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Category:Letter type:NRC
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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-23-0029, Snubber Program for the Fourth 10-Year Testing Interval2023-06-0505 June 2023 Snubber Program for the Fourth 10-Year Testing Interval NRC-23-0030, 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 2024-09-03
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J. Todd Conner Site Vice President DTE Energy Company 6400 N.Dixie Highway, Newport, MI 48166 Tel: 734.586.4849 Fax 734586.5295 Email: connerj@dteenergy.com PTE Energy-10 CFR 50.55a October 22, 2013 NRC-13-0058 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Submittal of Inservice Testing Program Relief Request PVRR-001, for the Third Ten-Year Interval Pursuant to 10 CFR 50.55a(a)(3)(ii), DTE Electric Company (DTE) hereby requests NRC approval of the enclosed relief request, PVRR-001, for the Fermi 2 Power Plant.
Relief Request PVRR-001 proposes relief from the component test frequency specifications of the ASME OM Code on the basis that the Code requirement presents an undue hardship without a compensating increase in the level of quality and safety.
DTE proposes an alternative consistent with ASME Code Case OMN-20. Approval of the proposed alternative is requested for the remaining duration of the Fermi 2 third IST ten-year interval which started on February 17, 2010. DTE requests NRC approval of this relief request within one calendar year of the date of this letter.
No new commitments are being made in this submittal.
Should you have any questions or require additional information, please contact Mr.
Zackary Rad of my staff at (734) 586-5076.
Sincerely,
USNRC NRC-13-0058 Page 2
Enclosure:
IST Relief Request PVRR-001, ASME OM Code Test Frequencies cc: NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 5, Region III Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission
Enclosure to NRC-13-0058 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 IST Relief Request PVRR-001 ASME OM Code Test Frequencies
Enclosure to NRC-13-0058 Page 1 Relief Request PVRR-001 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
Hardship or Unusual Difficulty without a Compensating Increase in Level of Quality and Safety
- 1. ASME Code Component(s) Affected All Pumps and Valves contained within the Inservice Testing Program (IST) scope.
2. Applicable Code Edition and Addenda
ASME OM Code, 2004 Edition (Section IST)
- 3. Applicable Code Requirement This request for relief applies to the frequency specifications of the ASME OM Code for all pump and valve testing contained within the IST Program scope per 'Technical Specification 5.5.6. The applicable ASME OM Code (2004 Edition) sections include the following:
ISTA ISTB ISTC APP. I APP. II General Pumps Valves Safety Relief *CVCM Requirements Valves 3120 3400 3510 1320 4000 6200 3540 1340 3630 1350 3700 1370 5221 1380 5222 1390 5230 5240 5260
4. Reason for Request
Pursuant to 10 CFR 50.55a, "Codes and standards," paragraph (a)(3)(ii), relief is requested from the frequency specifications of the ASME OM Code. The basis of the Relief Request is that the Code requirement presents an undue hardship without a compensating increase in the level of quality and safety.
Enclosure to NRC-13-0058 Page 2 Relief Request PVRR-001 The ASME OM Code, 2004 Edition, establishes the inservice test frequency for all components within the scope of the Code. The frequencies (e.g., quarterly) have always been interpreted as "nominal" frequencies (generally as defined in Table 3.2 of NUREG 1482, Revision 1) and owners routinely applied the surveillance extension time period (i.e., grace period) contained in the plant Technical Specifications (TS) Surveillance Requirements (SRs). The TS typically allow for a less than or equal to 25% extension of the surveillance test interval to accommodate plant conditions that may not be suitable for conducting the surveillance (SR 3.0.2). However, regulatory issues have been raised concerning the applicability of the TS grace period to ASME OM Code required inservice test frequencies.
The lack of a tolerance band (grace period) on the ASME OM Code IST frequency restricts operational flexibility. There may be a conflict where an IST test could be required (i.e., its frequency could expire), but it is not possible or not desired that it be performed until sometime after a plant condition or associated Technical Specification is applicable. Therefore, to avoid this conflict, the IST test intervals should be allowed to be extended by up to 25%.
Thus, just as with TS required surveillance testing, some tolerance is needed to allow adjusting OM Code testing intervals to suit the plant conditions and other maintenance and testing activities. This assures operational flexibility when scheduling IST tests that minimize the conflicts between the need to complete the test and plant conditions.
- 5. Proposed Alternative and Basis for Use Code Case OMN-20 is included in the ASME OM Code, 2009 Edition; and will be used as an alternative to the frequencies of the ASME OM Code. The requirements of Code Case OMN-20 are described below.
"ASME OM Division: 1 Section IST and earliereditions and addenda ofASME OM Code specify component testfrequencies based either on elapsed time periods (e.g.,
quarterly,2 years, etc.) or based on the occurrence ofplant conditions or events (e.g.,
cold shutdown, refueling outage, upon detection of a sample failure,following maintenance, etc.).
- a. Components whose testfrequencies are based on elapsed time periods shall be tested at the frequencies specified in Section IST with a specified time period between tests as shown in the table below The specified time period between tests may be reduced or extended asfollows:
- 1) Forperiods specified as fewer than 2 years, the period may be extended by up to 25% for any given test.
Enclosure to NRC-13-0058 Page 3 Relief Request PVRR-001
- 2) Forperiods specified as greater than or equal to 2 years, the period may be extended by up to 6 months for any given test.
- 3) All periods specified may be reduced at the discretion of the owner (i.e., there is no minimum period requirement).
Periodextension is to facilitate test scheduling and considersplant operating conditions that may not be suitablefor performance of the requiredtesting (e.g.,
performance of the test would cause an unacceptable increase in the plant riskprofile due to transientconditions or other ongoing surveillance,test or maintenance activities). Periodextensions are not intended to be used repeatedly merely as an operationalconvenience to extend test intervals beyond those specified.
Periodextensions may also be appliedto acceleratedtestfrequencies (e.g., pumps in Alert Range) and other less than two year testfpequencies not specified in the table below.
Periodextensions may not be applied to the testfrequency requirements specified in Subsection ISTD, Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants, as Subsection ISTD contains its own rulesfor periodextensions.
Frequency Specified Time Period Between Tests Quarterly (or every 3 months)
Semiannually (or every 6 months)
Annually (or every year) x calendaryears where 'x' is a whole number of years > 2
- b. Components whose testfrequencies are based on the occurrence ofplant conditions or events may not have theirperiodbetween tests extended except as allowed by ASME OMDivision: 1 Section IST 2009 Edition through OMa-2011 Addenda and earlier editions and addenda of the ASME OM Code."
Enclosure to NRC-13-0058 Page 4 Relief Request PVRR-001
- 6. Duration of Proposed Alternative This proposed alternative will be used for the remaining duration of the Fermi 2, third ten-year IST interval, which started on February 17, 2010.
- 7. Precedents
" Three Mile Island Nuclear Station, Unit 1 - Relief Requests PR-01, PR-02, and VR-02, Associated With The Fifth 10-Year Inservice Test Interval (TAC Nos.
MF0046, MF0047 and MF0048), dated August 15, 2013. (ADAMS Accession No. ML13227A024)
" Milestone 2 and 3 - Acceptance Review of Alternative Request G-001, Adopt ASME Code Case OMN-20, dated August 13, 2013. (ADAMS Accession No. ML13224A031)
" Callaway Plant, Unit 1 - Summary of Telephone Conference Re: Verbal Authorization for Relief Request PR-07 (TAC No. MF2642), dated September 9, 2013. (ADAMS Accession No. ML13246A307)
" Virgil C. Summer Nuclear Station (VCSNS), Unitl - Acceptance of Requested Licensing Action Re: Request Relief from ASME Code Requirements in VCSNS 4 t" Ten Year Inservice Inspection Interval (TAC Nos. MF1900, MF1901, and MF1902)(RC-13-0069), dated July 10, 2013. (ADAMS Accession No. ML13177A099)
" Virginia Electric and Power Company (Dominion) North Anna Power Station Units 1 and 2 ASME Inservice Testing Program for Pumps and Valves Request for Alternative to Requirements of ASME OM Code, Request for Alternative G-1, dated July 17, 2013. (ADAMS Accession No. ML13204A117)
" Virginia Electric and Power Company Surry Power Station Units 1 and 2 ASME Inservice Testing Program for Pumps and Valves Fifth Ten Year interval Update and Associated Relief Requests, dated May 1, 2013. (ADAMS Accession No. ML13128A104)