Vincent
on 07/11/22
SUNSI Review
ADAMS:
Non-Publicly Available Non-Sensitive Keyword:
By: WLC1
Yes No
Publicly Available
Sensitive
OFFICE
DORS/EB1
DORS/EB1
NAME
WCullum
VGaddy
SIGNATURE
RA
DATE
7/10/22
7/11/22
- 1 -
Enclosure
Request for Information
Design-Basis Capability of Power-Operated Valves
WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3
Inspection Report: 05000382/2022013
EPID Number:
I-2022-013-0002
Information Gathering Dates:
August 8, 2022
Onsite Inspection Dates:
September 19, 2022, and October 3, 2022
Inspection Procedure:
IP 71111, Attachment 21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a
Requirements
Lead Inspector:
Wes L. Cullum, Reactor Inspector
I.
Information Requested for Information Gathering Visit (August 8, 2022)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of the lead inspector by August 8, 2022, to facilitate the
reduction in the items to be selected for a final list of components. The inspection team
will finalize the selected list during the prep week using the documents requested in 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 pressurized water reactor
technology. If requested documents are large and only hard copy formats are available,
please inform the inspectors, and provide subject documentation during the first day of
the onsite inspection.
1.
Provide the valve characteristics for the valves listed in the attached list as described
in Appendix C of NRC Inspection Procedure 71111, Attachment 21N.02, Design
Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.
2.
List of power-operated valves (POVs) important to safety for the Waterford Steam
Electric Plant Station, Unit 3. The list should include (a) component identification
number; (b) applicable plant system; (c) ASME Boiler and Pressure Vessel Code
(BPV Code) Class; (d) safety-related or nonsafety-related classification; (e) valve
type, size and manufacturer; and (f) actuator type, size, and manufacturer. If the
NRC has granted a license amendment to categorize structures, systems, and
component in accordance with 10 CFR 50.69, please provide the risk-informed
safety category of the structure, system, or component.
3.
List of POVs sorted by risk importance, including internal and external risk
considerations.
- 2 -
Enclosure
4.
Word-searchable updated final safety analysis report (UFSAR), license conditions,
technical specifications, and most recent inservice testing (IST) program plan (and
bases document), including any standards that have been committed to with respect
to POV capability and testing. Also, identify which UFSAR sections address
environmental, seismic, and functional qualification of POVs.
5.
Provide copies of the latest POV program level procedures or manuals.
6.
NRC Safety Evaluation Report(s) associated with the IST program including relief
and alternative requests submitted in accordance with 10 CFR 50.55a for POVs.
7.
Provide any responses to NRC Generic Letter (GL) 89-10, Safety-Related Motor-
Operated Valve Testing and Surveillance, (and its supplements) and GL 96-05,
Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated
Valves.
8.
Provide the most recently completed audit, self-assessment, or benchmark of POV
programs at Waterford Steam Electric Plant Station, Unit 3.
9.
List of systems, system numbers/designators, and corresponding names.
10. List of site contacts that will be associated with the inspection.
II.
Discussions Requested During the Information Gathering Visit
1.
Interview with a representative to discuss site POV capability analyses, including
plant drawings and assumptions. This includes analysis for accident conditions.
2.
Interview with a representative to discuss POV maintenance elements as integrated
into plant programs and procedures.
3.
Interview with a representative to discuss maintaining the design-basis capability of
POVs if they have entered a period of extended operation, if applicable.
III.
Information Requested for Inspection Preparation (September 12, 2022) *
1.
Calculations and/or evaluations associated with the selected POVs, as applicable.
For example, these may include those related to motor-operated valve (MOV) torque
switch setpoint, MOV terminal (degraded) voltage, maximum expected differential
and pressure, torque switch bypass settings, rate of loading, environmental and
process conditions during normal/accident operation, seismic and weak-link analysis,
and pressure locking and thermal binding, etc. (Ten specific valves will be identified
and communicated to you prior to August 22, 2022.)
2.
Environmental qualification files associated with the selected POVs, as applicable.
3.
Vendor manuals and technical sheets associated with the selected POVs.
- 3 -
Enclosure
4.
Provide results (i.e., completed work orders) from the last three performances of
diagnostic (static and/or dynamic) testing and inservice testing (stroke time, leak
rate, etc.) of the selected POVs.
5.
Provide performance (or failure) trending data for the selected POVs.
6.
List of modifications related to the selected POVs.
7.
List of corrective action program documents, with a brief description, related to the
selected POVs over the past five years.
8.
List of preventive maintenance activities for the selected POVs (valve and actuator).
Include the identification number, title and/or description, and frequency.
9.
System training manuals and/or design basis documents associated with the
selected POVs.
10. Piping and instrument diagrams for systems related to the selected POVs.
11. Tours of the rooms in which the selected POVs are installed. If the inspection will be
performed remotely, multiple pictures of selected valve and valve location can be
provided. The pictures must have an orientation reference, a size reference, pictures
of the surrounding environment, and pictures of the nameplates of both valve and
valve operator.
IV.
Discussions Requested During the First Inspection Week (September 19, 2022)
1.
Brief presentation of POV programs at Waterford Steam Electric Plant Station, Unit
3.
2.
Interviews with representatives to discuss the design-basis capability of POVs based
upon the teams review of gathered information.
- Please sort the Section III responses by each selected POV.
Inspector Contact Information:
Reactor Inspector
817-200-1563
Wes.Cullum@nrc.gov
Reactor Inspector
817-200-1126
Fabian.Thomas@nrc.gov
Senior Reactor Inspector
817-200-1104
Ron.Kopriva@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wes L. Cullum
1600 East Lamar Blvd.
Arlington, TX 76011-4511
- 4 -
Enclosure
- 1 -
Enclosure
Valves of Interest
Design-Basis Capability of Power-Operated Valves
WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3
No.
ACT
Valve Size
Valve Type
System Name
Utility ID
1.
16
Butterfly
ACC
ACC-110A
2.
6
Butterfly
ACC
ACC-112A
3.
3
Gate
BAM
BAM-113B
4.
3
Gate
BAM
BAM-133
5.
4
Gate
BD
BD-102A
6.
20
Butterfly
CC-135A
7.
8
Butterfly
CC-835A
8.
4
Gate
CVC
CVC-183
9.
2
Globe
CVC
CVC-216B
10.
3
Globe
CVC
CVC-507
11.
4
Globe
EFW-223A
12.
4
Globe
EFW-229B
13.
6
Globe
FW-166A
14.
16
Globe
FW-173A
15.
8
Butterfly
HVC
HVC-202A
16.
18
Butterfly
HVR
HVR-304A
17.
20
Butterfly
HVR
HVR-313B
18.
8
Globe
MS
MS-116A
19.
2
Globe
MS
MS-120A
20.
HOV
40
Gate
MS
MS-124B
21.
6
Gate
MS
MS-401B
22.
4
Gate
SI-120A
23.
4
Gate
SI-121B
24.
10
Gate
SI-125A
25.
8
Gate
SI-135A
26.
2
Globe
SI-308A
27.
14
Gate
SI-401A
28.
14
Gate
SI-407A
29.
1.5
Globe
SI-6012
30.
24
Butterfly
SI-602A