|
---|
Category:Inspection Plan
MONTHYEARIR 05000445/20230052023-08-23023 August 2023 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2023005 and 05000446/2023005)- Mid Cycle Letter 2023 ML23068A3782023-03-0909 March 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000445/2023011 and 05000446/2023011) and Request for Information IR 05000445/20220062023-03-0101 March 2023 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2022006 and 05000446/2022006) IR 05000445/20220052022-08-22022 August 2022 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2022005 and 05000446/2022005) ML22179A3032022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000445/2022401; 05000446/2022401 ML22124A3042022-05-0505 May 2022 Notification of NRC Triennial Heat Exchanger/Sink Performance Inspection (05000445/2022003 and 05000446/2022003) and Request for Information IR 05000445/20210062022-03-0202 March 2022 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2021006 and 05000446/2021006) ML21253A2332021-09-0909 September 2021 Request for Information: Comanche Peak Nuclear Power Plant, Units 1 and 2 (05000445 and 05000446); Occupation Radiation Safety (71124.01, 71124.02, 7511) ML21245A3072021-09-0202 September 2021 Request for Information ML21245A307 IR 05000445/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2021005 and 05000446/2021005) ML21176A1292021-06-25025 June 2021 CPNPP FFD Inspection Doc Request 2021 ML21103A3982021-04-13013 April 2021 CP Security Inspection Information Request 2021403 ML21027A4322021-01-27027 January 2021 Information Request, Security IR 2021401 ML20309A3602020-11-0404 November 2020 Notification of NRC Design Bases Assurance Inspection (Teams) (Inspection Report 05000445/2021011 and 05000446/2021011) and Initial Request for Information IR 05000445/20200052020-09-0101 September 2020 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2020005 and 05000446/2020005) ML20139A1452020-05-18018 May 2020 Notification of NRC Design Bases Assurance Inspection (Programs) (05000445/2020010 and 05000446/2020010) and Initial Request for Information ML20055E1052020-03-0303 March 2020 CP2019006 Annual Assessment Letter ML20045E3512020-02-13013 February 2020 Information Request February 13, 2020 Notification of Inspection and Request for Information Comanche Peak Unit 2 NRC Inspection Report 05000446/2020002 IR 05000445/20190052019-08-30030 August 2019 Updated Inspection Plan for Comanche Peak, Units 1 and 2, Reports 05000445/2019005 and 05000446/2019005 IR 05000445/20180062019-03-0404 March 2019 Annual Assessment Letter for Comanche Peak, Units 1 and 2 (Report 05000445/2018006 and 05000446/2018006) ML19043A9442019-02-20020 February 2019 2019 CP Brq RFI Letter IR 05000445/20180052018-08-31031 August 2018 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2018005 and 05000446/2018005) IR 05000445/20170062018-03-0101 March 2018 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2017006 and 05000446/2017006) IR 05000445/20170052017-08-28028 August 2017 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2017005 and 05000446/2017005) IR 05000445/20160062017-03-0101 March 2017 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2016006 and 05000446/2016006) ML16302A1002016-10-27027 October 2016 Notification of Inspection (NRC Inspection Report 05000445/2017002 and 05000446/2017002) and Request for Information IR 05000445/20160052016-09-12012 September 2016 Errata for Mid-Cycle Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2016005 and 05000446/2016005) ML16239A2522016-08-31031 August 2016 Mid-Cycle Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2016005 and 05000446/2016005) IR 05000445/20164012016-08-31031 August 2016 Non-Public Security Inspection Plan for Comanche Peak Nuclear Power Plant (NRC Physical Security Inspection Report Numbers 05000445/2016401 and 05000446/2016401) IR 05000445/20150062016-03-0202 March 2016 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2015006 and 05000446/2015006) IR 05000445/20154012015-09-0101 September 2015 Non-Public Security Inspection Plan for Comanche Peak Nuclear Power Plant (NRC Physical Security Inspection Report Numbers 05000445/2015401 and 05000446/2015401) IR 05000445/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2015005 and 05000446/2015005) IR 05000445/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2014006 and 05000446/2014006) IR 05000445/20144022014-09-0202 September 2014 Non-Public Security Inspection Plan for Comanche Peak Nuclear Power Plant (NRC Physical Security Inspection Report Numbers 05000445/2014402 and 05000446/2014402) IR 05000445/20130012014-03-0404 March 2014 IR 05000445-13-001 & 05000446-13-001, 02/12/2014, Comanche Peak, Units 1 & 2, Annual Assessment Inspection Plan ML13282A5002013-10-0909 October 2013 Notification of NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000445-14-008 and 05000446-14-008) and Request for Information IR 05000445/20130062013-09-0303 September 2013 (Report 05000445/2013006 and 05000446/2013006) IR 05000445/20128012013-03-0404 March 2013 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2012801 and 05000446/2012801) ML13060A4352013-03-0101 March 2013 Notification of NRC Component Design Bases Inspection IR 05000445-13-007 and 05000446-13-007, and Initial Request for Information IR 05000445/20120062012-09-0404 September 2012 Mid-Cycle Letter for Comanche Peak Nuclear Power Plant Units 1 and 2 (Reports 05000445/2012006 and 05000446/2012006) IR 05000445/20120012012-03-0505 March 2012 Annual Assessment Letter for Comanche Peak Nuclear Power Plant Units 1 and 2 (Report 05000445/2012001 and 05000446/2012001) ML1124306442011-09-0101 September 2011 Mid-Cycle Performance Review and Inspection Plan - Comanche Peak Nuclear Power Plant - Units 1 and 2 CP-201101030, Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 6, (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2000, Second Interval)2011-08-0202 August 2011 Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 6, (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2000, Second Interval) CP-201101031, Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 0 (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2010, Third Interval)2011-08-0202 August 2011 Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 0 (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2010, Third Interval) IR 05000445/20110012011-03-0404 March 2011 IR 05000445-11-001, 05000446-11-001, 03/01/2011 - 02/29/2012, Comanche Peak Nuclear Power Plant, Units 1 and 2, Annual Assessment Letter ML1024403972010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plant - Comanche Peak Nuclear Power Plant IR 05000445/20100012010-03-0303 March 2010 Annual Assessment Letter - Comanche Peak Nuclear Power Plant (Reports 05000445-10-001 and 05000446-10-001) CP-200900848, Submittal of Unit 2 Inservice Inspection Plan for Refueling Outage No .112009-07-30030 July 2009 Submittal of Unit 2 Inservice Inspection Plan for Refueling Outage No .11 IR 05000445/20090012009-03-0404 March 2009 Annual Assessment Letter - Comanche Peak Steam Electric Station (Reports 05000445/2009001 and 05000446/2009001) ML0824606392008-09-0202 September 2008 2008 Midcycle Assessment Letter Comanche Peak and Inspection Plan 2023-08-23
[Table view] Category:Letter
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] |
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
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.
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
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.
2
Inspector Contact Information:
Wayne C. Sifre Gerond George Wes Cullum
Senior Reactor Inspector Senior Reactor Inspector Reactor Inspector
817-200-1193 817-200- 1562 817-200- 1563
Wayne.Sifre@nrc.gov Gerond.George@nrc.gov Wes.Cullum@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4
3
Comanche Peak Valves of Interest
No. ACT Size Valve System Utility ID Selection
(in) Type Basis
1. MOV 8 Gate Unit 1 - AFW - AFW Pump 1-HV-2482 Risk
Emergency Supply Flowpath
2. MOV 8 Gate Unit 1 - CVCS - ECCS 1-LCV-0112E Risk
Injection Flowpath &
Boration
3. AOV 10 Butterfly Unit 1 - CCW - Flowpath 1-FV-4537 Risk
Boundary
4. AOV 3 Ball Unit 1 - CCW - Safety 1-PV-4553
Chilled Water Condenser
Cooling
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 1-HV-2134 LERF
& Containment Isolation
8. AOV 3 Globe Unit 1 - RCS - Post Accident 1-PCV-0455A Risk
Vent Path/Vent Path
Isolation
9. MOV 12 Gate Unit 1 - RHR - 1-8701B Risk
Flowpath/Containment
Isolation
10. MOV 8 Gate Unit 1 - SI - ECCS 1-8804B Risk
Recirculation
Flowpath/Passive Pipe
Break Isolation
11. MOV 4 Gate Unit 1 - SI - ECCS to Cold 1-8835 Risk
Legs Flowpath/ECCS to Hot
Legs Flowpath
12. MOV 10 Gate Unit 1 - SI - ECCS to Cold 1-8809B Risk
Legs Flowpath/ECCS to Hot
Legs Flowpath
13. MOV 10 Gate Unit 1 - SI - ECCS to Hot 1-8840 Risk
Legs Flowpath/ECCS to
Cold Legs
14. MOV 24 Butterfly Unit 1 - Service Water 1-HV-4287 Risk
Flowpath/Throttling
15. MOV 4 Gate Unit 2 - Containment 2-HV-2492B Risk
Isolation & AFW to Faulted
SG Flow
16. MOV 2 Globe Unit 2 - CVCS - ECCS 2-8110 Risk
Flowpath Boundary
17. AOV 10 Butterfly Unit 2 - CCW Flowpath 2-FV-4536 Risk
Boundary
18. MOV 18 Butterfly Unit 2 - CCW - RHR Heat 2-HV-4572 Risk
Exchanger Cooling Flowpath
Attachment
No. ACT Size Valve System Utility ID Selection
(in) Type Basis
19. AOV 3 Ball CCW - - Safety Chilled 2-PV-4552 Risk
Water Condenser Cooling
20. AOV 18 Globe Feedwater Isolation 2-FCV-0520 Risk
21. HOV 18 Gate Feedwater Isolation & 2-HV-2137 Risk
Containment Isolation
22. HOV 2 Globe Unit 2 - FW - Feedwater 2-HV-2137 Risk
Isolation & Containment
Isolation
23. HOV 2 Globe Unit 2 - MS - Steam Line 2-HV-2333A Risk
Isolation & Containment
Isolation
24. MOV 3 Gate Unit 2 - RCS - Post Accident 2-8000A Risk
Vent Path/Vent Path
Isolation
25. MOV 6 Gate Unit 2 - SI - ECCS Flowpath 2-8806 Risk
Boundary (during
Recirculation)
26. MOV 14 Gate Unit 2 - SI - ECCS 2-8811A Risk
Recirculation
Flowpath/Containment
Isolation
27, MOV 10 Gate Unit 2 - SI - ECCS to Cold 2-8809A Risk
Legs Flowpath/ECCS to Hot
Legs Flowpath
28. MOV 4 Gate Unit 2 - SI - - ECCS to Hot 2-8802B Risk
Legs Flowpath/ECCS to
Cold Legs
29. MOV 6 Gate Unit 2 - SI - Passive Pipe 2-8923B Risk
Break Isolation
A-2