ML20139A145
| ML20139A145 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| 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) | |
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
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
Senior Reactor Inspector
817-200- 1562
Gerond.George@nrc.gov
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
Emergency Supply Flowpath
1-HV-2482
Risk
2.
MOV 8
Gate
Injection Flowpath &
Boration
1-LCV-0112E
Risk
3.
10
Butterfly
Unit 1 - CCW - Flowpath
Boundary
1-FV-4537
Risk
4.
3
Ball
Unit 1 - CCW - Safety
Chilled Water Condenser
Cooling
1-PV-4553
5.
3
Containment Isolation
1-LCV-1003
6.
18
Globe
Unit 1 - Feedwater Isolation
1-FCV-0540
7.
HOV
18
Gate
Unit 1 - Feedwater Isolation
& Containment Isolation
1-HV-2134
8.
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
Recirculation
Flowpath/Passive Pipe
Break Isolation
1-8804B
Risk
11.
MOV 4
Gate
Legs Flowpath/ECCS to Hot
Legs Flowpath
1-8835
Risk
12.
MOV 10
Gate
Legs Flowpath/ECCS to Hot
Legs Flowpath
1-8809B
Risk
13.
MOV 10
Gate
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
Flowpath Boundary
2-8110
Risk
17.
10
Butterfly
Unit 2 - CCW Flowpath
Boundary
2-FV-4536
Risk
18.
MOV 18
Butterfly
Exchanger Cooling Flowpath
2-HV-4572
Risk
A-2
No. ACT
Size
(in)
Valve
Type
System
Utility ID
Selection
Basis
19.
3
Ball
CCW - - Safety Chilled
Water Condenser Cooling
2-PV-4552
Risk
20.
18
Globe
Feedwater Isolation
2-FCV-0520
Risk
21.
HOV
18
Gate
Feedwater Isolation &
Containment Isolation
2-HV-2137
Risk
22.
HOV
2
Globe
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
Boundary (during
Recirculation)
2-8806
Risk
26.
MOV 14
Gate
Recirculation
Flowpath/Containment
Isolation
2-8811A
Risk
27,
MOV 10
Gate
Legs Flowpath/ECCS to Hot
Legs Flowpath
2-8809A
Risk
28.
MOV 4
Gate
Legs Flowpath/ECCS to
Cold Legs
2-8802B
Risk
29.
MOV 6
Gate
Unit 2 - SI - Passive Pipe
Break Isolation
2-8923B
Risk