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Category:Inspection Plan
MONTHYEARML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) ML24205A2162024-07-23023 July 2024 September 2024 Emergency Preparedness Program Inspection - Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information IR 05000445/20230062024-02-28028 February 2024 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 Reports 05000445/2023006 and 05000446/2023006 IR 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) 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) 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 05000445/20150062016-03-0202 March 2016 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2015006 and 05000446/2015006) IR 05000445/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2015005 and 05000446/2015005) IR 05000445/20154012015-09-0101 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 05000445/20144022014-09-0202 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 05000445/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2014006 and 05000446/2014006) IR 05000445/20130012014-03-0404 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-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) 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) 2024-08-19
[Table view] Category:Letter
MONTHYEARCP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24031A6322024-09-11011 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24228A2252024-08-22022 August 2024 Relief to Use Later Code Edition for Inservice Inspection Program ML24179A0772024-08-20020 August 2024 Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants CP-202400120, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400100, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400097, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe IR 05000445/20240012024-04-26026 April 2024 Integrated Inspection Report 05000445/2024001 and 05000446/2024001 ML24080A1802024-04-26026 April 2024 Ltr to Ken J. Peters, Sr VP and Chief Nuclear Officer, CPNPP re-NOA Final Plant Specific Supplement 60 ML24108A1542024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Achp 2024-09-03
[Table view] |
See also: IR 05000445/2021011
Text
November 4, 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 (TEAMS)
(INSPECTION REPORT 05000445/2021011 AND 05000446/2021011) AND
INITIAL REQUEST FOR INFORMATION
Dear Mr. Peters:
On February 8, 2021, the Nuclear Regulatory Commission (NRC) will begin a triennial
baseline component design bases inspection at the Comanche Peak Nuclear Power Plant.
A six-person team will perform this inspection using NRC Inspection Procedure 71111,
Attachment 21M, Design Bases Assurance Inspection (Teams).
The inspection focuses on the maintenance of component design bases and modifications
made to structures, systems, and components. The samples reviewed during this inspection
will be identified during an information gathering visit and during the subsequent in-office
preparation week. In addition, operating experience issues will also be selected for review.
The inspection will include an information gathering site visit by the team leader and
two weeks of onsite inspection by the team. The inspection will consist of a team lead
inspector, two mechanical inspectors, two electrical inspectors, and an operations inspector.
The current inspection schedule is as follows:
Information Gathering Visit: January 4-8, 2021
Preparation Week: February 1-5, 2021
Onsite Weeks: February 8-12 and February 22-26, 2021
The purpose of the information gathering visit is to meet with members of your staff to identify
potential risk-significant components and operator actions. The lead inspector will also request
a tour of the plant with members of your operations staff and probabilistic safety assessment
staff. During the inspection, up to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> will be needed on the plant-referenced simulator in
order to facilitate the development and inspection of operator action-based scenarios. It has not
yet been determined if the inspection will be onsite or conducted remotely. If the inspection is
performed remotely, we are requesting that, as a minimum, actual on-site time be made
available for 1-2 days to perform component and modification walkdowns. Simulator activities
K. Peters 2
would have to be performed on site. Additional information and documentation needed to
support the inspection will be identified during the inspection, including interviews with
engineering managers, engineers, and probabilistic safety assessment staff.
Our experience with these inspections has shown that they are extremely resource intensive,
both for the NRC inspectors and the licensee staff. 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. The request has been divided into two groups. The first group lists
information necessary for the information gathering visit and for general preparation. This
information should be available to the regional office no later than January 4, 2021, unless
otherwise stated. If possible, this information should be provided electronically to the lead
inspector. Since the inspection will be concentrated on high-risk/low-margin components and
modifications, calculations associated with your list of high-risk components and modifications
should be available to review during the information gathering visit to assist in our selection of
components based on available design margin.
The second group of documents requested lists information necessary to aid the inspection
team in tracking issues identified as a result of the inspection. It is requested that this
information be provided to the lead inspector as the information is generated during the
inspection. An additional request will be made by the team during the preparation week once
the specific components and modifications have been selected. Additional requests by
inspectors will also be made throughout the onsite weeks for specific documents needed to
complete the review. 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
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 Ronald A. Kopriva, Senior Reactor Inspector. If there
are any questions about the inspection or the requested materials, please contact the lead
inspector by telephone at 817-200-1104 or by e-mail at Ron.Kopriva@nrc.gov. It is our
understanding that Mr. Gary Merka will be our licensing contact for the inspection.
PAPERWORK REDUCTION ACT STATEMENT
This letter contains mandatory information collections that are subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)
approved these information collections (approval number 3150-0011). Send comments
regarding this information collection to the Information Services Branch, Office of the Chief
Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office
of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and
Budget, Washington, DC 20503.
PUBLIC PROTECTION NOTIFICATION
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request
for information or an information collection requirement unless the requesting document
displays a currently valid OMB control number.
K. Peters 3
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public
Inspections, Exemptions, Requests for Withholding.
Sincerely,
Vincent G. Digitally signed by Vincent
G. Gaddy
Gaddy Date: 2020.11.04 10:53:56
-06'00'
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 (Teams) Request for
Information
cc w/ encl: Distribution via LISTSERV
ML20309A360
SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword:
By: RAK Yes No Publicly Available Sensitive NRC-002
OFFICE SRI:EB1 C:EB1
NAME RAKopriva VGGaddy
SIGNATURE /RA/ /RA/
DATE 11/04/2020 11/04/2020
Initial Request for Information
Design Bases Assurance Inspection (Teams)
Comanche Peak Nuclear Power Plant
Inspection Report: 05000445/2021011 and 05000446/2021011
EPID ID: I-2021-011-0002
Information Gathering Date: January 4-8, 2021
Inspection Dates: February 8-12, 2021, and February 22-26, 2021
Inspection Procedure: IP 71111, Attachment 21M, Design Bases Assurance
Inspection (Teams)
Lead Inspector: Ronald A. Kopriva, Senior Reactor Inspector
I. Information Requested Prior to Information Gathering Visit (January 4, 2021)
The following information (Section I of this enclosure) should be sent to the Region IV
office in hard copy or electronic format (electronic database preferred), to the
attention of Ronald A. Kopriva, Senior Reactor Inspector, by January 4, 2021, to
facilitate the reduction in the items to be selected for a final list. The inspection team
will finalize the selected list during the prep week using the additional documents
requested in Section II of 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 boiling water reactor technology. If requested documents are large and only hard
copy formats are available, please inform the inspector and provide subject
documentation during the first day of the onsite inspection.
1. An Excel spreadsheet of equipment basic events (with definitions), including
importance measures sorted by risk achievement worth and Fussell-Vesely
from your internal events probabilistic risk assessment. Include basic events
with risk achievement worth value of 1.3 or greater.
2. A list of the top 50 cut-sets from your PRA.
3. Copies of probabilistic risk assessment system notebooks and the
latest probabilistic risk assessment summary document.
4. An Excel spreadsheet of probabilistic risk assessment human action basic
events or risk ranking of operator actions from your site-specific PSA sorted by
risk achievement worth and Fussell-Vesely. Provide copies of your human
reliability worksheets for these items.
Enclosure
5. If you have an external events or fire PSA model, provide the information
requested in items 1-4 for external events and fire.
6. A list of high large early release frequency impact events and
associated components.
7. Structures, systems, and components in the Maintenance Rule (a)(1) Category.
8. A list of high risk maintenance rule systems/components and functions; based
on engineering or expert panel judgment.
9. Site top 10 issues list, if available.
10. Any pre-existing list of components and associated calculations with low
design margins.
11. A list of operating experience evaluations for the last 3 years.
12. A list of all time-critical operator actions in procedures.
13. A list of current operator work arounds/burdens.
14. Procedures, including emergency and abnormal, used to accomplish
operator actions associated with the basic events credited in your PRA.
15. Lists of permanent and temporary modifications performed in the past 5
years to structures, systems, and components sorted by component
identified in Item 1.
16. List of root cause evaluations associated with component failures or design
issues initiated/completed in the last 5 years.
17. A list of any common-cause failures of components in the last 3 years.
18. A copy of any internal/external self-assessments and associated corrective
action documents generated in preparation for this inspection.
19. A copy of engineering/operations-related audits completed in the last 2 years.
20. Electronic copies of the Technical Specifications, Technical Specifications
Bases, and the Final Safety Analysis Report, as updated.
21. A copy of the Individual Plant Examination of External Events, if
available electronically.
22. One-line drawings of emergency core cooling system, ultimate heat sink,
emergency feedwater, safety-related electrical systems.
2
23. A copy of condition reports associated with inspection findings from the
previous NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M
inspection).
24. A list of licensee contacts for the inspection team with phone numbers.
25. A copy of the current management and engineering organizational charts.
II. Information Requested to be provided throughout the inspection.
1. Electronic copies of the design bases documents for selected components
and modifications.
2. Electronic copies of the system health notebooks for selected components
and modifications.
3. A list of the design calculations that provide the design margin information for
selected components. (Calculations for selected components should be
available during the information gathering visit.)
4. Calculations and drawings associated with selected components.
5. Modification documentation associated with modifications selected from
Item I.15, this includes:
a. Post-modification testing, including performance characteristics affected,
assumptions, and acceptance criteria associated with modifications
selected.
b. Updated maintenance and surveillance procedures associated with
modifications.
c. Updated operation procedures and training plans associated with the
modifications.
6. Copies of any corrective action documents generated as a result of the
teams questions or queries during this inspection.
7. Copies of the list of questions submitted by the team members and the
status/resolution of the information requested (provide daily during the
inspection to each team member).
Inspector Contact Information: Mailing Address:
Ronald A. Kopriva U.S. NRC, Region IV
Senior Reactor Inspector ATTN: Ronald A. Kopriva
817-200-1104 - Work 1600 East Lamar Blvd.
Ron.Kopriva@nrc.gov Arlington, TX 76011-4511
3