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Category:Inspection Plan
MONTHYEARIR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) IR 05000263/20220062023-03-0101 March 2023 Annual Assessment Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2022006) ML23058A1522023-02-27027 February 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2023002 IR 05000263/20220052022-08-29029 August 2022 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2022005) IR 05000263/20210062022-03-0202 March 2022 Annual Assessment Letter for Monticello Nuclear Generating Plant, Unit 1 (Report 05000263/2021006) ML21322A2362021-11-18018 November 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2022401 IR 05000263/20210052021-09-0101 September 2021 Updated Inspection Plan for Monticello Nuclear Generating Plant 2 (Report 05000263/2021005) ML21215A2172021-08-0303 August 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21147A5082021-06-0303 June 2021 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21099A0902021-04-0808 April 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000263/2021011 ML21085A8582021-03-26026 March 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2021010 IR 05000263/20200062021-03-0404 March 2021 Annual Assessment Letter for the Monticello Nuclear Generating Plant (Report 05000263/2020006) ML21029A2982021-01-29029 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2021002 ML20275A3942020-10-0101 October 2020 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at the Monticello Nuclear Generating Plant IR 05000263/20200052020-09-0101 September 2020 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2020005) ML20134H9282020-05-12012 May 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000263/2020013 IR 05000263/20190062020-03-0303 March 2020 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2019006 and 07200058/2019006) ML19324F8512019-11-20020 November 2019 Long-Term Replacement Steam Dryer Inspection Plan ML19322C0512019-11-14014 November 2019 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report Number 05000263/2020011 IR 05000263/20190052019-08-28028 August 2019 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2019005) ML19136A0202019-05-15015 May 2019 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza) ML19065A0832019-03-0505 March 2019 Ltr. 03/05/19 Monticello Nuclear Generating Plant - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2019002 (DRS-E.Fernandez) IR 05000263/20180062019-03-0404 March 2019 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2018006 and 07200058/2018006) IR 05000263/20180052018-08-28028 August 2018 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2018005) IR 05000263/20170062018-03-0202 March 2018 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2017006) ML17345A8402017-12-11011 December 2017 Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Monticello Nuclear Generating Plant IR 05000263/20170052017-08-28028 August 2017 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2017005) ML17159A6992017-06-0808 June 2017 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2017409 ML17094A4352017-04-0303 April 2017 Monticello - Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000263/20160062017-03-0101 March 2017 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2016006) ML17026A4302017-01-26026 January 2017 Notification of NRC Triennial Fire Protection Baseline Inspection and Request for Information 05000263/2017007 IR 05000263/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2016005) IR 05000263/20150062016-03-0202 March 2016 Annual Assessment Letter for Monticello Nuclear Generating Plant (Inspection Report 05000263/2015006) ML16041A0482016-02-0909 February 2016 Ltr. 02/09/16 Monticello Nuclear Generating Plant - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000263/2016002 IR 05000263/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2015005) IR 05000263/20140012015-03-0404 March 2015 Annual Assessment Letter for the Monticello Nuclear Generating Plant, (Report 05000263/2014001) ML15027A0412015-01-26026 January 2015 ISI Request for Information ML14245A1442014-09-0202 September 2014 Mid-Cycle Assessment Letter for Monticello Nuclear Generating Plant ML14216A5132014-08-0404 August 2014 Information Request to Support Upcoming Biennial Problem Identification and Resolution Inspection at the Monticello Nuclear Generating Plant IR 05000263/20130012014-03-0404 March 2014 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2013001) ML13246A2312013-09-0303 September 2013 2013 Monticello MOC Letter Combined ML13221A5712013-08-0909 August 2013 Ltr 8/9/13 Monticello MOD 50.59 Request for Information IR 05000263/20120012013-03-0404 March 2013 Annual Assessment Letter for Monticello Nuclear Generating Plant, (Report 05000263-12-001) ML12249A4222012-09-0404 September 2012 Mid-Cycle Assessment Letter for Monticello Generating Plant IR 05000263/20110072012-03-0505 March 2012 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263/2011007) IR 05000263/20110062011-09-0101 September 2011 Mid-Cycle Performance Review and Inspection Plant for Monticello Nuclear Plant 05000263-11-006 IR 05000263/20110012011-03-0404 March 2011 Annual Assessment Letter for Monticello Nuclear Generating Plant (Report 05000263-11-001) ML1104705722011-02-16016 February 2011 Request Notification of NRC Inspection and Request for Information ISI ML1024400642010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Monticello Nuclear Generating Plant IR 05000263/20100012010-03-0303 March 2010 Monticello Nuclear Generating Plant EOC Annual Assessment Letter (Report 05000263-10-001) 2023-08-30
[Table view] Category:Letter
MONTHYEARML24025A9362024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0055 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000263/20230042024-01-31031 January 2024 Integrated Inspection Report 05000263/2023004 ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20244012024-01-22022 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2024401 L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000263/20234022023-12-13013 December 2023 Security Baseline Inspection Report 05000263/2023402 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000263/20230032023-11-13013 November 2023 Integrated Inspection Report 05000263/2023003 and 07200058/2023001 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 ML23291A1102023-10-23023 October 2023 Environmental Audit Summary and RCIs and RAIs ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23248A2092023-09-18018 September 2023 Proposed Alternative VR-11 to the Requirements of the ASME OM Code Associated with Periodic Verification Testing of MO-2397, Reactor Water Cleanup Inboard Isolation Valve ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection IR 05000263/20230102023-09-0707 September 2023 Commercial Grade Dedication Inspection Report 05000263/2023010 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 ML23214A2412023-08-31031 August 2023 Letter: Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application IR 05000263/20230052023-08-30030 August 2023 Updated Inspection Plan for Monticello Nuclear Generating Plant (Report 05000263/2023005) L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 ML23241A9732023-08-21021 August 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1, Subsequent License Renewal Application (Docket No. 50-263) L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence ML23215A1312023-08-0909 August 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application IR 05000263/20230022023-08-0707 August 2023 Plantintegrated Inspection Report 05000263/2023002 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 ML23198A0412023-07-28028 July 2023 LRA Availability Letter ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan IR 05000263/20235012023-07-13013 July 2023 Emergency Preparedness Inspection Report 05000263/2023501 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24022A0212024-01-20020 January 2024 NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f) ML23268A0252023-09-25025 September 2023 SLRA - Requests for Confirmation of Information - Set 2 ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23237A4832023-08-25025 August 2023 SLRA - Request for Additional Information - Set 3 ML23219A1072023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen ML23219A1082023-08-0707 August 2023 SLRA - Requests for Additional Information - Set 2 ML23201A0352023-07-24024 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23200A3502023-07-19019 July 2023 SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos ML23200A3512023-07-19019 July 2023 SLRA - Request for Additional Information - Set 1 ML23059A3522023-03-0101 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000263/2023010 ML23058A1522023-02-27027 February 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000263/2023002 ML23004A1982023-01-0404 January 2023 NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing ML22206A1662022-07-25025 July 2022 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Monticello Nuclear Generating Plant ML22175A1602022-06-24024 June 2022 NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection ML22181A1962022-06-24024 June 2022 NRR E-mail Capture - Draft RAI Monticello Alternative VR-08 ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22123A2822022-05-0303 May 2022 NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency ML21322A2362021-11-18018 November 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000263/2022401 ML21085A8582021-03-26026 March 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000263/2021010 ML21068A2772021-03-0909 March 2021 NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20302A1972020-10-26026 October 2020 NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request ML20191A0252020-07-0101 July 2020 NRR E-mail Capture - Draft Request for Additional Information Monticello Alternative Request RR-016 Related to H8, H9, and H 10 Weld Examinations ML20133K0532020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20134H9282020-05-12012 May 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000263/2020013 ML20120A0272020-04-28028 April 2020 NRR E-mail Capture - Request for Additional Information Monticello Long Term Steam Dryer Inspection Plan ML20099F3622020-04-0606 April 2020 Lr Phase 4 Request for Information ML20055F3672020-02-24024 February 2020 Information Request to Support Upcoming Temporary Instruction 2515/193 Inspection at Monticello Nuclear Generating Plant ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19270E8652019-09-27027 September 2019 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Rbaker) ML19080A2182019-03-21021 March 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Remove Note TS LCO 3.5.1 ML19070A1302019-03-0808 March 2019 Ltr. 03/08/19 Monticello Nuclear Generating Plant - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000263/2019003 (DRS-V.Petrella) ML19031A9132019-01-31031 January 2019 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt 10 CFR 50.69 ML18269A3572018-09-26026 September 2018 NRR E-mail Capture - Request for Additional Information Monticello License Amendment Request to Adopt TSTF-425 ML18173A0512018-06-22022 June 2018 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (L-2018-LLE-0001) ML18130A7472018-05-0909 May 2018 NRR E-mail Capture - Request for Information Monticello TSTF-542 License Amendment Request ML18121A2542018-05-0101 May 2018 Enclosurequest for Additional Information (05/01/2018, E-Mail from C. Jacobs/Dsfm to S. Jurek Monticello Exemption: NRC Clarification Questions on RAI#1 Responses) ML18065A5482018-03-0606 March 2018 EnclosuRAI-1 (non-proprietary) (Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15) ML17293A0912017-10-18018 October 2017 NRR E-mail Capture - Request for Additional Information Monticello Request for Exemption from Appendix R Requirements (CAC No. MF9586; EPID L-2017-LLE-00012) ML17235B0012017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Monticello EAL Scheme Change Amendment Request ML17221A3882017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization ML17219A0752017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant License Amendment Request Dated March 24, 2017 Emergency Response Organization ML17086A0602017-03-27027 March 2017 NRR E-mail Capture - Request for Additional Information Monticello Nuclear Generating Plant Integrated Leak Rate Test Interval Extension Request ML16323A2422016-11-18018 November 2016 NRR E-mail Capture - Monticello ILRT Extension Amendment Request for Additional Information ML13336A7072013-12-0404 December 2013 Request for Additional Information Changes to Security Plan Revision 18 ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13275A1872013-10-28028 October 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051 ML13154A4702013-06-0404 June 2013 Rai'S Following Ifib Analysis 2013 Decommissioning Funding Status Report for Prairie Island 1 and 2 and Monticello ML12279A2952012-10-12012 October 2012 Request for Additional Information 10 CFR 50.54(p)(2) Changes to Security Plan ML12221A3362012-08-0808 August 2012 Draft RAI on Revision to Security Plan 2024-01-20
[Table view] |
See also: IR 05000263/2020013
Text
May 12, 2020
Mr. Thomas Conboy
Site Vice President
Monticello Nuclear Generating Plant
Northern States Power Company, Minnesota
2807 West County Road 75
Monticello, MN 55362-9637
SUBJECT: MONTICELLO NUCLEAR GENERATING PLANT - NOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) AND INITIAL
REQUEST FOR INFORMATION: INSPECTION REPORT 05000263/2020013
Dear Mr. Conboy:
On August 17, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin a baseline
Design Bases Assurance Inspection (Programs) at Monticello Nuclear Generating Plant. This
inspection will be performed in accordance with NRC Baseline Inspection Procedure
71111.21N, Design Bases Assurance Inspection (Programs), Attachment 2, Design-Basis
Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.
This inspection will evaluate the reliability, functional capability, and design basis of
risk-important power-operated valves (POVs) as required by 10 CFR 50.55a and applicable
10 CFR Part 50, Appendix A and Appendix B, requirements. In conducting this inspection, the
team will select risk-important POVs used to prevent and mitigate the consequences of a design
basis accident.
The inspection will include two weeks of onsite inspection. The inspection team will consist of
three NRC inspectors. The current inspection schedule is as follows:
- Preparation week: August 10 - 14, 2020
- Onsite weeks: August 17 - 21, 2020, and August 31 - September 4, 2020
Additional information needed to support the inspection will be identified during the preparation,
and onsite inspection weeks.
Experience with previous baseline engineering inspections of similar depth and length has
shown this type of inspection is 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 for both parties, we have enclosed a request for information needed for
the inspection. 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. Insofar as possible, this information should be provided
electronically to the lead inspector. The information request has been divided into four groups:
- The first group lists information necessary for our initial inspection scoping activities.
This information should be provided to the lead inspector no later than June 15, 2020.
T. Conboy -2-
By July 3, 2020, the lead inspector will communicate the initial selected samples and any
additional information needed to support the in-office preparation activities.
- The second group of documents requested is those items needed to support our
in-office preparation activities. This set of documents should be provided to the lead
inspector no later than August 3, 2020. During the preparation activities, the team may
identify additional information needed to support the inspection.
- The last group includes the additional information above as well as plant-specific
reference material. This information should be available to the team onsite on
August 17, 2020. It is also requested that corrective action documents and answers to
questions developed during the inspection be provided to the lead inspector as the
documents are generated.
In addition, the enclosure includes information and requests addressing inspection logistics.
The lead inspector for this inspection is Elba Sanchez Santiago. We understand that our
licensing contact for this inspection is Gustavo Hernandez of your organization. If there are any
questions about the inspection or the material requested in the enclosure, contact the lead
inspector at 630-829-9520 or via e-mail at elba.sanchezsantiago@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, Control Number
3150-0011. The NRC may not conduct or 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 Office of Management and Budget Control Number.
T. Conboy -3-
This letter and its enclosure 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,
/RA/
Elba Sanchez Santiago
Senior Reactor Inspector
Engineering Branch 2
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosure:
Design Bases Assurance Inspection
(Programs) Document Request
cc: Distribution via LISTSERV
T. Conboy -4-
Letter to Thomas Conboy from Elba Sanchez Santiago dated May 12, 2020.
SUBJECT: MONTICELLO NUCLEAR GENERATING PLANT - NOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) AND INITIAL
REQUEST FOR INFORMATION: INSPECTION REPORT 05000263/2020013
DISTRIBUTION:
Jessie Quichocho
Omar Lopez-Santiago
RidsNrrDorlLpl3
RidsNrrPMMonticello
RidsNrrDroIrib Resource
John Giessner
Kenneth OBrien
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML20134H928
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII
NAME ESanchezSantiago:
mb via e-mail
DATE 05/12/2020
OFFICIAL RECORD COPY
DESIGN BASES ASSURANCE INSPECTION - POV PROGRAM
REQUEST FOR INFORMATION
I. ADMINISTRATIVE INSPECTION INFORMATION
Inspection Report Number: 05000263/2020013
Onsite Inspection Dates: August 17 - 21, 2020, and August 31 - September 4, 2020
IP 71111.21N, Design Bases Assurance Inspection
(Programs), Attachment 2, Design-Basis Capability of
Inspection Procedure:
Power-Operated Valves Under 10 CFR 50.55a
Requirements.
Elba Sanchez Santiago, Senior Reactor Engineer, RIII/DRS
Lead Inspector: 630-829-9520
elba.sanchezsantiago@nrc.gov
Ijaz Jesse Hafeez, Reactor Inspector, RIII/DRS
Teammate Inspectors:
Michael Jones, Reactor Inspector, RIII/DRS
II. LOGISTICS
Email the following inspection logistics to the lead inspector by August 3, 2020, or sooner:
1. Inspection room name/number, directions from the main access facility, and phone number;
2. Interview room name/number;
3. Response team contact information (names and phone numbers) and team roles (e.g.,
management sponsor, lead, inspector counterpart);
4. Any site access/badging actions needed for each inspector;
5. Any dosimetry actions needed for each inspector;
6. Entrance meeting time (preferably after 2:30 p.m. Central Time) and location;
7. Confirmation that the team will have access to a licensee computer with a nearby printer;
8. Confirmation that the team will have Wi-Fi access;
9. Cafeteria location and hours;
10. Inspection response team normal working hours; and
11. Any potential resource conflicts during the inspection (e.g., emergency drills and all-staff
meetings).
Enclosure
III. INFORMATION REQUEST
Contact the lead inspector as soon as possible if you have any questions regarding this
information request. Provide the information electronically in searchable formats, if possible.
The files 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 light water reactor technology.
Important Note: For the purpose of this inspection, POVs are valves with power actuators.
Examples include motor-operated valves (MOVs), air-operated valves (AOVs),
hydraulic-operated valves (HOVs), solenoid-operated valves (SOVs), and pyrotechnic-operated
valves (e.g., squib valves).
1. Information Requested for Initial Inspection Scoping Activities
The following information is requested by June 15, 2020, or sooner, to facilitate the initial
sample selection.
1.1. List of systems, system numbers/designators, and corresponding system names.
1.2. Probabilistic safety analysis (PSA) system notebooks and latest PSA summary
document. Also, identify the top ten risk significant functions per the PSA.
1.3. List of POVs from your site-specific PSA sorted by Risk-Achievement Worth (RAW).
Include values for Birnbaum Importance, Risk-Reduction Worth, and Fussell-Veseley
(as applicable). The list should include (a) component identification number;
(b) applicable plant system; (c) ASME Boiler and Pressure Vessel Code (BPV Code)
Class; (d) safety-related or 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.
1.4. All corrective action documents, evaluations, and NRC correspondence, including any
associated NRC requests for additional information (RAIs) and Safety Evaluation
Report(s), generated in response to the NRC communications listed below. Also, any
NRC inspection reports that were conducted to close out the sites associated
responses.
1.4.1. Generic Letter (GL) 89-10;
1.4.2. GL 96-05;
1.4.3. GL 95-07;
1.4.4. Bulletin 85-03;
1.4.5. Regulatory Issue Summary (RIS) 2000-03; and
1.4.6. GL 88-14.
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1.5. NRC Safety Evaluation Report(s) associated with the In-Service Testing (IST) Program
and relief and alternative requests submitted in accordance with 10 CFR 50.55a for
POVs. 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 self-imposed standards related to the IST Program elements
applicable to POVs.
1.6. IST Program documents, including implementing procedures, IST plan, and the
document that identifies the in-scope valves and the associated IST Program
requirements for each valve (e.g., IST valve table identifying category, active/passive
function).
1.7. Any NRC correspondence regarding the stations POV programs other than the IST
Program, including any associated NRC RAIs and any NRC Safety Evaluation
Report(s). Identify any self-imposed standards related to these programs.
1.8. Site (and corporate if applicable) procedures associated with implementation of the
POV programs required by 10 CFR 50.55a(b)(3)(ii) and/or ASME OM Code Mandatory
Appendix III.
1.9. List of any valve removed from a POV program and basis for removal.
1.10. List of corrective action documents related to the POV programs for the last 5 years,
including the document identifier and brief description. Provide a separate list for each
POV program.
1.11. List of POVs in the Maintenance Rule (a)(1) category for the last 5 years. The list
should include a brief description of the surrounding circumstances.
1.12. Current list of operator workarounds.
1.13. List of open operability evaluations related to POVs.
1.14. List of permanent plant modifications to POVs completed in the last 5 years. For the
purpose of this inspection, permanent plant modifications include permanent plant
changes, design changes, set point changes, equivalency evaluations, suitability
analyses, and commercial grade dedications. The list should contain the modification
identifier, title, revision/date, the affected system, completion date, and a brief
modification description.
1.15. Any self-assessment and/or audit of POV programs completed in the last 5 years.
1.16. Updated Final Safety Analysis Report, Technical Specifications, Technical
Specifications Bases, and Technical Requirements Manual.
1.17. The lead inspector will deliver forms to the licensee point of contact identified in the
letter for approximately 30 valves. Fill out the valve characteristics in the form fields. It
is possible that not all fields can be completed. For those fields that cannot be filled,
leave the fields blank.
1.18. All emergency and abnormal operating procedures.
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1.19. Current management and engineering organizational chart.
2. Information Requested to Support Inspection Preparation Activities
The following information is requested by July 31, 2020, or sooner, to facilitate the final
inspection preparation.
2.1. Preventive Maintenance (PM) Program document, implementing procedures, and PM
templates applicable to POVs.
2.2. Title 10 CFR 50, Appendix J Program document and implementing procedures.
2.3. Corrective Action Program procedures, including the operability/functionality
determination procedure.
2.4. Quality Assurance Program document.
2.5. Procedure for addressing issues captured in 10 CFR 21 notifications.
2.6. Joint Owners Group (JOG) MOV program classification evaluation.
2.7. For each selected POV, including its actuator (the response should be separated by
POV such as by creating a folder for each valve that includes the associated
documents):
2.7.1. Procurement and design specifications, and Certificate of Conformance;
2.7.2. Vendor documents addressing installation, operation, and maintenance;
2.7.3. Piping and instrumentation drawings (PI&Ds) for the associated system;
2.7.4. Electrical diagrams, including control logic diagrams;
2.7.5. Valve and actuator component drawings;
2.7.6. System description and/or training documents associated with the POV;
2.7.7. Operations procedures that direct operators to control the valve, including
alarm response procedures;
2.7.8. Applicable Maintenance Rule scoping document and the Maintenance Rule
performance criteria which would cause the system or component to be
moved from (a)(2) status to (a)(1) status. Also, documents (e.g., corrective
action and work orders) associated with any instance the POV was placed in
(a)(1) status during the last 5 years;
2.7.9. List of tests, including technical specification surveillances. The list should
identify the test periodicity and test procedure identifier;
2.7.10. Completed tests and surveillances performed during the last 5 years. For
those tests and surveillances performed at a periodicity of less than 1 year or
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greater than 5 years, provide the latest three performed. Include the
associated acceptance criteria basis calculations;
2.7.11. Completed preservice testing (PST);
2.7.12. List of applicable PMs. The list should identify the PM periodicity and last
completion date, and briefly describe the PM;
2.7.13. Completed PMs performed during the last 5 years, including any post
maintenance testing. For those PMs performed at a periodicity of less than
1 year or greater than 5 years, provide the latest three performed;
2.7.14. Corrective maintenance work orders performed on the POV during the last
5 years, including any post maintenance testing;
2.7.15. An all-inclusive list of calculation revisions in effect associated with the POV.
The list should include the document identifier, title, and revision number;
2.7.16. Calculations associated with the POV. Data files may be excluded.
Calculation examples include (as applicable):
- Minimum available and required voltage at transient and steady state;
- Thermal overload sizing evaluation;
- Critical setpoint calculations (e.g., limit switch settings);
- Maximum differential pressure;
- Ambient room temperature under normal and accident conditions;
- Environmental qualification (EQ) file;
- (For AOVs) Pneumatic supply sizing and setpoint calculations;
- System hydraulic calculations;
- Pressure locking/thermal binding evaluations; and
2.7.17. History of permanent modifications performed on the POV since installation.
Include modification identifier and brief modification description;
2.7.18. List of corrective action documents associated with the POV for the last
5 years. The list should include the document identifier, brief description, and
status (e.g., open or completed); and
2.7.19. Open and closed operability evaluations originated during the last 5 years.
3. Additional Information to Be Provided Onsite
3.1. During the in-office preparation activities, the team may identify additional information
needed to support the inspection. The lead inspector will provide a list of the
additional information needed during the week of August 17, 2020.
3.2. Information requested to be provided throughout the inspection:
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3.2.1. Any corrective action documents generated as a result of the teams
questions during this inspection as the documents are generated.
3.2.2. List of questions and/or document requests submitted by the team and their
status (e.g., open, closed) sorted by inspector. Provide to each inspector
daily 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> prior to the daily debrief. It is recommended to provide the
team leader with a master list sorted by inspector and each inspector with a
list containing only the items originated by that inspector.
3.2.3. If available in hardcopy form, one complete set of P&IDs and simplified
drawings (e.g., training schematics). If any of these documents is not
available in hardcopy form, contact the lead inspector.
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