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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNRC-24-0050, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2024-08-12012 August 2024 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-24-0048, Submittal of Inservice Inspection Summary Report2024-08-0606 August 2024 Submittal of Inservice Inspection Summary Report ML24240A3582024-07-11011 July 2024 Inservice Testing Program for Pumps and Valves, Part 5: IST Valve Scope Table, Revision 5 NRC-24-0049, Inservice Testing Program for Pumps and Valves, Part 11: 1st Program Valve Basis, Revision 22024-06-27027 June 2024 Inservice Testing Program for Pumps and Valves, Part 11: 1st Program Valve Basis, Revision 2 ML23283A0292023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 7: IST Program Relief Request Revision 3 ML23283A0282023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 6: IST Check Valve Condition Monitoring Plans Rev. 3 ML23283A0272023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 5: IST Valve Scope Table Revision 4 ML23283A0262023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 4: IST Valve Testing Program (Revision 3) ML23283A0252023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 3: IST Pump Scope Table (Revision 4) ML23283A0242023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 2: IST Pump Testing Program (Revision 3) ML23283A0232023-10-0909 October 2023 Inservice Testing Program Fourth Ten-Year Interval ML23283A0302023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 8: IST Program Cold Shutdown Justifications Rev. 4 ML23283A0312023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 9: IST Program Refueling Outage Justifications Rev. 4 ML23283A0322023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 10: IST Program Technical Positions Revision 2 ML23283A0342023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 11: IST Program Valve Basis Revision 1 NRC-23-0063, Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 12023-10-0909 October 2023 Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1 NRC-23-0056, Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval2023-08-31031 August 2023 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval NRC-23-0030, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2023-06-0505 June 2023 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-23-0029, Snubber Program for the Fourth 10-Year Testing Interval2023-06-0505 June 2023 Snubber Program for the Fourth 10-Year Testing Interval ML24240A3632022-01-14014 January 2022 Inservice Testing Program for Pumps and Valves, Part 10: IST Program Technical Position, Revision 2 ML24240A3592022-01-14014 January 2022 Inservice Testing Program for Pumps and Valves, Part 6: IST Check Valve Condition Monitoring Plans, Revision 3 ML24240A3622021-02-0303 February 2021 Inservice Testing Program for Pumps and Valves, Part 9: IST Program Refueling Outage Justifications, Revision 4 ML24240A3612021-02-0303 February 2021 Inservice Testing Program for Pumps and Valves, Part 8: IST Program Cold Shutdown Justifications, Revision 4 ML24240A3642021-01-25025 January 2021 Inservice Testing Program for Pumps and Valves, Part 12: IST Program Pump Basis, Revision 1 ML24240A3602021-01-25025 January 2021 Inservice Testing Program for Pumps and Valves, Part 7: IST Program Relief Requests, Revision 3 ML24240A3562021-01-25025 January 2021 Inservice Testing Program for Pumps and Valves, Part 3: IST Pump Scope Table, Revision 4 ML24240A3542021-01-25025 January 2021 Inservice Testing Program Fourth Ten-Year Interval - IST Program Description, Revision 4 NRC-20-0064, Inservice Inspection Summary Report2020-11-0303 November 2020 Inservice Inspection Summary Report ML24240A3552020-02-17017 February 2020 Inservice Testing Program for Pumps and Valves, Part 2: IST Pump Testing Program, Revision 3 ML24240A3572020-02-17017 February 2020 Inservice Testing Program for Pumps and Valves, Part 4: IST Valve Testing Program, Revision 3 NRC-20-0012, Submittal of Valve Relief Requests VRR-010 and VRR-011 for the Inservice Testing Program Fourth 10-Year Interval2020-01-24024 January 2020 Submittal of Valve Relief Requests VRR-010 and VRR-011 for the Inservice Testing Program Fourth 10-Year Interval NRC-19-0047, Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval2019-06-14014 June 2019 Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval NRC-19-0025, Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval2019-05-29029 May 2019 Submittal of Valve Relief Requests for the Inservice Testing Program Fourth 10-Year Interval NRC-19-0015, Submittal of Pump Relief Requests for the Inservice Testing Program Fourth 10-Year Interval2019-03-27027 March 2019 Submittal of Pump Relief Requests for the Inservice Testing Program Fourth 10-Year Interval NRC-19-0016, Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Fourth Ten-year Interval2019-02-28028 February 2019 Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Fourth Ten-year Interval NRC-19-0010, Inservice Inspection Summary Report for Activities Performed at DTE Electric Company'S (DTE) Fermi 2 Nuclear Power Plant During the 19th Refueling Outage in Fall 20182019-01-23023 January 2019 Inservice Inspection Summary Report for Activities Performed at DTE Electric Company'S (DTE) Fermi 2 Nuclear Power Plant During the 19th Refueling Outage in Fall 2018 NRC-17-0081, Supplement to Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval2017-12-0808 December 2017 Supplement to Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval NRC-17-0047, Inservice Inspection Summary Report2017-07-17017 July 2017 Inservice Inspection Summary Report ML16189A2182016-06-29029 June 2016 BWR Vessel and Internals Project - Vessel Internals Inspection Summaries for Fall 2015 Outages NRC-16-0001, Request for Relief from ASME OM Code 5-Year Test Interval2016-03-16016 March 2016 Request for Relief from ASME OM Code 5-Year Test Interval ML16053A1852016-02-22022 February 2016 Inservice Inspection Summary Report for 17th Refueling Outage in Fall 2015 NRC-15-0027, Submittal of Inservice Testing Program Relief Request PRR-012 for Quarterly Test of Core Spray Pumps2015-03-0505 March 2015 Submittal of Inservice Testing Program Relief Request PRR-012 for Quarterly Test of Core Spray Pumps NRC-14-0024, Inservice Inspection Summary Report2014-07-0202 July 2014 Inservice Inspection Summary Report NRC-13-0040, Submittal of Inservice Testing Program Relief Request PRR-011, for the Third Ten-Year Interval2013-08-0707 August 2013 Submittal of Inservice Testing Program Relief Request PRR-011, for the Third Ten-Year Interval NRC-12-0052, Inservice Inspection Summary Report2012-08-0101 August 2012 Inservice Inspection Summary Report ML12272A0552012-05-18018 May 2012 Inservice Testing Program, Third Ten-Year Interval, Third Interval Start - February 17, 2010 NRC-11-0006, Inservice Inspection Summary Report During Refueling Outage 142011-02-23023 February 2011 Inservice Inspection Summary Report During Refueling Outage 14 NRC-10-0033, Response to Request for Additional Information Regarding Relief Requests PRR-002 and PRR-003 for the Inservice Testing Program Third Ten-Year Interval2010-04-22022 April 2010 Response to Request for Additional Information Regarding Relief Requests PRR-002 and PRR-003 for the Inservice Testing Program Third Ten-Year Interval NRC-10-0004, Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Third Ten-year Interval2010-01-20020 January 2010 Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Third Ten-year Interval NRC-08-0012, Inservice Inspection Summary Report for 20072008-02-15015 February 2008 Inservice Inspection Summary Report for 2007 2024-08-06
[Table view] Category:Letter type:NRC
MONTHYEARNRC-24-0064, Supplement to License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance2024-10-31031 October 2024 Supplement to License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance NRC-24-0058, Status of License Renewal Commitments2024-10-0303 October 2024 Status of License Renewal Commitments NRC-24-0057, Update to NRC 24-0041: Technical Specification (TS) 5.6.7 – Post Accident Monitoring Report2024-09-0303 September 2024 Update to NRC 24-0041: Technical Specification (TS) 5.6.7 – Post Accident Monitoring Report NRC-24-0053, Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30, 20242024-08-30030 August 2024 Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30, 2024 NRC-24-0050, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2024-08-12012 August 2024 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-24-0048, Submittal of Inservice Inspection Summary Report2024-08-0606 August 2024 Submittal of Inservice Inspection Summary Report NRC-24-0046, Fenni 2 Power Plant - Approval of the National Pollutant Discharge Elimination System Permit Application for Reissuance2024-07-25025 July 2024 Fenni 2 Power Plant - Approval of the National Pollutant Discharge Elimination System Permit Application for Reissuance NRC-24-0020, Submittal of Revision 51 to the Fermi 2 Radiological Emergency Response Preparedness Plan2024-07-24024 July 2024 Submittal of Revision 51 to the Fermi 2 Radiological Emergency Response Preparedness Plan NRC-24-0044, Enrico Fermi 1 License Expiration - 10 CFR 50.51 (Continuation of License)2024-07-10010 July 2024 Enrico Fermi 1 License Expiration - 10 CFR 50.51 (Continuation of License) NRC-24-0041, Technical Specification (TS) 5.6.7 - Post Accident Monitoring Report2024-06-21021 June 2024 Technical Specification (TS) 5.6.7 - Post Accident Monitoring Report NRC-24-0042, Regulat01y Issues Summaty (RIS) 24-01 Preparation and Scheduling of Operator Licensing Examinations to Submit Fonn 536, Operator Licensing Examination Data2024-06-18018 June 2024 Regulat01y Issues Summaty (RIS) 24-01 Preparation and Scheduling of Operator Licensing Examinations to Submit Fonn 536, Operator Licensing Examination Data NRC-24-0040, Verification of No Significant Hazards Considerations for License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance Supplement Provided in NRC-24-00332024-06-0606 June 2024 Verification of No Significant Hazards Considerations for License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance Supplement Provided in NRC-24-0033 NRC-24-0033, DTE Electric Company - Final Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance2024-05-30030 May 2024 DTE Electric Company - Final Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance NRC-24-0017, 2023 Annual Radioactive Effluent Release Report and 2023 Radiological Environmental Operating Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report and 2023 Radiological Environmental Operating Report NRC-24-0032, Transmittal of the Core Operating Limits Report for Cycle 232024-04-25025 April 2024 Transmittal of the Core Operating Limits Report for Cycle 23 NRC-24-0027, Partial Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance2024-04-24024 April 2024 Partial Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance NRC-24-0031, Retake Exam Outline Submittal Letter2024-04-22022 April 2024 Retake Exam Outline Submittal Letter NRC-24-0018, 2023 Annual Non-Radiological Environmental Operating Report2024-04-0909 April 2024 2023 Annual Non-Radiological Environmental Operating Report NRC-24-0015, Enrico Fermi Atomic Power Plant, Unit 1, Decommissioning Funding Status Report2024-03-31031 March 2024 Enrico Fermi Atomic Power Plant, Unit 1, Decommissioning Funding Status Report NRC-24-0001, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, TSTF-439, Rev. 2, Eliminate Second Completion2024-03-21021 March 2024 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, TSTF-439, Rev. 2, Eliminate Second Completion NRC-24-0019, Submittal of 2023 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2024-03-14014 March 2024 Submittal of 2023 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-24-0023, NRC-24-0023, Post Exam Package Submittal Letter to NRC2024-03-0707 March 2024 NRC-24-0023, Post Exam Package Submittal Letter to NRC NRC-24-0008, Levels and Sources of Property Insurance Coverage2024-02-15015 February 2024 Levels and Sources of Property Insurance Coverage NRC-24-0009, Request for NRC to Suspend Regulatory Audit of License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance for Fermi Unit 22024-02-0606 February 2024 Request for NRC to Suspend Regulatory Audit of License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance for Fermi Unit 2 NRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-24-0007, Report of Changes to Quality Assurance Program for Radioactive Material Packages2024-01-12012 January 2024 Report of Changes to Quality Assurance Program for Radioactive Material Packages NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 222023-12-14014 December 2023 Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22 NRC-23-0077, Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan2023-12-0404 December 2023 Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan NRC-23-0075, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notification Implementation2023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notification Implementation NRC-23-0073, Guarantee of Payment of Deferred Premiums2023-11-29029 November 2023 Guarantee of Payment of Deferred Premiums NRC-23-0071, Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-10-13013 October 2023 Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0068, Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-09-28028 September 2023 Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0064, Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-09-11011 September 2023 Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0057, Independent Spent Fuel Storage Installation Cask Registration2023-08-31031 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0054, Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 20232023-08-31031 August 2023 Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 2023 NRC-23-0056, Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval2023-08-31031 August 2023 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval NRC-23-0061, Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water..2023-08-30030 August 2023 Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water.. NRC-23-0059, Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0060, Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0053, Independent Spent Fuel Storage Installation Cask Registration2023-08-23023 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0050, Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-10010 August 2023 Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0048, Independent Spent Fuel Storage Installation Cask Registration2023-08-0101 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0049, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-07-24024 July 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0043, Independent Spent Fuel Storage Installation, Cask Registration2023-06-27027 June 2023 Independent Spent Fuel Storage Installation, Cask Registration NRC-23-0020, License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance2023-06-13013 June 2023 License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance NRC-23-0039, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-06-0606 June 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0030, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2023-06-0505 June 2023 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-23-0029, Snubber Program for the Fourth 10-Year Testing Interval2023-06-0505 June 2023 Snubber Program for the Fourth 10-Year Testing Interval NRC-23-0037, 56542-EN 56542 - Fermi2023-05-26026 May 2023 56542-EN 56542 - Fermi 2024-09-03
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DTE Electric Company 6400 N. Dixie Highway Newport, MI 48166 10 CFR 50.55a August 31, 2023 NRC-23-0056 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Fermi Unit 2 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval In accordance with the American Society of Mechanical Engineers (ASME) OM Code, Section ISTA General Requirements, 2012 Edition, attached for your information is a copy of the Fermi 2 IST Program for the Fourth 10-Year Interval. The Fourth 10-Year Interval IST Program Plan complies with the requirements of the ASME Section ISTA-3120 2012 Code Edition. The Fourth 10-Year Interval began on February 17, 2020, and concludes on February 16, 2030. The IST Program plan was originally sent to the Fermis NRC Project Manager via e-mail on 10/18/2021 to comply 10 CFR 50.55a(f)(7). This submittal is being made to the Document Control Desk to allow the Fourth 10-Year Interval IST Program Plan to be retrievable through the Agencywide Documents Access and Management System (ADAMS).
No new commitments are being made in this submittal.
Should you have any questions or require additional information, please contact me at (734) 586-4772.
Sincerely, Eric Frank Manager - Nuclear Licensing
Enclosure:
IST Program Plan cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III DTE
Enclosure to NRC-23-0056 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 IST Program Plan
DSN:IST Program Description, Rev.4, Page 1 of 16 DTE Energy - Fermi 2 Inservice Testing Program Fourth Ten-Year Interval Fermi 2 Nuclear Operations Center 6400 N. Dixie Highway Newport, Michigan 48166 Date of Commercial Operation 23-1988 Fourth Interval Start - February 17, 2020 Revised per LCR 20-045-151.
APPROVALS:
Prepared By:
Jeffrey D. Auler, e55603, see attached email.
1ST Program Manager Craig Shepherd, e55018, see attached email.
Reviewed By: -===============--- Date:...
1 1
18 12 1--.....
Qualified Program Engineer Reviewed By:
James Wines, e54431, see attached email.
Date: ~111_81_2_1 -~
...!:::::===============-----
Supervisor Performance Engineering Randy Breymaier, e50801, see attached I
A d B
1_18_12_1 __
pprove y:..!e=m=a=1=.=============---
Manager Performance Engineering C
B Mark D. Wilson, CA1702, see attached email Date*.
11/19/21 oncurrence y: -=================-
ANH INFORMATION AND PROCEDURES Rev:
4 Date:
1/25/21 QUAL PE-03 r@
PE-03 rgj NIA NIA NIA DSN: 1ST Program Description DTC: TMPLAN File:
1715.04 Recipient: ______ _
Date Approved: ________ _
Release authorized by: ___________ _
1ST PROGRAM PLAN PART l Page 1
DSN:IST Program Description, Rev.4, Page 2 of 16 1ST Program Plan Description 1ST PROGRAM PLAN MASTER INDEX Part 1 IST Program Description DSN: IST Program Description Part 2 IST Pump Testing Program DSN: IST Pump Testing Program Part 3 IST Pump Scope Table DSN: IST Pump Scope Table Part 4 IST Valve Testing Program DSN: IST Valve Testing Program Part 5 IST Valve Scope Table DSN: IST Valve Scope Table Part 6 IST Check Valve Condition Monitoring Plans DSN: IST CVCM Plans Part 7 IST Program Relief Requests DSN: IST Program Relief Requests Part 8 IST Program Cold Shutdown Justifications DSN: IST Program CSJ Part 9 IST Program Refueling Outage Justifications DSN: IST Program ROJ Part 10 IST Program Technical Positions DSN: IST Program Tech Positions Part 11 IST Program Valve Basis DSN: IST Program Valve Basis Part 12 IST Program Pump Basis DSN: IST Program Pump Basis PROGRAM PLAN TABLE OF CONTENTS PART 1 1ST Program Description 1.1 Purpose 1.2 Scope 1.3 Requirements 1.4 Plant Systems 1.5 Test Intervals PART 2 1ST Pump Testing Program 1.1 Pump Inservice Testing Plan Description 1.2 Pump Plan Table Description 1.3 Measurement of Test Quantities 1.4 Allowable Ranges of Test Quantities 1.5 Instrument Accuracy 1.6 Reference Values
- 1. 7 Applicable Code Cases 1.8 Mandatory Appendix V PART 3 1ST Pump Scope Table PART 4 1ST Valve Testing Program 1.0 Inservice Testing Plan for Valves 2.0 IST Exam Definitions 3.0 MOV Program 4.0 Applicable Code Cases PART 5 1ST Valve Scope Table 1ST PROGRAM PLAN PART 1 Page 2
DSN:IST Program Description, Rev.4, Page 3 of 16 PART 6 1ST Check Valve Condition Monitoring Plans CMJNo.
CMJ-01 CMJ-02 CMJ-03 CMJ-04 CMJ-05 CMJ-06 CMJ-07 CMJ-08 CMJ-09 CMJ-10 CMJ-11 CMJ-12 CMJ-13 CMJ-14 CMJ-15 CMJ-16 CMJ-17 CMJ-18 Description RHR Service Water Return Checks Standby Liquid Control CIV Checks RHR Min Flow Checks Core Spray Pump Discharge Checks Core Spray Pump Min Flow Checks HPCI Booster Pump Suction Checks EECW Return/ RCIC Pump Suction Checks EECW Pump Discharge Checks HPCI Turbine / RCIC Pump Min Flow Checks HPCI I RCIC Turbine Exhaust Checks EECW Nozzle Checks Nitrogen Inerting Checks LPCI Injection Checks RBCCW I CCHV AC Checks EESW Min Flow Checks RCIC Pump Discharge Check Core Spray Injection Checks EDG Starting Air Receiver Checks PART 7 1ST Program Relief Requests 7.1 DTE Relief Request Submittals 7.2 NRC Safety Evaluation Reports PART 8 1ST Program Cold Shutdown Justifications 8.1 CSJ Index 8.2 Cold Shutdown Justifications PART 9 1ST Program Refueling Outage Justifications 9.1 ROJ Index 9.2 Refueling Outage Justifications PART 10 1ST Program Technical Positions 10.1 Technical Positions Index 10.2 Fermi 2 IST Program Technical Positions PART 11 1ST Program Valve Basis 11.1 Plant Equipment Identification with IST scoping basis PART 12 1ST Program Pump Basis 12.1 Plant Equipment Identification with IST scoping basis 1ST PROGRAM PLAN PART 1 Page 3
DSN:IST Program Description, Rev.4, Page 4 of 16 1ST Program Plan Description 1.1 Purpose To provide requirements for the performance and administration of assessing the operational readiness of those pumps and valves whose specific functions are required to either:
Shutdown the reactor to the safe shutdown condition, and/or Maintain the safe shutdown condition, and/ or To mitigate the consequences of an accident.
Fermi 2 was designed and licensed to operate with the Hot Shutdown condition (Mode
- 3) defined as the "safe" shutdown condition. Since Safe Shutdown is defined in the Fermi 2 licensing basis as the hot shutdown condition, inservice testing of components which are required to achieve cold shutdown is unwarranted. However, decay heat removal is an important safety function that must be accomplished or core damage could result. Although the RHR shutdown cooling subsystem does not meet a specific criterion of 10 CFR 50.36( c )(2)(ii), it is identified as a significant contributor to risk reduction. For the purposes ofIST scoping the term "Safe Shutdown" will be conservatively defined as a Cold Shutdown condition (Mode 4). All components necessary to achieve and maintain a Cold Shutdown condition will be included within the IST scope. OM ISTB-3420 and ISTC-3570 require IST Program testing to remain current unless a System is in a mode where it is not required to be operable. Systems must be tested within 3 months ofretuming to operable status. For Systems with requirements to remain operable during Modes 4 and 5, IST Program testing must commence prior to Mode 4. Reference TS 3.5.2.7 (CARD 20-27489) as an example.
The Fermi 2 Inservice Testing Program (IST) is required by 10CFR50.55a including applicable OM Code Conditions. Fermi 2 used the following guidance documents in developing the IST Program:
System Design Basis Documents ISI Program Boundary Drawings Technical Specifications Technical Requirements Manual UFSAR NUREG-1482 Revision 2, Guidelines for Inservice Testing at Nuclear Power Plants" 1ST PROGRAM PLAN PART 1 Page 4
DSN:IST Program Description, Rev.4, Page 5 of 16 The Fermi 2 Fourth 120-month interval Pump and Valve Inservice Testing Plan will be in effect as follows:
Begin: 02/17/2020 End: 02/16/2030 The key features of this Plan are: the Pump and Valve table listings, Relief Requests, Refueling Outage Justifications, Cold Shutdown Justifications, Check Valve Condition Monitoring Plans, Technical Positions, and the Program Scoping Basis document. The component level basis information and testing data is maintained within the Iddeal software. The 2012 Edition of the ASME OM Code defines all scoping and classification requirements.
Grace for IST testing is 25% for periods specified as fewer than 2 years and 6 months for periods equal to or greater than 2 years per Code Case OMN-20.
The IST Program Interval history is as follows:
First Interval (Start 1/23/1988)
Second Interval (Start 2/17/2000)
Third Interval (Start 2/17/2010)
Fourth Interval (Start 2/17/2020)
The second interval started approximately twelve years after the start of the first interval. The extension was due to a 389 day extended outage for a main turbine blade failure and an elective 1 year extension. This extension follows the OM Code sections ISTA-3120 (d) and (e). No additional interval extensions can be applied in the future without NRC approval.
1.2 Scope The IST program plan has been prepared to meet the requirements of the American Society of Mechanical Engineers (ASME) OM Code 2012 Edition. Mandatory Appendix I, II, III, and V. As noted above, modification of the OM Code requirements is made as applicable by following the conditions listed in IOCFR 50.55a.
The IST Program Plan provides a complete listing of those pumps and valves included in the program per the requirements of the following:
ASME OM Code 2012, Subsection ISTA, "General Requirements" ISTA contains the requirements directly applicable to inservice testing including the Owner's Responsibility and Records Requirements.
ASME OM Code 2012, Subsection ISTB, "Inservice Testing of Pumps in Light-Water Reactor Nuclear Power Plants" 1ST PROGRAM PLAN PART 1 Page 5
DSN:IST Program Description, Rev.4, Page 6 of 16 ISTB establishes the requirements for inservice testing of pumps in light-water reactor nuclear power plants. The pumps covered are those provided with an emergency power source, which are required in the shutting down the reactor to the safe shutdown condition, in maintaining the safe shutdown condition, and/or in mitigation of the consequences of an accident.
ASME OM Code 2012, Subsection ISTC, "Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants" ISTC establishes the requirements for inservice testing of valves in light-water reactor nuclear power plants. The valves covered include those which provide overpressure protection and those which are required to perform a specific function, either actively through the changing of valve obturator position or passively by maintaining required obturator position in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.
ASME OM Code 2012, Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" ISTD establishes the requirements for inservice testing of snubbers in light-water reactor nuclear power plants including the Owner's Responsibility and Records Requirements. The Snubber Program is managed outside of the IST Program as an independent program.
ASME OM Code 2012, Mandatory Appendix I, "Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants" Provides the requirements for performance testing and monitoring of nuclear plant pressure relief devices. Methods, intervals, and record requirements for monitoring and testing are established, as well as guidelines for the evaluation of results. The Appendix applies to safety valves, safety relief valves, pilot-operated pressure relief valves, power-actuated pressure relief valves, nonreclosing pressure relief devices and vacuum relief devices, including all accessories and appurtenances.
ASME OM Code 2012, Mandatory Appendix II, "Check Valve Condition Monitoring Program" Provides an alternative to the testing or examination requirements ofISTC-3510 through ISTC-5221. The purpose of this program is both to improve valve performance and to optimize testing, examination, and preventive maintenance activities to maintain the continued acceptable performance of a select group of check valves.
ASME OM Code 2012, Mandatory Appendix III, "Preservice and Inservice Testing of Active Electric Motor Operated Valve Assemblies in Light-Water Reactor Power Plants" 1ST PROGRAM PLAN PART 1 Page 6
DSN:IST Program Description, Rev.4, Page 7 of 16 The purpose of this program is to establish the requirements for preservice and inservice testing of motor operated valves.
ASME OM Code 2012, Mandatory Appendix V, "Pump Periodic Verification Test Program" The purpose of this program is to establish the requirements for implementing a pump periodic verification test for certain pumps with specific design basis accident flow rates in Technical Specifications, Technical Requirements, or updated safety analysis report. The test verifies that a pump can meet the required pressure as applicable, at the highest design basis accident flow rate.
1ST PROGRAM PLAN PART 1 Page 7
DSN:IST Program Description, Rev.4, Page 8 of 16 1.3 Requirements 1.3.1 The IST Plan is implemented through the performance of implementing procedures to satisfy testing requirements identified for each component in the program.
1.3.2 The acceptability of component performance is determined by comparison to the identified acceptance criteria contained in the implementing procedure.
That acceptance criteria are derived from Technical Specifications and ASME Code requirements.
1.3.3 Periodic review of selected performance data associated with pumps and valves is performed for trending purposes.
1.3.4 Maintenance activities are reviewed to determine the impact on the performance of the IST Program pumps and valves.
1.3.5 The content of the IST Plan is revised as necessary during the interval due to Code edition upgrade, design changes or program enhancements.
1.3.6 Applicable changes to implementing test procedures are reviewed to ensure IST Plan compliance.
1.3.7 Component performance anomalies are analyzed, and input provided for program resolution.
1.4 Plant Systems Plant systems are identified by a single alphabetic character followed by two numeric characters. The list below identifies the three character system identifiers and system names included in the In-service Testing Program for Pumps and Valves. Plant drawing 6M721-5808 identifies the individual ISI boundary drawings for each system.
Plant Identification System (PIS) Codes for Plant Systems B21 - PIS Number for the Nuclear Boiler System B31 - PIS Number for the Reactor Recirculation System Cl I - PIS Number for the Control Rod Drive System C41 - PIS Number for the Standby Liquid Control System CS I - PIS Number for the Neutron Monitoring System El I - PIS Number for the Residual Heat Removal System E21 - PIS Number for the Core Spray System 1ST PROGRAM PLAN PART 1 Page 8
DSN:IST Program Description, Rev.4, Page 9 of 16 E41 - PIS Number for the High Pressure Coolant Injection System ES I - PIS Number for the Reactor Core Isolation Cooling System G 11 - PIS Number for the Radwaste System G33 - PIS Number for the Reactor Water Cleanup System G41 - PIS Number for the Fuel Pool Cooling and Cleanup System G51 - PIS Number for the Torus Water Management System NI 1 -
PIS Number for the Main Steam Supply System N21 - PIS Number for the Feedwater System Pl I - PIS Number for the Condensate Storage and Transfer System P34 - PIS Number for the Post Accident Sampling System P42 - PIS Number for the Reactor Building Closed Cooling Water System P44 - PIS Number for the Emergency Equipment Cooling Water System P45 - PIS Number for the Emergency Equipment Service Water System PSO - PIS Number for the Station and Control Air System R30 - PIS Number for the Diesel Generator System T23 - PIS Number for the Primary Containment System T41 - PIS Number for the RBHVAC & CCHVAC Systems T46 - PIS Number for the Standby Gas Treatment System T48 - PIS Number for the Containment Atmosphere Control System T49 - PIS Number for the Primary Containment Pneumatic System TSO - PIS Number for the Primary Containment Atmosphere Monitoring System 1ST PROGRAM PLAN PART 1 Page 9
DSN:IST Program Description, Rev.4, Page 10 of 16 1.5 Test Intervals The following table lists the codes that may be used in the valve tables to describe the intervals at which various tests are performed IST Exam Interval table Frequency Frequency in Code Days (app.)
Frequency Description Q
92 Quarterly RO 550 Reactor Refuel cs NIA Cold Shutdown AppJ NIA Per Appendix J Option B 2Y 732 2 Years App3 NIA Per Appendix III MOV PM frequencies 6M 183 183 Days SY 1825 5 Years 6Y 2190 6 Years IOY 3652 10 Years CM Varies Check Valve Condition Monitoring Frequency 3Y 1100 3 Years 3C 2190 6 Years based on two-year cycle 1ST PROGRAM PLAN PART 1 Page 10
Jeffrey D Auler From:
Sent:
To:
Subject:
Craig E Shepherd Friday, January 8, 2021 12:39 PM Jeffrey D Auler Approvals, 1ST Program Description To: Jeff Auler, 1ST Program Manager I have reviewed and approved the following OTC DSN Revision TM PLAN 1ST Program 4
Description DSN:IST Program Description, Rev.4, Page 11 of 16 Approval Reviewer:
Craig Shepherd I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Regards, Craig Shepherd 1
Jeffrey D Auler From:
Sent:
To:
Subject:
Jeffrey D Auler Friday, January 8, 2021 1 :15 PM Jeffrey D Auler 1ST Program Description I have prepared and approve the following OTC DSN Revision TM PLAN 1ST Program 4
Description DSN:IST Program Description, Rev.4, Page 12 of 16 Approval Preparer:
Jeffrey D. Auler /s/
I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Regards, Jeffrey D. Auler 1
Jeffrey D Auler From:
Sent:
To:
Cc:
Subject:
Attachments:
James D Wines Monday, January 11, 2021 3:48 PM Jeffrey D Auler Randy D Breymaier FW: Program Description DSN:IST Program Description, Rev.4, Page 13 of 16 1ST Program Plan Part 1 Program Description.pdf I have reviewed and approve the following as the Supervisor - Programs Engineering OTC DSN Revision Approval TMPLAN 1ST Program 4
Reviewed by or Description Approved by:
I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSIP-20-0005.
James Wines I Supervisor-Nuclear Engineering (Programs)
Phone: 734.586.1701 I Text: 734.625.3154 I Pager: 734.227.0076 I eMail: James.Wines@dteenergy.com 1
Jeffrey D Auler From:
Sent:
To:
Mark D Wilson Tuesday, January 19, 2021 7:43 AM Jeffrey D Auler DSN:IST Program Description, Rev.4, Page 14 of 16
Subject:
RE: ANII signature for 1ST Program Parts
- Jeff, I have reviewed and concur as the ANII with the following Revision to the 1ST Program:
OTC DSN Revision TM PLAN 1ST Program 4
Description Mark D. Wilson, ANII The Hartford Steam Boiler Inspection and Insurance Company From: Jeffrey D Auler <jeffrey.auler@dteenergy.com>
Sent: Wednesday, January 13, 2021 9:45 AM To: Mark D Wilson <mark.wilson@dteenergy.com>
Subject:
ANII signature for 1ST Program Parts Approval Concurred by: Mark D.
Wilson -ANII /s/
Mark, I placed a copy of 1ST Program Parts 1, 3, 5, 7, 11, and 12 into the Y: temp folder under your name.
Part 1 is the only cover page that requires a signature however I put all the documents in the drop box for you for reference.
These documents have been reviewed by Craig Shepherd, the Licensing Engineer, Jim, and Randy. I would have attached the signature emails but Randy filled his out incorrectly.
Please send back the following:
I have reviewed and concur as the ANII - Programs Engineering OTC DSN Revision Approval TM PLAN 1ST Program 4
Concurred by: Mark D.
Description Wilson -ANII /s/
1
DSN:IST Program Description, Rev.4, Page 15 of 16 I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Regards, Mark D. Wilson 2
DSN:IST Program Description, Rev.4, Page 16 of 16 Jeffrey D Auler From:
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To:
Subject:
Randy D Breymaier Friday, January 15, 2021 1 :54 PM Jeffrey D Auler Approval of program description (part 1)
I have reviewed and approve the following as Manager, Engineering Programs OTC DSN Revision TM PLAN 1ST Program 4
Description Approval Manager Approval Randy Breymaier /s/
I also authorize any page renumbering required by inclusion of this email within the overall document as required per NSI P-20-0005.
Randy Breymaier Manager Performance Engineering 734 586-1811 1