ML22187A036: Difference between revisions

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See also: [[see also::IR 05000382/2022013]]
See also: [[followed by::IR 05000382/2022013]]


=Text=
=Text=
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES
                        NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION
                                          REGION IV
REGION IV
                                      1600 E. LAMAR BLVD.
1600 E. LAMAR BLVD.
                                  ARLINGTON, TX  76011-4511
ARLINGTON, TX  76011-4511
 
July 11, 2022
                                      July 11, 2022
 
Mr. John Ferrick, Site Vice President
Mr. John Ferrick, Site Vice President
Entergy Operations, Inc.
Entergy Operations, Inc.
17265 River Road
17265 River Road
Killona, LA 70057
Killona, LA 70057
 
SUBJECT:  WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION OF NRC  
SUBJECT:  WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000382/2022013)  
          DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000382/2022013)
AND REQUEST FOR INFORMATION
          AND REQUEST FOR INFORMATION
 
Dear Mr. Ferrick:
Dear Mr. Ferrick:
 
On September 19, 2022, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite  
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  
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,  
perform this inspection using NRC Inspection Procedure 71111, Attachment 21N.02,
Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements,  
Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements,
dated October 9, 2020.  
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  
This inspection will evaluate the reliability, functional capability, and design basis of
10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Waterford  
risk-significant power-operated valves as required by 10 CFR 50.55a and applicable
Steam Electric Plant Station, Unit 3 operating license.  Additionally, the team will perform an  
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-
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,
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
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
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
conducting this inspection, the team will select power-operated valves used to prevent and  
mitigate the consequences of a design basis accident.
mitigate the consequences of a design basis accident.
 
The inspection will include an information gathering site visit by the team leader and two weeks  
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  
of onsite inspection by the team.  The inspection team will consist of three NRC inspectors.  The
current inspection schedule is as follows:
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


      Onsite Information Gathering Visit:  August 8, 2022
J. Ferrick
      Preparation Week:  September 12, 2022
- 2 -
      Onsite Weeks:  September 19, 2022, and October 3, 2022
The purpose of the information gathering visit is to meet with members of your staff to become  
J. Ferrick                                 - 2 -
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  
The purpose of the information gathering visit is to meet with members of your staff to become
your staff to become familiar with the regulations and standards applicable to power-operated  
familiar with the power-operated valve activities at Waterford Steam Electric Plant Station, Unit
valves at the site.  Additional information and documentation needed to support the inspection  
3.  The lead inspector will request a meeting with your personnel to discuss the site
will be identified during the inspection, including interviews with engineering managers and  
power-operated valve procedures.  Additionally, the lead inspector will request a discussion with
engineers.
your staff to become familiar with the regulations and standards applicable to power-operated
To minimize the inspection impact on the site and to ensure a productive inspection, we have  
valves at the site.  Additional information and documentation needed to support the inspection
enclosed a request for information needed prior to the inspection.  This information should be  
will be identified during the inspection, including interviews with engineering managers and
made available to the lead inspector during the August 8, 2022, visit.  Since the inspection will  
engineers.
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  
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.
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  
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  
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  
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  
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  
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  
to each inspector to ensure information requests, questions, and concerns are addressed in a
timely manner.
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 lead inspector for this inspection is Mr. Wes Cullum.  We understand that our licensing
the requested materials, please contact the lead inspector by telephone at 817-200-1563 or by  
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.
e-mail at Wes.Cullum@nrc.gov.
PAPERWORK REDUCTION ACT STATEMENT
PAPERWORK REDUCTION ACT STATEMENT
 
This letter contains mandatory information collections that are subject to the Paperwork  
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)  
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  
approved these information collections (approval number 3150-0011).  Send comments
regarding this information collection to the Information Services Branch, Office of the Chief  
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  
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  
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  
Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and
Budget, Washington, DC 20503.
Budget, Washington, DC 20503.
PUBLIC PROTECTION NOTIFICATION
PUBLIC PROTECTION NOTIFICATION
 
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request  
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  
for information or an information collection requirement unless the requesting document
displays a currently valid OMB control number.
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.


This letter, its enclosure, and your response (if any) will be made available for public inspection
J. Ferrick
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
- 3 -
Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public
Inspections, Exemptions, Requests for Withholding.
J. Ferrick - 3 -
Sincerely,
Sincerely,
                            
                            
Line 130: Line 116:


  ML22187A036
  ML22187A036
  SUNSI Review       ADAMS:   Non-Publicly Available Non-SensitiveKeyword:
  SUNSI Review
  By:WLC1     Yes    No Publicly Available   Sensitive
ADAMS:
OFFICE       DORS/EB1     DORS/EB1
Non-Publicly Available Non-Sensitive Keyword:  
NAME         WCullum       VGaddy
By: WLC1
SIGNATURE     RA           RA
Yes    No
DATE         7/10/22       7/11/22
Publicly Available
Sensitive  
OFFICE
DORS/EB1
DORS/EB1
NAME
WCullum
VGaddy
SIGNATURE
RA
RA
DATE
7/10/22
7/11/22


                             
- 1 -
                                  Request for Information
Enclosure
                    Design-Basis Capability of Power-Operated Valves
Request for Information
                WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3
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.


  Inspection Report:               05000382/2022013
- 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: 
Wes Cullum (Lead)
Reactor Inspector
817-200-1563
Wes.Cullum@nrc.gov
Fabian Thomas
Reactor Inspector
817-200-1126
Fabian.Thomas@nrc.gov
Ron Kopriva
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


EPID Number:                    I-2022-013-0002
- 4 -
Enclosure


Information Gathering Dates:    August 8, 2022
- 1 -
 
Enclosure
Onsite Inspection Dates:        September 19, 2022, and October 3, 2022
Valves of Interest
 
Design-Basis Capability of Power-Operated Valves
Inspection Procedure:            IP 71111, Attachment 21N.02, Design-Basis Capability of
WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3
                                  Power-Operated Valves Under 10 CFR 50.55a
No.
                                  Requirements
ACT
 
Valve Size
Lead Inspector:                  Wes L. Cullum, Reactor Inspector
Valve Type
 
System Name
 
Utility ID
I.        Information Requested for Information Gathering Visit (August 8, 2022)
1.
 
MOV
      The following information should be provided to the lead inspector in hard copy or
16
      electronic format, to the attention of the lead inspector by August 8, 2022, to facilitate the
Butterfly
      reduction in the items to be selected for a final list of components.  The inspection team
ACC
      will finalize the selected list during the prep week using the documents requested in this
ACC-110A
      enclosure.  The specific items selected from the lists shall be available and ready for
2.
      review on the day indicated in this request.  *Please provide requested documentation
AOV
      electronically in pdf files, Excel, or other searchable formats, if possible.  The
6
      information should contain descriptive names and be indexed and hyperlinked to
Butterfly
      facilitate ease of use.  Information in "lists" should contain enough information to be
ACC
      easily understood by someone who has knowledge of pressurized water reactor
ACC-112A
      technology.  If requested documents are large and only hard copy formats are available,
3.
      please inform the inspectors, and provide subject documentation during the first day of
MOV
      the onsite inspection.
3
 
Gate
      1.  Provide the valve characteristics for the valves listed in the attached list as described
BAM
          in Appendix C of NRC Inspection Procedure 71111, Attachment 21N.02, Design
BAM-113B
          Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.
4.
 
MOV
      2.  List of power-operated valves (POVs) important to safety for the Waterford Steam
3
          Electric Plant Station, Unit 3.  The list should include (a) component identification
Gate
          number; (b) applicable plant system; (c) ASME Boiler and Pressure Vessel Code
BAM
          (BPV Code) Class; (d) safety-related or nonsafety-related classification; (e) valve
BAM-133
          type, size and manufacturer; and (f) actuator type, size, and manufacturer.  If the
5.
          NRC has granted a license amendment to categorize structures, systems, and
AOV
          component in accordance with 10 CFR 50.69, please provide the risk-informed
4
          safety category of the structure, system, or component.
Gate
 
BD
      3.  List of POVs sorted by risk importance, including internal and external risk
BD-102A
          considerations.
6.
 
AOV
                                            - 1 -                                Enclosure
20
      4.  Word-searchable updated final safety analysis report (UFSAR), license conditions,
Butterfly
          technical specifications, and most recent inservice testing (IST) program plan (and
CC
          bases document), including any standards that have been committed to with respect
CC-135A
          to POV capability and testing.  Also, identify which UFSAR sections address
7.
          environmental, seismic, and functional qualification of POVs.
AOV
 
8
      5.  Provide copies of the latest POV program level procedures or manuals.
Butterfly
 
CC
      6.  NRC Safety Evaluation Report(s) associated with the IST program including relief
CC-835A
          and alternative requests submitted in accordance with 10 CFR 50.55a for POVs.
8.
 
MOV
      7.  Provide any responses to NRC Generic Letter (GL) 89-10, Safety-Related Motor-
4
          Operated Valve Testing and Surveillance, (and its supplements) and GL 96-05,
Gate
          Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated
CVC
          Valves.
CVC-183
 
9.
      8.  Provide the most recently completed audit, self-assessment, or benchmark of POV
SOV
          programs at Waterford Steam Electric Plant Station, Unit 3.
2
 
Globe
      9.  List of systems, system numbers/designators, and corresponding names.
CVC
 
CVC-216B
      10.List of site contacts that will be associated with the inspection.
10.
 
MOV
II.        Discussions Requested During the Information Gathering Visit
3
 
Globe
      1.  Interview with a representative to discuss site POV capability analyses, including
CVC
          plant drawings and assumptions.  This includes analysis for accident conditions.
CVC-507
 
11.
      2.  Interview with a representative to discuss POV maintenance elements as integrated
AOV
          into plant programs and procedures.
4
 
Globe
      3.  Interview with a representative to discuss maintaining the design-basis capability of
EFW
          POVs if they have entered a period of extended operation, if applicable.
EFW-223A
 
12.
III.      Information Requested for Inspection Preparation (September 12, 2022) *
AOV
 
4
      1.  Calculations and/or evaluations associated with the selected POVs, as applicable.
Globe
          For example, these may include those related to motor-operated valve (MOV) torque
EFW
          switch setpoint, MOV terminal (degraded) voltage, maximum expected differential
EFW-229B
          and pressure, torque switch bypass settings, rate of loading, environmental and
13.
          process conditions during normal/accident operation, seismic and weak-link analysis,
AOV
          and pressure locking and thermal binding, etc.  (Ten specific valves will be identified
6
          and communicated to you prior to August 22, 2022.)
Globe
 
FW
      2.  Environmental qualification files associated with the selected POVs, as applicable.
FW-166A
 
14.
      3.  Vendor manuals and technical sheets associated with the selected POVs.
AOV
 
16
 
Globe
 
FW
 
FW-173A
                                            - 2 -                                  Enclosure
15.
      4.  Provide results (i.e., completed work orders) from the last three performances of
MOV
          diagnostic (static and/or dynamic) testing and inservice testing (stroke time, leak
8
          rate, etc.) of the selected POVs.
Butterfly
 
HVC
      5.  Provide performance (or failure) trending data for the selected POVs.
HVC-202A
 
16.
      6.  List of modifications related to the selected POVs.
MOV
 
18
      7.  List of corrective action program documents, with a brief description, related to the
Butterfly
          selected POVs over the past five years.
HVR
 
HVR-304A
      8.  List of preventive maintenance activities for the selected POVs (valve and actuator).
17.
          Include the identification number, title and/or description, and frequency.
MOV
 
20
      9.  System training manuals and/or design basis documents associated with the
Butterfly
          selected POVs.
HVR
 
HVR-313B
      10.Piping and instrument diagrams for systems related to the selected POVs.
18.
 
AOV
      11.Tours of the rooms in which the selected POVs are installed.  If the inspection will be
8
          performed remotely, multiple pictures of selected valve and valve location can be
Globe
          provided.  The pictures must have an orientation reference, a size reference, pictures
MS
          of the surrounding environment, and pictures of the nameplates of both valve and
MS-116A
          valve operator.
19.
 
MOV
IV.      Discussions Requested During the First Inspection Week (September 19, 2022)
2
 
Globe
      1.  Brief presentation of POV programs at Waterford Steam Electric Plant Station, Unit
MS
          3.
MS-120A
 
20.
      2.  Interviews with representatives to discuss the design-basis capability of POVs based
HOV
          upon the teams review of gathered information.
40
 
Gate
* Please sort the Section III responses by each selected POV.
MS
 
MS-124B
 
21.
Inspector Contact Information:
MOV
 
6
Wes Cullum (Lead)              Fabian Thomas                  Ron Kopriva
Gate
Reactor Inspector              Reactor Inspector              Senior Reactor Inspector
MS
817-200-1563                  817-200-1126                    817-200-1104
MS-401B
Wes.Cullum@nrc.gov            Fabian.Thomas@nrc.gov          Ron.Kopriva@nrc.gov
22.
 
MOV
 
4
Mailing Address:
Gate
 
SI
U.S. NRC, Region IV
SI-120A
Attn:  Wes L. Cullum
23.
1600 East Lamar Blvd.
MOV
Arlington, TX 76011-4511
4
 
Gate
 
SI
                                            - 3 -                                Enclosure
SI-121B
- 4 -                                Enclosure
24.
                            Valves of Interest
MOV
              Design-Basis Capability of Power-Operated Valves
10
          WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3
Gate
 
SI
 
SI-125A
No.   ACT     Valve Size     Valve Type     System Name       Utility ID
25.
1.   MOV         16           Butterfly         ACC         ACC-110A
MOV
2.   AOV         6           Butterfly         ACC         ACC-112A
8
3.   MOV         3             Gate             BAM         BAM-113B
Gate
4.   MOV         3             Gate             BAM           BAM-133
SI
5.   AOV         4             Gate             BD           BD-102A
SI-135A
6.   AOV         20           Butterfly           CC           CC-135A
26.
7.   AOV         8           Butterfly           CC           CC-835A
AOV
8.   MOV         4             Gate             CVC           CVC-183
2
9.   SOV         2           Globe             CVC         CVC-216B
Globe
10.   MOV         3           Globe             CVC           CVC-507
SI
11.   AOV         4           Globe             EFW         EFW-223A
SI-308A
12.   AOV         4           Globe             EFW         EFW-229B
27.
13.   AOV         6           Globe             FW           FW-166A
MOV
14.   AOV         16           Globe             FW           FW-173A
14
15.   MOV         8           Butterfly         HVC         HVC-202A
Gate
16.   MOV         18           Butterfly         HVR         HVR-304A
SI
17.   MOV         20           Butterfly         HVR         HVR-313B
SI-401A
18.   AOV         8           Globe             MS           MS-116A
28.
19.   MOV         2           Globe             MS           MS-120A
MOV
20.   HOV         40             Gate             MS           MS-124B
14
21.   MOV         6             Gate             MS           MS-401B
Gate
22.   MOV         4             Gate             SI           SI-120A
SI
23.   MOV         4             Gate             SI           SI-121B
SI-407A
24.   MOV         10             Gate             SI           SI-125A
29.
25.   MOV         8             Gate             SI           SI-135A
SOV
26.   AOV         2           Globe             SI           SI-308A
1.5
27.   MOV         14             Gate             SI           SI-401A
Globe
28.   MOV         14             Gate             SI           SI-407A
SI
29.   SOV         1.5           Globe             SI           SI-6012
SI-6012
30.   MOV         24           Butterfly           SI           SI-602A
30.
 
MOV
 
24
 
Butterfly
 
SI
 
SI-602A
 
 
 
 
 
 
 
 
 
 
 
 
                                  - 1 -                          Enclosure
}}
}}

Revision as of 16:33, 27 November 2024

Notification of NRC Design Bases Assurance Inspection (Programs) (05000382/2022013) and Request for Information
ML22187A036
Person / Time
Site: Waterford Entergy icon.png
Issue date: 07/11/2022
From: Vincent Gaddy
NRC/RGN-IV/DORS/EB1
To: Ferrick J
Entergy Operations
References
IR 2022013
Download: ML22187A036 (9)
v • d • e


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

ML22187A036

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

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:

Wes Cullum (Lead)

Reactor Inspector

817-200-1563

Wes.Cullum@nrc.gov

Fabian Thomas

Reactor Inspector

817-200-1126

Fabian.Thomas@nrc.gov

Ron Kopriva

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.

MOV

16

Butterfly

ACC

ACC-110A

2.

AOV

6

Butterfly

ACC

ACC-112A

3.

MOV

3

Gate

BAM

BAM-113B

4.

MOV

3

Gate

BAM

BAM-133

5.

AOV

4

Gate

BD

BD-102A

6.

AOV

20

Butterfly

CC

CC-135A

7.

AOV

8

Butterfly

CC

CC-835A

8.

MOV

4

Gate

CVC

CVC-183

9.

SOV

2

Globe

CVC

CVC-216B

10.

MOV

3

Globe

CVC

CVC-507

11.

AOV

4

Globe

EFW

EFW-223A

12.

AOV

4

Globe

EFW

EFW-229B

13.

AOV

6

Globe

FW

FW-166A

14.

AOV

16

Globe

FW

FW-173A

15.

MOV

8

Butterfly

HVC

HVC-202A

16.

MOV

18

Butterfly

HVR

HVR-304A

17.

MOV

20

Butterfly

HVR

HVR-313B

18.

AOV

8

Globe

MS

MS-116A

19.

MOV

2

Globe

MS

MS-120A

20.

HOV

40

Gate

MS

MS-124B

21.

MOV

6

Gate

MS

MS-401B

22.

MOV

4

Gate

SI

SI-120A

23.

MOV

4

Gate

SI

SI-121B

24.

MOV

10

Gate

SI

SI-125A

25.

MOV

8

Gate

SI

SI-135A

26.

AOV

2

Globe

SI

SI-308A

27.

MOV

14

Gate

SI

SI-401A

28.

MOV

14

Gate

SI

SI-407A

29.

SOV

1.5

Globe

SI

SI-6012

30.

MOV

24

Butterfly

SI

SI-602A

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