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{{#Wiki_filter:May 18, 2020
{{#Wiki_filter:May 18, 2020  
Mr. Ken Peters
Senior Vice President and Chief Nuclear Officer
Attention: Regulatory Affairs
Vistra Operations Company LLC
Mr. Ken Peters  
P.O. Box 1002
Senior Vice President and Chief Nuclear Officer  
Glen Rose, TX 76043
Attention: Regulatory Affairs  
SUBJECT:       COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -
Vistra Operations Company LLC  
                NOTIFICATION OF NRC DESIGN BASES ASSURANCE INSPECTION
P.O. Box 1002  
                (PROGRAMS) (05000445/2020010 AND 05000446/2020010) AND INITIAL
Glen Rose, TX 76043  
                REQUEST FOR INFORMATION
Dear Mr. Peters:
SUBJECT:  
On August 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -  
inspection at the Comanche Peak Nuclear Power Plant. A three-person team will perform this
NOTIFICATION OF NRC DESIGN BASES ASSURANCE INSPECTION  
inspection using NRC Inspection Procedure 71111.21N.02, Design Bases Inspection
(PROGRAMS) (05000445/2020010 AND 05000446/2020010) AND INITIAL  
(Programs), Attachment 2, Design-Basis Capability of Power-Operated Valves Under
REQUEST FOR INFORMATION  
Title 10 of the Code of Federal Regulations (10 CFR) 50.55a Requirements.
This inspection will evaluate the reliability, functional capability, and design basis of
Dear Mr. Peters:  
risk-important 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 Comanche
On August 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite  
Peak Nuclear Power Plant Operating License. Additionally, the team will perform an inspection
inspection at the Comanche Peak Nuclear Power Plant. A three-person team will perform this  
of the documentation files to verify that the plant activities associated with safety-related
inspection using NRC Inspection Procedure 71111.21N.02, Design Bases Inspection  
motor-operated valves meet your commitments to Generic Letter (GL) 89-10, Safety-Related
(Programs), Attachment 2, Design-Basis Capability of Power-Operated Valves Under
Motor-Operated Valve Testing and Surveillance, and GL 96-05, "Periodic Verification of
Title 10 of the Code of Federal Regulations (10 CFR) 50.55a Requirements.  
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
This inspection will evaluate the reliability, functional capability, and design basis of
consequences of a design basis accident.
risk-important power-operated valves as required by 10 CFR 50.55a and applicable
The inspection will include an information gathering site visit by the team leader and 2 weeks of
10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Comanche  
onsite inspection by the team. The inspection will consist of three NRC inspectors. The current
Peak Nuclear Power Plant Operating License. Additionally, the team will perform an inspection  
inspection schedule is as follows:
of the documentation files to verify that the plant activities associated with safety-related  
        Onsite Information Gathering Visit: July 28-29, 2020
motor-operated valves meet your commitments to Generic Letter (GL) 89-10, Safety-Related  
        Preparation Weeks: August 3-7, 2020, and August 17 - 21, 2020
Motor-Operated Valve Testing and Surveillance, and GL 96-05, "Periodic Verification of  
        Onsite Weeks: August10-14, 2020, and August 24 - 28, 2020
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 2 weeks of  
onsite inspection by the team. The inspection will consist of three NRC inspectors. The current  
inspection schedule is as follows:  
Onsite Information Gathering Visit: July 28-29, 2020  
Preparation Weeks: August 3-7, 2020, and August 17 - 21, 2020  
Onsite Weeks: August10-14, 2020, and August 24 - 28, 2020  


K. Peters                                         2
K. Peters  
The purpose of the information gathering visit is to meet with members of your staff to become
2  
familiar with the power-operated valve activities at the Comanche Peak Nuclear Power Plant.
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 the Comanche Peak Nuclear Power Plant.
The lead inspector will request a meeting with your personnel to discuss the site power-
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
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
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
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.
identified during the inspection, including interviews with engineering managers and engineers.
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. This information should be
In order to minimize the inspection impact on the site and to ensure a productive inspection, we  
made available to the lead inspector during the July 28-29, 2020, visit. Since the inspection will
have enclosed a request for information needed for the inspection. This information should be  
be concentrated on safety-related and risk-significant power-operated valves, a list of such
made available to the lead inspector during the July 28-29, 2020, visit. Since the inspection will  
power-operated valves should be available to review during and following the information
be concentrated on safety-related and risk-significant power-operated valves, a list of such  
gathering visit to assist in our selection of appropriate power-operated valves to review.
power-operated valves should be available to review during and following the information  
It is requested that this information be provided to the lead inspector as the information is
gathering visit to assist in our selection of appropriate power-operated valves to review.  
generated during the inspection. Additional requests by inspectors will be made during the
onsite weeks for specific documents needed to complete the review of specific power-operated
It is requested that this information be provided to the lead inspector as the information is  
valves and associated activities. It is important that all of these documents are up-to-date and
generated during the inspection. Additional requests by inspectors will be made during the  
complete in order to minimize the number of additional documents requested during the
onsite weeks for specific documents needed to complete the review of specific power-operated  
preparation and/or the onsite portions of the inspection. In order to facilitate the inspection, we
valves and associated activities. It is important that all of these documents are up-to-date and  
request that a contact individual be assigned to each inspector to ensure information requests,
complete in order to minimize the number of additional documents requested during the  
questions, and concerns are addressed in a timely manner.
preparation and/or the onsite portions of the inspection. In order to facilitate the inspection, we  
The lead inspector for this inspection is Wayne C. Sifre. We understand that our licensing
request that a contact individual be assigned to each inspector to ensure information requests,  
engineer contact for this inspection is Gary Murka. If there are any questions about
questions, and concerns are addressed in a timely manner.  
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.
The lead inspector for this inspection is Wayne C. Sifre. We understand that our licensing  
Paperwork Reduction Act Statement
engineer contact for this inspection is Gary Murka. If there are any questions about
This letter contains mandatory information collections that are subject to the Paperwork
the inspection or the requested materials, please contact the lead inspector by telephone
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)
at 817-200-1193 or by e-mail at Wayne.Sifre@nrc.gov.
approved these information collections (approval number 3150-0011). Send comments
regarding this information collection to the Information Services Branch, Office of the Chief
Paperwork Reduction Act Statement  
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
This letter contains mandatory information collections that are subject to the Paperwork  
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)  
Budget, Washington, DC 20503.
approved these information collections (approval number 3150-0011). Send comments  
The burden to the public for these voluntary information collections is estimated to average
regarding this information collection to the Information Services Branch, Office of the Chief  
2,250 hours per examination, including the time for reviewing instructions, searching existing
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,  
data sources, gathering and maintaining the data needed, and completing and reviewing the
DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office  
information collection. You may submit comments on any aspect of the information collection,
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and  
including suggestions for reducing the burden, to the FOIA, Privacy and Information Collections
Budget, Washington, DC 20503.  
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by
 
electronic mail to INFOCOLLECTS.RESOURCE@NRC.GOV; and to the Desk Officer, Office of
The burden to the public for these voluntary information collections is estimated to average  
Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and
2,250 hours per examination, including the time for reviewing instructions, searching existing  
Budget, Washington, DC 20503.
data sources, gathering and maintaining the data needed, and completing and reviewing the  
information collection. You may submit comments on any aspect of the information collection,  
including suggestions for reducing the burden, to the FOIA, Privacy and Information Collections  
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by  
electronic mail to INFOCOLLECTS.RESOURCE@NRC.GOV; and to the Desk Officer, Office of  
Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and  
Budget, Washington, DC 20503.  


K. Peters                                       3
K. Peters  
Public Protection Notification
3  
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request
Public Protection Notification
for information or an information collection requirement unless the requesting document
 
displays a currently valid OMB control number.
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request  
This letter will be made available for public inspection and copying at
for information or an information collection requirement unless the requesting document  
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
displays a currently valid OMB control number.  
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
                                                Sincerely,
This letter will be made available for public inspection and copying at  
                                                Vincent G. Gaddy, Chief
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in  
                                                Engineering Branch 1
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.  
                                                Division of Reactor Safety
Docket Nos. 05000445 and 05000446
Sincerely,  
License Nos. NPF-87 and NPF-89
Enclosure:
Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Initial Request for Information
Vincent G. Gaddy, Chief  
w/Attachment: Comanche Peak
Engineering Branch 1  
Valves of Interest
Division of Reactor Safety  
cc w/ encl: Distribution via LISTSERV
Docket Nos. 05000445 and 05000446  
License Nos. NPF-87 and NPF-89  
Enclosure:  
Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Initial Request for Information  
w/Attachment: Comanche Peak
Valves of Interest  
cc w/ encl: Distribution via LISTSERV  




ML20139A145
  ML20139A145  
  SUNSI Review:   ADAMS:         Non-Publicly Available Non-Sensitive Keyword:
  SUNSI Review:     ADAMS:               Non-Publicly Available         Non-Sensitive           Keyword:
By: WCS           Yes  No    Publicly Available     Sensitive     NRC-002
By: WCS                 Yes   No
OFFICE         SRI:EB1     C:EB1
  Publicly Available                 Sensitive                   NRC-002  
  NAME           WSifre       VGaddy
OFFICE  
  SIGNATURE     /RA/         /RA/
SRI:EB1  
  DATE           05/18/2020   05/18/2020
C:EB1  
                                     
   
                                  Initial Request for Information
        Design Bases Assurance Inspection (Programs), Power-Operated Valves
                COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2
Inspection Report:                      05000445/2020010 AND 05000446/2020010
NAME  
Information Gathering Dates:            July 28-29, 2020
WSifre  
Inspection Dates:                        August 10-14, 2020 and August 24-28, 2020
VGaddy  
Inspection Procedure:                    IP 71111, Attachment 21N.02, Design Bases Assurance
   
                                        Inspection (Programs) Attachment 2, Design-Basis
                                        Capability of Power-Operated Valves Under
                                        10 CFR 50.55a Requirements
Lead Inspector:                          Wayne C. Sifre, Senior Reactor Inspector
SIGNATURE  
Inspectors:                              Gerond George, Senior Reactor Inspector
/RA/  
                                        Wes Cullum, Reactor Inspector
/RA/  
I.    Information Requested for Information Gathering Visit (July 28, 2020)
   
      The following information should be provided to the lead inspector in hard copy or
      electronic format to the attention of Wayne Sifre by July 20, 2020, 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
DATE  
      enclosure. The specific items selected from the lists shall be available and ready for
05/18/2020  
      review on the day indicated in this request. *Please provide requested documentation
05/18/2020  
      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 71111.21N.02, Design Bases
            Inspection (Programs), Attachment 2, 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 Comanche Peak
            Nuclear Power Plant. The list should include (a) component identification number;
            (b) applicable plant system; (c) American Society of Mechanical Engineers (ASME)
            Boiler and Pressure Vessel Code (BPVC) Class; (d) safety-related or non-safety
            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 component.
                                                                                          Enclosure


    3. Listing of the POVs sorted by risk importance, including external risk considerations.
    4. Comanche Peak Nuclear Power Plant word-searchable updated final safety analysis
        report (UFSAR), License Conditions, Technical Specifications, and most recent
Enclosure
        Inservice Testing (IST) program plan. Specifically identify which UFSAR sections
Initial Request for Information
        address environmental, seismic, and functional qualification of POVs.
Design Bases Assurance Inspection (Programs), Power-Operated Valves
    5. NRC Safety Evaluation Report(s) associated with the Comanche Peak Nuclear
COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2
        Power Plant IST program and relief and alternative requests submitted in
        accordance with 10 CFR 50.55a for POVs.
    6. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants
Inspection Report: 
        (OM Code) that is the Code of Record for the current 10-year IST Program interval,
05000445/2020010 AND 05000446/2020010
        as well as any standards to which the Comanche Peak Nuclear Power Plant has
 
        committed with respect to POV capability and testing.
Information Gathering Dates:
    7. Comanche Peak Nuclear Power Plant Power Operated Valve Program Documents.
July 28-29, 2020
    8. List of systems, system numbers/designators and corresponding names.
 
    9. List of site contacts that will be associated with the inspection.
Inspection Dates:
II.                                Discussions Requested
August 10-14, 2020 and August 24-28, 2020
    1. Interview with a Comanche Peak Nuclear Power Plant representative to discuss site
 
        POV capability analyses, including plant drawings and assumptions. This includes
Inspection Procedure:
        analysis for accident conditions.
IP 71111, Attachment 21N.02, Design Bases Assurance
    2. Interview with a Comanche Peak Nuclear Power Plant representative to discuss
Inspection (Programs) Attachment 2, Design-Basis
        POV maintenance elements as integrated into plant programs and procedures.
Capability of Power-Operated Valves Under 
    3. Interview with a Comanche Peak Nuclear Power Plant representative to discuss
10 CFR 50.55a Requirements
        maintaining the design-basis capability of POVs if they have entered a period of
        extended operation, if applicable.
Lead Inspector:
III. Information Requested for Inspection Preparation (August 3, 2020)
Wayne C. Sifre, Senior Reactor Inspector
    1. Documentation files, including test reports, for the electrical and mechanical
Inspectors:
        components associated with the POVs selected by the lead inspector (10 specific
Gerond George, Senior Reactor Inspector
        valves will be identified and communicated to you prior to August 3, 2020).
    2. References associated with the electrical and mechanical components document
Wes Cullum, Reactor Inspector
        files.
    3. Vendor manuals and technical sheets associated with the selected POVs.
    4. Tours of the rooms in which the selected POVs are installed.
I.  
                                              2
Information Requested for Information Gathering Visit (July 28, 2020)  
The following information should be provided to the lead inspector in hard copy or
electronic format to the attention of Wayne Sifre by July 20, 2020, 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 71111.21N.02, Design Bases
Inspection (Programs), Attachment 2, 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 Comanche Peak  
Nuclear Power Plant.  The list should include (a) component identification number; 
(b) applicable plant system; (c) American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (BPVC) Class; (d) safety-related or non-safety
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 component.  


Inspector Contact Information:
Wayne C. Sifre                 Gerond George            Wes Cullum
2
Senior Reactor Inspector      Senior Reactor Inspector Reactor Inspector
3. Listing of the POVs sorted by risk importance, including external risk considerations.
817-200-1193                   817-200- 1562            817-200- 1563
Wayne.Sifre@nrc.gov           Gerond.George@nrc.gov   Wes.Cullum@nrc.gov
4. Comanche Peak Nuclear Power Plant word-searchable updated final safety analysis
Mailing Address:
report (UFSAR), License Conditions, Technical Specifications, and most recent
U.S. NRC, Region IV
Inservice Testing (IST) program plan.  Specifically identify which UFSAR sections
Attn: Wayne Sifre
address environmental, seismic, and functional qualification of POVs.
1600 East Lamar Blvd.
5. NRC Safety Evaluation Report(s) associated with the Comanche Peak Nuclear
Power Plant IST program and relief and alternative requests submitted in
accordance with 10 CFR 50.55a for POVs.
6. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants
(OM Code) that is the Code of Record for the current 10-year IST Program interval,
as well as any standards to which the Comanche Peak Nuclear Power Plant has
committed with respect to POV capability and testing. 
7. Comanche Peak Nuclear Power Plant Power Operated Valve Program Documents.
8. List of systems, system numbers/designators and corresponding names.
9. List of site contacts that will be associated with the inspection. 
II.
Discussions Requested
1. Interview with a Comanche Peak Nuclear Power Plant representative to discuss site
POV capability analyses, including plant drawings and assumptions.  This includes
analysis for accident conditions. 
2. Interview with a Comanche Peak Nuclear Power Plant representative to discuss
POV maintenance elements as integrated into plant programs and procedures.
3. Interview with a Comanche Peak Nuclear Power Plant 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 (August 3, 2020)
1. Documentation files, including test reports, for the electrical and mechanical
components associated with the POVs selected by the lead inspector (10 specific
valves will be identified and communicated to you prior to August 3, 2020). 
2. References associated with the electrical and mechanical components document
files.
3. Vendor manuals and technical sheets associated with the selected POVs.
4. Tours of the rooms in which the selected POVs are installed.
 
3
Inspector Contact Information:  
Wayne C. Sifre  
Senior Reactor Inspector  
817-200-1193  
Wayne.Sifre@nrc.gov  
Gerond George
Senior Reactor Inspector
817-200- 1562
Gerond.George@nrc.gov  
Wes Cullum
Reactor Inspector
817-200- 1563
Wes.Cullum@nrc.gov
Mailing Address:  
U.S. NRC, Region IV  
Attn: Wayne Sifre  
1600 East Lamar Blvd.  
Arlington, TX 76011-4
Arlington, TX 76011-4
                                          3


Comanche Peak Valves of Interest
No. ACT   Size   Valve         System                       Utility ID Selection
          (in)  Type                                                    Basis
Attachment
1. MOV 8       Gate           Unit 1 - AFW - AFW Pump     1-HV-2482   Risk
Comanche Peak Valves of Interest  
                                Emergency Supply Flowpath
No. ACT  
2. MOV 8       Gate           Unit 1 - CVCS - ECCS         1-LCV-0112E Risk
Size  
                                Injection Flowpath &
(in)
                                Boration
Valve  
3. AOV   10     Butterfly     Unit 1 - CCW - Flowpath     1-FV-4537   Risk
Type
                                Boundary
System  
4. AOV   3     Ball           Unit 1 - CCW - Safety       1-PV-4553
Utility ID  
                                Chilled Water Condenser
Selection  
                                Cooling
Basis  
  5. AOV   3     Diaphragm     Containment Isolation       1-LCV-1003 LERF
1.  
6. AOV   18     Globe         Unit 1 - Feedwater Isolation 1-FCV-0540
MOV 8  
  7. HOV   18     Gate           Unit 1 - Feedwater Isolation 1-HV-2134   LERF
Gate  
                                & Containment Isolation
Unit 1 - AFW - AFW Pump  
8. AOV   3     Globe         Unit 1 - RCS - Post Accident 1-PCV-0455A Risk
Emergency Supply Flowpath
                                Vent Path/Vent Path
1-HV-2482  
                                Isolation
Risk  
9. MOV 12       Gate           Unit 1 - RHR -               1-8701B    Risk
2.  
                                Flowpath/Containment
MOV 8  
                                Isolation
Gate  
10. MOV 8       Gate           Unit 1 - SI - ECCS           1-8804B    Risk
Unit 1 - CVCS - ECCS  
                                Recirculation
Injection Flowpath &
                                Flowpath/Passive Pipe
Boration
                                Break Isolation
1-LCV-0112E  
11. MOV 4       Gate           Unit 1 - SI - ECCS to Cold   1-8835      Risk
Risk  
                                Legs Flowpath/ECCS to Hot
3.  
                                Legs Flowpath
AOV  
12. MOV 10       Gate           Unit 1 - SI - ECCS to Cold   1-8809B    Risk
10  
                                Legs Flowpath/ECCS to Hot
Butterfly  
                                Legs Flowpath
Unit 1 - CCW - Flowpath  
13. MOV 10       Gate           Unit 1 - SI - ECCS to Hot   1-8840      Risk
Boundary
                                Legs Flowpath/ECCS to
1-FV-4537  
                                Cold Legs
Risk  
14. MOV 24       Butterfly     Unit 1 - Service Water       1-HV-4287   Risk
4.  
                                Flowpath/Throttling
AOV  
15. MOV 4       Gate           Unit 2 - Containment         2-HV-2492B  Risk
3  
                                Isolation & AFW to Faulted
Ball  
                                SG Flow
Unit 1 - CCW - Safety  
16. MOV 2       Globe         Unit 2 - CVCS - ECCS         2-8110     Risk
Chilled Water Condenser  
                                Flowpath Boundary
Cooling  
17. AOV   10     Butterfly     Unit 2 - CCW Flowpath       2-FV-4536   Risk
1-PV-4553
                                Boundary
   
18. MOV 18       Butterfly     Unit 2 - CCW - RHR Heat     2-HV-4572   Risk
5.  
                                Exchanger Cooling Flowpath
AOV  
                                                                          Attachment
3  
Diaphragm  
Containment Isolation  
1-LCV-1003  
LERF  
6.  
AOV  
18  
Globe  
Unit 1 - Feedwater Isolation  
1-FCV-0540  
   
7.  
HOV  
18  
Gate  
Unit 1 - Feedwater Isolation  
& Containment Isolation
1-HV-2134  
LERF  
8.  
AOV  
3  
Globe  
Unit 1 - RCS - Post Accident  
Vent Path/Vent Path  
Isolation  
1-PCV-0455A
Risk
9.  
MOV 12  
Gate  
Unit 1 - RHR -  
Flowpath/Containment  
Isolation  
1-8701B
Risk
10.  
MOV 8  
Gate  
Unit 1 - SI - ECCS  
Recirculation  
Flowpath/Passive Pipe  
Break Isolation  
1-8804B
Risk
11.  
MOV 4  
Gate  
Unit 1 - SI - ECCS to Cold  
Legs Flowpath/ECCS to Hot  
Legs Flowpath  
1-8835
Risk
12.  
MOV 10  
Gate  
Unit 1 - SI - ECCS to Cold  
Legs Flowpath/ECCS to Hot  
Legs Flowpath  
1-8809B
Risk
13.  
MOV 10  
Gate  
Unit 1 - SI - ECCS to Hot  
Legs Flowpath/ECCS to  
Cold Legs  
1-8840
Risk
14.  
MOV 24  
Butterfly  
Unit 1 - Service Water  
Flowpath/Throttling
1-HV-4287  
Risk  
15.  
MOV 4  
Gate  
Unit 2 - Containment  
Isolation & AFW to Faulted  
SG Flow  
2-HV-2492B
Risk
16.  
MOV 2  
Globe  
Unit 2 - CVCS - ECCS  
Flowpath Boundary
2-8110  
Risk  
17.  
AOV  
10  
Butterfly  
Unit 2 - CCW Flowpath  
Boundary
2-FV-4536  
Risk  
18.  
MOV 18  
Butterfly  
Unit 2 - CCW - RHR Heat  
Exchanger Cooling Flowpath
2-HV-4572  
Risk  


No. ACT Size Valve System                       Utility ID Selection
        (in) Type                                          Basis
A-2
19. AOV 3   Ball CCW - - Safety Chilled       2-PV-4552 Risk
No. ACT  
                  Water Condenser Cooling
Size  
20. AOV 18   Globe Feedwater Isolation         2-FCV-0520 Risk
(in)
21. HOV 18   Gate Feedwater Isolation &       2-HV-2137 Risk
Valve  
                  Containment Isolation
Type
22. HOV 2   Globe Unit 2 - FW - Feedwater     2-HV-2137 Risk
System  
                  Isolation & Containment
Utility ID  
                  Isolation
Selection  
23. HOV 2   Globe Unit 2 - MS - Steam Line     2-HV-2333A Risk
Basis  
                  Isolation & Containment
19.  
                  Isolation
AOV  
24. MOV 3   Gate Unit 2 - RCS - Post Accident 2-8000A    Risk
3  
                  Vent Path/Vent Path
Ball  
                  Isolation
CCW - - Safety Chilled  
25. MOV 6   Gate Unit 2 - SI - ECCS Flowpath 2-8806    Risk
Water Condenser Cooling
                  Boundary (during
2-PV-4552  
                  Recirculation)
Risk  
26. MOV 14   Gate Unit 2 - SI - ECCS           2-8811A    Risk
20.  
                  Recirculation
AOV  
                  Flowpath/Containment
18  
                  Isolation
Globe  
27, MOV 10   Gate Unit 2 - SI - ECCS to Cold   2-8809A    Risk
Feedwater Isolation  
                  Legs Flowpath/ECCS to Hot
2-FCV-0520  
                  Legs Flowpath
Risk  
28. MOV 4   Gate Unit 2 - SI - - ECCS to Hot 2-8802B    Risk
21.  
                  Legs Flowpath/ECCS to
HOV  
                  Cold Legs
18  
29. MOV 6   Gate Unit 2 - SI - Passive Pipe   2-8923B    Risk
Gate  
                  Break Isolation
Feedwater Isolation &  
                              A-2
Containment Isolation
2-HV-2137  
Risk  
22.  
HOV  
2  
Globe  
Unit 2 - FW - Feedwater  
Isolation & Containment
Isolation
2-HV-2137  
Risk  
23.  
HOV  
2  
Globe  
Unit 2 - MS - Steam Line  
Isolation & Containment
Isolation
2-HV-2333A  
Risk  
24.  
MOV 3  
Gate  
Unit 2 - RCS - Post Accident  
Vent Path/Vent Path  
Isolation  
2-8000A
Risk
25.  
MOV 6  
Gate  
Unit 2 - SI - ECCS Flowpath  
Boundary (during  
Recirculation)  
2-8806
Risk
26.  
MOV 14  
Gate  
Unit 2 - SI - ECCS  
Recirculation  
Flowpath/Containment  
Isolation  
2-8811A
Risk
27,  
MOV 10  
Gate  
Unit 2 - SI - ECCS to Cold  
Legs Flowpath/ECCS to Hot  
Legs Flowpath  
2-8809A
Risk
28.  
MOV 4  
Gate  
Unit 2 - SI - - ECCS to Hot  
Legs Flowpath/ECCS to  
Cold Legs  
2-8802B
Risk
29.  
MOV 6  
Gate  
Unit 2 - SI - Passive Pipe  
Break Isolation  
2-8923B
Risk
}}
}}

Latest revision as of 21:44, 24 May 2025

Notification of NRC Design Bases Assurance Inspection (Programs) (05000445/2020010 and 05000446/2020010) and Initial Request for Information
ML20139A145
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 05/18/2020
From: Vincent Gaddy
Region 4 Engineering Branch 1
To: Peters K
Vistra Operations Company
References
IR 2020010
Download: ML20139A145 (9)
v • d • e


See also: IR 05000445/2020010

Text

May 18, 2020

Mr. Ken Peters

Senior Vice President and Chief Nuclear Officer

Attention: Regulatory Affairs

Vistra Operations Company LLC

P.O. Box 1002

Glen Rose, TX 76043

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -

NOTIFICATION OF NRC DESIGN BASES ASSURANCE INSPECTION

(PROGRAMS) (05000445/2020010 AND 05000446/2020010) AND INITIAL

REQUEST FOR INFORMATION

Dear Mr. Peters:

On August 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite

inspection at the Comanche Peak Nuclear Power Plant. A three-person team will perform this

inspection using NRC Inspection Procedure 71111.21N.02, Design Bases Inspection

(Programs), Attachment 2, Design-Basis Capability of Power-Operated Valves Under

Title 10 of the Code of Federal Regulations (10 CFR) 50.55a Requirements.

This inspection will evaluate the reliability, functional capability, and design basis of

risk-important 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 Comanche

Peak Nuclear Power Plant 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 2 weeks of

onsite inspection by the team. The inspection will consist of three NRC inspectors. The current

inspection schedule is as follows:

Onsite Information Gathering Visit: July 28-29, 2020

Preparation Weeks: August 3-7, 2020, and August 17 - 21, 2020

Onsite Weeks: August10-14, 2020, and August 24 - 28, 2020

K. Peters

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 the Comanche Peak Nuclear Power Plant.

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.

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. This information should be

made available to the lead inspector during the July 28-29, 2020, 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.

It is requested that this information be provided to the lead inspector as the information is

generated during the inspection. 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 of these documents are 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 Wayne C. Sifre. We understand that our licensing

engineer contact for this inspection is Gary Murka. 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.

The burden to the public for these voluntary information collections is estimated to average

2,250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> per examination, including the time for reviewing instructions, searching existing

data sources, gathering and maintaining the data needed, and completing and reviewing the

information collection. You may submit comments on any aspect of the information collection,

including suggestions for reducing the burden, to the FOIA, Privacy and Information Collections

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by

electronic mail to INFOCOLLECTS.RESOURCE@NRC.GOV; and to the Desk Officer, Office of

Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and

Budget, Washington, DC 20503.

K. Peters

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.

This letter 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,

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 05000445 and 05000446

License Nos. NPF-87 and NPF-89

Enclosure:

Design Bases Assurance Inspection

(Programs) Power-Operated Valve

Initial Request for Information

w/Attachment: Comanche Peak

Valves of Interest

cc w/ encl: Distribution via LISTSERV

ML20139A145

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

By: WCS Yes No

Publicly Available Sensitive NRC-002

OFFICE

SRI:EB1

C:EB1

NAME

WSifre

VGaddy

SIGNATURE

/RA/

/RA/

DATE

05/18/2020

05/18/2020

Enclosure

Initial Request for Information

Design Bases Assurance Inspection (Programs), Power-Operated Valves

COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2

Inspection Report: 05000445/2020010 AND 05000446/2020010

Information Gathering Dates:

July 28-29, 2020

Inspection Dates:

August 10-14, 2020 and August 24-28, 2020

Inspection Procedure:

IP 71111, Attachment 21N.02, Design Bases Assurance

Inspection (Programs) Attachment 2, Design-Basis

Capability of Power-Operated Valves Under

10 CFR 50.55a Requirements

Lead Inspector:

Wayne C. Sifre, Senior Reactor Inspector

Inspectors:

Gerond George, Senior Reactor Inspector

Wes Cullum, Reactor Inspector

I.

Information Requested for Information Gathering Visit (July 28, 2020)

The following information should be provided to the lead inspector in hard copy or

electronic format to the attention of Wayne Sifre by July 20, 2020, 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 71111.21N.02, Design Bases

Inspection (Programs), Attachment 2, 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 Comanche Peak

Nuclear Power Plant. The list should include (a) component identification number;

(b) applicable plant system; (c) American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code (BPVC) Class; (d) safety-related or non-safety

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 component.

2

3. Listing of the POVs sorted by risk importance, including external risk considerations.

4. Comanche Peak Nuclear Power Plant word-searchable updated final safety analysis

report (UFSAR), License Conditions, Technical Specifications, and most recent

Inservice Testing (IST) program plan. Specifically identify which UFSAR sections

address environmental, seismic, and functional qualification of POVs.

5. NRC Safety Evaluation Report(s) associated with the Comanche Peak Nuclear

Power Plant IST program and relief and alternative requests submitted in

accordance with 10 CFR 50.55a for POVs.

6. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants

(OM Code) that is the Code of Record for the current 10-year IST Program interval,

as well as any standards to which the Comanche Peak Nuclear Power Plant has

committed with respect to POV capability and testing.

7. Comanche Peak Nuclear Power Plant Power Operated Valve Program Documents.

8. List of systems, system numbers/designators and corresponding names.

9. List of site contacts that will be associated with the inspection.

II.

Discussions Requested

1. Interview with a Comanche Peak Nuclear Power Plant representative to discuss site

POV capability analyses, including plant drawings and assumptions. This includes

analysis for accident conditions.

2. Interview with a Comanche Peak Nuclear Power Plant representative to discuss

POV maintenance elements as integrated into plant programs and procedures.

3. Interview with a Comanche Peak Nuclear Power Plant 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 (August 3, 2020)

1. Documentation files, including test reports, for the electrical and mechanical

components associated with the POVs selected by the lead inspector (10 specific

valves will be identified and communicated to you prior to August 3, 2020).

2. References associated with the electrical and mechanical components document

files.

3. Vendor manuals and technical sheets associated with the selected POVs.

4. Tours of the rooms in which the selected POVs are installed.

3

Inspector Contact Information:

Wayne C. Sifre

Senior Reactor Inspector

817-200-1193

Wayne.Sifre@nrc.gov

Gerond George

Senior Reactor Inspector

817-200- 1562

Gerond.George@nrc.gov

Wes Cullum

Reactor Inspector

817-200- 1563

Wes.Cullum@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Wayne Sifre

1600 East Lamar Blvd.

Arlington, TX 76011-4

Attachment

Comanche Peak Valves of Interest

No. ACT

Size

(in)

Valve

Type

System

Utility ID

Selection

Basis

1.

MOV 8

Gate

Unit 1 - AFW - AFW Pump

Emergency Supply Flowpath

1-HV-2482

Risk

2.

MOV 8

Gate

Unit 1 - CVCS - ECCS

Injection Flowpath &

Boration

1-LCV-0112E

Risk

3.

AOV

10

Butterfly

Unit 1 - CCW - Flowpath

Boundary

1-FV-4537

Risk

4.

AOV

3

Ball

Unit 1 - CCW - Safety

Chilled Water Condenser

Cooling

1-PV-4553

5.

AOV

3

Diaphragm

Containment Isolation

1-LCV-1003

LERF

6.

AOV

18

Globe

Unit 1 - Feedwater Isolation

1-FCV-0540

7.

HOV

18

Gate

Unit 1 - Feedwater Isolation

& Containment Isolation

1-HV-2134

LERF

8.

AOV

3

Globe

Unit 1 - RCS - Post Accident

Vent Path/Vent Path

Isolation

1-PCV-0455A

Risk

9.

MOV 12

Gate

Unit 1 - RHR -

Flowpath/Containment

Isolation

1-8701B

Risk

10.

MOV 8

Gate

Unit 1 - SI - ECCS

Recirculation

Flowpath/Passive Pipe

Break Isolation

1-8804B

Risk

11.

MOV 4

Gate

Unit 1 - SI - ECCS to Cold

Legs Flowpath/ECCS to Hot

Legs Flowpath

1-8835

Risk

12.

MOV 10

Gate

Unit 1 - SI - ECCS to Cold

Legs Flowpath/ECCS to Hot

Legs Flowpath

1-8809B

Risk

13.

MOV 10

Gate

Unit 1 - SI - ECCS to Hot

Legs Flowpath/ECCS to

Cold Legs

1-8840

Risk

14.

MOV 24

Butterfly

Unit 1 - Service Water

Flowpath/Throttling

1-HV-4287

Risk

15.

MOV 4

Gate

Unit 2 - Containment

Isolation & AFW to Faulted

SG Flow

2-HV-2492B

Risk

16.

MOV 2

Globe

Unit 2 - CVCS - ECCS

Flowpath Boundary

2-8110

Risk

17.

AOV

10

Butterfly

Unit 2 - CCW Flowpath

Boundary

2-FV-4536

Risk

18.

MOV 18

Butterfly

Unit 2 - CCW - RHR Heat

Exchanger Cooling Flowpath

2-HV-4572

Risk

A-2

No. ACT

Size

(in)

Valve

Type

System

Utility ID

Selection

Basis

19.

AOV

3

Ball

CCW - - Safety Chilled

Water Condenser Cooling

2-PV-4552

Risk

20.

AOV

18

Globe

Feedwater Isolation

2-FCV-0520

Risk

21.

HOV

18

Gate

Feedwater Isolation &

Containment Isolation

2-HV-2137

Risk

22.

HOV

2

Globe

Unit 2 - FW - Feedwater

Isolation & Containment

Isolation

2-HV-2137

Risk

23.

HOV

2

Globe

Unit 2 - MS - Steam Line

Isolation & Containment

Isolation

2-HV-2333A

Risk

24.

MOV 3

Gate

Unit 2 - RCS - Post Accident

Vent Path/Vent Path

Isolation

2-8000A

Risk

25.

MOV 6

Gate

Unit 2 - SI - ECCS Flowpath

Boundary (during

Recirculation)

2-8806

Risk

26.

MOV 14

Gate

Unit 2 - SI - ECCS

Recirculation

Flowpath/Containment

Isolation

2-8811A

Risk

27,

MOV 10

Gate

Unit 2 - SI - ECCS to Cold

Legs Flowpath/ECCS to Hot

Legs Flowpath

2-8809A

Risk

28.

MOV 4

Gate

Unit 2 - SI - - ECCS to Hot

Legs Flowpath/ECCS to

Cold Legs

2-8802B

Risk

29.

MOV 6

Gate

Unit 2 - SI - Passive Pipe

Break Isolation

2-8923B

Risk

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